ML20207N838

Final Radiation Survey of Nuclear Matl Development Facility

ML20207N838
Person / Time
Site:	07000025
Issue date:	12/19/1986
From:	Chapman J ROCKWELL INTERNATIONAL CORP.
To:
Shared Package
ML20207N825	List: ML20207N823 ML20207N838
References
N704SRR990027, NUDOCS 8701140453
Download: ML20207N838 (82)

Text

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PAGE 1 OF TOTAL PAGES REV LTR/CH NO hUMBER 95722 39001 82 82 net.v N7045RR990027 PROGR AM TITLE Building 055 Decontamination and Deactivation DOCUMENT TITLk Final Radiation Survey of the NMDF DOCUMENT TYPE KEY NOUNS Safety Review Report Decontamination, Decommissioning ORIGINAL ISSUE DATE R EL. DATE APPROVALS DATE

/c2 - / 9-P6 Se i

Tuttleh iby hth6 M

PREPARED 8Y/DATE DEPT MAIL ADDR J. A. Chapman 641 T100 H. E. Remley gggf

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IR PROGRAM? YES O NO F IF YES. ENTFR TPA NO DISTRIBUTION ABSTRACT NAME AD Following the removal of equipment and previously detectable radioactivity from the

• J. W. Carroll (5)

LB11 Nuclear Materials Development Facility (NMDF)

• J. A. Chapman (2)

T100 during the course of the decontamination effort,

• F. C. Schrag T020 a formal final radiological survey was performed.

• M. E. Remley (10)

LA06 The purpose of the final survey is to determine

• C. J. Rozas CB01 the level of effectiveness of the decontamination

• R. J. Tuttle (2)

T100 effort and to demonstrate that the building meets

• NMDF File T100 release criteria for unrestricted use. The results

• R&NS File T100 show that all inspection tests were satisfactorily

• F&IE LB05 passed and that the area is acceptably clean of radioactive materials.

This survey demonstrates that the facility meets the requirements of Annex B to NRC License No SNM-21,

" Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material (July 1982)."

RESERVED FOR PROPRIETARY / LEGAL NOTICE 5 h hh$$$$25 PDR 0195Y/bes

% COMPLETE DOCUMENT NO ASTERISK TITLE PAGE/

SUMMARY

OF CHANGE PAGE ONLY FORM 734-C REV 12-84

I C5 No.:

N7045RR990027 Page: 2 CONTENTS Page I.

Introduction.....................................................

5 II.

Identification of Facility Premises..............................

8

~A.

Bui l di ng C ha ra cte ri sti c s....................................

8 B.

Radiological Condition......................................

13 III. Decontamination Efforts..........................................

16 IV.

Survey Scope.....................................................

'18 A.

Data Acquisition............................................

19 B.

Data Reduction..............................................

21 C.

Data Analysis...............................................

24 V.

Sampling Inspection..............................................

27 A.

Counting Statistics.........................................

27 B.

Sampling Inspection by Variables............................

30 VI.

Procedures.......................................................

33 A.

Calibration and Instrument Checks...........................

33 B.

Average Contamination Measurements.........................

34 C.

Maximum Contamination Measurements..........................

35 D.

Removable Contamination Measurements........................

35 E.

Miscellaneous Gamma Qualification Inspection................

35 F.

Surveys of Special Structural Features and Components.......

36 VII. Survey Results...................................................

37 A.

Statistical Results.........................................

37 B.

Areas of Increased Sampling.................................

52 C.

Results for Special Structural Features and Components......

56 D.

Anomalies...................................................

60 VIII.

Conclusions.......................................................

62 IX.

References.......................................................

63 Appendices i

A.

Sampling Inspection Data Group by Lot.......................

64 B.

USNRC License SNM-21, Annex B...............................

79

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N704SRR990027-Page:

3 TABLES Page 1.

Summary of Survey Results (Office Area and Other Unposted Areas).

37

.2.

Summary of Survey Results (Glovebox Room)........................

37 3.

Summary of Survey Results (Posted Areas).........................

38 4.

Maximum Surface Activity (Hot Spots).............................

39 5.

Additional Sampling Locations....................................

53 6.

Summary of Various Equipment and Features Surveyed for Contamination.....................................................

57 A.1 Sampling Inspection Results of the Office Area and All Other Unposted Areas.........................................

65 A.2 Sampling Inspection Results of the Glovebox Room.................

69 A.3 Sampling Inspection Results of the Posted Area Except for the Glovebox Room.....................................

74 FIGURES 1.

Rocketdyne Santa Susana Field Laboratory.........................

9 2.

The NMDF Site....................................................

10 3.

The NMDF Architectural Plan......................................

11 4.

Facility Layout and Room Descriptions............................

12 5.

(Pu Release) Locations in Glovebox Room..........................

14 6.

The Gaussian Probability Density Function........................

28 7.

The Gaussian Cumulative Distribution Function....................

29 8.

Operating Characteristics Curve..................................

32 9.

Average Alpha Activity (Office Area - unposted)..................

40 10.

Removable Alpha Activity (Office Area - unposted)................

41 11.

Average Beta Activity (Office Area - unposted)...................

42 12.

Removable Beta Activity (Office Area - unposted).................

43 13.

Average Alpha Activity (Glovebox Room - posted)..................

44 14.

Removable Alpha Activity (Glovebox Room - posted)................

45 15.

Average Beta Activity (Glovebox Room - posted)...................

46 i

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N7045RR990027 Page:

4 FIGURES (Cont'd)

Page 16.

Removable Beta Activity (Glovebox Room - posted).................

47 17.

Average Alpha Activity (Remaining posted area)...................

48 18.

Removable Alpha Activity (Remaining posted area).................

49 19.

. Average Beta Activity _ (Remaining posted area)....................

50 20.

Removable Beta Activity.(Remaining posted area)..................

51 21.

Survey Results of Room 126 (Process Laboratory) 100% Floor Sample................................................

54 22.

Survey. Results of the Vault 100% Floor Survey....................

55

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N704SRR990027 Page:

5 1.

INTRODUCTION Located in the Simi Hills of Ventura County, California, the Nuclear Materials Development Facility (NMDF) was designed, constructed, and operated by Rockwell International for research, development, and production work with alpha emitting and/or highly radiotoxic nuclear and radioisotopic fuels. The major effort at this facility involved plutonium-bearing fuels, primarily plutonium-239. The final products were solid reactor fuel materials, radio-isotope heat sources, or radiation sources in a variety of forms and composi-tions.

Various forms of plutonium and depleted uranium (oxide, carbide, metallic) were used as feed materials for all projects.

All of the operations involving unencapsulated radiotoxic materials were performed in gloveboxes which contained all aerosols generated during normal handling processes. The facility was operated for a total of about 16 years, and experienced only three contamination incidents. The first occu red in 1973,-when a plastic bag connected to a glove port on gloveboxes 17 and 17A ruptured and released measurable plutonium contamination onto the eastern side of the glovebox room.

In the second incident, a vacuum pump leak resulted in the release of detectable plutonium contamination on the glovebox room floor, toward the vault.

Both releases were determined to be localized to the immediate area of the incident although small quantities of contamina-tion did spread throughout the room, including the overhead pipes and duct work. A spill of contamination also occurred in the process laboratory, which was used as a waste handling and packaging room during operations; consequent-ly, this room was suspect as containing trace quantities of plutonium or depleted uranium.

Except for the boiler located in Room 128, the emergency diesel genera-tor located in Room 132, and associated compressors and air conditioning units located outside of the building on cement foundations, the building has been gutted. Most of the equipment removed was disposed of as radioactive waste under the burial criteria for transuranic waste. All detectable radioactive material was removed.

Residual contamination in the facility is well below applicable limits specified by Annex B to Special Nuclear Materials License No. SNM-21.

~

No.:

N704SRR990027 Page:

6 Surveys were performed during the decontamination work to identify any areas needing further decontamination.

After these surveys showed that the facility was completely clean and that the decontamination effort was fin-ished, a formal documented survey was performed to provide a quantitative demonstration of the satisfactory level of residual contamination. This sur-vey is an application of a sampling inspection method, inspection by varia-bles. This application is similar in performance to inspection by attributes and variables discussed in Reference 2 (Decon-1).

In this sampling inspection, a minimum sample of 11% of the surface was performed on the floors, walls, and ceilings to measure the average alpha sur-face activity, removable alpha surface activity, average beta surface activ-i ity, and removable beta surface activity. Because of the very low residual activity found, the surface dose rate was not measured. Samples of soil, drain line sludge, paint, and miscellaneous samples were collected and ana-lyzed as necessary; special structural features were surveyed when determined appropriate. The inspection sample was structured on the basis of a uniform j

3-meter-square grid, with a single 1-meter-square location selected for meas-urement from the nine locations in each grid.

The 1-meter-square location in each grid was selected with the intent of choosing a location where there could be potentially higher residual contamination.

(The use of the 3-meter-square grid assures roughly uniform distribution of sample locations through-out the facility.) One-meter-square locations were surveyed with alpha and 2

beta sensitive equipment, and 100 cm of the surface in each location was swiped and tested for removable activity.

If the results of the 1-m survey exceeded 80% of the release criteria, additional sampling in nearby locations j

was perf ormed and the results incorporated into the analysis. All areas determined during this survey to be. greater than 80% of the acceptance criteria were decontaminated further.

While the Nuclear Regulatory Commission has adopted surf ace contamination limits established in Annex B of Rockwell International's license SNM-21, docket 70-25, as suitable for release of equipment and facilities for i

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N7045RR990027 Page: 7 unrestricted use, the goal is to eliminate residual contamination to the extent reasonable. This has been done and is demonstrated by the results of the survey.

The statistical test applied to the survey, inspection by variables, is based on a consumers' risk of acceptance at 10% defective, that is, 0.1, and assumes that the data follows a Gaussian probability density function.

In all cases, the measurements show that the test is satisfactorily passed and the building is acceptably clean.

t No.:

N7045RR990027 Page: 8 II.

IDENTIFICATION OF FACILITY PREMISES A.

BUILDING CHARACTERISTICS The premises to be released for uncontrolled use consist of Build-ing T055, a security post on the north side of the building, and equipment yards surrounding the building but within the facility security control fence.

It is located at the Santa Susana Field Laboratory in the Simi Hills of Ventura County, California, shown in Figure 1.

The HMDF site is presented in Figure 2.

The NMDF building enclosure is a tilt-up concrete structure 200 ft long (running north and south), 60 ft wide, and 16 ft high. The building is divided into an administration area, change rooms, chemistry and other service laboratories, a glovebox room, a vault, and facility equipment rooms. The architectural plan is shown in Figure 3.

The entire facility site was a con-trolled access area; however, the building was divided into posted and un-posted radiologically controlled areas.

Figure 4 identifies each room of the facility and shows the posted and unposted areas.

The building is constructed of noncombustible materials including window-less, precast, tilt-up concrete slab walls of 6-in. thickness and a concrete slab floor. The roof, consisting of lightweight concrete, tarred felt, and gravel, is supported on steel deck panels and girders. The portion of the building surrounding the radiologically posted area was totally enclosed by painted concrete surfaces, weatherproofed doors, and suitable partitions. The floors of the glovebox room and chemistry laboratory had polyvinyl sheet covering to provide an easily decontaminable surface.

Prior to the demolition of the building interior, systems in place included:

air conditioning, radio-active exhaust system for posted areas, a separate radioactive exhaust system for gloveboxes, unshielded gloveboxes, radioactive liquid waste holdup, j

electrical power distribution, annunciator and controls, alarms and instru-mentation, fire protection, and plumbing.Section III of this report i

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12 FIGURE 4 - FACILITY LAYOUT AND ROOM DESCRIPTIONS.

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1 101 Office atry 2

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i No.:

N7045RR990027 Page: 13 provides information regarding the decontamination ef fort, equipment removed, radiological problems encountered, and final condition of the building prior to the final survey.

B.

RADIOLOGICAL CONDITIONS The only radioactive materials handled in the facility were plutonium (consisting of mixtures of Pu-238, Pu-239, Pu-240, Pu-241, Pu-242. Am-241) and cariched and depleted uranium.

All of the isotopes decay by alpha emission with the exception of Pu-241, which decays by beta emission to Am-241, which in turn decays by alpha emission.

In addition, depleted uranium, primarily U-238, decays by alpha emission to thorium-234, which has such a short half life compared to U-238 that the daughter product is in equilibrium with the parent. Thorium-234 decays by beta emission, to Pa-234, which also has a short half-life and decays by beta emission to U-234.

Thereise[sentiallyno U-234 present in the depleted uranium. Therefore, two beta particles are emitted following the emission of the U-238 alpha particle. Since the beta activity is much easier to measure than is the U-238 alpha activity, it has been chosen, for this survey, as the indicator of depleted uranium contamina-tion. Annex B establishes limits for U-238 and associated decay products based upon alpha activity. Since two beta particles are emitted for each alpha decay of U-238, the acceptance limits based on measurements of beta activity are taken to be twice the limits based on alpha activity.

The facility was operated in a radiologically controlled manner; only three contamination incidents occurred during its operation, two involving the release of plutonium into the glovebox room; one involving release of activity in the Process Lab. Figure 5 shows.the location of the. releases in the glove-box room. The first release occurred in June of 1973 when gloveboxes number 17 and 17A were inadvertently overpressurized. Although small amounts of contamination were discovered spread over the entire room, the majority was confined to the localized area of the release.

