Text

Insp Rept 70-0133/98-02 on 980223-26 & 0323.No Violations Noted.Major Areas Inspected:Special Announced Insp to Perform Confirmatory Radiological Survey of Former Clevite Facility
	ML20216B158
Person / Time
Site:	07000133
Issue date:	04/07/1998
From:	; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	;
Shared Package
ML20216B145	List: ML20216B140; ML20216B158;
References
	70-0133-98-02, 70-133-98-2, NUDOCS 9804130382
	Download: ML20216B158 (54)
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U.S. NUCLEAR REGULATORY COMMISSION REGION 11!

Docket No:

070-00133 (Terminated)

License Nos:

SNM-183 (Terminated)

C-3692; C-3790 (Terminated) 34-00653-01/02 (Terminated)

Report No:

070-00133/98002(DNMS)

Former Licensee:

Clevite Corporation 540 East 105th Street Cleveland, OH 44108 Inspection Dates:

February 23-26,1998 March 23,1998 Location:

Shorebank Enterprise Group 540 East 105th Street Cleveland, OH 44108 Inspectors:

John E. House, Senior Radiation Specialist John T. Buckley, Project Manager

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Accompanying James Webb Personnel:

Ohio Department of Health Approved By:

Bruce L. Jorgensen, Chie Decommissioning Branch Division of Nuclear Materials Safety 9804130382 980407 PDR ADOCK 07000133 C

PDR

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EXECUTIVE

SUMMARY

FORMER CLEVITE FACILITY Inspection Report 070-00133/98002(DNMS)

This was a special announced inspection to perform a confirmatory radiological survey of the former Clevite facility. The purpose of this survey was to determine if the condition of the facility was accurately described by the remediation contractor's final survey data and met the NRC unrestricted use guidelines.

The confirmatory survey was based on NUREG/CR-5849. Areas that had been designated as affected in the contractor's remediation plan were scan surveyed. ' One area in which waste drums were stored could not be surveyed. Seventy wipe samples and eight soil samples were taken at the facility.

Confirmatory survey and sample analytical results of the facility did not identify any residual radioactive materialin excess of the NRC's unrestricted use guidelines for enriched uranium or thorium. Pending only a final survey of the waste drum storage area after the drums are removed, the contractor appeared to have adequately remediated the facility such that it can be released for unrestricted use.

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s Report Details 1.0 Backaround Special Nuclear Material License No. SNM-183 was issued to Clevite Research Center, Division of Clevite Corporation on March 10,1958. This license authorized the use and possession of enriched uranium (EU) at its facility located at 540 East 105th Street in i

Cleveland, Ohio. The licensed activities included melting, alloying, forging, rolling, welding, pickling, machining, stamping, sintering, and chemical and metallographic analyses of EU powder and ceramic materials for the production and fabrication of fuel elements for nuclear reactors. The license initially authorized about 9 kilograms (kgs) of 90% EU, and subsequent amendments raised this authorization to nearly 56 kgs. An area on the first floor in the rear of the building was reserved for fuel fabrication.

i Other research activities, covered under Source Material License Nos. C-3790 and C-3692, authorized about 90 kgs of natural uranium and 5 grams of thorium sulfide, respectively, j

Gould, Inc., the successor of Clev;te Corporation, contracted with Sevenson Environmental Services, Inc., (Sevenson) to develop and implement a remediation/ survey plan to render the property fit for release for unrestricted use. The i

I contractor submitted the Site Characterization Survey / Termination Survey, Remediation, and Health and Safety Plan on May 10,1995, and was authorized by the NRC to proceed with site characterization in a letter dated June 1,1995. The site characterization, remediation and final surveys have been completed.

Sevenson submitted the Final Status Survey Plan (FSP) to the NRC on November 24,

-1997. The FSP was approved by NRC on December 12,1997. Previous inspections j

have verified that the responsible party has conducted remediation activities in accordance with its approved Remediation Plan (Inspection Reports 070-00133/95001, j

070-00133/95002, 070-00133/96001, 070-00133/98001).

On February 23-26,1998, NRC personnel accompanied by a representative from the Ohio Department of Health, Bureau of Radiation Protection, conducted an inspection at the former Clevite Corporation facility site. The scope of the inspection was to evaluate the remediation contractor's final survey of the facility, and to conduct a confirmatory survey of the facility to determine if the facility would meet the NRC release criteria defined in Guidelines for Decontamination of Facilities and Eauipment prior to Release for Unrestricted Use or Termination of Licenses for Bvoroduct. Source. or Special Nuclear Material dated August,1987.

