ML20238C998

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Forwards Amend to Final Rept Re Dismantlement & Disposition of Facility,Including Survey Maps Denoting Grids Surveyed & Survey Data on Ventilation Duct Work & Stack,In Response to Items Identified in Insp Rept 50-124/87-01
ML20238C998
Person / Time
Site: 05000124
Issue date: 09/03/1987
From: Furr A
VIRGINIA POLYTECHNIC INSTITUTE & STATE UNIV., BLACKSB
To: Berkow H
Office of Nuclear Reactor Regulation
References
NUDOCS 8709100489
Download: ML20238C998 (33)
v • d • e


Text

_ _ - . _

VIRGINIA TECH 4 1

Department of Illacksburg, Virginia 24061 licalth and Nfcty . (703) 961 6775

' September 3, 1987 ,

Herbert N. Berkow, Director Standardization and Non-Power Reactor Project Directorate Division.of Reactor Projects III, IV, V'and Special Projects Office of Nuclear Reactor Regulations United States Nuclear Regulatory Commission Washington, D. C. 2f)555 ,

I

Subject:

Amendment 1 to Final Report

Reference:

1) Docket 50-124 l
2) Inspection Report 50-124/87-01

Dear'Mr. Berkow:

The subject enclosure amends the final report on the dismantlement and disposition of the' Virginia Tech Argonaut Reactor (VTAR) as requested by Region II Inspection and-Enforcement. .

Specifically, this additional information includes.the response to items identified in Reference 2, the I and E report as follows:

Finding a. Survey maps denoting the grids surveyed

-Finding b. Survey data on the facility ventilation duct work and stack Finding c. Roof survey data ,

Finding d. Release survey data on materials released for disposal at the VP1 owned landfill

' Finding e. Material remaining inside the building l

We request timely review of this information.in order that the facility license be )

terminated and the area returned to productive educational use. ]

l Sincerely, Certificate of Acknowledgment:

County of Montgomery

'[  % Commonwealth of Virginia Dr. A. Keith Furr Signedbeforemethis3rddayofSeptember,1987)

Department Head 0 m Enclosure u

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.y,,My Commission expires u ,u/ f 9, /97/.

Virginia Polytechnic Institute and State tiniversity 8709100499 870903 PDR -ADOCK 05000124 G< PDR s

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  • TABLE OF CONTENTS
FINDING
a. Final Release Grid Survey 1 ,
b. Ventilation System Surveys 5
c. Roof Surveys 11
d. Surveys on Materials Released to Landfill 15
e. Material (s) Remaining in the Facility 20 n

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FINDING a FINAL RELEASE AND SURVEY l

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. Finding a. - Final Release Grid Survey.

The Final Report did not indicate which grids were actually surveyed.

RESPONSE: Appendix a shows. maps of the facility, denoting grids which were surveyed for the final report.

. Grids that were surveyed as part of the Final Survey have been identified with diagonal lines. This helps to show the actual surface area (s) covered in the survey.

In addition, the following Table, a-1, summarizes the Final.

Survey Grid Plan (Section 8.1 of the Final Report).

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i APPENDIX a-1 FACILITY MAP 5 SHOWING GRIDS SURVEYED (9 Pages) 1658J 1

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Table a.1 Sumary of Final Survey Grid Plan Low Potential Areas (3M X 3M. grids)

Includes: All facility ceilings, control room and office (Rm.108) walls and floors.

Total number of- grids in these areas - 57 Nunber of grids surveyed in Final. Survey - 32 Medium Potential Areas (2M X 2M grids) i Includes: Room 10 floors and walls, the Chemistry Lab and adjacent rooms (Rm 6, 6A, 8 and 8A).

Total number of grids in these areas - 256 Nunber of grids surveyed in Final Survey - 90 High Potential Areas (lM X lM grids)

Includes: Reactor shield floor and excavated area and the pump-process pit. l 1

l Total nunber of grids in these areas - 91 Nunber of grids surveyed in Final Survey - 91 a

This information is presented on the grids maps (Appendix a-1). ,

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FINDING b.

