ML20138N697

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Forwards Repts Re Irradiation,Decontamination & DBA Testing, Per Request of Y Korobov of Carboline Co
ML20138N697
Person / Time
Site: Comanche Peak, 05000000
Issue date: 09/18/1984
From: Brooksbank R, Rosalyn Jones, Laing W
OAK RIDGE NATIONAL LABORATORY
To: Ippolito T
Office of Nuclear Reactor Regulation
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ML20138M609 List: ... further results
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FOIA-85-59 NUDOCS 8511050324
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Post orrcE sox x OAK RIDGE NATIONAL LABORATORY OPERATED SV MARTes MAReETTA EteERGY SYSTEMS. pdc Septe-ter 18, 1984 Mr. Thomas A. Ippolito Project Director Comanche Peak Division of Licensing U. S. Nuclear Regulation Commission Washington D. C. 20555

Dear Mr. Ippolito:

The enclosed documents are being sent to you at the request of Mr. Yuly Koroboy of Carboline Company. To confirm that these are copies of reports in our files we have initialed each page and signed the cover letters.

Samples not requested have been deleted from these reports.

If there are any questions or we can be of further service please call on us.

Sincerely, Y {. 'M W. R. Laing, Section Head Analytical Chemistry Division R. D. Brooksbank Chemist

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September 18, 1984 Mr. Thomas A. Ippolito Project Director Comanche Peak Division of Licensing U. S. Nuclear Regulation Commission Washington D. C. 20555

Dear Mr. Ippolito:

The enclosed documents are being sent to you at the request of Mr. Yuly Koroboy of Carboline Company. To confirm that these are copies of reports in our files we have initialed each page and signed the cover letters.

Sanp'ies not requested have been deleted from these reports.

If there are any questions or we can be of further service please call on us.

Sincerely, Y. b .  %

W. R. Laing, Section Head Analytical Chemistry Division R. D. Brooksbank Chemist l $$

R. E. Jones Chemist WRL:1p Enclosure cc: Yuly Korobov w/o enclousre l

.v OAK RIOGE NATIONAL LABORATORY OPERATED BY union CARBIDE CORPORATION NUCLEAR DIVI $l0N e

POST OFFICE BOX X OAK RIDGE, TENNESSEE 37830 June 24, 1976 Mr. Charles J. Wiegers Power Industry Manager Carboline 350 Hanley Industrial Court St. Louis, Missouri 63144

Dear Mr. Wiegers:

Enclosed are the results of the Decontamination, Irradiation, and DBA tests we ran on your coated steel panels and concrete blocks. The three separate DBA tests (i.e., tables of test condi-tions, results) are identified by the three different dates noted at the upper right-hand corner of the report sheets. The photographs of systems CBCS 1, 4,12, and 13 and of the de-contamination test panels will follow shortly.

If we can be of further assistance, please feel free to i contact us.

Sincerely yours, L. T. Corbin Analytical Chemistry Division LTC:dmw Enclosures cc: G. Goldberg f0 & Y YNYY

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-o Analytical Chemistry Division Oak Ridge National Laboratory Date: June 21, 1976 Report of Irradiation, Decontamination, and DBA Testing Carboline, St. Louis, Missouri The Irradiation, Decontamination, and Design Basis Accident (DBA) te'sts are conducted, respectively, in accordance with Bechtel Corporation Standard Specification Coatings for Nuclear Power Plants, Spec, tbs. CP-951, CP-952, and CP-956. The tests are designed also to meet the specifications set in both A.N.S.I. Report N 101.2-1972, Protective Coatings (Paints) for Light .

Water Nuclear Reactor Containment Facilities, and N 5.12-1974, Protective Coatings (Paints) for the Nuclear Industry. The DBA test spray solution and the test conditions are listed in Tables 1 and 2. After both the DBA and the irradiation tests, the coatings are examined for signs of cha'lking, blistering, cracking, peeling, delamination, and flaking, according to ASTM standards where applicable. All except the decontamination test panels are returned to the coating manufacturer, ,

The irradiation tests are run using a spent fuel assembly, removed from the High Flux Isotope . Reactor (HFIR) at ORNL, as the source of radiation.

These fuel assemblies are stored under 20 feet of demineralized water. The fuel is 93% enriched U2 " as U30 combined with aluminum. The spent fuel as-semblies are removed after each 23-megawatt day period. Irradiation is done using.the gamma energy from the accumulated mixed fission products. This more readily simulates conditions around a reactor than does a cobalt source. 4 Also, the higher gama activity affords shorter irradiation time to achieve ac-cumulated doses. The dose rate four days after removal of a fuel assembly from the reactor is 1 x 10' rads / hour.