The surface contamination limits for Uranium are 5,000 disintegrations per minute (dpm) per 100 square centimeters with a maximum of 15,000 dpm and 1,000 dpm removable. For Thorium the limits are 1,000 dpm per 100 square centimeters with a maximum of 3000 dpm and 200 dpm per 100 square centimeters removable.

Soil release limits are 30 picocuries per gram for enriched Uranium and 10 picocuries per gram for Thorium.

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Inspection Activities 2.1-Instrumentation. Survey Methods and Tables Scan surveys were conducted with Ludium 44-9 Geiger-Mueller " pancake" probes connected to a Ludlum Model 3 rate meter or a Model 2249-2 rate meter / scaler (Table 3). Scan surveys were conducted with the probe approximately one-half inch or less from the surface and at a scan speed of approximately one detector width per

- second. Area dose rate measurements were performed with Ludlum Model 19 micro R meters at a distance of one meter from the horizontal surface. Seventy wipe l

samples were taken using laboratory grade 47 millimeter filter paper circles. Each sample area covered an area of approximately 100 square centimeters. Eight soil samples were taken in representative areas around the facility.

Table 1 contains data for wipe samples including location and activity in disintegrations per minute. Table 2 contains the gamma spectroscopy analyses of soil samples, and Table 3 contains survey instrument information.

2.2 Confirmatory Survey of the Clovite Facility 2.2.1 Scope This confirmatory survey was conducted to determine the adequacy of the remediation contractor's final status survey and was based on NUREG/CR-5849 which recommends evaluation of approximately ten percent of the site. The inspectors evaluated from 10 to 100 percent of the affected areas using both random and biased survey techniques.

Radiological surveys were performed in the following areas:

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Southeast Wing Rooms 1, 7, 8, 9,10,11,18, test cell, test cell pit, and SE Wing hall between Rooms 9 and 11; West Wing Rooms 5,6,7,14,16,18, Hall B, interior loading dock, and the tin shed; i

Second Floor West Wing Grid Semi Room; and The welding shop area was surveyed previously (IR 070-00133/98001) and released j

- for unrestricted use.

2.2.2 Southwest Wina Observations and Findinas Inspectors performed scans of the floors, walls and upper areas of affected rooms in j

' the Southeast Wing. The' surveys emphasized crevices, wall / floor junctions, drain areas, overhead horizontal surfaces, and remediated areas. Direct survey measurements and wipe samples were collected from floors, walls and overhead pipes and ducts to determine if removable contamination was present above NRC -

release guidelines. Exposure rate readings were taken one meter above the floor in most of the areas surveyed during the inspection.

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i 2.2.2.1 Room 1

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The inspectors scan surveyed approximately 100% of the floor, including.100% of the remediated area, and approximately 75% of the walls to a height of 2 meters.

Readings ranged from 20-60 cpm on the floor and 20-80 cpm on the walls. These readings were consistent with background measurements.

Eight wipe samples and direct radiation measurements were taken in this room.

' Direct reading measurements ranged from 30-60 cpm. Results of the wipe samples are presented in Table 1.' Activity on the wipe samples was consistent with I

background or below the release limits, as were the one minute. count readings.

General area dose rates were 5-7 uR/ hour.

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2.2.2.2 Rooms 7 and 18

.. Inspectors performed a 20-30% scan survey on the floor, including 100% of the -

remediated areas. Readings ranged from 50-80 cpm. Inspectors also surveyed the j

horizontal surfaces of overhead I-beams located along the West wall. Readings ranged from 30-40 cpm. These readings were consistent with background measurements.

Four wipe samples and direct radiation measurements were taken in this area at locations with known higher activity levels. Direct reading measurements ranged j

from 60-150 cpm. Results of the wipe samples are presented in Table 1. These small areas of elevated activity were identified by Sevenson in the final survey report.

2 However, the average surface activity level within a contiguous 1 m area containing

. the elevated areas was less than the NRC guideline value. General area dose rates were 4-5 uR/ hour.

2.2.2.3 Room 8 The inspectors scan surveyed approximately 50% of the floor, including 100% of the remediated area, and approximately 20% of the walls to a height of 2 meters.