Following the incident, the room was cleaned as necessary and returned to service. The second release r

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N704SRR990027 Page:

15 occurred when a seal on a vacuum pump used for the gloveboxes ruptured. This release was entirely localized to the immediate area. The leaked oil was removed and the floor cleaned. The building was then returned to service.

In the Process Laboratory, a bag of waste broke, releasing a small amount of unidentified contamination. Special care was taken in these areas during the dismantling, demolition, and final survey to ensure that the area is truly clean. No conclusive evidence suggests that the building ever experienced other contamination probleras.

No.:

N704SRR990027 Page:

16 III. DECONTAMINATION EFFORTS Decontamination and deactivation of the Nuclear Materials Development

- Facility were initiated 'in November 1982. The progression of the decontamina-tion efforts was as follows:

(1) decontamination and then' removal of glove-boxes and connecting tunnels, including glovebox equipment, (2) removal of utilities and low-volume exhaust system, (3) decontamination of support area,

'(4)' disposal of NaK in glovebox atmosphere purifiers, (5) removal of liquid waste holdup system, and (6) removal of high-volume exhaust system. The waste generated during cleanup operations was packaged concurrent with the generat-ing operation and shipped for disposal at the discretion of Radioactive Materials Disposal Facility.

Decontamination of the glovebox surfaces was accomplished utilizing ALARA strippable paint. This proved to be'an effective and efficient method of sur-face decontamination.

Glovebox and tunnel section removal was completed in November 1965. Survey of the decontaminated gloveboxes was conducted to assure that they were not TRU waste and were within the criteria of LSA waste.

All components of the low-volume exhaust system, consisting of blowers,.

absolute filter' banks, and associated valves and controls, were removed except for the stack which was still linked to the high-volume exhaust system. This was completed in February 1985. The utilities that were removed and disposi-tiened included those used specifically for glovebox Loperations, i.e., cooling water, argon, helium, dry air, vacuum, and electrical and control wiring, and those utilities whicn serviced the glovebox room, i.e., compressed air, elec-trical power, lighting, PA system, phones, sprinklers, fire alarm circuits, radiation alarm system, and intrusion alarms.

Removal of utilities servicing the glovebox room was completed in November 1984.

All equipment and materials in the support area were surveyed and dispo-

-sitioned according to the level of activity found. This included furniture, sinks, light fixtures, and other office and laboratory equipment.

Decontami-nation of the support areas was completed in October 1984.

Only material with no-detectable radioactivity was disposed of as conventional waste.

No.:

N704SRR990027 Page:

17 Disposal of the NaK in the glovebox atmosphere purifiers and NaK bubblers required the installation of a special NaK disposal facility at the NMDF, incorporating remnants of the facility utilities and liauid taste system. The NaK bubblers were not only a problem because of c.hemical hazard of NaK but trace quantities of alpha materials were present which required stringent con-tainment. The NaK removal prccess involved a combination of evaporation of K and Na at ~900*F, steaming, and finally, a water rinse.

Following cleaning, tne bubblers were surveyed to verify them as LSA waste and transferred to the RMDF for packaging and staging for shipment to a disposal site. The process water generated during the removal of NaK f rom the bubblers was neutralized, transferred to the RMDF, and evaporated; the residual solids were packaged and staged for shipment to a disposal site.

Removal and neutralization of the NaK from the bubblers was accomplished in June 1986.

The removal of the liquid waste system required the removal of all drain lines between the various sources, for example, laboratory sinks and shower drains, and removal of the for process and storage tanks and their associated equipment. All component: were packaged and dispositioned as necessary.

Com-plete removal of the liquid waste holdup system was accomplished in May 1986.

The components of the high-volume exhaust system which were removed for dis-posal as LSA waste include the hood in the glovebox room; all filters, duct-ing, and controls associated with the hoods and filters; and ducting and con-trols in the glovebox room and vault.

The high-volume exhaust system removal, which was the final step of the decontamination effort, was accomplished in August 1986.

The contaminated waste generated on this program were shown to be within the requirements of low specific activity category with the exception of some process equipment from inside the gloveboxes. This process equipment was handled as TRU waste.

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No.:

N704SRR990027 Page: 18 IV.

SURVEY SCOPE A sampling inspection plan using variables, discussed in the next sec-tion, has been used to demonstrate that the' residual contamination in the building is below the following limits:

Alpha Beta

• Criteria (dom /100 cm)

Total, averaged over 1 m2 100 10,000 Total, maximum over 100 cm2 300 30,000 Removable over 100 cm2 20 2,000 The acceptable beta contamination limits were derived from alpha contami-nation limits presented in Annex B of USNRC license SNM-21 for U-nat, U-235, U-238, and associated decay products. The beta values are twice those of the alpha limits reported based on the two beta particles emitted from the decay of Th-234, the first daughter of U-238, and Pa-234. The alpha limits cor-respond with the license annex limits for transuranics.

For the sake of the NMDF analysis, the building was divided into three

. sample areas: The office area and Rooms 128, 132, 133, and the air condition-ing room (all unposted areas); the glovebox room (posted); and Rooms 117, 118, 119,120,121,122,123,124,126,129, and 130 (remaining posted areas).

For each of the three sampling lots, the office area (unposted), the glovebox room (posted), and the remaining posted areas, a minimum of an 11%

survey was conducted on the walls, floors, and ceilings.

Figure 4 pictorially shows the sample lots. The sampling inspection plan that was used is based 2

2 upon a uniform 3-m grid superimposed on the inspection area.

A 3-m grid has been adopted to be consistent with guidance provided in NRC and State of California documents. The grid was superimposed on the wall, floor, and ceil-ing of each room.

Each survey area was identified in matrix notation with

No.:

N704SRR990027 Page:

19 codes indicating the surface (F = floor, C = ceiling, N, E, S. W = north, east, south, west, respectively) and a two-figure Cartesian coordinate indi-cating the distance in meters from a local benchmark. The (1,1) position for the floor was benchmarked as the northwest corner of the room; an identical grid was reflected onto the ceiling. The (1,1) position of the walls was benchmarked as the top left hand corner of the wall as an observer would view 2

2 it from the middle of the room.

From each 3-m grid, a 1-m was surveyed; 2

hence, a minimum 11% survey. Each 1-m area was surveyed for 5 min and a 2

100 cm area was smeared for removable contamination.

A.

DATA ACQUISITION 2

2 Within each 3-m grid, a single 1-m area was surveyed.

Each area was outlined by paint, with its coordinates marked beside the area. The loca-2 tion of the 1-m area was left to the surveyor's judgment.

It was to be the area, in his judgment, that was most likely to have retained the most residuai 2

contamination of any similar area within the 3-m grid. The surveyor was instructed to do this conscientiously to assure that any significant residual contamination would be detected before a report of acceptability was made to a regulatory agency. The use of a predetermined grid with discretion for the exact location provides a uniform survey biased toward the high end of the 2

distribution. Selection of the 1-m area out of the nine within each grid square provides an 11% sampling.

If a particular surface of a room was smaller than 9 m2 (3m x 3m), a minimum of 1 m2 was surveyed for contamina-tion; in rr.any cases within the office area, where a wall measured typically 6 m, the sampling area was 17%.

In order to determine the level.of effectiveness of the decontamination 2

effort, four radiological characteristics were measured for each m ; average alpha surf ace activity, average beta surface activity, removable alpha surf ace activity, and removable beta surface activity. An alpha probe and beta probe were each connected to Ludlum 2220-ESG scalers for these measurements.

No.:

N704SRR990027 Page:

20 Measurements of the average alpha surface activity were made by use of a large-diameter (9.6-cm) alpha scintillation detector, sensitive only to alpha particles with energy exceeding about 1.5 MeV. This detector was calibrated by use of a Pu-239 alpha source. The energy of the Pu-239 alpha particles (5.1 MeV) is similar to that of the isotopes which are alpha emitters handled at the NMDF; Pu-238, Pu-239, Pu-240, Pu-242, and U-238 (DU).

Measurements of the average beta surface activity were made by use of a thin-window pancake Geiger-Mueller tube. While this detector is equally sen-sitive to alpha and beta particles and slightly sensitive to X-and gamma-rays, it is so predominately used to measure beta-activity that it is generally called a " beta-detector." This detector was calibrated by use of a Tc-99 beta source. The energy of the Tc-99 beta particles (maximum 0.3 MeV) is close to those from the U-238 ' daughters, Th-234 (maximum 0.2 MeV) and Pa-234 (maximum 0.5 MeV). The measurements were made over the same area as was used for each measurement of average alpha surface activity.

Measurements of removable surface activity (alpha and beta) were made by 2

wiping approximately 100 cm of surface area, using a Nucon-type cloth disk (NPO cloth sampling sinears 2 in. diameter). The activity on the disks was measured using a thin-window gas-flow proportional counter, calibrated using larger diameter Pu-239 and Tc-99 sources.

In order to f acilitate the survey, the alpha and beta probes were con-nected by a face plate such that the separation distance was no greater than a 2

couple of cm.

Each m was surveyed using the assembly for 5 min; this cor-responds to a transit velocity of approximately 3.3 cm/s. The ANSI draft standard N13.12 states that the transit velocity (in cm/s) shall not exceed one-third the numerical value of the detector window dimension (in cm) in the direction of the scan. The diameter of the window is 10 cm, and therefore, this transit velocity complies with the standard. The number of counts registered by the instrument in a 5-min scan were recorded by location.

If a contaminated spot was detected during the course of the " average scan" survey, the location was identified; subsequently, a 5-min stationary survey of the

~

No.:

N704SRR990027 Page:

21 2

location was conducted. The average surface activity of the m, the maximum 2

surface activity of one spot located within the m, and the removable activ-2 2

ity of 100 cm in the m were recorded.

2 In order to report the results in disintegrations / min per 100 cm.

2 (dpm/100 cm ), conversion factors were applied as follows.

First, " natural background" was determined by measurements made in an area of the building which was known to be uncontaminated. Second, an efficiency factor for the survey instrument was calculated by comparing the number of counts recorded by the instrument to the number of disintegrations yielded by a calibration source. These detertninations were made three times each day; first thing in the morning, at noon, and just before quitting time in the evening. Third, the correction factor for the area of the window was calculated in order to 2

present results per 100 cm,

Thus, for the surface contamination measurements of alpha and beta activ-ity, data included the sample location, the total counts recorded in the 5-min scan, the maximum hot spot, natural background for 5 min, efficiency factor, and the area factor. The same data was recorded for the removable contamina-tion measurements except for the area factor, which is not applicable for the gas proportional detector since the sample size and check source size are very nearly equivalent.

B.

DATA REDUCTION The data was entered into VISICALC, a spreadsheet software program on the IBM PC.

Columns were established to calculate the total, maximum, and remova-2 ble contamination per 1-m in dpm/lD0.cm. The standard error associated with the measurement was also calculated.

~

1 No.:

N7045RR990027 Page:

22 Data input:

1.

Room number 2.

Grid location, example N(1,3) 3.

Alpha total activity, averaged over 1 m2 (counts in 5 min) 4.

Alpha maximum activity for hot spot (counts in 5 min)

.5.

Alpha removable activity (counts in 5 min) 6.

Beta total activity, averaged over 1 m2 (counts in 5 min) 7.

Beta maximum activity, averaged over 1 m2 (counts in 5 min) 8.

Beta removable activity (counts in 5 min) 9.

Alpha survey instrument background (5 min), efficiency factor.

(dpm/ cpm), and area factor 10.

Alpha gas-proportional detector background (5 min) and efficiency factor (dpm/ cpm) 11.

Beta survey instrument background (5 min), efficiency factor

-(dpm/ cpm), and area factor 12.

Beta gas-proportional detector background (5 min) and efficiency factor (dpm/ cpm).

Output:

1.

Alpha total activity averaged over 1 m2 with standard deviation (dpm/100 cm2) 2.

Alpha maximum activity and standard deviation (dpm/100 cm2) 3.

Alpha removable activity and standard deviation (dpm/100 cm2) 4.

Beta total activity averaged over 1 m2 with standard deviation (dpm/100 cm2) 5.

Beta maximum activity and standard deviation (dpm/100 cm2) 6.

Beta removable activity and standard deviation (dpm/100 cm2),

No.:

N7045RR990027 Page:

23 The counts observed for the alpha and beta surface activity were con-2 verted to dpm/100 cm by:

t SA = (C - 8) E (100)

(Eq. 1) where:

SA = surf ace activity (this is applied to either the average or maximum activity)

C = total count in 5 min 5 = count time, min B = background count in 5 min (generally 0-5 for alpha and about 440-460 for beta)

E = ef ficiency factor, dpm/ cpm (averages about 4.4 for alpha and about 4.3 for beta) 2 100 = 100 cm standard area A = probe sensitive area (71 cm for Ludium model 43'-l circular alpha scintillator; 20 c,2 for Ludlum model 44-9 pancake G-M).

Note that the analysis is done using counts rather than count rates. The 2

standard error or deviation of the measurement in dpm/100 cm is given by:

d2+B2 C

E (100)

(Eq. 2) 5 A

(

-0 o

No.:

N704SRR990027 Page:

24 The results of the smears counted by the gas-flow proportional counter for the alpha and beta removable surface activity were converted to 2

dpm/100 cm by:

SA = (C - B)(E)

(Eq. 3) 5 where the appropriate alpha and beta background and efficiency factos were used.

Backgrounds are typically 0-2 counts for alpha and 120-150 counts for beta in a 5-nin time period.