VENTILATION SYSTEM SURVEYS 1658J

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1 FINDING b -- Ventilation System /Ductwork and Process Pit Pipe / Penetrations g, - It was identified that more technical information regarding )

the final survey of these areas be provided in the Final l Report.

RESPONSE: Final Report, Section 8.3 "Special Surveys":

1 8.3 SPECIAL SURVEYS The procedure for surveying pipes, drain 1ines, ventilation system ductwork, and heater was as follows:

The nearest accessible locations were surveyed with suitable instruments and wiped for removable contamination as far inside as could reasonably be rea ched. These locations included the ends of accessible pipes, the interior surfaces of inlet and outlet vents, and the water traps and exit

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points of drain lines. No significant radioactivity was found at any of the entry or exit locations.

A " wipe" was pulled through representative pipes, drain lines, and duct work to ensure no contamination was present. Pipes that contained contamination above Table IV limits were cut up and disposed of as radioactive waste. This included portions of the primary coolant system supply and return lines, pool drain pipe, and core cavity drain piping.

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l In addition, survey results for the Process Water System piping were summarized in Section 3.2.5, " Dismantlement of Process Water System":

3.2.5 Dismantlement of Process Water System The old cooling system was disassembled, removed, surveyed and disposed of as metal scrap. The 150 gallon " dump tank", which was used as a water collection sump during concrete sawing,

'was later decontaminated, cut open for survey, and released as scrap metal .

The 500 KW upgrade cooling system components located inside Room 10 (which were never used for reactor operations) were disassembled and surveyed to verify the absence of contamination. The heat exchanger, pump and piping were surveyed " clean" and retained as salvage. At the point where l the piping exists Room 10, smears of the interior piping were taken to confirm that no contamination was present, and to ,

release the balance of the system. All components of this system met criteria for release. The remaining sections of discharge (sewer) pipe (s) have been surveyed per Section 8.0 and satisfactorily meet release criteria.

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The actual data from these surveys has been tabulated on the following Table, b-1, " Ventilation System and Pipes / Penetrations".

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TABLE- b-1 Page 1 of 2

-FINAL RELEASE SURVEY DATA

SUMMARY

VENTILATION SYSTEM AND PIPES / PENETRATIONS i

Survey Results (Net Values) oose . Fixed

( (uR/hr LOCATION 100cm2) 0 lcm) ,

1 1

(VENTILATION SYSTEM)'

  1. 1-(See map, Figure- ) 304 0.2
  1. 2 46 ND
  1. 3 ND ND

. #4 98 0.2

  1. 5. ND 0.1
  1. 6 ND ND
  1. 7 304 0.2
  1. 8 46 0.5
  1. 9 ND 0.2
  1. 10 46 0.5

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  1. 11 407 0.8
  1. 12 ND 0.3
  1. 13 98 0.3
  1. 14- ND 0.8 Average- TC4 0.3 Maximum- 407 0.8 HEATER UNIT (S.W. Corner, RM 10)
  1. 15 46 0.3
  1. 16 46 0.1
  1. 17 ND ND l #18 ND 0.2
  1. 19 304 0.1
  1. 20 46 0.2 i
  1. 21 96 0.4 l
  1. 22 98 0.3
#23 ND ND l #24 ND ND l
  1. 25 ND 0.1 Average- 37 8 0.2 Maximum- 304 0.4 1658J 4

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Table b-1 (con't) l ,2 .Page 2 of 2

-FINAL RELEASE SURVEY DATA

SUMMARY

VENTILATION SYSTEM AND PIPES /PENE1 RATIONS Survey Results (Net Values) oose _ Fixed

( (uk/hr LOCATION 100cm2) 0 lcm)

PROCESS PIT (RM 10)

