IR 05000313/1981002

IE Insp Repts 50-313/81-02 & 50-368/81-02,on 810113-15. Noncompliance Noted:Improper Radioactive Shipment & Radiation Surveys of Shipment Boxes & Vehicles Not Correctly Documented

ML20126J921
Person / Time
Site:	Arkansas Nuclear
Issue date:	03/19/1981
From:	Brown G, Everett R, Nicholas J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20126J916	List: IR 05000313/1981002 ML20126J912 ML20126J917
References
50-313-81-02, 50-313-81-2, 50-368-81-02, 50-368-81-2, NUDOCS 8105070269
Download: ML20126J921 (13)

Text

r U. S. Nuclear Regulatory Commission (o) Office of Inspection and Enforcement Region IV Docket Nos. 50-313/81-02 License Nos. DPR-51 50-368/81-02 NPF-6 Licensee: Arkansas Power and Light Company P. O. Box 551 Little Rock, Arkansas 72203 Facility Name: Arkansas Nuclear One (ANO), Units 1 and 2 Inspection at: AN0 Site, Russellville, Arkansas Inspection Conducted: January 13-15, 1981 i

Inspectors: [1 4 'Jti R. J. Everett, Radiation Specialist 3 9/5'/

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Ya B.~ Ni-holag, Raidation Specialist 3l/9lP/

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Approved by: ~.

h*OM, ./ //t 13 Brown, Chief', Technical Inspection Branch J//'f/'7/

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Inscection Summary Insoection conducted during the ceriod of January 13-15. 1981 (Recort Nos. 50-313/81-02 e - 50-368/31-02)

Areas Insoected: Routine, announced inspection of the licensee's radiochemistry measurements program including sample collection, treatment and analysis, >

analytical orocedures and quality controls. The Region IV mobile lacoratory was utili:ec for on site comparisons of samole result In addition, the !

ircumstances sur9uncing a 2.72 rem exposure and an "nacverten: sni: ment of L3A material were reviewec. The inspection involvec M onsi e , curs oy ;no NRC inspectors, lecults: One violation was identified; an improper radioactive shipment (See paragraph 1).

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DETAILS Persons Contacted (AP&L)

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• J. P. O'Hanlon, ANO General Manager

^ H. Miller, Engineering and Technical Support Manager

• 0. D. Snellings, Technical Analysis Superintendent

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• G. Fiser, Radiochemistry Supervisor

• 0. Glenn, Health Physics Supervisor  :

• Frala, Assistant Radiochemistry Supervisor ,

• 0. Wagner, Assistant Health Physics Supervisor

• Denotes those present at the exit intervie ' Status of Previous Inspection Findings ,

(Closed) open item (50-313/79-18/2): This item identified a need for a documented QC program in the radiochemistry counting laboratory and the undesirable environment of the radiochemistry counting laboratory as a i result of its location in a radiation control area and lack of adequate '

temperature control to maintain laboratory instrument performanc The l QC program and Procedure 1604.19 were reviewed and the radiochemistry ,

counting laboratory has been moved to a location which is considered acceptable. This item is considered close ; Significant Radiation Exposure  !

A NRC inspector reviewed the circumstances surrounding the exposure of an '

AP&L employee to about 2.72 rem whole body on December 22, 198 An 6 inexperienced engineer was under escort in order to inspect components ;

of the Makeup and Purification System of Unit 1. The T-36B tank room was surveyed (1-2 R/h) by the health physics technician, who was acting as the escort, and he withdrew from the tank room leaving the engineer in ;

the area. The engineer, not under visual contact and not having been *

instructed otherwise, proceedea to the aajacent room (T-36A tank room)

whe a radiation levels were 300-400 R/h. Upon exiting both areas, tne engineer noted that both of nis pocket cosimeters had discharged off-scal ,

Suosequent reading of the engineer's TLD indicated a dose of about L 2.72 rem. The NRC insoector's findings are as follows:  ; There was poor communications between the hesitn anysics tecnnician #

and the engineer as to anat areas were to be visitec and tne raciation ;

levels associated with each are ) The health physics technician conducted the escort and insoection >

under a general RWP rather than an applicable S'w i

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! The health physics technician was unfamiliar with the plant lay-out, in particular, the makeup tank room j The' postings at the access to these high radiation areas did not reflect the higher radiation levels in T-36A tank roo l i There appears to be a need for guidance on what the term " escort"  ;

means at the ANO sit ,

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The licensee conducted a' SRC management audit of the event on December 29,  !