The fuel assembly is 20 inches high. A 20-foot long, 31/2-inch diameter pipe, with one end capped, is used for the air irradiation tests. The capped end is lowered into the four-inch opening of the center of the fuel assem-bly. The open end, above the water level, is covered with an "0" ring sealed ,

flange to which is attached a steel cable and an air outlet hose. The air inlet is located at the bottom of the pipe. The test specimens are connected p 9///[gf Evaluated J2 M uu u -

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Date: June 21, 1976 to the bottom of the cable and lowered into the radiation field. Also at the center of the fuel assembly is a stainless steel clad cadmium tube used as a neutron absorber. This prevents contamination of the test specimens by induced radiation.

The decontamination procedure is as follows: a mixture of fission product nuclides (aged greater than 90 days and less than three years) is neutralized to pH 4 and immediately applied to the test specimens. The speci-mens are previously degreased in alcohol. After the contaminated spot is air dried, the activities of four of the nuclides are measured by counting with a Ge(L1) detector and a multichannel pulse height analyzer. The specimens are then suspended in a beaker of water at 25'C and washed by stirring for 10 minutes. The specimens are removed, the backs rinsed in water, air dried, and counted as above. The ratios of the activities before, to those after the decontamination are reported as decontamination factors for water. The decontamination and counting steps in 25'C and 80*C acids are repeated, and the respective decontamination factors calculated. The " total overall D. F."

is calculated as the ratio of the total activity at the beginning of the test to the total activity at the completion of the three washing steps. All activities are corrected for decay between counts. A computer has been pro-gramed to do all the calculations.

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Manufacturer: Carboline Analytical Chemistry Division Oak Ridge National Laboratory Date: June 15,1976 Decontamination Test Results:

These tests perfonned according to'ORNL Master Analytical Manual Method No. 2 0920 and Bechtel Corp. Spec. CP-952.

ORNL Log Book No. A 7562; 4-23-6 Decontamination Factor (DF)

Percent of Sample Water Acid Acid Number Contaminant 925'C 025'C 080'C Overall Activit{

Removed

~

~

810 Ce-144 5.9 10 >24 ->1500

, CZ-11/ Ru-105 16 1.7 1.7 44 305 Cs-137 >480 6.2 2.2 ->6500 Zr-95 3.6 13 2.0 94 TOTAL 9.6 5.1 2.2 110 99.1

' Percent of total activity removed = (1 - h) x 100. ,

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O OAK RIDGE NATIONAL LABORATORY OPERATED BY union CARBIDE CORPORATION NUCl[AR DIVl510N POST OFFICE BOX X OAK RIDGE. TENNESSEE 37430 August 17, 1978 Mr. Dan W. McBride Nuclear Market Specialist Carboline 350 Hanley Industrial Court St. Louis, M0 63144

Dear Mr. McBride:

Enclosed are the results of the irradiation, decontamination, and DBA tests you requested. The conditions of the two DBA tests were identical and are listed in Table 2.

If we can be of further assistance, please feel free to call on us.

Sincerely yours, L. T. Corbin, Section Head Analytical Chemistry Division LTC:dmw Enclosures Y 9//7/8f ff skw

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Manufacturer: Carboline Analytical Chemistry Division St. Louis, M0 Oak Ridge National Laboratory Date: Aug. 16, 1978 Report of Irradiation, Decontamination,"and DBA Testing  ;

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'.The irradiation, decontamination, and design basis accident (DBA) tests are conducted, respectively, in accordance with Bechtel Corp. Standard Specification Coatings for Nuclear Power Plants, spec. Nos. CP-951, CP-952, and CP-956 (or with modifications as noted in Table 2 DBA test conditions).

The tests are designed also to meet the specifications set in both A.N.S.I.

j report N 101.2-1972, Protective Coatings (Paints) for Light Water Nuclear Reactor Containment Facilities, and N 5.12-1974, Protective Coatings (Paints) for the Nuclear Industry. The DBA test spray solution and the test conditions are listed in Tables 1 and 2. After both the DBA and the irradiation tests, the coatings are examined for signs of chalking, blistering, cracking, peeling, delamination, and flaking, according to ASTM standards where applicable. All except the decontamination test panels are returned to the coating manufac-

.. turer.

The irradiation tests are run using a spent fuel assembly, removed from the High Flux Isotope Reactor (HFIR) at ORNL, as the source of radiation.

These fuel assemblies are stored under 20 feet of demineralized water. The fuel is 937, enriched U235 as U30s combined with aluminum. The spent fuel assemblies are removed after each 23-megawatt day period. Irradiation is

done using the gama energy from the accumulated mixed fission products.

l This more readily simulates conditions around a reactor than does a cobalt source. Also, the higher gamma activity affords shorter irradiation time I to achieve accumulated doses. The dose rate four days after removal of a l

fuel assembly from the reactor is 1 x 10e rads / hour. -

The fuel assembly is 20 inches high. A 20-foot long, 3-1/2-inch

. diameter pipe, with one end capped, is used for the air irradiation tests.

i .The capped end is lowered into the four-inch opening of the center of the fuel assembly. The open end, above the water level, is covered with an "0" ring sealed flange to which is attached a steel cable and an air outlet hose. The air inlet is located at the bottom of the pipe. The test speci- ,

mens are connected to the bottom of the cable and lowered into the

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radiation field. Also at the center of the fuel assembly is a stainless steel clad cadmium tube used as a neutron absorber. This prevents contami-nation of the test specimens by induced radiation.

