ML18044A349

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IE Insp Rept 50-255/79-16 on 790706,09,23-24,0813-14,0918, 29-30 & 1001.Noncompliance Noted:Shipment of Licensed Matl to Licensed Burial Facility in Unauthorized Form
ML18044A349
Person / Time
Site: Palisades Entergy icon.png
Issue date: 11/05/1979
From: Cooley W, Davis A, Fisher W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML18044A347 List:
References
50-255-79-16, NUDOCS 7912190799
Download: ML18044A349 (45)
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See also: IR 05000255/1979016

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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION III Report No. 50-255/79-16 Docket No. 50-255 Licensee: Consumers Power Company Facility Name: Palisades Inspection At: Palisades Site; Covert, Michigan Burial Site; Beatty, Nevada License No. DPR-20 Contractor's Facility; Prosser, Washington Inspection Conducted: July 6, 9, 23, and 24, 1979 August 13 and 14, 1979 September 18, 29, and 30, 1979 October 1, 1979 a_,?,f;--~~~ Inspectors :{;'W .. J. Cooley (RV) {)~ A * 'B'?"btv°is C. C. Peck II- J~ -- 7J (/-5- 79 >I -cr' --- 7'j

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t//1,~ Approved By: W. L. Fisher, Chief Fuel Facility Projects and Radiation Support Section Inspection Summary: /f-S- 7'1 Inspection on July 6, 9, 23, and 24, August 13, 14, September 18, 29, and 30, and October 1, 1979 (Report No. 50-255/79-16) Areas Inspected: Nonroutine, announced inspection of solid radioactive waste activities in response to two incidents involving shipment of free liquid in radwaste packages. The inspection involved approximately 95 inspector-hours on site by eight NRC inspectors. Results: In the area of solid radioactive waste, two apparent items of noncompliance were identified. One item was an infraction involving- shipment of licensed material to a licensed burial facility in an unauthor- ized form (liquid). (Section I, Paragraph 3). The other item was a deficiency involving failure tQ maintain records specified in a radwaste procedure. (Section III, Paragraph 3) . - 2 -

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DETAILS SECTION 1 Prepared By: L. J. Rueter N. E. DuBry 1. Persons Contacted J. Lewis, Plant Manager G. Petitjean, Technical Engineer T. Meek, Plant Health Physicist T. Neal, Radioactive Material Control Supervisor 2. General 3 . This inspection, which began at 12:45 p.m. on August 13, 1979, was conducted to examine the licensee's solid radwaste management program and related activities for compliance with regulatory requirements. -In particular, events leading to two shipments containing free liquid and corrective actions to preclude recurrence were examined. Types of Solid Radwaste The licensee generates three types of solid radioactive waste: spent demineralizer resins (bead and powdered), evaporator bottoms, and compactible and noncompactible trash (filters, paper, plastic, piping, etc.). a. Resins Bead type resins are sluiced into shipping containers and "dewatered" by removing the water through a filter mechanism placed on or very near the bottom of the container. Packages containing steam generator blowdown spent resin beads typically exhibit radiation levels of about three mR/hr at the container surface, while primary system cleanup spent resin beads typically exhibit radiation levels of about 20 R/hr at contact with the container. Shielding for the latter is provided by a certified shipping cask. A 195 cubic foot liner df dewatered spent bead resin was at the facility awaiting shipment at the time of this inspection. Licensee surveys showed radiation levels of about 20 R/hr at contact with liner without benefit of the shielding provided by the shipping cask. The shipment was being held onsite pending verification that free liquid was not present in the container. Such action was in response to an Immediate Action Letter,*dated August 10, 1979, issued by RIII. (The dewatered resin liner was shipped to a burial site on September 6, 1979, after the licensee completed tests designed to demonstrate that the dewatering method was capable of removing essentially all free water in the liners after the liner was dewatered a second time.) - 3 -

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Powdered type resins (Powdex) are used in the condensate demineral- izer system (secondary system). These spent resins are placed in a shipping container in an essentially dry form (no free-standing liquid). The condensate demineralizer system became operational in late 1978. This spent resin, some of which had detectable concentrations of radioactivity slightly above background levels, is presently handled as radioactive waste and is disposed of atcordingly. Earlier batches of this spent resin were disposed of in a local landfill. The licensee and the State of Michigan have been pursuing this matter since early June. No off-site contamination has been detected to date. This matter will be reviewed further during a future inspectfon. b. Evaporator Bottoms c. Evaporator bottoms are mixed with urea formaldehyde (and a catalyst) in SO cubic foot containers (DOT Specification 7A). The urea formaldehyde (UF) mixture results in a solid matrix of UF with the water physically.entrapped in the matrix. Free liquid is commonly encountered in UF solidified waste packages. These waste packages typically have radiation levels of 2S-30 lilR/hr at contact with the container. Licensee representatives at the site stated that use of the UF system would terminate when current inventories run out (approxi- mately 3-4 weeks). A mobile cement proces§ (Delaware solidifi- cation process) is to be used for an interim period of approxi- mately two years at which time the licensee plans to have an asphalt solidification system installed and operational for processing evaporator bottoms and spent resins. No urea formaldehyde solidified waste has*been shipped from the licensee's facility since a June 27, 1979, shipment to NECO at Beatty, Nevada. Three containers in this shipment exhibited signs of leakage upon arrival at the burial site. The licensee is periodically draining and measuring the drained volume of liquid from UF containers still onsite. This information will be used in developing a method of assuring the absence of free liquid in future shipments. Compactible and Non-Compactible Waste Compacted radioactive wastes are shipped in SS-gallon drums. Noncompactible radioactive wastes are packaged in SS-gallon drums o.r plastic lined wooden boxes (7 1/2 ft. x 4 ft. x 4 ft.). These boxes, in addition to being secured with nails, are banded with metal bands if certain weight limits are exceeded as specified by plant procedures. Activities and radiation levels associated with compactible and noncompactible waste shipments are normally quite low. - 4 -

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On Tuesday, August 7, 1979, the licensee notified the NRC that a SS-gallon drum shipped from Palisades to a burial facility was examined at the burial facility and found to be two-thirds full of free liquid. An examination of the licensee's records revealed the following information about Shipment No. 79-02S-S: a. The shipment consisted of 136 SS-gallon drums. b. The individual drums were recorded as containing compacted trash, noncompactible trash, and powdex resin mixed with sand and miscellaneous trash. c. The drums were shipped as Solid, Type A quantity, LSA, Normal Form material, Transport Group 3, on August 2, 1979. d. The highest activity and radiation levels were associated with drum No. 2 which contained 130 millicuries and read 200 mR/hr at contact and lS mR/hr at three feet. e. The total shipment activity was 108S millicuries in approxi- mately 1002 cubic feet. Each drum smeared at less than the 400 dpm/100 cm administrative limit. f. g. General isotopic content consisted of S9% Co-58, 1S% Co-60, 1S% Cr-Sl, and 9% Mn-S4, based on analysis of a floor smear of a contaminated area. The truck survey revealed no problems. h. One drum (No. '12s) was removed because liquid was detected during loading. Information from the burial facility is as follows. Drum No. 136, designated as containing powdex, was found to be leaking water. The drum measured 3 mR/hr at contact. Upon opening the drum, a piece of wet plastic was found floating on about 3S gallons of water. Analysis of the water by the State of South Carolina indicated about 0.3 MPC combined fraction of the 10 CFR 20 concentration limits of water for release to an unrestricted area. The licensee also obtained a sample of the w~ter for both isotopic and chemical analysis, the latter in an effort to determine the source of the liquid. However, neither of these analyses were available on August 14, 1979. In late August the licensee relayed the following analytical results: 7.3 E-6 pCi/ml Cs-137; 3.5 E-6 ~Ci/ml Co-58 nondetectable tritium; less than 0.2 ppm boron; 2.0 ppm calcium; 0.8 ppm magnesium; and 180 ppm sodium. The licensee concluded that the source of liquid was indeterminate from these data . - s -