Efficiency factors are about 3.5 for alpha and 3.9 for beta. Theoretical standard deviations were also calculated.

Software was developed to read the data output from the Visicalc file 2

into a graphics utility which plots the activity (dpm/100 cm ) against the Gaussian cumulative distribution function (cdf) on a probability scale.

For convenience, the distribution function, F(x), is plotted as the abscissa (probability grades), and x, the activity, is plotted as the ordinate (linear grades). The Gaussian function plotted in the following section takes on the shape of a straight line due to the orientation of the axes and the nonlinear x-axis.

C.

DATA ANALYSIS From the plot of activity vs. cumulative probability, the mean contamina-tion value of the lot is the value on the ordinate axis where the distribution intersects the 50% cumulative probability.

The figures oisplay the results on an expanded scale so that the variations in the data can be seen in detail.

The distribution is analyzed in terms of sampling inspection, " inspection by variables.". The test is satisfied if the Gaussian straight line (clearly l

visible in the figure) passes below the intersection of the upper limit U on the y axis and 93% cumulative probability.

In most cases, however, the upper limit is off scale on the graphs presented; the area is well below contamina-tion limits.

l l

l l

l

a, No.:

'N704SRR990027 Page:

25 The test statistic x + ks is compared to the acceptance' limit U, where:

x = average (arithmetic mean of measured values) s = observed sample standard deviation k = tolerance factor calculated from the number of samples to achieve desired sensitivity to the' test U = acceptance limit.

The State of California has stated that the consumer's risk of acceptance (B) at 10% defective (LTPD) must be 0.1.

For these choices of B and LTPD, Kg=K2 = 1.282. The number of samples is n.

Values of k for each sample size are calculated in accordance with the following equations:

2 K2+

K - ab

_K K

k=

a = 1 2 ( n-1 )

b=K -

B (Eq. 4) 2 2

n where tolerance factor k

=

The normal deviate exceeded with probability of 8, 0.10.

K2

=

(from tables, K = 1.282)

The normal deviate exceeded with probability equal to the LTPD, K

=

g 10% (from tables, K = 1.282) n = number of samples The criteria for acceptance are r >sented as a plan of action. The plan of action is:

1)

Acceptance:

If the test statistic (x+ks) is less than or equal to the limit (U), accept the region as clean.

(If any single measured value exceeds of the limit, decontaminate that location to as near background as is possible, but do not change the value in the analysis.)

l l

l

No.:

N7045RR990027 Page:

26 2)

Collect additional measurements:

If the test statistic (i+ks) is greater than the limit (U), but i itself is-less than U, independently.resample and combine all measured values to determine if x+ks < = U for the combined set;.if so, accept the region as clean.

If not, reject the region.

3)

Rejection:

If_the test statistic (x+ks) is greater than the limit (U) and x > = U, reject the region.

In additior, to the formal survey measurements made for computerized data reduction, search and survey techniques were conducted throughout the building on special structural features and components where contamination might have deposited. Applicable correction factors were used to convert the counts 2

recorded into meaningful data units (dpm/100 cm ).

If the area being measured was contaminated to a level which was 80% of the acceptance limit, the result was recorded and the area decontaminated to ALARA principles.

6 l

l l

m

e o

No.:

N7045RR990027 q

Page:

27 k

V.

SAMPLING INSPECTION i

i A.

' COUNTING STATISTICS 4

The emission of-atomic and nuclear radiation obeys the rules of quantum theory. As a result of this, one can only determine the probability that an emission will occur.

If one attempts to measure.the number of particles emit-ted by a radioactive source, that number is not constant in time; it has a statistical variation because of the probabilistic nature of the phenomenon c

under study. The number of particles emitted per unit time is different for successive units of time. Therefore, one can only determine the average num-ber of particles emitted per unit time and.per unit area.

Because.of the-probabilistic nature of particles emitted by radioactive elements, repeated measurements of the average number of emissions per unit time will show a distribution approximated by the -Gaussian (or normal). probability density function (pdf). -If measurements are made at many similar locations, these measurements will generally show a somewhat greater variability, but the distribution will remain adequately represented by a Gaussian function.

Thus the number of occurrences of particular contamination values, f(x),'shows a

-Gaussian pdf relative to the contamination value, and the data can be plotted accordingly. Subsequently, based on the results of the data analysis, a conclusion can be made regarding the level of residual contamination in the building.

1 The Gaussian distributiin, g(x), is given by:

1 I

g(x)dx =

exp

- *~"

dx 2

(yf2?.)o 2E I

l

. - ~. -. - - - -

No.:

N704SRR990027 Page:

28 where probability that the value of x, the measured value, lies g(x)dx

=

between x and x + dx Average or mean of the distribution m =

2 Variance of the distribution.

a

=

A graph of g(x) vs x gives the following bell-shaped curve:

i l

8 h

r=o 4, o.s i

.i i

x o

m-omm+o x x+dx x

Figure 6.

The Gaussian Probability Density Function Furthermore, the cumulative distribution function (caf), G(x), (equal to the integral of the pdf, for a continuous random variable) is:

X G(X) =

g(x)dx

-~

P(x <= X)

=

l This function is commonly referred to as the error function, (erf). The graph l

of the Gaussian cdf is:

No.:

N704SRR990027 Page:

29 3as - - - - - - - -,

i l

i 0

x=m x

Figure 7.

The Gaussian Cumulative Distribution Function If x is the survey measurement (in the case of radiation measurements, the number of counts), the standard deviation of the measurement is the square root of x.

Background radiation must also be considered to calculate the net number of counts. Thus, the error, or standard deviation associated with the

. measurement, becomes:

S=!C

+B (Eq. 5)

T where C = The number of counts recorded in time, T, of the sample B = The number of counts recorded in time, T, of the background radiation environment T = Time of count, assumes the sample count time is equal to the back-I ground count time.

Finally, corrections must be made for instrumentation parameters including geometry and efficiency.

/

.o No.:

N704SRR990027 Page:

30

~

B.

SAMPLING INSPECTION BY VARIABLES Acceptance inspection by variables is a method of judging whether a lot of items is of acceptable quality by examining a sample from the lot, or popu-lation.

In the case of determining alpha contamination in the NMDF, it would be unacceptably time consuming and not cost effective to measure and document 100% of the building. ~ However, by applying sampling inspection by variables methods, the confidence of the conclusion made about the level of contamina-tion is not sacrificed due to the decrease in number of sampling locations.

In acceptance inspection by attributes, the radiation measurement in a given area is recorded numerically and classified as either being defective or nondefective, according to regulatory acceptance criteria. A defect means an instance of a failure to meet a requirement imposed on a unit with respect to a single quality characteristic. Second, a decision is made f rora ths number of defective areas in the sample whether the percentage of defective areas in the lot is small enough for the lot to be considered acceptable.

In accept-ance inspection by variables, the result is recorded numerically and is not treated simply as a boolean statistic, so fewer areas need to be inspected for a given degree of confidence in judging a lot's acceptability.

The test statistic, x + ks is compared to the acceptance limit U, where:

x = average (arithmetic mean of measured values) s = observed sample standard deviation k = tolerance factor calculated f rom the number of samples to achieve the desired sensitivity for the test U = acceptance limit.

4

o No.:

N704SRR990027 Page: 31 The sample mean, standard deviation, and acceptance limit are easily cal-culable quantities; the value of k, the tolerance factor, bears further dis-cussion. Of the various criteria for selecting plans for acceptance sampling by variables, the most appropriate is the metaod of Lot Tolerance Percent Defective (LTPD), also referred to as the Rejectable Quality Level (RQL). The LTPD is defined as the poorest quality in an individual lot that should be accepted. Associated with the LTPD is a parameter referred to as consumer's risk (B), the risk of accepting a lot of quality equal to the LTPD. USNRC Regulatory Guide 6.6 states that the value for the consumer's risk should be 0.10.

Conventionally, the value assigned to the LTPD has been 10%. These a priori determinations are consistent with the literature and regulatory posi-tion and are the same values used by the State of California.(2) Thus, based on sampling inspection, we are willing to accept the hypothesis that the probability of accepting a lot as not being contaminated which is in f act 10%

defective is 0.10.

The value of k, which is a function of the a priori deter-minations made for 6 and LTPD is given by Equation 4 in the previous section.

Figure 8 demonstrates.this principle. The operating characteristics curve of a Gaussian sample distribution shows the principles of consumer's and producer's risk, in addition to LTPD and the acceptable quality level. The criteria for acceptance of a lot are presented in Section IV.

The coefficients K and K are equal because of the choice for the 2

g values of 6 and LTPD as 0.10.

Statistics textbooks listed in the reference section (5-7) provide additional explanation of this sampling principle. The

(

a priori values chosen for the sampling coefficients are consistent with industrial sampling practice and regulatory guides.

l I

No.:

N704SRR990027 j

Page:

32 1

0 0.95 td PRODUCER'S RISK u

e z

i i

6-1 Q.

I ld i

U i

N i

1 g

O t

-l

'~

3

-l 1

m i

O I

g l

CONSUMER 5 RISK i

o.E l

O.10 ---+-------r---

i i

OO AOL ROL p= LOT FRACTION DEFECTIVE Figure 8.

Operating Characteristics Curve

.O o

No.:

N7045RR990027 Page: 33 VI.

PROCEDURES The following procedures were used in performing this survey.

(Reference supporting document, N704DWP990084, " Final Radiological Survey Detailed Work Procedure").

A.

CALIBRATION AND INSTRUMENT CHECKS Instrument qualification data sheets were recorded for each background and source check.

Instruments used for the final survey were calibrated and checked a minimum of every morning, noon, and evening for the duration of the project as.follows.

Portable Survey Instruments (Ludlum 2220-ESG Scalers):

1)

Turn the instrument 'ON' and allow to warm up for 5 min.

2)

Check high voltage (700-750 V alpha,-800-950 V beta).

3)

Check threshold (140-190 alpha, 250-350 beta).

4)

Window in/out switch is set to out.

5)

Check battery (greater than 500).

6)

Set range selector to 1, response to fast, and count time to 5 min.

7)

Take and record a 5-min background count in an uncontaminated area which typifies the area to be surveyed.

8)

Take and re:ord a 5-min count of known alpha and beta stand-ards; an electroplated Pu-239 and electroplated Tc-99 source, respectively. The. efficiency factor (dpm/ cpm) is calculated as the ratio of 2 times the 2w emission rate of the source (dpm) to the net count rate of the instrument. The radio-activity of the calibration sources is traceable to NBS.

No.:

N704SRR990027 Page:

34

.9)

Calculate the area of the end window and record value.

(This is performed only once for each probe type.).

Gas-flow Proportional:

1)

Equipment is to be left in the '0N' position at all times.

2)

Using uncontaminated planchets, take four 5-min background counts.

3)

Take and record 5-min counts of known alpha and beta stand-ards; 2-in. Pu-239 and Tc-99 sources, respectively.

Calcu-late ef ficiency factors accordingly.

Average the Daily Results:

Calculate the average background and efficiency factor of each instrument for morning and afternoon. The morning value should be the average of the 7:00 a.m. and 11:30 a.m. measurements; the af ternoon value should be the average of the.1:30 a.m. and 16:00 p.m. measurements.

B.

AVERAGE CONTAMINATION MEASUREMENTS

~

1)

Identify 1-m2 area to be measured:

1m2 2

per 9 m sur-f ace should be surveyed to be consistent with a minimum 11%

sampling plan.

2)

With portable scalar instrumentation (Ludlum '2220-ESG) set for 5-min count time, using an alpha probe (Ludlum Model 43-1) on one instrument and a beta probe (Ludlum 44-9) on another, uniformly scan the area.

(Watch and listen for

" hot spots" where radioactivity may exceed the average limit. These are to be resurveyed later.)

l 3)

Record the location, total count, background, ef ficiency factor, area factor, and date/ time.

4)

Enter the data into Visicalc spreadsheet.

No.:

N704SRR990027 Page: 35

- C.

MAXIMUM CONTAMINATION MEASUREMENT 1)

Return to any-area identified as having a " hot spot."

2)

Repeat the-uniform scan of only the hot. spot area, covering approximately 100 cm2 with the probe.

3)

Record the location, total count, background, efficiency f actor, area factor, date/ time, and maximum contamination

.value.

4)

Enter the data into Visicalc spreadsheet.

D.

REMOVABLE CONTAMINATION MEASUREMENTS 1)

Using an NPO 2-in.-diam cloth swipe, wipe an "S" pattern, with legs approximately 6 in. long, so as to sample removable i

contamination f rom an area of approximately 100 cm2 within the 1-m2 grids identified and sampled with the survey meters.

2)

Place smear in envelope kit and record the location of the sample grid on the envelope. Save until ready for counting.

4 3)

Count radioactivity using gas-flow proportional' counter (NMC Model ACS-77) for 5 min.

4)

Record the location, total alpha and beta counts, background, and efficiency factors for each.

5)

Enter the data into Visicalc spreadsheet.

i E.

MISCELLANEOUS GAMMA QUALIFICATION INSPECTION 1)

As necessary, collect various samples of debris, dirt, and other material which indicate detectable alpha activity.

Because Pu and DU were the only radioactive materials handled at the facility, it is desirable to qualify the measurement.

2)

Place the sample in the calibrated high-purity germanium (HPGe) detector and use the multichannel analyzer to qualify the radioactive material.

4 4

- - - - - - - - - _ -,.. -. ~ -,, _ - _,. - - - _. - _. -,, _ _ _ -. _. - -.. _ _ _. _ _ _ _ - - - -

O No.:

N7045RR990027 Page: 36 F.