198 Several deficiences and proposed corrective actions were identifie l The licensee has agreed to provide guidance on " escort" responsibilitie It was agreed that an escort would maintain visual contact with the person ,

he is escorting in most cases. However, the escort should consider his '

own exposure and take advantage of available shielding if possible. Before  ;

withdrawing from temporary visual contact, the escort should assure himself r

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that all accessible areas and sources have been surveyed and that there has been effective communication with the person being escorted. The NRC  !

inspector stated that until such time as the corrective actions described -

.in the management audit and those items identified by the NRC inspector L have been implemented, the event would be considered an open item j (50-313/81-02/1).  ;

e Radioactive Waste Shioment  !

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A NRC inspector investigated the events and practices that led to an f inadvertent shipment of low specific activity material from ANO on  ;

December 17, 1980. The shipment in question (RSR-43-80) consisted of i six LSA wooden boxes containing noble gas, halogen, and metal oxide (

activities on charcoal. The shipment was sent to Nuclear Consulting i Services, Int.., in Columbus, Ohio. Upon arrival in Columbus, the  !

boxes were sJrveyed and one box (80-76) was found to have radiation i levels on the outside surface of 12 mR/h. The recipient notified the l NRC Region III office of the initial finding The regional office {

advised the recipient to open the box, survey the contents, and report l the findings. The box was found to contain radioactive waste (metal, '

plastic, and paper items) at levels up to 30 mR/h. AP&L perscnnel aere  !

notified of the shipment discrepancy and cispatened a man to Columous , Chio,  ;

to re-package the uaste and charcoal and ship it back to the ANO sit The radioactive shi;: ment record prepared by ANC personnel on :ecem er l , l 1980, indicated surface radiation levels of 3.2 mR/h and an activity  !

content of 1.08 millicuries. Radiation levels for the loadec sole use i vehicle were recorded as <0.1 mR/h on the external surf ace of the venicle  ;

and <0.1 mR/h 5 feet frcm the external surface of the vehicle. As noted above the radiation level measured en cox 20-75 in Columcus was 12 mR/h at contact and up to 30 mR/h inside. Based On these readings  !

it was apparent that the activity content of the cox was much greater than  ;

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-4-1.08 millicuries. A survey taken of the vehicle used for the return ship-ment of the box prior to leaving Columbus, Ohio, revealed readings of mR/h at the vehicle external surface and 0.3 mR/h at 6 feet from the external surface of the vehicl ;

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The licensee stated that the shipment had been loaded on about December 16, 1980, by Bechtel employees and apparently they had located and loaded the wrong box (80-76). The ANO Radioactive Waste Coordinator was on site the ,

date of the shipment and signed the RSR certifing that all shipping :

requirements had been met. Since the radiation surveys in question were .

not properly documented, it is not known whether the survey was actually performed. The NRC inspector identified the following items as contributors to the inadvertent shipmen i Radiation surveys of radioactive shipment boxes and vehicles were not properly documented, Boxes, crates, and other containers stored in the waste storage ,

building were not identified properly as to their content The NRC inspector stated that the failure to properly identify the contents of radioactive shipments and the activity content of each container was an item of violation. However, it should be noted that the box in question was properly packaged, labeled, and shipped and radiation levels present ;

were within regulatory requirements for LSA shipment !

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This is a Severity Level IV violation (Supplement V.D). ' Radiochemistry Quality Control -

The NRC inspectors visited the radiochemistry counting laboratory facility ;

and reviewed the radiochemistry QC progra Procedure 1604.09," Quality -

. Control Guidelines and Acceptance Criteria," Revision 4, issued October 20, 1979, was reviewed along with trend charts and other documentation of instrument performance. The NRC inspectors noted that the QC program and i procecures had been revised and tne raciochemistry counting laboratory i relocated; tnerefore, closing open item (50-313/79-18/2).  !

Samples of health pnysics surveys, a plant gas decay tank, a plant liquid i radioactive waste tank, and Unit 1 reactor coolant uere collected for :

analysis by the Region IV mobile lacorator Analytical comoarisons are reported in caragrapn l No items of /iolation were identifie !

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6. Analytical Measurements , Confirmatory Measurements ,

Confirmatory measurements were performed on the following samples in the mobile laboratory at the ANO site during the inspection: Health Physics Particulate Filter . Health Physics Charcoal Cartridge' Gaseous Waste

Liquid Waste , Reactor Coolant from Unit No. 1 RESL Charcoal Cartridge Standard RESL Particulate Filter Standard  :

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The confirmatory measurements tests consist of comparing measurements ;

made by the licensee, NRC's mobile laboratory, and NRC's reference laboratory, Radiological and Environmental Sciences Laboratory (RESL) '

in Idaho Falls, Idaho. RESL's and the NRC's mobile laboratory measure-ments are referenced to the National Bureau of Standards by laboratory intercomparison Confirmatory measurements are made only for -

those nuclides identified by the mobile laboratory or RESL as being present in concentrations greater than 10% of the respective isotopic -

values for liquid and gas concentrations as stated in 10 CFR Part 20, .