The license of the burial facility at Barnwell, South Carolina does not authorize receipt of liquid. 10 CFR 30.41(c) requires the transferor to verify that the transferee's license authorizes receipt of the type, form, and quantity of the byproduct material to be transferred. 10 CFR 30.4l(d) specifies requirements for verifying authorization. Failure of the licensee to verify the transferee's authorization to receive the liquid is an item of noncompliance. Further, this shipment violates the licensee's Radiological Control Procedure H.P.6.16 Revision 0 dated October 4, 1978. This procedure states in Paragraph 4.2 under "Precautions and Limitations," "No liquids to be shipped for radwaste burial. 11 In an effort to preclude recurrence of liquid in radwaste packages, the licensee is drafting a new radwaste procedure. In addition to the prohibition against shipping liquid for radwaste burial con- tained in the current procedure, the draft*procedure requirements include: direct health physics coverage of compactible and non- compactible trash packaging; placement of 5 gallons of absor~nt material in each SS-gallon.drum or 10 gallons in the standard wooden box; and a checksheet to be affixed to each container before use which will stay with the container through shipping. The checksheet serves to verify presence of absorbent material, type(s) of material in the package, a check to ensure that no liquid is present at time of package closure and/or at time of shipment, and survey data. This matter will be reviewed further during a future inspection. - 6 -

.;. DETAILS SECTION II Prepared By: W. J. Cooley B. A. Riedlinger 1. Persons Contacted Russell P. Moore, Acting Site Manager, Nuclear Engineering Company Brian D. Thayer, Acting Assistant Site Manager, NECO Steve M. Lehman, Radiation Safety Officer, NECO Darwin D. Garvin, Officer in Charge, Federal Highway Administration, Department of Transportation Stephen L. Bump, Radiation Control Specialist, Nevada State Health Division Milton J. Jury, Radiological Training and Coordination Supervisor, Consumers Power Company 2. Background On June 27, 1979, a shipment of low-level radioactive waste was made from Consumers Power Company to the Nuclear Engineering Company (NECO), Beatty, Nevada burial site. The carrier was Tri-State Motor Transit. The shipment arrived at Beatty on the afternoon of july 2, 1979. (See Bill of Lading, Annex E.) The shipment consisted of 12 metallic cylinders, purportedly containing solid evaporator concentrates, and one wooden box of solid, noncompactible trash. (See Radioactive Shipment Record, Annex B and Radioactive Materials Shipment Record, Annex C.} Upon arrival at the site, Nuclear Engineering was informed by the driver that he had observed liquid dripping from the bottom of the trailer at a stop in Las Vegas and a stop at Lathrop Wells. NECO, thereupon, made a survey of moisture and sediment which had dripped to the metal understructure of the trailer. The survey made by a c~oth wipe indicated greater than 9000 counts per minute per 100 cm . The surface where the wipe was taken was damp at the time of the contamination check. See Beatty site survey sheet, Annex F, dated July 2, 1979. On July 3, 1979, the trailer was moved to a point adjacent to an available trench and resurveyed by NECO. See Beatty Site Survey Sheet Annex G, dated.July 3, 1979. The location of the trailer relative to the trench is shown on the attached Annex A and photo- graph 5 of Annex M. NECO removed the 12 cylinders and the box to the trench on July 3, 1979, as illustrated in Annex A. - 7 - l

On July 5, 1979, NECO completed a contamination survey of the interior floor of the trailer by direct readings. The results ranged from 1,000 - 12,000 counts per minute. See Annex H. *Attached as Annex D is a copy of a radiation survey made by Consumers Power Company on June 26, 1979. Those radiation levels agree reasonably well with those found by NECO in their surveys on July 2 and 3, 1979. (Annex F and G). Attached as Annex I is a Consumers Power Company certification that they have read and understand the requirements of the NECO license number 13-11-0043-02 issued by the Nevada Department of Human Resources. 3. Inspection Findings Region V inspectors arrived at the Beatty site at 8:00 a.m. on July 6, 1979. NECO representatives stated that at least two containers had leaked at some time during the shipment. They said those leaks were still evidenced by a whitish sediment*on the interior floor of the trailer and parts of the metallic understructure of the trailer. They also stated that the truck driver, his wife, and the cab had been surveyed for contamination and released from the site. The driver and his wife left in the truck cab soon after the survey. NECO representatives stated that their Nevada State license had been suspended and that they were no longer receiving shipments of radio- active waste. They indicated that one such shipment had already been diverted from Beatty to an alternate site. NECO representatives also stated that they had been ordered by Governor List of Nevada to repackage the 12 cylinders and to remove the shipment from the State of Nevada. NECO indicated that they would probably repackage the shipment and send it back to Consumers Power, although the method of repackaging and final destination of the shipment were still uncertain. They further indicated that they were reluctant to certify the safety of the proposed reshipment, due to the doubtful condition of the 12 cylinders. A NECO representative presented Region V with copies of information attached to this report as Annex B through H and the information shown on Annex A. At that time, NECO employees were researching possibilities for repacking the shipment. The size of overpacks available to them from their Sheffield site were of some concern, as their inner diameters would barely accommodate the cylinders. - 8 -

The inspectors proceeded to the trench where the containers were located, as shown in Annex A. That Annex also provides the locations of the containers as they had been placed in the trailer during the shipment and indicates the order of removal from the trailer. The inspectors conducted radiation surveys as illustrated in Annex J. Radiation levels ranged from 26 mR per hour to 97 mR per hour, compar- able to the levels indicated on the Radioactive Shipment Record, Annex B. The inspectors then obtained at least one swipe of the outer surface of each cylindrical container. The smeared location, area, and results obtained using Region V counting equipment are given in the attached Annex L. Some removable contamination was found on the top surface of four containers. The inspectors then viewed the interior of the trailer, where a white sediment was evident, indicating that one or more of the containers leaked onto the floor. The general location of the sediment is indicated by the dark lines in the attached Annex K and Photograph No. 1, Annex M. A. swipe obtained in the contaminated area indicated 488 disintegrations per minute per 100 square centi- meters. Additional swipes obtained outside the obviously contamin- ated area indicated a maximum of 54 disintegrations per minute per 100 square centimeters. The locations of those wipes identified as (A), (B), and (C) are superimposed on the diagram of Annex K. The general radiation field inside the trailer ranged from 250 to 600 counts per minute, due primarily to the proximity of the burial trench. Region V inspectors were unable to find contamination levels on the order of 9,000 counts per minute as was found by NECO in its initial truck survey on July 2, 1979 as shown in Annex F and in Annex G. NECO had taken this sample by using a dry cloth over the wet under- structure of the trailer. The 300 counts per minute measurement taken by an NRC inspector at the center of the trailer approximately 3 feet over the contaminated area is indicated on Annex K. No other surveys closer to the contamina- tion were made by the inspector. NECO, however, surveyed this area and other locations on the trailer floor on July 5, 1979, as shown in Annex H. NECO's surveys were made with a pancake GM probe almost in contact with the trailer floor. Their results ranged from 300 to 12,000 counts per minute. The inspectors have no reason to disagree with those results. Picture No. 2, Annex M, metal understructure of cylinder B of Annex A. 9,000 counts per minute shows the white sediment deposits on the the trailer located approximately beneath It was at that point that NECO measured the recorded in their surveys, Annex F and Annex G. - 9 -