Readings ranged from 40-60 cpm on the floor and 20-40 cpm on the wall. These j

readings were consistent with background measurements.

i Two wipe samples and direct radiation measurements were taken in this room.

Direct reading measurements ranged from 40 50 cpm. Results of the wipe samples are presented in Table 1. Activity on the wipe samples was below the release criteria and the one minute count readings were consistent with background.

' General area. dose rates were 7-9 uR/ hour.

2.2.2.4 Test Cell An approximate 100% scan survey was performed on the floor, and 75% on the walls to a height of 2 meters. Readings ranged from 40-60 cpm on the floor and 30-50 cpm on the walls. These readings were consistent with background measurements.

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.Three wipe samples and direct radiation measurements were taken in this room l

Direct reading measurements ranged from 30-50 cpm. Results of the wipe samples are presented in Table 1. Activity on the wipe samples was consistent with background, as were the one minute count readings. General area dose rates were 8-11 uR/ hour.-

l 2.2.2.5 Test Cell Pit An approximate 100% scan survey was performed on the floor, including 100% of the remediated area, and approximately 75% of the walls (1.5 meters high) were

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scan surveyed. Readings on the floor and walls ranged from 40-60 cpm. These 1

readings were consistent with background measurements.

j One wipe sample and a direct radiation measurement was taken in the pit area. The direct reading measurement was 43 cpm which was consistent with background.

Activity on the wipe samples was below the release criterit General area dose rates were 8-11 pR/ hour.

- 2.2.2.6 Room 9 i

The inspectors scan surveyed approximately 100% of the floor, and approximately 50% of the walls. Readings ranged from 40-70 cpm. Inspectors also surveyed approximately 10-20% of the horizontal surfaces of overhead lighting,1-beams, and ventilation ducts. Readings ranged from 40-60 cpm. These readings were -

consistent with background measure'nents.

Six wipe samples and direct radiat;on measurements were taken in this room. Direct reading measurements ranged from 20-40 cpm. Activity on the wipe samples was below the release guidelines and the one minute count readings were consistent with background. General area dose rates were 4-6 R/ hour 2.2.2.7 Room 10 1

The inspectors performed a 100% scan survey on the floor, and approximately 50%

scan survey on the East wall. Readings ranged from 40-70 cpm on the floor and 40-80 cpm on the wall inspectors also curveyed approximately 10-20% of the horizontal surfaces of overhead lighting,1-beams, and ventilation ducts. Readings 4

ranged from 40-60 cpm. These readings were consistent with background measurements.

Three wipe samples and direct radiation measurements were taken in this room.

Direct reading measurements ranged from 20-30 cpm and were consistent with I

background. Activity on the wipe samples was consistent with background.

j 2.2.2.8 Hall Between Rooms 9 and 11 A 100% scan survey was performed on the floor. Readings ranged from 50-80 cpm.

Three wipe samples and direct radiation measurements were taken in this room.

Direct reading measurements ranged from 20-40 cpm. Activity on the wipe samples was consistent with background, as were the one minute count readings.

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1 2.2.2.9 Room 11 The inspectors performed a 75% scan survey on the floor, including 100% of the i

remediated area, and approximately 75% scan survey on the walls to a height of 2 meters. Readings ranged from 50-70 cpm on the floor and 60-120 cpm on the brick wall. These readings were consistent with background measurements.

Three wipe samples and direct radiation measurements were taken in this room.

Direct reading measurements ranged from 20-40 cpm. Activity on the wipe samples was consistent with background, as were the one minute count readings.

t 2.2.3 West Wina Observations and Findinas The inspectors performed sh.ans of the floors, walls and upper areas of affected rooms in the West Wing. The surveys emphasized crevices, wall /floorjunctions, drain areas, overhead horizontal surfaces, and remediated areasc The inspectors also selected locations and performed direct survey measurements for beta / gamma j

radiation, and collectsd wipe samples from floors, walls and overhead pipes and ducts to determine if removable contamination was present above NRC release guidelines. Exposure rate readings were taken one meter above the floor in most of the areas surveyed during the inspection.