  • T'he decontamination procedu're is as follows: a mixture of fission product nuclides (aged greater than 90 days and less than three years) is neutralized to pH 4 c.d imediately applied to the test specimens. The specimens are previously degreased in alcohol. After the contaminated spot is air dried, the activities of four of the nuclides are measured by counting with a Ge(Li) detector and a multichannel pulse height analyzer. The spect-mens are then suspended in a beaker of water at 25'C and washed by stirring for 10 minutes. The specimens are removed, the backs rinsed in water, air dried, and counted as above. The ratios of the activities before, to those i after the decontamination are reported as decontamination factors for water.

The decontamination and counting steps in 25'C and 80'C acids are repeated, and the respective decontamination fa? tors calculated. The " total overall D.F." is calculated as the ratio of the total activity at the beginning of

'

  • the test to the total activity at the completion of the three washing steps.

All activities are corrected for decay between counts. A computer has been i programmed to do all the calculations.

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l Manufacturer: Carboline Analytical Chemistry Division l l Oak Ridge National Laboratory .

St. Louis, M0 Date: Aug. 16, 1978 l

Table 1. DBA solution composition, distilled water 0.28 M, boric acid (3,000 ppm baron) 0.064 M_ sodium thiosulfate Adjusted to pH 9.5 with sodium hydroxide Table 2. DBA test conditions

  • Time Temperature (*F) Pressure (psig) Comments start /30 -

O& hy* & /fla 4 2dQ 10 seconds 307 60 Steam injection.

2 hrs 47 min 307 60 5 minutes 307-280 60-30 Injected cold spray.

. 20 minutes 280-250 30 Adjusted pressure.

4 days 250 30 3 minutes 250-230 10 Drained; injected cold spray.

15 minutes 230-200 10 Adjusted pressure.

3 days 200 10 End of test

  • These data are taken from recorder charts on permanent file at ORNL.

ORNL Log Book No. A7562; A7-17-8

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Manufacturer: Carboline Analytical Chemist. y Division St* Louis

  • M0 Oak Ridge National Laboratory 1

Date: Aug. 16, 1978 g

System Identification: x Steel Concrete Block CZil/305 Fin 08A Test Results:

j ORNL Master Analytical Manual Method No. 2 0922; ORNL Log Book No. A 7562; A7-17-8 i

Sample No. DBA Phase Coments**

r

S6-105 spray

_(SA) Few blisters. #6. sides A. B.56-108 soray ISA) Side A: few blisters. f6. Side B: coatinas intact, no defects.

n S6-110 _ spray 4

(SA) Coatinos intact. no defects. sides A. 8.56-112 spray (SA) Coatinos intact, no defects, sides A. B.

i 56-115 _ spray (GR) Coatings intact. no defects, sides A. 8.

j .56-116 spray 4

(GR) Coatinas intact. no defec'ts. sides A. 8.56-119 spray (SH) Coatinos intact, no defects sides A. B.

3 56-120 soray (SH) Coatinas intact. no defects. sides A. B.

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    • (SA) = sand blast; (SH) = shot blast; (GR) = grit blast.

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a-Manufacturer: Carboline Analytical Chemistry Division St. Louis, M0 Oak Ridge National Laboratory Date: Aug. 16, 1978 System Identification: x Steel Panel Concrete Block CZ11/305 Fin Radiation Tolerance Test Results:

ORNL Master Analytical Manual Method No. 2 0921; Bechtel Corp. Spec. No. CP-951; ORNL Log Book No. A 7562; A7-17-8 Initial Dose Rate: 1.5 x 107 rads /hr Test Conducted In: x air water Cumulative Dose Rate: Comments Sample Nq._ 1 X 10' rads 1 x 10' rads S6-101 Coatings intact, no defects, sides A. B.

S6-102 Coatinas intact, no defects, sides A. B.

I Additional Coments:

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CAK RIDGE NATIONAL LABORATORY OPERATED BY M\RTIN MARIETTA ENERGY SYSTEMS, INC.

POST OFFICE BOX X. OAK RIDGE, TENNESSEE 37831 SENDER: y, g, gygg '*

MR THOMAS A IPPOLITO PROJECT DIRECTOR COMANCHE PEAK DIVISION OF LICENSING U S NUCLEAR REGULATION COMMISSION WASHINGTON DC 20555 1

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