Appendix B, Table II, and above the Lower Limit of Detection (LLD)

for stack samples. Stack charcoal cartridge and stack particulate ,

i filter comparisons are based on established Lower Limits of Detection (LLD) for total activity per sampl ;

Attacnment No. 1 contains the criteria used to compare result i

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t Attachment No. 2 lists the LLD's for stack samole I The following tables show tne various sample comoarisons: ; Health Physics Particulate Filter (collectec 3157, January 14, '

1981, curing tne neaa puli on Unit No. 1)

Nuclide concentrations identified by Regicn IV mobile lacoratory e were less than LLD No comparison mad ;

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Health Physics Charcoal Cartridge (collected 0157, January 14, ;

1981, during the nead pull on Unit No. 1)  !

Nuclide NRC Measurement Licensee Measurement (1) Decision f I 1.7510.14E-10 uCi/cc 2.02+0.20E-10 uCi/cc Agreement f

( ) Analytical results as reported by the health physics counting facility, f Gas (Waste Gas Decay Tank, T-18, collected 1130, January 14, 1981) ;

Nuclide NRC Measurement Licensee Measurement (1) Decision l

Xe 2.55+0.001E+00 uCi/cc 2.63+0.001E+00 uCi/cc Agreement 1 *Xe 5.00+0.34E-03 uCi/cc 5.58+0.11E-03 uCi/cc Agreement U

Xe 3.00+0.10E-02 aCi/cc 3.00 0.12E-02 uCi/cc Agreement

Kr 6.98+0.21E-02 uCi/cc 7.37+0.32E-02 uCi/cc Agreement (1) Analytical results as reported by the radiochemistry counting j facilit ,

Liquid (Monitor Tank, T-16A, collected 1450, January 14, 1981)

Nuclide NRC Measurement Licensee Measurement (1) Decision ,

i tritium (2) 4.83+0.02E-02 uCi/ml (3)

gross beta 2.24+0.09E-04 uCi/ml 2.76+0.08E-04 uCi/mi Agreement t

5r (2) 1.40+0.02E-06 uCi/ml (3)

Sr (2) 1.37+0.35E-07 uCi/ml (3) >

Cr 3.63_+0.35E-05 uCi/mi 3.93_+0.99E-05 uCi/ml (4) !

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Mn 1.71:0.35E-06 uCi/ml 1.37 0.98E-06 uCi/ml (4) [

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Co 2.97+0.01E-04 uCi/ml 3.31:0.03E-04 uCi/ml Disagreemen !

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' Fe 2.35+0.09E-05 uCi/mi

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3.77+0.25E-05 uCi/mi

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Possible I Agreement l O (

Co 7.9710.09E-05 uCi/mi 1.04:0.02E-04 uCi/mi Possible i Agreement :

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Zr 3.1210.61E-06 uCi/ml 5.34+1.66E-06 uCi/ml (4)

Nb 9.7610.44E-06 uCi/mi 9.4910.99E-06 uCi/ml (4)

Nb 4.8010.35E-06 uCi/ml Not Reported (4)

Mo 9.8012.43E-06 uCi/mi 1.0310.64E-05 uCi/ml (4).

99*Tc 1.9810.05E-05 uCi/mi 1.4410.08E-05 uCi/ml (4)

103 Ru 7.3110.48E-06 uCi/ml 1.0210.15E-05 uCi/ml (4) ;

110m Ag 4.6210.34E-06 uCi/ml 7.1611.34E-06 uCi/ml Agreement 131 I 3.5910.01E-04 uCi/mi 4.42+0.03E-04 uCi/ml Possible Agreement 134 Cs 1.0810.05E-05 uCi/mi 1.3010.14E-05 uCi/mi Agreement 137 Cs 2.1010.04E-05 uCi/ml 2.70+0.12E-05 uCi/ml Possible Agreement 140 La 7.86+0.09E-05 uCi/mi 1.0210.02E-04 uCi/ml Possible Agreement (1) Analytical results as reported by the radiochemistry counting facilit (2) Analytical results were not available at time of report. Formal documentation of these analyses will appear in the next radiological inspection repor (3) Analytical results were not available at time of report; therefore, no comparison is mad ( ) Activity concentration identifiea by NRC was less than 10% of the isotopic value as stated in 10 CFR Part 20, Appendix B, Table II, therefore, r.o formal comparison is made, Reactor Coolant Licuia from Unit No.1 (collected 08 5, January 14, 1981)

Nuclide NRC Measurement Licensee Measurement ( ) Decision '

Cr 5.5011.06E-03 uCi/ml 3.51 2.01E-03 uCi/mi Agreement

Mn 1.00:0.12E-03 uCi/mi 7.25:1.41E-04 uCi/ml Agreement

• 7 Co 2.45+0.68E-04 uCi/ml Not Reported Disagreement i

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Co 3.0110.01E-01 uCi/mi 2.30+0.01E-01 uCi/mi Disagreement l