Photograph Nos. 3 and 4 show the trailer and its license plate and serial numbers. They also show the placards on the front and on one side of the truck. "Radioactive" placards, as shown on photograph 4, were placed on all four sides of the trailer (See also picture No. 5.) Photograph No .. 5 shows the relative locations of the trailer and the trench containing the box and the 12 cylinders. Photograph No. 6 shows several containers and an example of the cylinder labeling, which read, "NUPAC, USA DOT-7A Type A, Radioactive Material." Most of the word "NUPAC" was painted over on the cylinder shown in this picture. Photograph No. 7 shows a leak near the weld on the bottom of cylinder K as indicated on Annex A of the report. The white globular stalactite formation to the right of the larger rock near the container rim is some of the leaked materi&l. Photograph No. 8 shows a leak near the weld on the bottom of Cylinder B as indicated on Annex A of the report The globular material is in the shade of the adj a cent container. * Photograph No. 9 shows the cloth-like "patch" at the base of Cylinder B. To the right of the "patch" at the container rim is the solidified sediment at the point of leakage as is also shown in Photograph No. 8. Photograph No. 9 was taken while cylinder B was lifted several feet above the ground by the crane shown in Photograph No. 5, which was operated by NECO personnel. Photograph No. 10 again shows the elevated cylinder B. A freshly impacted area to the right of the sediment formation is shown. Photograph No. 11 is another view of the area shown in Photograph No. 10. Photograph No. 12 shows fill plugs and fixtures on the top of Cylinder A. Note that the fill plug was screwed down tightly at an angle. Photograph No. 13 shows an open fill plug. That fill plug was hand-tight and was removed by hand by inspectors. That container is identified as Cylinder G in Annex A. Because the container was so easy to open, it was chosen by the representative of the State of Nevada as the one to be core sampled. That sample was submitted to Idaho National Engineering Laboratory. The results are attached to this report as Annex H-R. Photograph No. 14 shows the fill plug and some fixtures on the top of Cylinder 1. The fill plug was hand-tight. The material within the guard ring appeared to have leaked from that port. However, a swipe of this area indicated only eight disintegrations per minute per 100 square centimeters. See Annex 1 for swipe results. There was no sediment visible outside the guard ring. - 10 -

4. Comments on Attachments B Through R Annex B is a Radioactive Shipment Record executed by Consumers Power Company, personnel at the Palisades plant. The item numbers on that record should not be confused with the Region V notation on Annex A, which indicates the order of removal of the cylinders from the trailer. Annex C is a Radioactive Shipment Record executed by Consumers Power Plant personnel at the Palisades facilities. Both Annex B and C indicate that the shipped material is in solid form. Annex D is the vehicle survey performed on June 26, 1979 by* Palisades personnel. Annex Eis the Bill of_Lading. It is noted that a minimum of descrip- tive information on the shipment appears on the form. A NECO representa- tive stated that NECO refused to sign the Bill of Lading as the consignee because they did not want to accept a leaking shipment. Annex F is a Beatty site survey sheet showing the NECO survey performed on July 2, 1979, at the time the shipment arrived. It was the first written indication of radioactive contamination outside the trailer. That survey has.been discussed previously. Annex G is a Beatty site survey sheet indicating the results of the survey on July 3, 1979, after the trailer had been relocated to the trench. It shows similar results to those in the survey of Annex F. Annex H is a Beatty site survey sheet showing the results of a survey taken on*July 5, 1979. That survey was made by taking direct readings on the.interior floor of the trailer with the probe approxi- mately 2 inches*from the floor. NECO routinely corrects its survey instrument readings with a 50% geometry correction and a 10% mixed fission-product.energy correction. The survey readings shown would therefore be multiplied by approximately 20 to convert them to disintegrations per minute. Annex I is signed by a representative of Consumers Power Company. Inspectors have no assurance that Palisades possessed a complete and current copy of the NECO license. Mr. John Vaden of the State of Nevada, in a telephone conversation on July 11, 1979, indicated to Region V that the phraseology of the paragraphs 5.4.6.l and 5.4.6.2 referenced in Annex I, taken along with other written communications to NECO from the State of Nevada, prohibited NECO from receiving any liquid radioactive waste . - 11 -

Annex J is the Region V record of the radiation survey made of the Consumers Power Company shipment as it was located in the trench at Beatty on July 6, 1979. The surveys were made with NRG instrument number 004280, which was calibrated in June of 1979 and was not due for recalibration until September 9, 1979. Annex K is a Region V radiation level and contamination survey of areas inside the trailer. This annex was discussed previously~ Annex L indicates the results of a Region V swipe survey made of the exterior surfaces of the 12 containers shipped by Consumers Power Company. These results were discussed earlier. Annex M consists of 14 photographs at Beatty, Nevada of the* liners and the -transport trailers. Annexes N-R are the re~ults of Idaho National Engineering Laboratory's analysis of core samples from cylinder G. 5. Summary ~ Conclusions The purpose of this inspection was to gather first hand information at the Nuclear Engineering Company (NECO), Beatty, Nevada, low-level radioactive waste disposal site regarding a shipment of radioactive waste from Consumers Power Company, Covert, Michigan to the Beatty site. The inspection included acquiring copies of pertinent records which had accompanied the shipment and others which had been generated by Nuclear Engineering Company at Beatty. Those records included radiation and contamination surveys; radioactive material shipment records; and certain available shipping papers. The inspection also included independent measurements by NRG Region V personnel of radiation levels and contamination levels to verify that type of information already available from the records listed above. A number of photographs were obtained showing the containers and the shipments. A representative of the State of Nevada Health Division obtained two core samples of the contents of one of the shipping containers and presented one of those samples to the Region V representa- tives. Region V sent that sample to the Idaho National Engineering Laboratory, Chemistry Division, to be analyzed for gross beta-gamma activities and Sr-90 content. The measurements made by Region V personnel are in substantial agreement with those obtained by Consumers Power Company and Nuclear Engineering Company both with regard to radiation and contamination levels. Substantial agreement also appears to exist with similar data obtained by the State of Nevada Health Division. Those measurements indicate about 40-60 dpm 300 square centimeters removable activity from certain contaminated areas of three containers and 400-500 dpm/100 square centimeters on the interior floor of the trailer. Observations by Region V were that three of the twelve cylinders in - 12 -

the shipment showed evidence of leakage; two at the cylinder base weld and one at a cylinder drain plug. A fourth cylinder appeared to have leaked at a fill port at the top of the cylinder but swipe results did not show appreciable contamination. See Annex A and Annex L of this report for cylinder and swipe identification. The contamination found on the floor of the trailer and its under- carriage was caused by at least one of the leaking cylinders. - 13 -