2.2.3.1 Second Floor Grid Seal Room Inspectors performed a 50% scan survey on the floor and approximately 75% scan l:

survey on the walls. Readings ranged from 20-60 cpm on the floor and 20-50 cpm on the walls.' Inspectors also performed a 10% scan of ceiling tiles and duct work, with readings ranging from 40-50 cpm. Since equipment in the room had been decontaminated,25% of this equipment was surveyed for radioactivity. Readings l-ranged from 20-30 cpm. These readings were consistent with background measurements. Two wipe samples and direct radiation measurements were taken in this room. Direct reading measurements ranged from 40-60 cpm. Activity on the wipe samples was below the release guidelines. The one minute count readings were consistent with background.

2.2.3.2 Hall B inspectors performed a 50% scan survey on the floor, including 100% scan of remediated areas, and approximately 50% scan survey on the walls. Readings on the floor ranged from 20-60 cpm on remediated areas and 50-80 cpm on unremediated areas. Readings on the walls ranged from 20-50 cpm on drywall and 40-80 cpm on brick. These readings were consistent with backgrcund measurements.

1 Eight wipe samples and direct radiation measurements were taken in this hallway.

1 Direct reading measurements generally ranged from 20-50 cpm with one reading l

reaching 60-100 cpm. Activity on the wipe samples was consistent with background, l

as were the one minute count readings. General area dose rate measurements in this hallway ranged from 7-9 uR/ hour l

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2.2.3.3 Room 5 and Inside Loadina Dock Area The inspectors scan surveyed approximately 50% of the floor and approximately 50% of the walls. Readings ranged from 60-80 cpm on the floor and from 20-60 cpm on the walls. These readings were consistent with background measurements.

Five wipe samples and direct radiation measurements were taken in this area.

Direct reading measurements ranged from 40-80 cpm. Activity on the wipe samples was consistent with background, as were the one minute count readings. General exposure rate measurements in this area ranged from 6-8 uR/ hour.

2.2.3.4 Room 6 The inspectors performed a 75% scan survey on the floor and approximately 100%

scan survey on the walls, up to 2 m high. Readings ranged from 20-60 cpm on the floor and from 20-80 cpm on the walls depending on whether the wall was cinder block or brick. Inspectors also performed a 20% scan of horizontal surfaces of overhead pipes, and beams. Readings ranged from 20-60 cpm. These readings were consistent with background measurements.

Three wipe samples and direct radiation measurements were taken in this area.

Direct reading measurements ranged from 20-40 cpm. Activity on the wipe samples was consistent with background, as were the one minute count readings. General exposure rate measurements in this area ranged from 6-8 uR/ hour.

2.2.3.5 Room 7 Inspectors performed an 80-90% scan survey on the floor, and approximately 20% of the walls to a height of two meters. Additional brick wall areas (approximately 5%)

above the false ceiling were surveyed. Readings generally ranged from 50-80 cpm for floor and walls, and were consistent with background measurements. One small area of elevated activity (135 CPM) wat located. This area of elevated activity had also been identified by Sevenson and analyzed. When the surface activity was 2

averaged within a contiguous 1 m area containing the elevated area, the activity was less than the NRC guideline values.

Five wipe samples and direct radiation measurements were taken in this room.

Direct reading measuremenis ranged from 53-135 cpm. Results of the wipe sample taken in the 135 cpm area indicated that there was no loose contamination. Activity levels of all samples and measurements were below the guideline values. General area exposure rates were 14-16 uR/ hour.

2.2.3.6 Room 14 Inspectors performed a 10% scan survey on the floor. Readings ranged from 40-60 cpm on the floor. These readings were consistent with background measurements. This room was lightly surveyed because the only remediation in this room consisted of removing one piece of pipe with surface contamination (roughly 4 feet long). No other contamination was found in this room. General area exposure rates were 5-6 uR/ hour.

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- 2.2.3.7 Room 16 l

~ The inspectors performed a 50% scan survey on the floor, including approximately -

' 75% of the remediated areas, and approximately 25% scan survey on the walls, g'

Readings ranged from 20-60 cpm on the floor and from 20-80 cpm on the walls

. depending on whether the wall was drywall or cinder block. Inspectors also i

performed a 10-20% scan of horizontal surfaces.of overhead pipes, lights, and beams.- Readings ranged from 20-60 cpm. These readings were consistent with

background measurements.

Ten wipe samples and direct radiation measurements were taken in this area. Direct o

reading measurements generally ranged from 30-80 cpm. Activity on the wipe L

' samples and the one minute count readings were below the release guidelines.