SURVEYS OF SPECIAL STRUCTURAL FEATURES AND COMPONENTS 1)

Using a Ludlum Model 12 count rate meter in connection with a Ludlum Model 43-5 rectangular alpha scintillation probe, sur-vey various building features and components'which are sus-pect of containing residual contamination.

2)

Perform an instrument calibration check three times daily using the Pu-239 source mentioned above.

3)

Ensure that the transit velocity (in cm/s) does not exceed one-third the numerical value of the detector window dimen-sion (in cm), in the direction parallel to the motion of the probe.

-c

.n..

., ~, - -

3 e

No.:

N7045RR990027 Page:

37 VII. SURVEY RESULTS A.

STATISTICAL RESULTS The survey of the NMDF was conducted using the survey plan previously described. A summary of the survey results appear below in Tables 1 through 3 for each of the inspection lots. The results used in the mathematical statis-tical analysis are shown in Appendix A.

TABLE 1

SUMMARY

OF SURVEY RESULTS (Office Area and Other Unposted Areas) 2 (dpm/100 cm )

Inspection Number of Average Maximum Test Measurement Location Value Value Statistic Limit Average alpha 141 2.6 14 8.1 100 Maximu'm alpha 0

300 Removable alpha 141 0.3 4

2.3 20 Average beta 141 54.3 1065 744.2 10000 Maximum beta 0

30000 Removable beta 141 5.2 34 19.2 2000 TABLE 2

SUMMARY

OF SURVEY RESULTS (Glovebox Room) 2 (dpm/100 cm )

Inspection Number of Average Maximum Test Measurement Location Value Value Statistic Limit Average alpha 202 7.1 94 23.6 100 Maximum alpha 11 1067 300 Removable alpha 202 0.5 11 2.4 20 Average beta 202 364.5 1361 1156.8 10000 Maximum beta 0

30000 Removable beta 202 5.1 36 20.5 2000

No.:

N704SRR990027 Page: 38 TABLE 3

SUMMARY

OF SURVEY RESULTS (Posted Areas) 2

.(dpm/100 cm )

Inspection Number of Average Maximum Test Measurement Location Value Value Statistic Limit Average alpha 201 5.7 140 26.7 100 Maximum alpha 11 10465 300 Removable alpha 201 0.4 15 E.4 20 Average beta 201-183.9 1431 978.6 10000 Maximum beta 9

41664 30000 Removable beta 201 3.4 28 18.6 2000 Because the number of hot spots discovered were few in number,-the aver-age value and inspection test statistic were not calculated; both values are meaningless. Table 4, however, lists the hot spot locations and_ corresponding levels of contamination. The hot spots found were smaller in area than the detector end window, thus the reported value is greater by a factor of 1.4 for alpha and 5 for beta such that the neasurement result is extrapolated to an 2

area equal to 100 cm,

In all cases where contamination was determined to be 80% of the accept-ante limits, the area was decontaminated to activity levels below the instru-ment detection limit. From the smears taken during the survey, no removable activity was found throughout the building.

l The survey data for each test characteristic are displayed as cumulative distribution functions in Figures 9 through 20. These figures show each sur-vey value, arranged in order of magnitude f rom lef t to right, and a straight line representing the derived Gaussian distribution.

In most cases the acceptance limit is substantially above the top edge of the graph; the graph is bounded in the positive y direction by the greatest measurement taken for that lot. The mean of each distribution is that value on the ordinate which L

l 6

e No.:

N704SRR990027 Page:

39 TABLE 4 MAXIMUM SURFACE ACTIVITY (Hot Spots) 2 (dpm/100 cm )

Location Alpha Beta Comment 127 E5,14 239 0

Orig, survey, paint sampled 127 E5,13 598 0

Add'1 survey, paint removed 127 E5,15 1067 0

Add'l survey, paint removed 127 ES,16 140 0

Add'l survey, paint removed 127 S1,1 87 0

Beam, contamination removed 127 S1,8 102 0

Beam, contamination removed 127 B2S10 58 0

Beam, contamination removed.

~

127 B3N6 79 0

Beam, contamination removed 127 B3516 29 0

Beam, contamination removed 127 B4N15 118 0

Beam, contamination removed 127 B4S6 146 0

Beam, contamination removed 126 F3,4 10465 1

Cleaned to NDA.. add'l surveys 130 F7,2 236 2

Cleaned to NDA, add'1 surveys 129 S1,2 0

1230 Cleaned to NDA VAULT F1,3 42 0

Cleaned to NDA, add'l surveys VAULT FS,3 0

41664 Cleaned to NDA, add'l surveys HOLDUP F4,3 92 0

Surveyed add'1 locations HOLDUP F6,5 191 1826 Surveyed add'1 locations HOLDUP F1,3 23 0

Surveyed add'1 locations HOLDUP F4,1 68 1742 Surveyed add'1 locations HOLDUP F4,2 94 1247 Surveyed add'1 locations HOLDUP F3,3 49 1333 Surveyed add'l locations HOLDUP F3,4 113 882 Surveyed add'l locations HOLDUP FS,2 158 1333 Surveyed add'l locations NDA: No Detectable Activity l

t

NMDFBLDF AVERAGE ALPHA ACTIVITY (0FFICE AREA UNP0STED) 14 s

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N704SRR990027 Page: 44 i

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No.:

N7045RR990027 Page:

52 corresponds to a 50% cumulative probability of the abcissa. One, two, and three standard deviations above the mean corresponds to 84%, 97.7%, and 99.8%

cumulative probability, respectively. The value of k used in the inspection test is very nearly 1.5 for each case; thus, the "k" line will run perpendicu-l lar to the abcissa corresponding to about a 93.3% cumulative probability. The Gaussian distribution line must pass below the intersection of the "k" line (about 93%) and the horizontal line showing the acceptance limit at that point in order to accept the lot as being noncontaminated.

For all survey result characteristics, the test statistic, x + ks, is well below the acceptance limit, U.

Th'e results summarized in these tables and graphs confirm that all areas are acceptable for release for unrestricted use at the present time.

Many times, because of the conservative action level we n:aintained (80%

of the acceptance level), additional samples were taken.

Areas of increased sampling are discussed in the following subsection, B.

Additionally, various components and special features of the building were qualitatively surveyed to 2

determine possible contamination problems in areas beyond the 1-m grids surveyed for statistical analysis. Concurrent with the final survey, addi-tional decontamination was performed. Finally, interesting anomalies were identified during the course of the final survey; these occurrences are described in Subsection E.

B.

AREAS OF INCREASED SAMPLING Sampling was increased above 11% in several areas of the building if either a square-meter grid was found to be contaminated to values exceeding 80% of the acceptance limits or if a particular section of the building was known to have experienced a contamination incident. Sampling was increased in two areas of the building which were suspect of containing residual contamina-tion from contamination incidents:

fourteen additional floor samples were collected near the east wall of the glovebox room where the glovebox overpres-surization incident took place; five additional floor samples were collected in the s'.cinity of the location of the vacuum pump, where a seal leaked oil and released contamination.

The samples collected above were not taker as a result of a positive indication of contamination. All 19 samples were included in the statistical analysis; no detectable activity was found.

~

No.:

N704SRR990027 Page:

53 On the other hand, additional sampling was performed in six separate location due to contamination results exceeding 80% of the acceptance criteria. The additional action taken upon discovery of the contamination is-summarized in Table 5.

TABLE 5 ADDITIONAL SAMPLING LOCATIONS Contamination Level Additional 2

Location (dpm/100 cm )

Measurements Results Rm 130 F7,2 236 alpha max F8,2 F7,1 F6,3 No hot spots found avg. alpha = 20 HOLDUP 49 alpha avg.

F4,1 F4,2 F3,3 Activity fairly uniform at F6,5 191 alpha max F3,4 F5,2 about 50 alpha ave and up to 158 alpha max Rm 127 E5,14 83 alpha avg.

E5,13 ES,15 Contamination determined to 239 alpha max ES,16 ES,9 be localized to the bottom ES,11 E4,11 grid, south of the exit door E4,17 E5,17 and north of the support E3,15 E4,14 beam. Area was cleaned.

E3,13 E2,16 E2,12 E2,13 Rm 126 F3,4 140 alpha avg.

100% survey See Figure 21 for results 10465 alpha max of floor VAULT F1,3 16 alpha avg.

100% survey See Figure 22 for results 42 alpha max of floor FS,3 41664 beta max Note:

Refer to Appendix B for specific values of contamination.

In all cases, the additional samples collected demonstrate that the con-tamination (most of it below acceptance criteria) was fairly localized to the immediate area. As mentioned earlier, all areas determined to be contaminated to a level equal to or exceeding 80% of the acceptance limit were decontami-nated to levels below the instrument lower limit of detection. The only grid areas with residual contamination above the acceptance limit were localized hot spots on the floor of Room 126, on the east wall of Room 127, and on the floor of the vault.

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N3.:

N704SRR990027 Page:

55 N

Result 2

F1,1 F1,2 F1,3 Location (dpm/100cm )

g 1

42 alpha 2

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3 2250 beta 4

2025 beta 5

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l 9

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/

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g F5,1 F6,1 FIGURE 22.

SURVEY RESOLTS OF THE VAULT 100% FLOOR SURVEY n._,-

-.n.,.--..,

No.:

N704SRR990027 Page:

56 C.-

RESULTS FOR SPECIAL STRUCTURAL FEATURES AND COMPONENTS During the course of the formal finci survey, the surveyors determined special features and components to qualitatively survey with the Ludlum Model 43-5 alpha scintillator in conjunction with the Ludlum Model 12 count rate meter.

G-M probes were not. considered appropriate because no beta con-tamination had been detected during the course of the final survey, except-for the floor of the vault.

Table 6 summarizes the features surveyed and the results of the survey. NDA is conveniently used to designate areas of No Detectable Activity. The contamination level is presented in cpm. The area f actor for a planar surface is about 1.3; however, most of the objects sur-veyed were geometrically disproportionate and only came in contact with about' 10% or less of the end window..The phencmenon creates two problems when try-ing to estimate the amount of activity deposited on the surface in 2

dpm/100 cm ; first, chances are the alpha particle is depositing all of its energy in air before it reaches the detector; second, the geometry factor applied as the conversion factor is grossly approximated based on the surveyor's judgment. Thus, we use the concept of a qualitative survey; if we observe more than 5 or 6 cpm on the instrument, we conclude that contamination exists on the object, but most.likely below acceptance limits. The efficiency factor of the instrument is about 7 for Pu-239 alpha particles.

All contami-nated objects are cleaned and resurveyed. All findings are reported before further decontamination was performed.

f Of the various components and features surveyed, only three major areas l

were found as containing observable contamination levels: the fire extin-1 l

guisher mount on the east wall of Room 127, the unpainted tops of the sprink-

.ler pipes in Room 127, and the beams.in Room 127.

Remaining identifiable contaminated areas were cleaned and resurveyed to ensure a complete decontami-nation of the premises.

i i-

i No.:

N704SRR990027 Page:

57 TABLE 6

SUMMARY

OF VARIOUS EQUIPMENT AND FEATURES SURVEYED FOR CONTAMINATION (Sheet 1 of 3)

Alpha Contamination Level Location-(cpm)

The office area which includes Rooms 101, 102, 103, 104, 105, 106, 107, 108, 109, 110, 111, 112, 114, 116, f ront hall, and security. Surveyed tops of doors, door handles, corners of rooms, parts of the baseboards / floor, and electrical outletse NDA 102 2 (ea) 1-in. x 8-in. x 24-in, boards NDA 104 - ledges of plastic partitions, telephone service panel, closet, entry and exit passageways NDA 108 - wood cover mounted on west wall NDA 109 - sink, floor area of sink, cleaning supply shelves, top and under hot water heater NDA 111 - sink, shelf, floor drain NDA 112 "I" beam on west wall NDA 116 - two doors and 100% baseboard survey NDA Front Hall - ledges, door facings, electrical panels NDA 128 - top, bottom sides of miscellaneous equipment, electrical control panels, meters, water pump, valves, holes in walls, cracks in floor, ducting, tubing, removed section of fiberglass from inside of a/c exhaust duct for gamma spectroscopy NDA 132 - horizontal surfaces of EDG, top of batteries and pipes, fire extinguisher bracket, junction boxes, l

door threshold NDA 133 - holes in wall, conduit seals, top of transformer housings, fire alarm boxes, switch boxes, door and threshold, top of buss units NDA A/C - spot checked floor; walls; ceiling; top, bottom, and sides of a/c equipment; air intake; door NDA l

t

,._-,.---.--..-,_.-m._--

No.:

N704SRR990027 Page:

58 TABLE 6

SUMMARY

OF VARIOUS EQUIPMENT AND FEATURES SURVEYED FOR CONTAMINATION (Sheet 2 of 3)