-.* -* DETAILS SECTION III Prepared By: B. L. Jorgensen 1. Persons Contacted . T. Meek, Plant Health Physicist T. Neal, Radioactive Material Control Supervisor 2. General 3. The licensee was notified in early July 1979 that a routine shipment of solidified bottoms had arrived at the Nuclear Engineering Company's (NECO) Beatty, Nevada waste burial facility with two (later deter- mined to be three) of twelve containers leaking liquid. Pursuant to a request by the NRC Region III Office of Inspection and Enforcement, the resident inspector reviewed procedures and data relating to "liner" packaging and shipment, focusing on the shipment in question, which was dispatched from the Palisades site on June 27, 1979. The inspector also accompanied Messrs. F. Tupper and W. Hill of the Office of Motor Carrier Safety, Federal Highway Administration, during their review of this matter at the Palisades site on July 9, 1979. Solidification Process The solidification system packages a catalysed mixture of urea- formaldehyde and water, primarily evaporator "bottoms," into steel containers of about 50 cubic foot capacity. These containers, right circular cylinders approximately 48 inches in height and diameter, are designed for compatability with solidification system hardware. Since the catalysed mixture is acidic, the interiors of the containers are coated with a corrosion resistant, heavy paint. The inspector physically examined eight containers awaiting filling, including a check of the quality of the interior coating. These containers were all found to be in good condition. ' After the containers are filled, the mixture "sets up" within about 15 minutes, and "cures" over a period of hours. According to licensee personnel, this curing process includes a physical volume shrinkage of about 10 percent and is accompanied by an equivalent release of free liquid. The licensee's procedure is to place each filled con- tainer on a drain stand, removing top vent plugs and a small drain plug very near the bottom on the side of the container. The drain stand is designed so* the container is tilted toward the drain plug. The free liquid drained is recycled through the system. The licensee estimated typical liquid drainage volume at about 30 gallons. In some cases, this information is written on the side of the container. - 14 -

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The draining containers are usually on a drain stand at least 24 hours. The controlling procedure (H.P. 6.16 Radwaste Procedure - Low Level) then requires a check of each container with the drain plug open, to verify the absence of "drainable" (5ml/min) water. The licensee stated this verification has been performed for all con- tainers, including those in the shipment of June 27. Procedure H.P. 6.16 also requires data from the free liquid leakage check to be logged. This was not done for any containers in the thirteen shipments made since the effective date of the procedure (October 4, 1978) including those on the shipment of June 27, 1979. Since adherence to Procedure H.P. 6.16 is a requirement of Technical Specifications 6.8.1.a, failure to log the required data is an item of noncompliance. When draining is complete, the containers are sealed by replacement of the vent and drain plugs. Contamination smears and direct surveys are taken, data tags are affixed to the containers,and the containers are stored until shipment. The storage period may vary from days to weeks or months. The licensee indicated that small amounts of liquid may accumulate while the sealed containers are stored, estimating a one or two percent accumulation *by volume. Free Water Content of Onsite UF Solidified Containers At the request of the inspector, the licensee opened and drained thirteen 50 cubic foot containers which were in storage on the site. The containers had been processed at various times over the preceeding several months and had been drained shortly after they were filled. The inspector observed this draining for nine containers; the volume drained averaged about 3 1/2 gallons with a minimum of less than a gallon and a maximum of eight gallons. Although the time in storage ranged from days to over three months, the amount of drainage did not have any apparent relationship to the storage duration. Two containers were marked to indicate that 20 and 70 gallons had been drained in the day or two after solidification . - 15 -

DETAILS SECTION IV Prepared By: C. C. Peck 1. Persons Contacted J. Harvey, President, Southwest Nuclear Co. F. Beierle, Southwest Nuclear Co. T. Neal, Radioactive Material Control Supervisor, Consumers Power Co. H. Curry, Quality Assurance Analyst, Consumers Power Co. T. Frazee, Radiation Cont~ol Specialist, Washington State Department of Social and Health W. Wilcox, Health Physicist, Southwest Nuclear Co. 2. General Southwest Nuclear Co. was engaged by Consumers Power Co. to receive the liners (initially sent to burial site at Beatty, Nevada), remove any remaining liquid, and repackage the containers in packages acceptable for burial at a licensed commercial burial site. 3. Draining of Waste Containers An NRC inspecto*r from Region III observed the draining of residual liquid from the twelve Palisades liners on September 29-30, 1979, at a facility near Prosser, Washington, acquired for the purpose by

  • Southwest Nuclear Company. The procedure for draining the containers

was prepared and performed by Southwest Nuclear Co. and approved by Consumers Power Company. Two representatives of Consumers Power Co. and a radiation control specialist from the Washington State Department of Social and Health Services observed the draining in addition to the NRC inspector. Liquid from each liner was collected in a 10-gallon container which was measured to permit determination of the liquid volume drained. The liners were tilted during draining to permit flow toward the vessel drain hole. The liners were allowed to drain for a minimum of twelve hours to a maximum of about 28 hours, after which the observers concluded that draining had either ceased or had decreased to an insignificant rate. The difference in drainage times results from the fact that about 16 hours were required to prepare, position, and begin the draining process, one liner at a time. When draining of the final liner had begun, all were allowed to drain overnight and drain plugs were reinserted the following day. - 16 -

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Pertinent observations and conclusions of the inspector are listed below: a. Three of the twelve liners were apparently dry. No liquid was collected despite efforts to promote draining by rodding through the drain hole. One of the three was identified as a liner that had shown evidence of leakage at the Beatty, Nevada burial site. The other two were not known leakers. In all three instances, there was evidence of vessel corrosion, particularly at the bottom seam. There was also some indication of leakage into the Bentonite clay in the Argonne bins associated with the three liners. b. A total of about 57 gallons of liquid was collected from the nine remaining liners, ranging from a low of 3.4 gallons to a high of 8.6. gallons. Two of the original leakers were in the group. There were indications of liner corrosion and probable minor leakage into .the Bentonite clay from the two original leakers and three other liners. The volume of liquid drained from the two leakers was.about the same as the average for all nine liners (six gallons). Disposal of Liners and Drained Liquid The liners were repackaged in their Argonne bins and the collected liquid was absorped in diatomaceous earth in three SS-gallon drums on September 30: The twelve bins and three drums were shipped to Nuclear Engineer,ing Company's waste burial site at Richland the following day (October 1), where the inspector witnessed their interment . - 17 -