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. General area exposure rates were 4-8 gR/ hour.

.I 2.2.3.8 Room 18 I

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The inspectors performed a 50% scan survey on the floor and approximately 75%

scan survey on the walls. Readings ranged from 40-60 cpm on the floor and from 20-60 cpm on the walls.' These readings were consistent with background measurements, i

Two wipe samples and direct radiation measurements were taken in this area.

Direct reading measurements generally ranged from 40-60 cpm, Activity on the wipe samples and the one minute count readings were below the release guidelines.

General area exposure rates were 6-7 R/ hour.

.i 2.2.3.9 Tin Shed The inspectors scan surveyed approximately 60% of the floor of the Tin Shed and approximately 20% of the walls up to 2 meters along with portions of metal shelving.

I Readings ranged from 50-70 cpm on the floor and shelv'ing, and 30-90 cpm on the j

walls. These readings were consistent with background.

Two wipe samples and direct radiation measurements were taken in the Tin Shed.

Direct reading measurements generally ranged from 55-67 cpm. Activity on the wipe j

samples and the one minute count readings were consistent with background.'

i General area exposure rates were 13-14 R/ hour, 2.2.4 - Conclusions Data from direct measurements and wipe samples indicated that radioactivity was within the NRC release guidelines. With the few exceptions described above, all survey measurements were generally consistent with background readings.

Analysis of the wipes showed that no residualloose radioactive material was present i

and in all cases, activity levels were below the release guidelines for unrestricted I

release.

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3.0 Exit Meeting At the conclusion of the inspection on February 23,1998, the preliminary results of the inspection were discussed with the individuals identified in this report. Mr. John Schoeniger, Shorebank Enterprise Group, was invited to the Exit Meeting but was unable to attend. On March 23,1998, results of the sample analyses were discussed with the remediation contractor. None of the information provided during the inspection was indicated to be l

proprietary.

l Persons Contacted Mr. Kim W. Lichfield Mr. James Cronmiller Project Manager Gould Electronics, Inc.

j Sevenson Environmental Services Mr. John Schoeniger l

Shorebank Enterprise Group l

i Mr. Rory Grube Radiation Safety Officer l

Sevenson Environmental Services Attachments: Table 1 Wipe Sample Results Table 2 Soil Sample Results Table 3 Survey Instrument Information Survey Grid Maps of Sample Locations l

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TABLE 1 i

WIPE DATA DISINTEGRATIONS PER MINUTE (DPM) PER 100 SQUARE CENTIMETERS SAMPLE WING ROOM GRID SURFACE ACTIVITY DPM 93 10-01 SE TEST CELL J-6 WALL