Alpha Contamination Level Location (cpm) 117 - towel and soap dispensers, plumbing stools, sinks, trash can, miscellaneous floor and wall locations NDA 118 - instrument shelves, magnahelic unit, electrical outlets, plumbing, entry to shower,100% baseboard NDA 119 - overhead pipes, a/c supply duct, metal plate on floor,100% baseboard survey NDA 120 - door and door kickplate, electrical outlet,100%

baseboard survey NDA 121, 122, 123, 124 - 100% baseboard survey, various floor and wall locations, electrical control box NDA 126 - overhead pipes, beams, electrical conduit and junction box, a/c inlet,100% baseboard survey NDA BH - electrical panel, fire alarm box, fire extinguisher rack,100% baseboard survey NDA MEZRM - pipe, edge of beam, top of a/c ducting NDA 130 - light fixtures, all upper horizontal surfaces, beams, pipes, top of doors to high bay, floor cracks, thresholds, door handles,100% Daseboarc NDA survey 129 - facility exhaust stack, louvers to blowers NDA louvers to outside 10-30 threshold, inside pipe to-roof, cutouts in north wall, 100% baseboard survey NDA Vault - east wall south port 40 ledge above door, round port above door, north square port and round ports,100% basrboard NDA i

.~

^..:

No.:

N704SRR990027' Page:

59 s

TABLE 6

SUMMARY

OF VARIOUS EQUIPMENT AND FEATURES SURVEYED FOR CONTAMINATION (Sheet 3 of 3)

' Alpha Contamination Level Location (cpm)

'ExitE! entrance door' threshold 4-exit door threshold 4

porch 10-12 door jamb 6

ExitW - horizontal surfaces, door window ledges, handles, top of sprinkler, thresholds NDA HOLDUP - top of rails,; ladder rungs, bottom of gauge rack, drain sump in pit, wall studs in pit NDA 1271-beams'2, 3, and 4 (numbered from the north wall) 20-30 top of fire extinguishers, exit door locks 8

top of vault door 20 east wall fire extinguisher mounting board 6

baseboard on east wall at meter 14 60 baseboard on east. wall at meter 15 21 baseboard on west wall.- meter 10-16 7

Concurrent with the final survey, all flooring in the posted area was removed, the fire extinguishers and the mounts located in the glovebox room

- were removed, the fire protection sprinkler system in the glovebox room was removed, the beams in the glovebox room were scrubbed, lights were removed f rom Room 130, peint was removed f rom the east wall of the glovebox room, and

~

ed ur g he de on am nat nefr were found to be ea add ion, i

. the stack plenum is clean.

l During periods of rain, water samples were collected f rom around the building and analyzed for Am-241 in a ganne spectrometer.

The soil around the removed drain lines was analyzed previously and found to be well below release I

criteria of 25 pCi/g of Pu.(9)

All water samples contain no Am-241.

i i

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No.:

N704SRR990027 Page: 60L D.

ANOMALIES This~ section briefly describes the natural radiological phenomenon and miscellaneous limitations which have impacted the data reduction and analysis methods used in the final survey.

Because the range of alpha particles is so short, the instrument back-i ground for detecting the presence of alpha particles is typically very low, on the order of-no more than 2 counts per minute.

However, under certain atmospheric conditions (i.e., when a building is locked tight for the night),

radon tends to build up within the building.

During the -final survey, an increase in natural alpha background was observed in the morning for a period of a couple of hours, until the building could'be opened up and allowed to air out.

The activity tended to collect more towards the ceiling of the glovebox room.

Furthe rmore, the " natural" background of alpha radiation will be increased by natural activity, such as Th-232 in shower tile located in 4

Room 119.

During the survey, we noticed a substantial increase in the alpha count. rate when-placed directly over the shower. tile. A tile sample was taken and analyzed in a gamma spectrometer.

The r.esults showed conclusively the presence of ' Ac-228, a daughter of Th-232.

The tile was not removed, and the data was not used in the analysis.

In the case of the outside intake louvers on the exhaust stack, an increase in activity was observed.

This phenomenon is to be expected due to the large flow rates of bypass achieved through the damper assembly.

Insofar as the distribution of low-level alpha activity is present on this equipment, we can only conclude that it is due to the natural environmental ' radioactivity.

A few difficulties in the survey were experienced.

The entrance ways to Rooms 128,132, and 133 are standard 7.5-ft doors, and the man-lif t could not be moved into these rooms.

The ceilings in each of these rooms is 16 ft.

The top two meters and the ceilings were not surveyed in these rooms.

Because these areas were unposted and since no radioactivity was found, it is felt that this omission did not significantly affect the results of the analysis.

i

-e.

-...... ~,.,,, - -,. - - _ -.. _ -,,,. - _.,.,,, _,., - -, _., - - - _, - -..,

No.:

N704SRR990027 Page:

61 In regard to the hot spot problems observed on the east wall of the glovebox room, paint samples were taken and analyzed on a gamma spectrometer to deter-mine the amount of Am-241 in the sample.

Several additional surveys were per-formed in the area to determine the extent of the contamination and whether the first or second coat of paint was contaminated.

Evidently, the glovebox room was painted in about 1974, af ter the glovebox overpressurization inci-dent.

The paint condition at the present is very spotty due to excessive peeling f rom the concrete sweating phenomenon; in many places there is no paint, one coat, and two coats.

Consequently, the entire area was surveyed (approximately 16 m ) and detectable activity exceeding 80% of the acceptance criteria was removed.

4

t l

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No.:

N704SRR990027 Page:

62 VIII.

CONCLUSIONS An appropriate survey has been conducted throughout the area to be released. Although a few localized hot spots were detected, the results of

= this survey show statistically that no residual contaminaion remains in the area and demonstrate a negligible risk of there being any undetected contami-nation exceeding the acceptance limits. With the concurrence of the U.S..

Nuclear Regulatory Commission, the facility license will be voluntarily termi-nated and the area will be released for unrestricted use.

4 i

4

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No.:

N7045RR990027 Page: 63 REFERENCES 1.

" Guidelines for Decontamination 'of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material," Annex B, USNRC License SNM-21, Docket 70-25, issued to Energy Systems Group of Rockwell International, last~ revision June 5, 1984.

2.

" State of California Guidelines for Decontaminating Facilities and Equipment Prior to Release for Unrestricted Use," DECON-1, revised March 24,1983.

3.

" Draft American' Nationa'i Standard Control of Radioactive Surface Contamination on Materials, Equipment, and Facilities to be Released for Uncontrolled Use," ANSI N13.12, August 1978, American National Standards Institute, Inc.

4.

" Building - 055 Decontamination and Deactivation Plan," N704TI990061, J. W. Carroll, F. C. Schrag, and V. A. Swanson, Rockwell International, October 1,1982.

5.

" Selected Techniques of Statistical Analysis," Statistical Research Group, Columbia University, McGraw-Hill Book Co., Inc.,1947.

6.

"Some lheory of Sampling," W. E. Deming, Dover Publications, Inc., New York, 1950.

7.

" Statistics in Research,"

B. Ostle and R. Mensing, The Iowa State University Press, 1979.

8.

" Measurement and Detection of Radiation," N. Tsoulfanidis, Hemisphere Publishing Corp., Washington, D.C., 1983.

9.

" Radiation Survey for Release for Unrestricted Use L-85 "

N001SRR140087, F. E. Begley, Rockwell International, March 6,1986.

10.

" Plutonium Concentrations in Soil Around Drain Lines at NMDF,"

N704SRR9900124 R. J. Tuttle, Rockwell International, April 3,1986.

11.

" Final Radiological Survey Detailed Work Procedure," N7040WP990084, V. A. Swanson, Rockwell International, September 22, 1982.

0195Y/bes

4 No.:

N704SRR990027 Page: 64 APPENDIX A SAMPLING INSPECTION DATA GROUPED BY LOT The inspection data was entered into Visicalc, a spreadsheet program which runs on the IBM PC.

The output of the Visicalc program gives the data which follows in three lots:

one for the lot located in the unposted areas (office area, Rooms 128, 132, 133, Security, and the air conditioning room);:

one for the glovebox room; and one for the remaining posted areas in addition to the liquid waste holdup platform located outside the building.

The grid locations are identified in matrix notation by room; measurements were made on the floor (F), ceiling (C), north wall (N), east 2

wall (E), south wall (S), and west wall (W).

The beams in the glovebox room (127) were surveyed, identified by (B) (beam number) (south or north) (grid location), for example B1S9.

A few of the room number identifiers bear further explanation:

FH

- front hall (unposted);

4 SEC

- security building; A/C

- air conditioning room located above Room 126.

Accessible only from outside; VAULT - storage vault adjacent to the glovebox room; BH

- back hall, connecting Rooms 120, 121, 122, 123, 124, 126, and 127; MEZRM - a small room accessible from the mezzanine; EXITW - the west emergency exit from the glovebox room; EXITE - the east emergency exit from the glovebox room; HOLDUP - The liquid waste holdup tanks cement slab located outside of the building.

The output shows the alpha and beta total average contamination per square meter, maximum in one square meter, and removable in one square meter; the standard deviations of the measurement are also calculated.

I

Page 1 cf.4 Pages.

TABLE A 1 Sampling Inspection Results cf the effica area and ether unposted cr:as.

++++++++++++ ALPHA

+++4&+++++++++++++++++++++++++

BETA ++++++++++++++++++

ROOM GRID DPM/100CH2 DPM/100CM2 NUMBER NAME TOT

+/-

MAX

+/-

REM

+/-

TOT

+/-

MAX

+/-

REM

+/-

101 F1,2 6

3

-1 1

672 142 12 13 101 F5,3 4

2 2

2 55 133

-4 12 101 C1,2 4

5

-1 1

697 142.

-3 12' 101 N2,2 5

5 2

2 542 140 26 13 101 Ei,5

-2 4

2 2

533 140

'3 12 101 S3,3 9

3

-1 1

-365 126 5

13 101 W2,2 4

2

-1 1

-172 129 12 13 102 F2,1 1

1

-1 1

672 142

-7 12 102 F3,1 4

2

-1 1

-80 131 16 13 102 C3,1 5

3 2

2 235 136

-16 12 102 N2,2 4

5

-1 1

516 140 0

12 102 E2,2 1

4

.2 2

-116 130

-5 12 102 W2,1 8

3

-1 1

-210 128

-2 12 103 F2,2 4

5 1

2~

907 146

-1 12 103 F2,4 6

3 1

2

-88 130

-2 12 103 C2,2 0

4 2

2 211 135 16 13 103 N1,1 4

2 2

2 328 137 5

13 103 E2,2 O

O

-1 1

-129 129

-5 12 103 S1,1 O

O 2

2

-307 127 5

13 103 W3,4

-2 4

-1 1

-69 130 11 13 104 F1,3 6

3 2

2 580 138 9

13 104 F1,4 6

3

-1 1

819 144 10 13 104 F2,1

-1 1

-1 1

176 132 10' 13 104 F3,4 6

3

-1 1

294 136 2

12 104 C1,4 13 4

2 2

235 136 13 13 104 C2,1 3

3 2

2 374 135 25 13 104 N2,2 4

3

-1 1

294 133 9

13 104 E2,2 4

2

-1 1

-256 128

-4 12 104 S2,4 1

2 2

2

-365 123 3

12 104 SG3,3 1

3 0

1

.-572 125 O

12 104 NG2,2 O

O 1

1

-167 132 8

12 104 W2,2 3

3 2

2

-21 128 12 13 105 F1,2

-1 3

3 2

1065 151

-3 12 105 F3,2

-1 3

-1 1

387 141

-2 12 yy 105 C3,2 14 5

2 2

235 133

-8 12 g,,

105 N2,2 3

3 3

2 323 134 12 13 105 E3,1 0

2 3

2 76 130 5

12 2

105 S2,2 3

4

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-211 131

-7 12

'gyj 105 W3,1

-2 3

-1 1

-53 134 3

12 g-106 F2,2 5

4

-1 1

955 150 24 13 g

82

TABLE A 1 Ppge 2 cf 4 pages

++++++++++++ ALPHA ++++++++++++++++++++++++++++++ BETA ++++++++++++++++++

ROOM GRID DPM/100CH2 DPM/100CH2 NUMBER NAME TOT

+/-

MAX

+/-

REM

+/-

TOT

+/-

MAX

+/-

REM

+/-

106 F1,4

-1 1

-1 1

92 130 19 13 106 C2,2 1

3

-1 1

233 139

-2 12 106 N2,1 5

4 3

2 475 142

-8 12

~

106 E3,4

-1 1

-1 1

122 131 O

12 106 S3,1 1

2

-1 1

-214 125 17 13 106 W1,2 0

3

-1 1

502 143 6

12 107 F1,3 5

3 3

2 659 139

-14 12 107 F1,2

-1 1

-1 1

290 133

-6 12 107 C1,2 3

4

-1 1

356 141 6

13 107 N1,3 1

2 3

2

-332 123 1

12 107 E1,2 3

3 3

2 403 135

-1 12 107 S3,1 3

4

-1 1

-4 135

-3 12 107 W2,1

-1 3

1 1

-334 129 2

12 108 F3,2

-1 3

-1 1

801 147 21 13 108 F1,3 0

2 0

1 92 130 5

12 108 C1,3 4

3

-1 1

76 130 13 13 108 N1,2

-1 1

-1 1

-374 123

-12 12 108 E2,1

-1 1

3 2

-361 123 O

12 108 S1,1 0

3 3

2

-348 129 0

12 108 W3,2 0

3 3

2

-458 127 6

12 109 F2,1 1

2 0

1 924 143 1

12 109 C2,1 0

2

-1 1

231 132 4

13 109 E2,2 0

2 0

1

-613 118

-5 12 109 W2,2

-1 1

-1 1

-441 121 8

12 110 F1,1 3

4 0

1

-53 134

-6 12 111 F2,3

-2 3

1 1

783 147 21 13 111 C2,3 0

3

'-1 1

53 136 5

13 til N2,3 0

3 0

1

-282 130 14 13 111 E3,2 6

4

-1 1

-150 132 15 13 111 S2,1

-2 3

-1 1

-405 128 O

12 111 W2,3 0

3

-1 1

-365 129 1

12 112 F3,1 9

4

-1 1

582 136 11 13 112 F1,3 0

2

-1 1

76 130

-2 12 y2 112 C1,3 13 4

-1 1

248 133 5

13 3.O 112 N1,2 2

2

-1' 1

-267 123 13 13 112 E3,3

-1 1

-1.