1. Persons Contacted DETAILS SECTION V Prepared By: L. R. Greger A. B. Davis L. J. Rueter R. DeWitt, General Manager of Consumers Power Company J. Lewis, Plant Manager H. Keiser, Superintende~t of Operations and Maintenance T. Meek, Plant Health Physicist T. Neal, Radioactive Material Control Supervisor 2. General A meeting was held with the licensee management representatives identified in Paragraph 1 on September 18, 1979, to discuss NRC inspection activities regarding Palisades radwaste performance in light of the two recent incidents involving the discovery of free liquid in supposedly dry solid radwaste containers and to discuss the licensee's general performance in the radwaste and radiation protection areas, including past problems and the prospects for future improvements. A subsequent telephone conversation was held with Mr. Lewis on October 26, 1979. 3. Urea Formaldehyde Shipment to Beatty, Nevada As previously noted in this report, three of twelve urea formal- dehyde solidified radwaste containers exhibited signs of leakage upon arrival at a burial facility near Beatty, Nevada on July 2, 1979. The containers were overpacked and held in storage at a contractor facility near Pleasanton, California until late September, at which time the containers were drained at a contractor facility near Prosser, Washington and subsequently buried at a licensed burial ground near Richland, Washington. Several locations at which the shipment stopped between the Palisades plant and Beatty, Nevada were surveyed for signs of leakage. No radiation levels in excess of background were detected. Causative and corrective actions regarding this incident were discussed. As a result of previ?ys problems with free water in urea formaldehyde solidified radwaste,- Palisades had commenced a program of draining l_/ IE Inspection Report No. 50-255/76-20 - 18 -

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all urea formaldehyde solidified radwaste containers shortly after processing. This draining commonly yiet9ed free water in quantities up to 5-10% of the container's volume.- Recent studies at Brookhaven National Laboratory also recognize that free w~7er is routinely present in urea formaldehyde solidified waste.- NRC (NRR) is currently evaluating the continued acceptability of urea formal- dehyde as a radwaste solidification mechanism. Although, as noted previously, no record existed to document the initial draining of the twelve urea formaldehyde solidified containers which arrived at the Beatty, Nevada burial site on July 2, 1979, it is felt, on the basis of the subsequent draining of these containers in Prosser, Washington, that the containers had been drained shortly after processing as claimed by the licensee. The quantities of water drained from the containers at Prosser, Washington were not excessive when compared. to the expected free water content resulting from a properly utilized urea formaldehyde solidification system. In light of these findings, no enforcement action is planned regarding the transfer of small amounts of free water in the twelve urea formaldehyde solidified liners. The license was, however, notified that future such shipments must meet the transferee's effect~ye license requirements in all regards, including free water. - Based upon licensee records of the radioactive contents of the twelve liners and selective verification by the NRC (analysis of a sample from one of the containers), the shipment contained less than Type B quantities of radioactive material and, therefore, was exempt from NRG packaging regulations contained in 10 CFR 71. Department of Transportation shipping regulations apply in such situations. As noted in this report, DOT representatives were present to examine activities associated with the shipment at various times. At the September 18, 1979, management meeting, the licensee committed to drain the twelve containers and to provide the NRC with ample notification to allow NRC the opportunity to observe the draining. As noted previously, the containers were drained on September 29 and 30, 1979, in the presence of an NRG inspector. 2/ Ibid 3/ Development of Free Standing Water Criteria, Neilsen and Colombo, dated June 19, 1979. !+/-_/ Letter from Keppler to Youngdahl dated 8/10/79. - 19 -

The licensee further stated during the September 18, 1979, meeting that use of the urea formaldehyde solidification system had been discontinued and that present.plans were to use a contract cement solidification service until installation of a bitumen solidi- fication system is completed in two to three years. The licensee was informed that one item of noncompliance for failure to follow plant procedures for recording quantities of liquid drained from urea formaldehyde solidified containers was found as a result of this portion of the inspection. 4. Liquid Shipped to Barnwell, South Carolina As previously noted in this report, a SS-gallon drum, supposedly containing dry radioactive waste, was two-thirds full of liquid when opened at the Barnwell, South Carolina burial facility on August 7, 1979. The liquid was subsequently solidified at the burial facility before being buried. Causative and corrective actions regarding this incident were discussed. According to licensee personnel, analysis results showed that the liquid was water containing small amounts of several radionuclides. Although the water's origin was not positively identified, licensee personnel suspect it was rain water which entered the drum at the licensee's site. The licensee stated that a procedure (Procedure H.P.2.44) designed to preclude future such shipments had been imple- mented and would be utilized for all future dry radioactive waste shipments. The licensee was informed that one item of noncompliance for failing to ensure that the radioactive material transferee was authorized to receive the transferred radioactive material (free liquid) was found as a result of this portion of the inspection. S. Secondary System Demineralizer Resin 6. The licensee agreed to keep the Region III Office informed of develop- ments regarding the location and analysis of possibly contaminated powdered resin (condensate demineralizers) which had been disposed of in a local landfill. The licensee was informed that this matter would be reviewed further during a future inspection. Licensee Performance The inspectors noted that licensee performance in the radiation protection and radwaste areas over the past several years has generally been below average in comparison with other Region III licensees. This observation is based upon several factors, including station personnel exposures, noncompliance items, and subjective evaluations by the regional inspection staff. - 20 -

Licensee personnel acknowledged the inspectors' comments. General corrective needs were discussed, including implementation of licensee commitments for strengthening.and improving management control over the radiation saf 5JY program as stated in a letter to the NRC dated October 27, 1978.- The inspectors noted that the recent personnel change in the Plant Health Physicist position provided an excellent opportunity to upgrade the radiation protection and radwaste programs. Licensee personnel indicated that efforts to upgrade these programs would continue. Attachments: Annexs A-R 'ii Letter from Hoffman to Keppler dated October 27, 1978. - 21 -

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- - I TOTALS TOTALS iG ~ =:..: .. :;:.~~: (::_ * I .* ,,_.. ;,,., - This is to certify that the abovo named articles are proporly classified, doscrlbcd, packaqo:d, marked, a"d labeled, :ind ore in oropor conditlo" tor Transpor::ition *ccordil"'(l to tt<e Jpplic:ibla rrgulati, of ti.e Ocp:irtmont of Tronsport:ition, It is :ilso certified that tho articl°' ;:ire in cornplial"'ca with ell regul:niont applic:iblo at tho doslgnatacl dis;:ioul site. , I . I O~l'/~:\\'S COPY ~ . . *' *. ' ,,. '* .#- _, 1 .. ~ *** Authori,~cl Sognatura i

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. LENGTH WIDTH HEIGHT {The g"'oturc t~re nc~ .. o-lrOiJr-1 iO"i"AL TR:,ILEP. SPACE_o_cc __ u_?_l_E_D __ 1-o=-":.::'.!..*.:.'.:.:".:.*..::O:.::"'.::"::".:.::."' ~~~*~_I __ _ Chci*gt"\\ od"o"'"cf UNlESS A GREATER VAWE IS DECLARED, THE SHIPPER HEREBY RELEASES THE VAlUE TO $5000.00 PEP. TON OF 2000 POUNDS FOP. EACH ARTIClf. ARlll\\'ED Al SlllPl'ER l.OAIJING CO.\\IPLETED l'l:R MANE NT PO~T UATE TIME . clt;,:*~1.

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"'. . . ... ... 7lvc1< Uh~>> L5/J.1i'1/1J,/ .//{;)~** ... : .. ~_..., .. ****:-:~'"** .. * ..... *~ . .. . .:*- ..... ... * . ~. . .*

,
..