Penetration #1 (Floor) 21 0.2

  1. 2 (Floor)- 74 0.1
  1. 3 (Floor)- 106 0.7
  1. 4 (Floor) 85 0.2
  1. 5 (Floor) 42 ND
  1. 6 (Floor) ND 0.3
  1. 7 (Floor) 21 0.2
  1. 1 (East Wall) 74 ND
  1. 2 (East Wall) ND 0.2
  1. 1 (South Wall) -ND 0.3
  1. 1 (West Wall) ND 0.5
  1. 2 (West Wall) 32 0.3
  1. 3 (West Wall) ND 0.4
  1. 4 (West Wall) 53 0.3
  1. 5 (West Wall) 127 0.4
  1. 6 (West Wall) 95 0.4
  1. 7 (West Wall) 53 ND Average- W1 F2 Maximum- 127 0.5 Instrumentation used:

Eberline PRM-7 #476 Calibrated 8/4/86 Eberline E-120 W/HP-210T #5813 Calibrated - 10/24/86 Eberline RM-14 W/HP-210T #2699 Calibrated - 11/6/86 Eberline MS-2 W/HP-210T #1130 Calibrated - 8/15/86 1658J

FIGURE b_-1 ,

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V.P.I". Robeson' Hall Reactor Room Vent 11ation' System (RgainingComponents) ,

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Booster Fan N

Centrifugal Blower

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Room 308

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Air Sampler ~ '

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+gs eater Unit Connection ( j dncorner)

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,- a Jnlet Plenu.m

(~30ft long, on Roon 8 S. Wall w/ 3

/ inlet baffles)

Damper Valve (to Fume' Hood) u[.jr/ '3M 5- 6 48% 4 6 @ 66 1658J _ _- -_____-__r-

. i FINDING c ROOF SURVEYS i

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' FINDING c:- Roof Surveys.

f No surveys of the roof area surrounding the reactor room stack outlet were reported.

, . RESPONSE:. The enclosed map, Figure c-1 and' Tables c-1 and ~c-2 show.the -

resul ts ,of- the'-survey performed on the . roof. This area meets the criteria for unrestricted use.

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TABLE c-1 V.P.I. FINAL RELEASE SURVEY - OVERALL DATA SUKMARY JULY ' 87 SURVEY INSTRUMENT DATA - FINAL RELEASE SURVEY - LOW POTENTIAL AREAS

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

INSTRUMENT MFG./ SERIAL CAL DUE INST. CORRECT DETECTOR TYPE MODEL NO. DATE EFF. FACTOR

  • BKG.(s)

Micro-R Ludlum Model3 w/ 38624 8-4-87 N/A N/A 1.7 uR/hr 44-2 (2x2 NaI Detector)

Bata-Gamma Eberline 425 8-17-87 0.13 51.50 40.1 cpm (Scaler) PRS-1 w/HP-210T (12.5%)