1

-185 126

-12 12 2

112 Si,1 0

2

-1 1

-59 128

-5 12

.M 112 W2,3 2

2

-1 1

365 133

-17 12 114 F3,2 10 4

1 1

554 136 30 13 1

114 F1,2 4

3

-1 1

144 130

-2 12 P

.h 114 C3,2 9

4

-1 1

-66 126 0

12 e

i TABLE A 1 Page 3 cf 4 pages

++++++++++++ ALPHA ++++++++++++++++++++++++++++++ BETA

++++++++++++++t+4+

ROOM GRID DPN/100CM2 DPM/100CM2 NUMBER NAME TOT

+/-

MAX

+/-

REM

+/--

TOT

+/-

MAX

+/-

REM

+/-

114 N3,1 4

3 0

1

-566 118 6

12 114 E2,2 7

3

-1 1

-443 120 19 13 114 S1,1 11 4

O 1

-467 120

-2 12 114 W2,2 6

3 O

1

-357 121 10 13 116 F1,1 10 4

-1 1

767 139 10 12 116 C1,1 7

3 2

2

-189 124 10-13 l

116 N1,3 2

2

-1 1

-533 118 8

12 116 E3,1 1

2 0

1

-418 120 14 12 r

116 S3,2 2

2

-1 1

-332 122 14 13-116 W2,1-4 3

O 1

-82 126 12 13 af FH F2,9 4

3 1

1 726 138

-1 11 2

l FH F1,1 10 4

-1 1

238 131 3

12 l

FH F7,9 2

2

-1 1

33 128

-4 12 j

FH C1,1 5

4

-1 1

-357 136 5

13 FH C7,9 12 5

2 2 -1021 124 10 13 FH N2,3 4

3

-1 1

-312 122 8

12 i

FH N2,10 4

3 0

1

-361 121 8

12 FH j,

E3,4 2

2 0

1

-439 120 16 12

'I FH S3,2 5

3

-1 1

-230 124 7

12 l!

FH S2,12 4

3 1

1

-262 123 13 12-FH W2,3 5

3

-1 1

-422 120 17 12 SEC F2,3

-1 3

0 1

-994 125 12 12 i

SEC F5,1

-4 3

-1 1 -1044 124

-2 12 SEC F1,5 O

3 0

1 -1132 122 10 12-SEC F4,5

-2 3

-1 1 -1150 122 9

12 120 F1,4 11 5

1 1

701 141

-1 12 128 F4,2 7

5 1

1 937 145 11 13 128 F8,2 9

5 1

1 836 143 10 13 128 F12,3

'2 4

3 2

626 140 18 13 128 N4,4 2

4 0

1

-437 123

-3 12 i

^

128 E4,12

-3 3

0 1

403 137

-18.s 12 128 S3,3 2

4

.3.

2 470 138 10-13 128 W5,13

-1 4

0 1

-214 127 2

12 y,

128 W3,1 0

4

-1 1

-248 126

-11 12 3,o 132 F1,2

-1 4

1 1

819 143 5

13 to -

132 F3,4

-2 3

1 1

706 141 15 13 1

132 N3,2

-1 3

1 1

-395 123 5

13 cn6 132 NG,4

-1 4

1 1

470 138 5

13 "S

132 E4,1 0

3 1

1

-353 124 2

12 E'

132 E3,5

-4 2

O O

-399 123 17 13 E

132 S4,2 1

3 1

1 71 131 14 13 8-0 s

)

was e

.. _m TABLE A.1 Page 4 cf 4'pages

,4-

+

a-

++++++++++++ ALPHA ++++++++++++++++++++++++++++++' BETA ++++++++++++++++++

ROGM GRID DPM/100CM2 DPM/100CM2.

NUMBER NAME TOT

' +/-

MAX

+/-

REM

+/-

TOT

+/-

MAX

+/-

. REM

- +/-

132 S3,6 3

4 O

O 441 137

~ - 12.

12.

132 W4,3 1

3 4

2 403 136 12 13 132 W5,4 4

4 3

1 273 134

-7 12 133 F2,1 6

4 3

2 626 140 5

12 133 FS,3 8

4 1

1 1004 145 9

13 133 N4,1 5

4 2

1

-546 121

'7 13 133 N5,6 5

4 O

O

-403 123

-10 12 i

133 E3,2

-4 2

1 1

-412 123 5

13 133 E4,5

-3 3

O O

-483 122 6

13 133 SS,1 3

4 1

1

-437 123 6

13 133 S4,5.

-1 3

O O

-252.

126 31 13 133 W4,1 0

3 1

1 160 133 34

'13 133 W4,6 6

4 1

1 252 134 19 13 A/C FS,2

-4 4

15 6

0 1

518 141 1085 150 9

12 A/C F6,3 9

5 1

1 14 133 5

12 A/C C5,2 0

4

-1 1

99 134 12 12-A/C C6,3 2

5

-1 1

149 135

-11 12 A/C S2.,2

-1 4

1.

1

-72 131

-3 12 A/C W1,4 4

5 O

1 923 147

-1 12

.??

'.2. :.

E 5.'

sR

~

e c,

TABLE A,2 Sampling Inspecti:n R:sults cf the Glcv2 Box Room NMDF12

++++++++++++ ALPHA ++++++++++++++++++++++++++++++ BETA ++++++++++++++++++

ROOM GRID DPM/100CM2 DPM/100CN2 NUMBER NAME TOT

+/-

MAX

+/-

REM

+/-

TOT

+/-

MAX

+/-

REM

+/-

127 N1,3 1

4 2

1

-435 116 30 14 127 N2,5 4

4 1

1

-189 120

-3 13 127 N4,3 4

4

-1 1

-126 134

-12 13 127 N5,6 14 5

-1 1

-108 134 5

13 127 N3,9 14 5

0 1

-365 130 2

12 127 N1,11 13 5

1 1

-184 136 13 13 127 N3,13 20 6

-1 1

-491 128 2

12 127 N5,14 22 6

-1 1

9 136

-2 12 127 N2,17 5

4 1

1

-83 138 4

13 i

127 E2,1 6

5 O

O

-70 122 25 13 l

l 127 E3,1 14 5

-1 1

1004 152 12 13 127 E2,5

'7 5

O O

405 146 20 13 1

127 E3,7 0

3

-1 1

779 148 2

12 l

127 E1,10 16 6

O O

386 146

-8 12 127 E2,15 5

4 1

1 616 149

-2 12 127 E1,17 1

4 O

O 478 147 30 13 l

127 E2,19 4

4 1

1 667 150 2

12 127 E3,23 5

4 1

1 630 146 8

13 127 E3,27 6

4 1

1 369 142 9

13 127 E5,3 15 6

1 1

153 138

-5 12 127 E4,10 10 5

0 1

464 143 14 13 127 E5,14 83 11 239 18 3

2 554 145 10 13 127 E4,19 5

4 O

O 527 144

-7 12 127

.E5,25 6

4 O

O

.410 143

-2 13 127 S1,1 19 6

87 11 6

'2

-350 134

-9 12 127 S2,5 4

4 1

1

-419 132 0

12 127 S1,0 14 5

102 12 1

1

-14 139 10 13 127 S3,10

-1 3

1 1

-256 122

-12 12 127 S2,13 4

4 1

1

-607 129 1

12 127 S3,18 0

3 7-2

-34 126 4

12 127 SS,3

-4 3

1 1

-118 124 1

12 oz 127 S4,7

-2 3

1 1

-189 123

-5 12 cE.

127 55,12 7

5 O

O

-277 122 9

13 3"

127 S4,16

-4 3

O O

-386 120 5 ~

13 2

127 WI,2 1

4 O

O 322 145 13 13 127 W3,6

-1 3

O O

252 135 6

13 127 W2,7 0

3 1

1 124 142 26 13 58

]

127 W3,11 0

3 2

1 710 138 3

12 127 W1,14 O

3 O

O 474 147 9

13 a

127 W1,16 2

4 O

O 359 145 32 13 y

l TABLE A.2 Page'2 cf 5 pages 4+++++++++++ ALPHA ++++++++++++++++++++++++++++++ BETA ++++++++++++++++++

, ROOM GRID DPM/100CM2 DPM/100CH2 NUMBER-NAME TOT

+/-

MAX

+/-

REM

+/-

TOT

+/-

MAX

+/-

REM

.+/-

127 W3,19 2

4 1

1 605 136 7

13 127 W3,24

-2 3

O O

655 137 11 13 127 W3,26 5

4 0

0 403 133 18 13 127 W5,3 4

4 1

1

-130 124 3

12 127 W5,8 1

4 O

O 601.

136 19 13 127 W4,15

-2 3

O O

223 130 7

13 127 W5,21 0

3 1.

1 643 137 3-12 127 W4,27

-1 3

O O

357 132

.12 13 127 W1,29 4

4 1

1 623 133 3

13 127 F2,2 8

5 1

1 1041 139

-4 13 127 F1,5 1

4 O

O 779 135-

-4 13 127 F3,9 0

4 1

1 882 137

-2 13 127 C2,2 1

4 O

O

-205 120

-5 12 127 C1,5 0

4 4

2

-213 120

-5 12 127 C3,9 4

4 3

1

-303 118 16 13 127 F4,1 11 5

O 1

1025 140

-3 12 127 F5,5 8

5

-1

.1 1235 143 7

13 127 F6,7 5

4 1

1 869 138

-3 12 127 F4,10 9

5 0

1 1142 142 10 13 127 F4,14 5

4

-1 1

1046 140 1

13 127 FS,16 5

4

-1 1

1079

,141 9

13 127 F7,2 0

4 O

1 1256 143

-16 12 127 F9,4 9

5

-1 1

1100 141

-12

'12 127 F8,7 4

4 2

2 1079 141

-6 12 127 F7,12 5

.4

-1 1

1033 140

-2 13 127 F8,13 5

4

,1 1

714 135 14 '

13 127 FB,19 1

4

-1 1-1147.

142

-11 12 127 F12,2 8

5

-1

'1 1243 143 1

13 127 F10,5 3

4

-1 1

1138 142

-7 12 127 F12,9 5

4

-1 1

1109 141 0

13 127 F11,10 9

5

-1, i

1075 141

-12 12 127 F11,14 6

5 1

1 1042 140 7

13 127 F10,17 3

4 0-1 798 137

-2 13 E

127 F13,1 10 5

1 1

1037 140 5

13 T

127 F14,6 5

4

-1 1

832 137

-29 12 z

127 F15,8

-1 3

-1 1

1260 144

-1 13 J

127 F13,12

-1 3

1

.1 1067 141 17 13 0

127 F15,15 4

4 1

1 764 142 2

13

$y 127 F15,17 10 5

0 1

1058 141

-4 12 127 F17,3 0

4

-1 1

962 139 2

13 a

127 F16,5

-3 3

0 1

785 136 1

13 0

j

l TABLE A 2 Pag? 3 of 5 pages J. --

i

++F+++++++++

ALPHA ++++++++++++++++++++++++++++++ DETA ++++++++++++++++++.

ROOM GRID DPM/100CH2 DPM/100CM2 NUMBER NAME TOT

+/-

MAX

+/--

REM

+/-

TOT

+/-

MAX

+/-

REM

+/-

127 F18,9 5

4 1

1 1058 141 12 13 127 F16,10 5

4 1

1 1197 143 2

13 127 F17,13 15 6

1 1

1084 141 13 13' 127 F18,18 4

4 1

1 932 139

-10 12' i

127 F21,2 5

4

-1 1

991 140

-9 12 127 F20,5 8

5 0

1 1361 145 4

13 127 F19,8 4

4

-1 1

748 136

-12 12 l

127 F21,12 23 6

O 1

844 143

-4 12 127 F21,14 15 6

1 1

806 141

-7 12 127 F19,16 23-6

-1 1

899 142 9.

13 ii 127 F23,1 6

4

-1 1

853 141 6

13 l

127 F22,6 14 5

-1 1

903 142

-4 12 127 F23,6 15 6

1 1

764 140

-16 12 127 F24,6 10 5

0 1

1004 145 21 13 i i 127 F25,6 9

5 1

1

-727 139-13 13

'l 127 F23,9 6-4 1

1 790 140

-9 12 127 F24,11.

15 6

-1 1

773 140 4

13 127 F23,13 14 5

0 1

752 140-

-5 12-127 F23,19 15 6

1 1

773 140

-2 12

/

127 F25,2 10 5

1 1

966 139.

3 12 127 F27,4 9

5 1

1 1029 140 0

12 127 F26,8 6

4 O

O 823 143 27 13 127 F27,12 17 6

O O

1088 145 9

13 127 F25,13 16 6

2 1

941 143 7

- 13 127

.F26,17 9

5 1

1-928 144

-14 12 i!