'Re.'""'.a.J'Ju: r1c;t.Wli..i..eA Q.,.ltJ!..ateA than t.Ae. t1cf...i..on le.vei.A" M!.([J.li..N!. f:Jr.e. .inrned.1.ate. rwti.Li.I:.!:r. U .. Dn 0 !. t..lte. 'P( & 5 0. c l..N:J.e l.n. Jted. l.nk. {} ni..eM. oth<!.Jw;i.Ae. - "J. *3 ',./. , .,., d.i.!1. !:. f.o n.. Le vr!JA C?Jt.e. i.n.. ~ '. em/li.v1.J..l1..1 a 'ri.i:1 ,11;ze.a, '- Lo cat lo n, 1 cvu?. /1. -Ur.. A cti.v i..t . * . A c.Li..v d~ .i.n. u[ ;_/ml No~ Jlme. Volwne. Be.ta tflnha. --*-* - .. s,;,,ver;.01t.: ~ ,,/ ~1 ...._/ /

==-~ ,,,. ; _ W'-c.A-n'...:lf,

' ' " ( ( CERTIFICATION THIS IS TO CERTIFY THAT. I HAVE READ AND UNDERSTAND THE REQUIREMENTS .OF LICENSE #13-11-0043-02 ISSUED TO NUCLEAR ENGINEERING COt.IPANY (NECO) BY THE NEVADA DEPART~IENT .OF HUMAN RESOURCES FOR THE RECEIPT AND DISPOSAL OF RADIO-. ACTIVE MATERIALS AT BEATTY, NEVADA, AS DESCRIBED IN

.

. . J PARAGRAPHS 5.1.1.3; b.l.1.4; 5.1.1.5; 5.1.1.6; 5.4.6.1; and 5.4.6.2 OF THE :NECO *SITE OPERATIONS MANUAL, AND I FURTHER CERTIFY THAT THE MATERIALS IN THIS SHIPMENT ARE IN CO~IFORMITY WITH THOSE REQUIREl\\IE:N""TS:

  • ~

DATE

,, -ANNi=x I-.

-- Lev~ls .a.P-pt:o°t\\ 0*n10.h:I \\) . 6 1ll\\chE;'_s_f('Q01_Tup- - I * 1, d eic_.:s ___ _ A_ .. ~-. 37r'<'l-r/h'r' G - Gonw'/Ar _________ _ .5 ... *-*--= ........ 1..3 rri.r-/IY:r ---* ...... *- .......... H. -~ _Cf 7 1111,//1'( ........ _ .. -*- C - .43D:w/hr ___________ .... __ .... X: ... -.. .... '-1-0m\\'/hl._ ...... ....... . _ D - ........ 3~ rwr/h-r ...... ... .. .,) - 2crm1/li1 . E" -:-:-.... . '-Ho m r /hr. . . .... _ ...... .. . K ~. ..?J '!° rl'I r /h -r .... . . .. . . --........ --L--=--.. -~/..O .. rnr /hr ____ .. __ . .. . L. - . ~(Q ml/~v- .. X Leve Is a{, ;2 11 fro~ St>.1'fC\\.c~s o-t C~linder- sides ___ ....... 2/_r.... J . ..= .,) iro rn CoYl \\ct ii)~ rs 17rt1r/nr lihe (60 K couh-ts per h1inut-c.)

  • s\\):fV~l.r~ ma.de ~~ 'tt\\t\\\\cfli~

le\\/~\\s C\\\\"CIA\\\\c\\. c.~lind~rs ~J\\ .... JL\\ \\'j.--~r-1_sn __ _

.... - /

  • ' - .. '

I \\ I l1 \\( I\\ L I . \\ I( . I \\ /0 /-' - - ' - .... ' .,,, \\' sw~e-B ,~: . ~. G s~i1P1=+\\ ,, ', ', ~ '~7 I J 1/ , __ ,, --- , J

s

11 F I \\ ' ' ' J'l.. I ' . ~ / . _.... --- - I ~ni. 0 1lcr c\\oo..-:. BM\\<. ~ Tro.i le'f

*--***><4-00cptn ci.t left

batto F1"I *c~ ... ~ -{:Y't\\ i l_e'i - o u-t side, -t. '<""<.\\; I~'('- X .B_~sctl9.1\\ .. le_~~L:_sv.-< .. v.e ~s ... -~o.'KeV\\. With T. A. PUG - .I AB ... su.f!/.e.tj. me.t~Y--..... with . J~.: 7 probe. ~~O_Q~.?.B.Q_. __ DLH! .... --f o'\\.. ___ .f..e.c:ct {1,b~a.-f;lo11 . ~11 9/9/7.9, _ .

  • -*

--. _D.o..~_K_ al\\eo..~ ,,~K.\\\\ccc.-Ce locations of rontcd11e\\' see.pct5e. Netts : ~o cp~-'C~o..d_u!J~-.UJ.C\\S __ +/-c.1_r;e_~ __ wtth __ i:-he. meter f"'Obe .. *°' boirt .. 0 1 ove_r_{b_e,___$_~c(_.iJ11.eL1._t_ . n~<::tec:rte.ct __ b':) .c~ Ii 1"cl.ec_ .. A, ... No .bc<cK~ ~""ow 'd .. l{}C(~_ ---*~ lt bitct ,-f-cd. .. . . Tu~_J)\\C{h . ba.ck5 ro.u~,_c\\ __ w.a. s ...... cl 1;t.t._ *c.. the. .. p l""o>< 1 .1:n1.f~ ._.a __ +/-.h.e_. __ l:Jv..O c\\,{_ *--t r_e_11~.I\\ (-5.r::.c.-Afi NEX .... A _). ..

  • R~~ulh,

-~.wlp_e._4c.a.n+/-a.1nit,tttecLo.r.e.C\\ .... : __ if ra i __ cl__is.!.~ft_e~ f~tlo1_~--* pe'<" __ M\\hu-k. __ (d.pm)) swipes wen~. of Swipes: ~w:1pe. __ e:i, 1'cleo.\\'\\' o:re.<X..: IO <ip.IY\\. ________ ... .

*--*-* _____ ..

to.k~n .eve' .SWi.pc c, dal'llp q\\eo. ~~I ho.cl evident!~ spilkcl i1\\ {J*\\\\$ c~({'<'.4 (G.,H)_ a.p?'OXJllia{c~ . d.l..l'C.LI'°;) s ()\\\\!. p \\" i 0 '(" s "i ~"' e "-l J : 5 ~ d F Yh I 00 en/* . - ANNEX K

( W;pes showi 113 no fenlD\\lct b!e ?°'cKg(ov.n cl: C31 i ncl e (' A 1 5 i cle.> C 5 fl ncl e 'f B , tcp s uhija~ c~ 1i*nde' 6 J nea.-1 Je*crK ;-pa.+ch C:;I fn d_er E, si ~ (~I i n cl e \\A. F, 5 i cl..0 (~I i n d e \\ G / r1u:l.Jv C ~ Jin cl el" I / si rl..0 c~ I; ri J c r- J, sd.l:.e,. ( uJipes shcwin9 sorne \\"'elYlOVable ?,'O co1ftan1i11cr{-ic:;t1. Ale fen10VQb/e. alpha cc1r{on;~1H-iiicn (1ja,S de..t-ed:ed. CJ \\;f,c{('.",~ G) +o-p SU,h~~