=a==========================================================

~~~~~~~~~~~..~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

SUMMARY

- SURVEY OF ROBESON HALL ROOF SURFACE (S)

(3 ORIGINAL DATA PAGES; C 13) 3M x 3M GRIDS)

FIXED CONTAMINATION : BETA-GAMMA Avg. [ net] cpm (pts. Ca-e]) - 1. 3 NOTE: All Roof grids Equivalent dpm/100cm-2 -

65.1 were surveyed per Final Report, Max. Cnet) cpm (e pt. I f] > -

6.9 Secton 8.2.

Equivalent dpm/100cm-2 -

355.3 See map for actual grid REMOVABLE CONTAMINATION : BETA-GAMMA locations.

Average (taken G pt. Cf3) -

65.1 (dpm/100cm-2)

Maximum (taken 0 pt. ( f] ) -

91.4 (dpm/100c m-2 )

GAKMA DOSE RATE (at 1 Meter) :

. Average (measured G pt. (a))- 0.1 uR/hr l Maximum (measured G pt. C al )- 0.3 uR/hr P =============r.==========================================================

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FINDING d SURVEYS ON MATERIALS RELEASED TO LANDFILL 1658J

. i FINDING d -- .. Materials Released to V.P.I. -Landfill: 1 Specific survey data for individual . items released to landfill should be included in Final Report.

]

l RESPONSE: The Final Report, Section 3.2.6 " Activated Concrete Removal" gave a description of the surveys performed on each piece as it was removed: q i

3.2.6 Paragraph F.:-

The 10-ton overhead crane was used to rig each concrete block' as it was separated from the shield. The block was weighed and moved to a low background area-where it was surveyed' (Section 8.0). This involved an assessment of the degree of surface contamination and measurements of the dose rate on contact and at one meter from each side of the block. Blocks and " chunks" which were below the dose rate and contamination criteria were transported to the University owned landfill (Table V).

The radioactive portions of the biological shield amounted to a total volume of approximately 1300 cubic feet.

Results of these surveys has been tabulated on the following Table, d-1,

" Inventory - Items Released to V.P.I. Landfill",

miscellaneous materials including soil were also surveyed using micro-R I

. ,ers at 1 meter, using the same procedure as for concrete blocks (See Final Report, Table V).

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Page 1 of 3 Table d-l ITEM INVENTORY TO VPI LANDFILL 1

Survey Results (Net Values)

Contamination (Max. )

Loose Fixed Piece Wei ght (dpm/

100cm2)(equiv.dpm uR/hr No Description (lbs.) per 100cm2 ) g jg 1 Pool Nase 6600 30.9 Bk gnd 1.6 2 SW Corner 4600 ND 3102 2.0 3 S Side W - E #1 5800 82.4 2068 1.2 4 S Side W - E #2 6000 41.2 4136 1.2 5 W End #1 6000 123.6 5687 1.4 6 SE Corner 7000 82.4 3619 0.3 7 5 Side W-E #5 (1/2) 4000 30.9 Bk gnd 0.9 8 S Side W-E (1/2) 5200 ND 2068 1.2 9 NW Corner 1500 ND 3619 1.2 10 SE Corner Partial 1000 175.1 2585 1.0 11 NE Side E - W #1 6600 20.6 5170 1.6 12 S Side W - E #4(10F2) 4000 ND 3619 1.9 13 S Side W - E #3 7600 N0 3102 1.6 14 S Side W - E #4(2 of 2) 2100 ND Bkgnd 1.8 15 N Side E - W #2 (Part 1) 4200 82.4 2068 1.7 16 N Pool Wall 2000 123.6 1551 2.0 17 N Side E - W #2 (Part 2) 1500 20.6 3102 0.6 18 NE Corner 7000 NO 2068 1.1 19 S Side W - E #5 (1 of 2) 4200 86.4 Bk gnd 1.2 20 S Side W - E #5 (2 of 2) 4100 ND 1551 0.7 21 N Side E - W #3 (1 of 2) 3400 21.6 3102 1.4 22 N Side E - W #3 (2 of 2) 4600 75.6 2068 1.0 23 N Side E - W #4 (1 of 2) 3300 1 18.8 Bk gnd 1.9 24 N Side E - W #4 (2 of 2) 3500 21.6 Bkgnd 1.6 25 N Side E - W #3 (1 of 2) 2200 10.8 2068 1.8 26 NW Corner (1 of 3) 5000 194.4 3102 1.8 27 NW Side 4800 30.9 Bk gnd 1.7 28 Bottom Pool (1 of 2) 5200 82.4 2068 1.6 29 Bottom Pool (2 of 2) 4300 123.6 2068 1.7 30 W Side Pool (1 of 2) 5600 175.1 4136 0.9 31 W Side Pool (2 of 2) 4200 20.6 5170 1.6 32 No Description 5200 123.6 3102 0.7 33 No Description 8000 76.3 4136 0.5 34 Bottom 7000 43.6 Bk gnd 1.7 35 Bottom 3000 152.6 1551 1.9 36 Bottom 1200 76.3 4136 0.7 37 Bottom 4000 65.4 3102 1.2 Near S. W. Corner 1900 109,0 2068 1.4