127 F30,1 16 6

O O

538 137 3

12 l

127 F29,5 9

5 1

1 706 139 2

12 127 F30,9' 9

5 1

1 911 142 7

13 127 F30,10 14 5

1 1

815 141 9-13 680 141 5

. 13 127 F28,14 O

O

'O O

i 127 F29,17 7

5 1

1 798 141 5

13 127 C4,1

-1 3

0 0

0 142 14 12 127 C5,5 1

4 1

1

-163 129 8

12 EE' 127 C6,7 O

3 O

O

-405 135 1G 12 127 C4,10 5

3-1-

1

-99 130 15 12 i

I 127 C4,14 1

4 O

O

-230 138 36 13 d

l 127 CS,16 15 5

1 1

-456 124-20 12

~E i

127 C7,2

'5 4

1 1

-78 141 30 13 127' C9,4 6

4 1

1

-30 132 19 12 E

127 CB,7 5

3 1

1

-3'01 127 3

12 8

h 127 C7,12 7

4 1

1

-378 126 11 12 ey

.e...

.Ae

+.

TABLE A.2 Page 4 cf 5 pages

++++++++++++ ALPHA ++++++++++++++++++++++++++++++ BETA ++++++++++++++++++

ROOM GRID DPM/100CM2 DPM/100CM2 NUMBER NAME TOT

'+/-

MAX

+/-

REM

+/--

TOT

+/-

MAX

+#-

REM

+/-

127 C8,13 5

3 1

1

-413 125 7

12 127 C 8, 1 9.-

5 3

1 1

-318 127

.1 12 127 C12,2 4

3 O

O

-262 128

-8 12 127 C10,5 5

3 O

O 9

132 14 13 127 C12,9 7-4 O

O

-258 128

-3 12 127 C11,10

-1 4

-1 1

-414 137 3

12 127 C11,14 0

5 0

1

-294 139 9

12 127 C10,17

-7 3

-1 1

-423 137 0

12 127 C13,1

-4 4

-1 1

-235 140 12 13 127 C14,6

-1 4 1

-189 141 7

12 127 C15,8

-6 4

-1 1

-235 140

-1 12 127 C13,12

.-1 4

1

-2

-18 135

-5 12 127 C15,15 11 6

-1 1

-36 134 16 13 127 C15,17 8

5 0

1 32 136 6

12 127 C17,3

-4 4

0 1

-207 132 17 13 127 C16,5 g O

4 1

2

-144 133

-3 12 127 C18,9

-1 3

0 1

-410 132

-17 12 l

127 C16,10 2

4 O

O.

-144 133-

-1 12 127 C17,13 2

4 1

1 5

136 1

12 i

127 C18,18

-2 3

O l'

59 137 15 13 l

127 C21,2

-1 3

0 1

-36 135

-4 12 127 C20,5 5

4 0

1 50 136 2

12 127 C19,8 8

5

-1 1

-144 133

-9 12 127 C21,12 0

'3

-1 1

-72 134 2

12 127 C21,14 0

3

-1 1

-203 132

-16 12 127 C19,16 5

4 O

1

-324 130

-5 12 127 C23,1 7

5 0

1

-81 134 10 13 127 C22,6 7

5 1

1 104-137 16 13 127 C23,9 2

4

-1 1

41-136 9

13 127 C24,11 5

4

-1 1

-140 133 O

12 127

.C23,13 O.

3 0

1

-45 135 11 13 l

127 C23,19 2

4 0

1

-212 132 16 13 127 C25,2 0

3 0

1

-140 133 4

13 2E 127 C27,4-O 3

1 1

-290 126 9

13 127 C26,8

-2 3

-1 1

-412 124 17 13 l

12 13 d

127 C27,12

-4 3

0 1

-466 123 127 C25,13

-1 3

-1 1

-84 129 4

13 "E

127 C26,17

'-1' 3

-1 1

-319 125 14 13-E 127 C30,1 1

4

-1 1

--365 125 2

13 127 C29,5 0

3

-1 1.

-361 125 2

12

-8 127 C30,9-

-1 3

0 1

-395 124 23 13 0

u l

s. n.,..

....c..

1 TABLE A.2 Page 5 of 5 pages p

++++++++++++ ALPHA ++++++++++++++++++++++++++++++ BETA ++++++++++++++++++

ROOM GRID DPM/100CH2 DPM/100CM2 NUMBER

'NAME TOT

+/-

MAX

+/-

REM.

+/-

TOT

+/-

MAX

+/-

REM

+/-

127 C30,10 0

3 0

1

-294 126 5

13 l

127 C28,14

-1 3

-1 1

-231 127

-4 12 127 C29,17 4

4 0

1

-248 126 3

13 a

127 BIN 9 4

4 1

1

-424 119 13 13 127 B1S7 28 7

O O

-458 118

-9 12 l

127 B2N3 12 5

O O

-521 117 6

13 127 B2S10 7

4.

58 9

1 1

-525 117 12 13 127 B3N6 22 6

79 11 1

1

-311 121

-9 12 127 B3S16 18 6

29 7

O O

-487 118 27 13 i

127 B4N15 29 7

118 13 5

2

-244 122

'13 13 4

t

^ l 127 B4S6-

/

24-6 146 14 1

1

-361 120 9

13 127 F13,16 2

2 O

O 1079 141 29 13 127 F15,13 7

3 2

1 1138 147 9

13 127 F15,18 7

3 O

O 949 13 <-

21 13 i

127 F16,18 4

3 1

1 1084 141 2

12 127 F17,11 9

4 1

1 970 139

-16 12 127 F17,15 -

6 3

1 1

1037 140' 15 13 127 F19,13 11 4

O O

1109 141 0

12 127 F20,15 9

4 2

1 1075 141 27

- 13 i

127 F21,17 11 4

1 1

945 139 16 13 127 F22,11 6.

3 1

1 781 136 1

12 127 F23,15 12 4

1 1

1033 140 9

13 127 F24,17 5

3 O

O 907 138

-2 12 127 F26,15 4

3 2

1 1121 141 30-13 127 F27,18 11 4

,0 0

,815 137

-6 12 127 ES,13.

94 11 598 27 O

O 122 128 20 13 127 E5,15 83 10 1067 36 1

1 664 137 0

12 127 E5,16 23 6

'140 13 1

1 697 137 2

12 127 ES,9 5

4 3

2 598 141

-5 13 127 E5,11 14 5

4 2

469 137 1

13 127 E4,11 i4 3

-1 1

447 138

-3 13 3

127 E4,17

-1 2

-1 1

718 143

-3 13 oz 127 ES,17-10 4

11 3

839 144 30 14 S.

3 127 E3,15 6

4 1'

1 533 140 1

13

.9 *

• 127 E4,14 20 6

1 1

482 139 5

13 m

127 E3,13 10 4

1 1

796 144

-4 13 UU 127 E2,16 6

4 2

2 628 141 23 14 127 E2,12 3

3 1

1 460 139 1

13 127 E2,13 6

4 6

2 843 144 20 13

'g I

O

~

I P;ge 1 cf 5 pages TABLE A.3-Sampling Inspecticn R:sults of th3 Pssted Arca Except for the Glove Box Room

++++++++++++ ALPHA ++++++++++++++++++++++++++++++~ BETA ++++++++++++++++++

ROOM GRID DPM/100CM2-DPM/100CM2 NUMBER NAME TOT

+/-

MAX

+/-

REM

+/-

TOT

+/-

MAX

+/-

REM

+/-

117 F1,3 4

3 1

1 727 141

-1 12 117 F3,3 4

3 O

O

-59 129 9

13 117 C1,3 1

3 0

.O -2092 96 23 13 117 C3,3 1

3 1'

1 126 132 10 13 117 N1,1 1

3 1

1

-735 118-5 13 117 E2,2 1

3' O

O

-592 120 16 13 117 S3,5 3

3 O

O

-143 128

--5 12 117 S3,1 0

3 1

1

-361 124 1

12 117 W1,2 0

3 O

O

-479 122 8

13 118 F3,2 6

3 O

O 722 141 4

13 110 F2,2 4

3 O

O 176 133

-7 12 118 C2,2 4

2 O

O 331 135 4

13 118 N2,3 3

3 O

O

-869 115 1

12 118 E3,1

-4 3

1 1.

-185 127 5

13 118 S3,3

-2 3

0 0

-172 127

-13 12 118 W2,1

-1 3

1 1

340 135

-7 12 119 F1,4

-1 3

1 1

813 143 1

12 119 C1,4 O

3 0

0 305 135 4

13 119 N3,4

-4 3

O O

-211 126

-8 12 119 E3,1

.O 3

1 1

-344 124*

19 13 119 S2,2 2

4 1

1 13 130 7

13 119 W2,1 0

3 O

O 624 140

-9 12 120 F1,2 0

3 O

O 740 142

-5 12 120 C1,2 0

3 1

'1 181 133 19 13 120 N3,3 1

4 1

1

-284 125 7

13 120 S1,2

-4 3

O O

-189 127

-9 12 121 F3,2 6

3 1

1 538 135 21 13 121.

C3,2 0

2

-1 1

315 131 5

12 121 N2,2 5

3 1

1

-118 124

-3 12 121 E1,5 5

3 2

2 546 135 20 13 121 S3,3 2

2

.O 1

-151 123 11 12 az.

121 W3,5

-1 1

-1 1

118 128

-2 12

$P 122 FS,2 1

2

-1 1

G53 139

-8 12 3"

122 C5,2 2

3 O

1 256 131 9

12.

um 122 N1,2 5

3 0

1

-210-123 11 12

1. 2j 122 E3,3 1

3

-1 1

-252 123 2

12

$1 122 S2,2 1

3 1

1

-223 123

-27 11.

122 W3,2 1

3 O

1

-97 125

-8 12 123 FS,2 1

3 0

1 1042 143 12 12 8

123 F2,i 2

3

-1 1

1063 143 0

12 0

TABLE A.3 Page 2 cf 5 pages

++++++++++++ ALPHA

&+++++++++++++++++++++++++++++

BETA ++++++++++++++++++

ROOM GRID DPM/100CM2 DPM/100CH2 NUMDER NAME TOT

+/-

MAX

+/-

REM

+/-

TOT

+/-

MAX

+/-

REM

+/-

123 C5,2 1

3 2

2 84 128 7

12 123 C2,1

-1 2

0 1

84 128

-1 12 123 N1,4 0

2 1

1

-210 123

-5 12 123 E1,5

-2 2

1 1

-160 124 3

12 123 S3,1 1

3

-1 1

-202 124 10 12 123 S1,4

-2 2

-1 1

-265 123

-4 12 123 W2,3

-1 2

0 1

-214 123 14 12 124 F1,3 6

4 1

1 655 137 14 13 124 F4,5 10 4

-1 1

991 142 6

12 124 FS,3 7

4

-1 1

815 140 22 13 124 C1,3 1

3

-1 1

315 128 2

12 124 C4,5 0

3

-1 1

101 124 10 13 124 C5,3 2

3 0

1 67 123 20 13 124 N2,2 0

3 1

1 38 123 9

13 j

124 N3,4 1

3 1

1

-265 123 9

13 1

124 E2,3 1

3 2

1 420 129 8

13 124 E5,5 10 4

2 1

449 134 8

13 j

124 S2,3 2

3 O

O 34 123

-3 12 i

124 W3,1

-1 2

O O

-118 125 8

13 124 W2,5 0

3 1

1

-113 120

-12 12 124 W4,3 4

3 1

1

-4 127 8

13 126 F3,1 4

4

-1 1

941 138 4

12 126 F3,4 140 13 10465 114 1

1 1252 142 32302 388 17 13 126 F1,4 10 5

1 1

1050 139

-16 12 126 F3,7 0

3 1

1 802 135

_9 13 126 F4,2 1

3 1

1 1264 142 25 13 126 F4,@

2 3

'1 1

1163 141 15 13 126 F5,5 0

3 1

1 1046 139 17 13 126 F6,9 2

3 0

1 911 137 17 13 126 C3,1 6

5 1

1 103 125 11 13 126 C1,4 3

4 1

1 82 124

-5 12 126 C3,7

-1 3

1 1

291 128 2

12

.m 126 C4,2 0

4 O

1 385 129 20 13 3o 126 C5,5 5

4 0

1 70 124

-7 12 P, "

126 C6,9 9

5 0

1 357 129 1

12 126 N2,2 0

3 2

2

-109 120 22 13 NG 126 N1,6 O

3 1

1

-176 119 3

12 l

126 E1,4

-1 3

0 1

-273 118

-1 12 g

l 126 -

S3,2 0

3

-1 1

-193 119

-5 12 m

126 S2,5 1

3

-1 1

-4 122' 14 13 8

126 W3,1 2

3 1

'1 752 135 1

12

.N

' TABLE A 3 Page 3 cf 5-pages

++++++++++++ ALPHA

+++++++++++++++++++++4++++++++

BETA ++++++++++++++++++

ROOM GRID DPM/100CH2 DPM/100CM2 NUMBER NAME TOT

+/-

MAX

+/-

REN

+/-

TOT

+/-

MAX

+/-

REM

+/-

130 W5,9

-2 3

0 1

-391 123

-13 13 129 F1,2 10 5

-1 1

616 153 13 13 129 F3,4 1

3

-1 1

570 153-6 12 129 F5,1 7

4 0

1 782 156 2

12 129 F8,3 11 5

-1 1

672 154

-9 12 129 F10,1 6

4

-1 1

727 155 2

12 129 F10,5 7

4

-1 1

497 151

-6 12 129 C1,2 2

4

-1 1

-324 131

-7 12 129 C3,4 1

4

-1 1

-347 130

-10 12 129 C5,1

-1 3

-1 1

-275 132 23 13 129 CB,3 1

4 0

1

-311 131-4 12 129 C10,1 2

4

-1 1

-230 132

-10 13 129 C10,5 1

4

-1 1

-297 131 16 13-129 N2,2 4

3

-1 1

-324 132

.11 13 129 N3,5 7

3

-1 1

-450 129 5

12 129 N5,4 i

2 2

-1 1

-432 130 15 13 129 Ei,3 6

3

-1 1

-405 130 9

12 129 E2,5 4

3

-1 1

-455 129

-2 12 129 E1,8 2

2 1

2

-293 132

-1 12 129 E3,12 5

3

-1 1

-252 133 2

12 129 E5,1 2

2

-1 1

-428 130 10 13 129 E4,7 12 5

-1 1

-335 127 5

12 129 E5,12 14 5

-1 1

-684 120

-9 12 129 ES,13 6

4

-1 1

-636 121 4

12 129

.S1,2 2

3

-1 1

,409 139 1230 151 11 13 129 S3,5 4

3 0

1 490 140 0

12 129 S5,3 6

4

-1 1

679 143 26 13 129 W2,2 4

3

-1 1

-366 126 9

12 129 W3,4 4

3

-1 1

-335 127 7

12 129 W1,8 7

'4

-- 1 1

-430 125 11 13 129 W2,11 5

3

-1 1

-443 125

,6 12 129 W4,7 -

4 3

-1 1

-391 126 6

12 mm 129 W5,10 6

4

-1 1

-421 125

-6 12

$P VAULT F1,3 16 5

42 8

O O

924 144

-4 12 3"

VAULT FS,3 9

4 O

O 907 144 41664 438 23 13 2

VAULT C1,3 5

4 0

0 571 139

-2 12 My VAULT.