53 d~IY\\ . c~ Ii rid E'1 c J tcp Slt~~te 0'~ wipe) : 58 d PM C ~ I; 1-\\ de.' D / to~ .s ~

t.J l d f tr\\

Cv\\ihde~ H 1 *"-opswiwo.: tJlf-rlt\\m.. . . ) v-_......_.. I This l.V*pe over . (~Ii (\\de\\"' ~ , top s v._,~*: ~ d f tr\\ ~ opp\\aXi n;c,t_{C?../j Joo cm"<. kJ;pe_~ t-aker. Ju.ly <0 1117'1 <1.nd counted 6!\\ Ju.f;j'7,1'17'l. NR c.. ~ ooo3i3 I pc-55 ~~s +!otV pro?ori ic110.I (t 1 l{flfe~-- used f:o-c anaf~sls .. Cov.n{er ef-Picic:>t'c,:;: 5?% * Backj""°"6L-\\nct; '+7 count-$ pet'" t11*itHrb::_. - ANNS/< L

' '

ANNEX M, p. l Photograph #1: Interior of Tri-State Trailer showing whitish residue Photograph #2: Under- carriage of Tri-States trailer showing more of the white residue

... \\ Photograph #3: Shows the license plate of the Tri-States Trailer Photograph #4: The front and one side of the Tri-States Trailer, its identification 1imm ..... number, and placards ANNEX M, p.2

_ ..... *

ANNEX M, p.3 -.. 0-4 .... ;~ Photograph #5: The relative locations of the Tri-States Trailer and the containers in the trench Photograph #6: The labeling on container K (see ANNEX A) J

l"* -- ANNEX M, p.4 ........... - Photograp~ #7: The whitish sediment is visible to the right of the rock near the base of container K (in center of photo) Photograph #8: A stalactite of whitish residue is visible near the base weld of the yellow cylinder B (in the shade of cylinder A)

..ANNEX M, p.5 Photograph #9: The crane-lifted cylinder B . The cloth-like "patch 11 (see ANNEX A) is visible on the left, and the stalactite of whitish residue (also shown in photo #8) appears on the right of the cylinder base Photograph #10: An impacted area to the right of the residue on cylinder B *

-" .'

ANNEX M, p.6 Photograph #11: A different view of the situation described in photo #10. Cylinder B. Photograph #12: A fill plug on the top of cylinder A was screwed down at an angle .

_ ... ' ANNEX M, p.7 Photograph #13: A hand-tight fill port on cylinder G, which was opened by inspectors. A core sample was removed from this cylinder and is being analyzed by INEL. Photograph #14: The top surface of cylinder L. See body of report for details.

j

i1 1. I! ":J-104 ~ .. \\ {Rev. 11*77) ** UNITED STATES 0 .T~vH::NT OF ENERGY l "I,: IDAHO OPERATIONS OFFICE C "'l I (Z,..-{,HJ er- ANALYTICAL CHEMISTRY BRANCH 'I

  • *

Rou*ine ' ,.Jf" i 1:;\\~ (. '(-\\ \\/ URGENT ./1,_ ~ - ll <(-'"'A lc*'~ to dct.:*t"n\\,1\\~: -"-(.' . c SAMPLE RECORD SHEET /* ' ' i I .1

  • I

./ ' ., I* i I it C' A,'(/"' R . Jr SAMPLE FROM: ' <** ! ,J *. ,, r J e cy <211 - St*r.*t)lr', 1f;.!rn1f3, -- l * *. . ,,.-. I ,, I .. COLLECTED BY i\\J~wo rr rt 7'~((~:r-.- lr.::'Q rh ), 't DATE SUBMITTED: ~ij(~' i 1,.:1zz SAMPLE SAMPLE DESCRIPTION NO I DATE HOUR ~:':; J.:~:(. 7/ 1-r 1 FVC: r)'r e.. /"' f* ( "'r rn r. 1<'.1.me**cr a1, ' .,

if ~l/I /0Ji<l,

.(-; J lc:c{ vJi{-h C..t pOu)d en\\ Sllb5t 1:.t.'1C"1- ob{o.i ncd *.f-1'() )'7~ 0,, c o n + c.\\ 1 n e " ,~t: rv1.:co. l'hnt c('n*tal ilCf- ll)ct 5* -hlf eel w;-f:h ~varoY.({to '":-.,.._ D.. \\; <:..-. ;1(:-<; 0 .... ,-1-- 1- -* C I ' "- - l .. I {" fl be ,_:i.: OI n.> f\\ p.A' 1(J. b (flt c,,.:* /IJif itct ,/\\ .. b~_) { h 1.2, U'l\\*CA -{-o ( ni o Id' el 1 ~y/ e / - ,.), . .- , Ff'cJ((:'C t:!, 0\\""l'jihC\\ \\ \\ 1 \\ <J l. \\:\\ Ir\\ I Ytbll\\ lO(t".:":> r\\**o ,_ h-\\ ~) \\\\ '11\\ bo'fic.. c.r.c*icl, I SAMPLES RECEIVED: r{ /J.J/'1'\\) /'; / 7. /' ..... ., ANALYSIS COMPLETED: II .~-*O I I> '/*~ ..... . f.. . -* .... n l / s'21Q NOTIFIED: t< s~. I l:I ') ,IJ,. r DATE: I ANAL. INST. QUANT. DATE COUNT GROSS FOR USED USED CNTD. TIME COUNT r.1- (1 h, I,., - ( 'r;~\\CCi ... n Sr* Cf() (J.5 r7 /11 ::--

~ 0

~'?S I : o-.....J '. - .... r ..... 1* i~ ') ~ ... -~ ... ~~-., .. ~ .. " ' . -~ ' - - -* ... rz./ 3 r.(/")' I ) -- BKGD. - ~'O -. -* ... .. --

  • -

- -*

.. -

AENCE: HEALT~sERvlce ~A!lOOATORY . I\\ ( \\ ~-\\ *:_\\* ~ \\ .... lilt SERIAL NO

    • f..;\\.::*,...,.<;

.Y\\ 12.1 i ANALYZED OY: ~l~,J ,,,. .. ,. /~"- .**J .. / v . ..__, _,// I ', /; i. J? APPROVED DY: /7 (// (_ /_,).// l./'.. ~ SECTION CHIEF NET RESULT !.1 CJ'

  • COUNT

)J. C;/ rr* -*** 5"'/.!; (~?.?10 r-) .... .1 - ,_) F -t:- - ~ I J ____ ,._J__ - .