l Table d-l ( Con ' t ) Page 2 of 3 ITEM INVENTORY TO VPI LANDFILL Survey Results (Net Value)

Contamination (Max. )

Piece (goose Fixed Weight pm/ (equiv.dpm Description UR/hr No (lbs.) 100cm2) per 100cm 2

0 1M 39 SE Corner (1 of 4) 900 1 19 .9 3102 1.1 40 -SE Corner ( 2 of 4) 9000 62.4 Bkgnd 1.1 41 NE Corner 8000 41.6 Bk gnd 0.8 42 NE Corner 1500 72.8 1.9 1551 43 SE Corner (3 of 4) 1200 31.2 1.7 4136 44 NW Corner (1 of 3) 1100 20.8 3102 2.5 45 NW Corner (2 of 3) 1500 123.6 1.8 3102 46 N Side E - W #1 5500 152.6 Bkgnd 1.1 47 N Side W .E #1 4500 30.9 0.7 2068 48 S Side (Rod Drive Area) 8000 ND 0.8 2068 49- N Side (Rod Drive Area)

(1 of 2) 4000 ND 3102 1.1 50 N Side (Rod Drive Area) l (2 of 2) 4000 82.4 Bkgnd 1.5 Total weight (large blocks) - 216,600 lbs.

51-85 Small (150 lbs ea)

Chunks of concrete.... 6,000 123.6 0.6 4136(max) 1-20 55 gal drums contain-ing concrete material 0 650 lb s. ea ch . . . . . 13,000 175.1 1.5 5687(max)

Thermal colunn door chunk................... 700 20.6 3102 1.8 Rock drilling Material (3 & 3/4 drums ). . . . . . . 3,4 50 lb s 82.4 Bk gnd Bk gnd TOTAL - 239,750 lbs (119.9 tons)

NOTE: PER SECTION 3.2.6, EACH ! TEM WAS SURVEYED IN A LOW BACKGROUND AREA AS IT WAS REMOVED. CONTACT AND IM DOSE RATE READINGS WERE TAKEN WITH A PRM-7 INSTRUMENT. RAND 0M SURVEYS WITH THE REUTER-ST0KES RSS-lli PIC WERE ALSO TAKEN FOR BACKUP. FIXED / LOOSE CONTAMINATION SURVEYS WERE PERFORMED USING AN OPEN WINDOW GM DETECTOR. MATERIALS THAT DID NOT SATISFACTORILY MEET RELEASE CRITERIA (TABLE IV) WERE PACKAGED AND DISPOSED OF AS RADI0 ACTIVE WASTE.

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Table d-l (Con't) Page 3 of 3 l

Instrumentation used:

Eberline PRM-7 #476 Calibrated - 8/4/86 Eberline E-120 W/HP-210T #5813 Calibrated - 10/24/86 Eberline RM-14 W/HP-210T #2699 Calibrated - 11/6/86 Eberline MS-2 W/HP-210T #1130 Calibrated - 8/15/86 i

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l 2 FINDING e MATERIAL REMAINING IN BUILDING 1658J

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

l-FINDING e - Disposition' of material from area underneath/ adjacent to reactor

,,. pedestal.

It was noted that further explanation of some of the data presented in the Final Report is necessary.

RESPONSE: Section 8.1, Paragraph 5 of the Final Report refers to a survey l that was conducted in Room 10 at the Reactor Pedestal / floor expansion joint interface. Results of this survey are presented {

in the Final Report Appendix B, page 5 of 5, "Special Survey of l

Room 10 Expansion Joint".

EXPLANATION: This " interface" separated the below-grade reactor bio-shield concrete from the 4" thick concrete floor. At select intervals, the concrete was gouged out to allow for direct survey of the vertical surfaces of the joint. Measurements were taken with a thin-window GM detector and a NaI scintillator' (" micro-R" meter). Results are recorded as " cpm /uR/hr" (as noted in the survey map).

In addition, samples of the concrete material were taken and analyzed on the ND-66 MCA system. This was done to allow for a comparison of direct survey meter measurements to actual specific activity contained in the concrete material. Results are listed on a table located below the survey map.

As reported, results of the required surveys are well below the limits of the release criteria (D&D Plan, Table V).

i s

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