C5,3 1

3 1

1 475 137 15 13 e.

VAULT N3,2 4

3 O

O

542, 138

-9 12 VAULT E1,2 8

4 1

1 617 139

-5 12 VAULT E2,4 7

4.

1 1

92 131 1

12 8

VAULT S3,1 4

3

'O O

731 141

-12 12 0

,t

. TABLE A.3 Paga 4 cf 5 pages-

++++++++++++ ALPHA ++++++++++++++++++++++++++++++ BETA ++++++++++++++++++

ROOM GRID DPM/100CM2-DPM/100CM2 NUMBER NAME TOT

+/-

MAX

+/-

REM

+/-

TOT

+/-

MAX

+/-

REM

+/-

BH F1,1 5

4

-1 1

812 136

-11 12 BH F1,11 3

4 1

1 750 135 15 13l BH F8,2 1

4 O.

1 726 135 5

12-BH F3,2 6

5

-1 1

763

.135

-4 12 BH C2,1 3

4 1

1 123 125 11 13 BH C1,11 3

4 1

1 447 150 5

12 BH C8,2

-3 3

1 1-189.

126

-6 12 BH C3,2 6

5

-1 1

41 124 2

12 l

BH N3,1.

-4 3 1

-133 128

-1 12 BH N2,4 0

4 0

1

-82 122 12 13 BH N3,11 5

~4 1

1

-287 118

-2 12 BH E3,3 3

4 0

1

-176 120 12 13 BH E2,7 3

4

-1 1

41 124 17 13 BH S1,1 9

5 1

1

-86 122

-10 12 Bd W1,2

-1 3

0 1

-148 121 9

13 MEZRM F3,2 13 5

O.

O 767 135 0

13 MEZRM C3,2 5

4-1 1-

-271 119 12 13

?

MEZRM S1,2 3

4 1

1

-234 119 9

13 130 F1,1 1

4 3

2 727 141

-20 13

i 130 FS,3 7

5 1

1 1021 145

-9 13 130 F7,2 12 5

236 17 2

2 848 143 1121 147

-2 14 130 F12,2 0

3 3

2 487 138

-5 13 130 C1,1 1

4 O

O

-395 130 9

13 i

130 C5,3 1

4 2

1

-382 130

-18 12-130 C7,2

-4 3

2 1

-533 127

-5 12 130 C12,2 5

5 1

1

-466 128 6

13 1

l 130 N2,2

-4 3

1 1

-487 128 10 13 130 N 4,'1

-2 3

-1 1

-416 123

-14 13 130 E3,3

-2 3

3 2

-311 125

-19 13 130 E1,6 0

4 O.

O

-651 125-4 13 130 E2,7

-3 3

1.

1

-584.

126 1

13 130 El,11 4

4 1'

'1

-391 130

-3

'13 oz 130 E5,2 2

4 1

1.

-202 127

-23 13 E.

i 130 E4,8 2'

4

_1 1

-260 126.13 3**

130 S2,1 1

4 2

1 357 141 16 13

=

130 SS,3 1

4 1

1

-118 128

-6 13 U2$

I 130 W1,3 1

4 1'

'1

-437-129 9-13 OI i

130 W2,5

-3 3

2

'l

-500 128 14 13

$y 130 W1,8 3

4 0

0

-794 123.

5 13 130 W3,12 1

4.

1 1

-349 124

-24 13 o

130 W4,2 1

4

-1' 1.

-286 125

-18 13 C.

i l

.. u

.e

~ TABLE A.3 Pag 2 5 cf 5 pages

++++++++++++ ALPHA ++++++++++++++++++++++++++++++ P"TA ++++++++++++++++++

ROOM

' GRID DPM/100CM2 DPM/100CM2 NUMBER NAME TOT

+/-

MAX

+/-

REM

+/ -

TOT

+/-

MAX

+/-

PEM

+/-

VAULT W1,2 5

4 O

O 596 139 6

13 VAULT W3,4 8

4 O

O 504 138

-3 12 EXITE F1,1 11 5

O O

962 145

-16 12 EXITE C1,1 8

4 O

O 382 136 16 13 EXITE N1,1 11 5

1 1

-80 129

-1 12 EXITE E3,3 4

3 O

O

-50 129 3

12 EXITE E2,6 1

3 O

O

-185 127 15 13 EXITE S2,1 3

3 1

1

-214 126

-15 12 i

EXITE W1,2 5

4 O

O 445 137 28 13 EXITE.

W3,5 8

4 2

1 374 136 1

12 EXITN F1,5 4

4 0

0-1012 146 0

12 EXITW C1,5

-1 3

1 1

21 131

-2 12 EXITW N2,1

'5 4

1 1

-59 130

-4 12 EXITW E2,3

-1 3

0 0

311 135 17 13 EXITW E3,5

-1 3

1 1.

319 136 9

13 EXITW S3:1 2

4 1.

1 92 132 26 13 EXITW W1,2

-4 3

1 1

42 131 9

13 EXITW W2,5 2

4 2

1'

-193 127

-1 12 HOLDUP.

F2,-1 33 7

.1 1

1104 154

-15 12 i

HOLDUP F4,3 53 9

92 11 1

1 1385 158 27 13 HOLDUP F6,5 49 8

191 16

-1 1

1431 159 1826 165 2

12 HOLDUP N3,2 6

4

-1 1

994 153 8

12 i

HOLDUP E4,1 4

4 O

1 1012 153

-5 12 HOLDUP S1,2 55 9

2 2

1164 155 11 12 HOLDUP F1,3 12 5

23 6_

O 1

902 151

-10 12 EXITE F6,1 1

3 1

1 865 140 8

13 EXITE W3,1 0

2 1

1

-407 119 5

13 EXITE W3,2 2

3 1

1 668 137 8

13 130 F8,2 12 5

15 3

525 138-

-1 13 130 F7,1 7

4 O

O 941 144 7

13 130 F6,3 25 6

4 2

718 141 4

13 y2 BH FS,2 3

3 O

O 550 141

-4 13

$.O BH F6,2 10 4

1 1

802 145

-12 13 HOLDUP F4,1 28 7

68 to 1

1 1419 153 1742 158 2

13 x

HOLDUP F4,2 53 9

'94 11

-1 1

1144 149 1247 151 3

13 yy HOLDUP F3,3 54 9

'49 8-0 1

1118 149-1333 152 21 13 4

HOLDUP F3,4 40 8

113 12 1

1 894 146 882 146 4

13 y

HOLDUP F5,2 66 10 158 15 4

2 1015 147 1333' 152 16 13

• 8 8

~

o.

a No.: N704SRR990027 Page: 79 Appendix B V

Annex B GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION,,0F LICENSES FOR BYPRODUCT, SOURCE, OR SPECIAL NUCLEAR MATERIAL

\\

q1 i

U. S. Nuclear Regulatory Comission Division of Fuel Cycle and Material Safety Washington, D.C.

20555 July 1982 e

?

s I

P e

~

~

No.: N704SRR990027 Page: 80 O.

The instructions in this guide, in conjuaction.with Table 1, specify the radionuclides and radiation exposure rate limits which should be used in decontamination and survey of surfaces or premises and equipment prior

.to abandonment or release for unrestricted use. The limits in Table 1 do not apply to premises, equipment, or scrap containing induced radio-activity for which the radiological considerations pertinent to their use may be different. The release of such facilities or items from regulatory contro'1 is. considered on a case-by-case basis.

1.

The licensee shall make a reasonable effort to eliminate residual contamination.

2.

Radioactivity on equipment or surfaces shall not be covered by '

paint, plating, or other covering material unless contamination levels, as detemined by a survey and documented, are below the limits specified in Table 1 prior to the application of the covering.

A. reasonable effort must be made to minimize the contamination prior to use of any covering.

3.

The radioactivity on the interior surfaces of pipes, drain lines, or ductwork shall be determined by making measurements at all traps, and other appropriate access points, provided that contam-ination at thes'e locations is likely to.be representative of contamination on the interior of the pipes, drain lines, or ductwork. Surfaces of premises, equipment, or scrap which are h-likely to.be contaminated but are of such size, construction, or location as to make the surface inaccessible for purposes of measurement shall be presumed to be contaminated in excess of the limits.

i Upon request, the Consission may. authorize a licensee to relinquish 4.

possession or control of premises, equipment, or scrap having surfaces contaminated with materials in excess of the limits specified.

This may include, but would not be limited to, special circumstances such as razing of buildings, transfer of premises to another organization continuing work with radioactive materials, or conversion of facilities to a long-tem storage or standby status. Such requests must:

i Provide detailed, specific information describing the premises, a.

equipmerit or scrap, radioactive contaminants, and the nature, extent, and degree of residual surface contamination.

b.

Provide a detailed health and safety analysis which reflects that the residual amounts of materials on surface areas, together with other considerations such as prospective use of the premises, equipment or scrap, are unlikely to result in an unreasonable risk to the health and safety of the public.

G l

.~.

r.

j-No.:

N704SRR990027

, Page:

81

'-(s,/

5.

Prior to release of premises for unrestricted use, the licensee shall make a comprehensive radiation survey which establishes that contamination is within the limits specified in Table 1.

A copy of the survey report shall be filed with the Division of Fuel Cycle and Material. Safety, USNRC, Washington, D.C.

20555, and also the Administrator of the NRC Regionai Office having jurisdiction. The

l report shou 14 be filed at least 30 days prior to the planned date

! l of abandonment. The survey report shall-a.

Identify the premises.

b.

Show that reason'able effort has been made to eliminate

~

residual contamination.

c.. Describe the scope of the survey and general procedures followed.

d.

State the findings of the survey in units specified in the instruction.

Following review of the report, the NRC will consider visiting the facilities to confirm the survey.

g

\\ J

6 e

D t

l

%, )

{-

.m L (5

f. -

t

(

il 1

.s.

e' ACCEPTABLE SURFACE CollTAMINATION LEVELS f

NUCLIDE5a AVERAGEbcf PMXifutbdf REMOVABLEbef 2

2 U-nat. U-235. U-238 and t

15.000 dpm e/100 cm 1.000 dpa e/100 cm asstelated decay products 5.000 dpa e/100 cu Trensuranics."Ra-226. Ra-228 2

300 dpe/100 cm.2 20 dpm/100 cm2 Th-230. Th-228. Pa-231, 100 dpsi/lGJ cm Ac-227. I-125. I-129 l

2 Ra-223. Ra-224. U-232. 3-126 1000.dpe/100 cm2

- 3000,dpe/100 cm2..

200 dps/100 cm Th-ne t. Th-232. Sr-90 I-131. I-133 I

Bata-gama emitters (nuclides 2

1000 dpa 31/100 cm2 i

with decay modes other than.

2 15,000 dpm sy/100 cm l

alpha emission or spontaneous 5000 dpm sy/100 cm fission) except Sr-go and others noted above.

EWhere surface contamination by both alpha-and beta-gasuna-emitting nuclides exists, the limits estabilshed for alpha-and beta-gassaa-emitt arcildes should apply independently.

b s used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background, efficiency, and geometric factors associated with the Instrume A

For objects of less surface area, the average clicasurements of average contaminant should not be averaged over more then.1 square meter.

should be derived for each such object.

ihe maximum contemination level applies to an area of not more than 100 cm2,

~

d

[

2 of surface area should be determined by wiping that area with dry filter or soft

'The amount of removable radioactive material per 100 cm chsorbent paper, applying moderate pressure, and assessing the amount of radioactive asterial on the wipe with an appr When removable contamination on objects of less surface area is determined, the pertinent levels should be reduced known efficiency.

proportionally and the entire surface should be wiped.

yy 0.2 mrad /hr at I cm and 1.0 mrad /hr at I cm. respectively, measured through not'more th g,,

f tstal absorber.

8 g

j g

8 1

2

~

l

.