*** *-----**--

-*

  • nANDOM UNCERTAINTIES REPORTED A.<~E 1 STANO.Ii RD DEV:ATION, 10:-SMALL NEGATIVE ANO OTHER RESULTS< 2CJ"AnE INTERPRE1El1 OY HSL AS

INCLUDING "ZERO" OR AS _NOT DETECTED. IF APPROPRIATE. ESTIMATES OF POSSIGLE SYSTEMATIC ERRORS ARE flLPORTED IN PAf1EN1HESES. - A~IAlr"V I\\ I *-

--~----~--~~-.;...... ..... , -**-- ..... M----*-***"-*****-*-*-,~--..... "'" -.... f I r => z z m x 0 I UNITED STATES DEPARTMENT OF: ENERG'T IDAHO OPERATIONS OFFICE ANALYTICAL CHEMISTRY BRA~~Cll' SERIAL 110. I 1700~A ANALYZED BY JSM, CR "'

A PP RO v ED BY ______ 9!i.YLn_0l §192iEit_~ . D::b G. Ol:on COLLECTION DAiE: 187.5417 DETECTOR: 2 DESCRIPTION: 1. 05E+01 G: lsJATER ¥.: HALF-LIFE AND RESULT ARE .. FOR NEAREST LONG LI\\IEI1 PARENT. NEVADA ST1HE HEALTH S. BUMP MATERIAL FROM PVC PIPE A llA L ~*SIS DECAY COUNT TOTAL GROSS BI( G JJ MI MOR MET DATE . TIME TI ME COUNT COUHT COUNT COUMT COUMT DAYS f1 IN CT/S CT/S CTIS CTIS 194.59 7. 16. 1461. 1. 480 1. 48 0 3 31 o. 3. 3 54 3 .. 35 4 18792. 19. 041 19.041 60810. 61. 617 a. 01::: G1.604 215603. 21 e. 465 218.465 32680. 33.113 33. 11 3 626. 0.634 0. 63 4 24143. 24. 463 0 ~ 001 24.463 ISOTOPE RESULTS LI N CE R T A HI n UCI1G 58 CE 1 44. 284. 3D3 3. 22E-04 5. 6E-0: 24 CR

-) 1 27.704fJ2

2. 0*5 E - a 3 l.7E-O* 55 cs 1 J4 2. 062'(5 1:99E-03 6. 3 E- 0 55 C SD1 :H 30.17'(:!. 8. 06E-03 2. 3E-8 I 27 co ~58' 70.8Dl 3. 31E-02 9 .. 4E-(' I 25 f1 N !54 312. 5D3 4. 89E-03 l.4E-(I 26 FE ~5 9. 44.6D4 2. 4:3E-04 3. 4E-C 27 co 60*5.271V1 5. 75E-03 1. 7 E-1 'J1 <Yo (/.ti'(-J: <J,07 )f-'f q) 7:--.-- (!. lf * 0, 3) f-y oiv /)A 'j-e {io<<*o'f-) c;s f)f /t.- (i~ 9 -f 0. l) E-t

.. '"I

    • ~*

,l\\.l\\ied ,, : .. * ~j d1emicc:il FORM ACC-5,;o;l (A**-*~16) IDAHO CHEMICAL PROGRAMS - OPERATIOl'JS OFFICE REQUEST FOR AMAL YSIS SY ANALYTICAL CHEP..~iSTRY BRANCH S/l!i!?L£ llA!AE __

  1. .._. ~~*

_e_,_~....:...'-'e...:::s:;_;_,---=-~'-'--'lt_.?_.::;/ _________ _ AHAL. LOG :w. a7t7a7 ........__. ___ _ DESCRIPTION OF S.\\HPLE. APPROXl:.!ATE COHCEHTRATIOli, ETC.----------------------- SU 5~ i 7T En 5 '! ----*~.;..._-._'P___;;_!f.;__.* "-.*:Y_lic:...:t .,....::.._ .:_/____ n ,\\ "7:: I REPORT RESULTS TD !411 ?c:-..plrct. I ' AooREss _~C,:;_,.,...:..__/-_-_,,b~fi_o __ _ SAMPLE CODE ~ ~ i:> t-- >-- ..c~

r

... r-- ... -,r- en \\<'I ~ -' FOR AnYTICA.L USE DtlLY RDUlE: /' l~ fj I. SPEC_ CHEM. 2_:1_2_:__/ 2. X-RAY ?-1.7--.79 ,\\L: i! YI TY t ::i;{/h r) _.!J_~'-~-* ._"'.i_/_-=--1--'-?J._....:_L.___.L....-- _ANALYTICAL REPRESENTATIVE _________ _ i.NALY SES DES I RED 3. Rt.DID CHEM. ___ _ 4. MASS SPEC.---~ 5. SHlfT LAB.

~~~~~:o BY _____ APPnovEo -------~~1-~..,;:.Jf;_-"'L.V

__ 1 __ DA TE _ ___,/~{l..-J-1 ___.9'---_ !/

- ANNEX P - . ~ ~">r~~.;--y ... _ .. -!,*-* .. -.*----~~~~:;~~~~,"1ffl!li:TL,....:;;r~~~~?~c!f!°~~~T!~*~':?t'~Z...!P.~+,..,~~~~~:. ... . . . --**"'- ...

...

  • .

~~.---.-*. Amed . -. f.lS ,. §.

, .. , *. ~ 11 . Chemical RECEIVED RUN REPORTED RECORD rm. S.~MPLE DISPOSAL RUN BY APPROVED Ag Al ,:;- B j - .. ..-; ....... , Be

  • Ca

Cd Co Cr Cu Fe -."- .,! Mg ,;f Mn

r

Mo Na . ')':"' -,;I- Ni Pb Si

r

Sn Ti v Zn Zr SPECTROCHEMICAL ANALYSIS ii ** ! I: ~ -j ' I .. , 1, ""' I I. ' -> "f C-: * I LOG NO. CODE ACTIVITY (mR/hr) REQUESTED BY REPORT RES UL TS TO CHARGE NO. DETERMINATIONS It, oz1**-;u7 ,..

. r I f 9!fov -*--;?- 3' ;i. - dot fo .... :/ .... (t?e,*- T = TRACE = < .1%

.

r "/I' ~RoY 6-77) Jil ' .,. " ... --~Allied ~i Chemical .DATE SUBMITTE_D 7-17-79 ALLIED CHEN\\JCAL CORPORATION IDAHO CHEMICAL PROGRAMS OPERATIONS OFFICE ANALYTICAL CHEMISTRY BRANCH

  • 1 _
11 r, -.9

l ..,, 1. 11 **> l I ..>-:

  • ' I

SPECTROSCOPY SECTION

  • !79-071707

L.OG* NO. 7-17-79 l-I.R.C. Residua DATE RUN CODE ACTIVITY ( mRfhr) P-28

  • RECORD NO.

x-ray powder came~a REQUESTED BY Ken Puphal .. RUN BY ESD REPORT "RESULTS TO Ken Puphal ESD/WAR

  • CALCULATED BY

SAMPLE DESCRIPTION ------....-~-----

  • -
  • ." . A??'RO*.'ED
JETER/'*~ I NATIONS*

. . **.: .. CHf'RGE NO * 89400-232-006 .'* ... *=========================================================================================== . . . . * Most of. this sample appears to be organic in nature. , is. present. -.. : ....

.

  • ,**:*** .:;=-** :_ * ..

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    • .-*. ~ :; .. :*::. *, .

.. :-;-*.:. . :.=:.:*_.::._}: .. . . .. .. ..... ;._ .. : .

-.*. *::.-::.* .. ~..:.;. . .

.. :': -~"}:\\:~,=-'* -* : .. . *.*.

  • ...

. . .. :-.\\ ...... -

.* .. *

. ~~ -::~. *. . . . *.\\:* ::- .

  • -.,~.--.

. ...... * Either H~BO or B O

J*.* ZJ

.: - . .

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!'.* .. .*** ..... - ..

-* ...... .
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