<MDA 98-10-02 SE TEST CELL J-9 FLOOR 22 98-10-03 SE TEST CELL I-10 FLOOR

<MDA 98-10-04 SE TEST CELL I-14 WALL

<MDA 98-10-05 SE 8

G-9 FLOOR 143 98-10-06 SE 8

J -9 FLOOR 15 i

98-10-07 WEST 7

G-9 FLOOR

<MDA 98-10-08 WEST 7

E-12 FLOOR

<MDA 98-10-09 WEST 7

M-11 WALL

<MDA 98-10-10 WEST 7

G-5 WALL

<MDA 98-10-11 WEST 7

D-11 FLOOR

<MDA 98-10-12 WEST DOCK l-14 WALL

<MDA 98-10-13 WEST DOCK J-11 FLOOR

<MDA 98-10-14 WEST DOCK G-9 FLOOR

<MDA 98-10-15 WEST 5

N-12 WALL

<MDA 98-10-16 WEST 5

G-13 FLOOR

<MDA 98-10-17 WEST 18 J-11 FLOOR 25 98-10-18 WEST 18 H-6 WALL

<MDA 98-10-19 WEST 16 E-9 PIPE

<MDA 98-10-20 WEST 16 K-7 CABLE 50 TRAY 98-10-21 WEST 16 N-10 FLOOR

<MDA 98-10-22 WEST 16 K-16 FLOOR

<MDA 98-10-23 WEST 16 K-4 WALL

<MDA 98-10-24 WEST 16 L-9 FLOOR

<MDA 98-10-25 WEST 16 J-8 FLOOR

<MDA 98-10-26 WEST 16 J-12 FLOOR

<MDA J

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98-10-26 WEST 16 J-12 FLOOR

<MDA 98-10-27 WEST 16 l-9 FLOOR

<MDA j

98-10-28 WEST 16 l-13 FLOOR

<MDA 98-10-29 WEST TIN SHED L-8 FLOOR

<MDA 98-10-30 WEST TIN SHED G-11 FLOOR

<MDA 98-12-01 SE 9

F-9 FLOOR

<MDA i

98-12-02 SE 9

H-9 FLOOR 25 i

98-12 SE 9

l-7 FLOOR

-<MDA 98-12-04 SE 9

l-6 FLOOR

<MDA 98-12-05 SE 9

K-7 FLOOR 117 98-12 06 SE 9

F-11 WALL 17 l

98-12-07 SE 10 l-8 WALL

<MDA 98-12-08 SE 10 1-11 FLOOR

<MDA 98-12-09 SE 10 K-11 FLOOR

<MDA 98-12-10 SE 11 P-7 FLOOR

<MDA l

98-12-11 SE 11 P-5 WALL

<MDA 98-12-12 SE 11 K-8 FLOOR

<MDA 98-12-13 SE HALL I-11 FLOOR

<MDA 98-12-14 SE HALL J-10 FLOOR

<MDA 98-12-15 SE HALL M-7 FLOOR

<MDA i

98-12-16 SE 18 N-7 FLOOR

<MDA 98-12-17 SE 18 L-11 FLOOR 18 98-12-18 SE 7

M-15 FLOOR

<MDA 98-12-19 SE 7

J-16 FLOOR (MDA 98-12-20 WEST GRIDSEAL G-7 FLOOR 37 l

l 98-12-21 WEST GRIDSEAL J-4 WALL

<MDA l-98-12-22 WEST HALL B P-G FLOOR

<MDA 98-12-23 WEST HALL B N-5 FLOOR

<MDA i

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98-12-26 WEST HALL B L-3 FLOOR

' MDA 98-12-27 WEST HALL B H-9 FLOOR

<MDA 98-12-28 WEST HALL B N-11 FLOOR

<MDA 98-12-29 WEST HALL B O-15 WALL

<MDA 98-11-01 SE 1

L-8 FLOOR

<MDA 98-11-02 SE 1

J-11 FLOOR

<MDA 98-11-03 SE 1

1-9 FLOOR

<MDA 1

98-11-04 SE 1

1-11 FLOOR

<MDA 98-11-05 SE 1

N-9 WALL 116 i

98-11-06 SE 1

D-11 WALL

<MDA 98-11 07 SE 1

H-14 WALL

<MDA 98-11-08 SE 1

K-14 WALL

<MDA 98-11-09 WEST 6

H-11 FLOOR

<MDA 98-11-10 WEST 6

J-9 FLOOR

<MDA 98-11-11 WEST 6

J-14 WALL

<MDA MINIMUM DETECTABLE ACTIVITY (MDA)

ALPHA 5 DISlNTEGRATIONS PER MINUTE PER WIPE BETA 14 DISINTEGRATIONS PER MINUTE PER WIPE

i TABLE 2 CLEVITE SOIL SAMPLE ANALYSES PICOCURIES PER GRAM SAMPLE NUMBER URANIUM THORIUM 1

10.30 1 1.62 1.3110.13 2

4.7011.37 1.3610.20 3

7.0511.80 1.3610.20 4

< 5.0 1.2210.40 5

< 5.0 1.2810.34 6

< 5.0 0.9010.30 7

< 5.0 0.9010.30 8

< 5.0 0.7810.30 i

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i TABLE 3 INSTRUMENTATION SURVEY KIT #6 NRC TAG 04695 LUDLUM 2241-2 RATE METER / SCALER SN 132192 LUDLUM 44-9 PANCAKE PROBE SN PR110149 LUDLUM MODEL 3 RATE METER SN 037303 WITH 44-9 PROBE LUDLUM MODEL 19 MICRO R METER SN 014808 THE ABOVE LISTED INSTRUMENTS WERE WITHIN THEIR CAllBRATION CYCLE AT THE TIME OF THE INSPECTION 1

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LOCATION: 1st Floor SE Wine Room 1 A INST / PROBE: 2 274-I 13-/-/

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SUMMARY

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