Co 1.33+0.02E-02 uCi/ml 9.55+0.21E-03 uCi/ml Disagreement l

Nb 3.49+0.16E-03 uCi/ml

~ 2.41+0.18E-03 uCi/ml

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Mo 2.05+0.10E-02 uCi/ml 2.69+0.16E-02 uCi/ml Agreement f

99*Tc 6.20+0.03E-02 uCi/ml 9.5010.07E-03 uCi/mi Disagreement 109 Cd 2.01+0.51E-02 uCi/mi 2.85+0.46E-02 uCi/ml Agreement 110m Ag 3.06+0.16E-03 uCi/ml 2.33+0.19E-03 uCi/mi Agreement I 122 Sb 1.56+0.04 E-02 uCi/mi 1.01+0.02E-03 uCi/ml Disagreement i 124 Sb 3.69+1.54E-04 uCi/mi Not Reported Disagreement 131 I 6.88+0.03E-02 uCi/mi 7.49+0.05E-02 uCi/ml Agreement l

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12 Te 4.48+0.14E-04 uCi/mi Not Reported Disagreement f 134 Cs 1.1710.004E-01 uCi/ml 1.40+0.007E-01 uCi/mi Possible Agreement 136 Cs 1.64+0.02E-02 uCi/ml 2.09+0.06E-02 uCi/mi

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Agreement 137 Cs 1.62+0.01E-01 uCi/ml 1.73+0.01E-01 uCi/ml Agreement 139 Ba Not Reported 6.36+1.05E-02 uCi/ml (2) I 140 Ba 7.40+0.51E-03 uCi/mi 5.13+0.78E-03 uCi/mi Agreement 140

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La 1.20+0.08E-03 uCi/mi 1.50 0.12E-03 uCi/mi Agreement ;

29 Np 4.43+0.17E-03 uCi/ml A.76:0.39E-03 uCi/mi Agreement f ( ) Analytical results reported oy the raciochemistry counting f acility, f ( ) Activity naa decayed to below lower level of detectaoility at .ime of sample analysis by NRC; therefore, no comparison is mad '

, RESL Charcoal Cartridge Hemocenous Standard (standardized 0900, f March 19, 1980)

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'Nuclide NRC Measurement Licensee Measurement (1) Decision

Co 2.28+0.09E-02 uCi/mi

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1.76+0.01E-02 uCi/ml Agreement

Co 1.73+0.07E-01 uCi/ml 1.37+0.01E-01 uCi/ml Agreement

Sr 7.54+0.30E-02 uCi/ml 5.42+0.16E-02 uCi/ml

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Y 2.92+0.12E-01 uCi/ml 2.39+0.02E-01 uCi/ml Agreement 113 Sn 5.75+0.02E-02 uCi/ml 2.44+0.04E-02 uCi/ml

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Disagreement 137 Cs 1.29+0.05E-01 uCi/ml

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9.48+0.03E-02 uCi/ml

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Possible Agreement 241 Am 3.19+0.13E-02 uCi/ml

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Not Reported Disagreement ,

(1) Analytical results as reported by the radiochemistry counting facilit g. RESL Particulate Filter Standard (standardized 0900, March 19, 1980)

Nuclide NRC Measurement Licensee Measurement (1) Decision

Co 2.28t0.09E-02 uCi/ml 2.73+0.05E-02 uCi/ml Agreement

Co 1.73t0.07E-01 UCi/mi 2.04+0.02E-01 uCi/ml

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Sr 7.54t0.30E-02 uCi/ml 7.74+0.92E-02 uCi/mi Agreement

Y 2.9210.12E-01 uCi/ml 3.56+0.08E-01 uCi/ml Agreement 113 Sn 5.7510.02E-02 uCi/mi 4.8210.23E-02 uCi/mi Agreement 137 Cs 1.2910.05E-01 uCi/mi 1.50+0.02E-01 uCi/ml

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Agreement 241 Am 3.1910.13E-02 uCi/ml Not Reported Di sagreement (1) Analytical results as reported oy the radicchemistry counting facilit .

Nuclide NRC Measurement Licensee Measurement (2) Decision

Co 2.22E-02 uCi/ml 3.31E-02 uCi/ml Possible Agreement

Co 1.73E-01 uCi/ml 2.34E-01 uCi/ml Possible Agreement

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Sr 7.54E-02 uCi/ml 1.16E-01 uCi/mi Possible Agreement .

Y 2.92E-01 uCi/ml 3.80E-01 uCi/ml Agreement 113 '

Sn 5.75E-02 uCi/ml 5.26E-02 uC1/ml Agreement 137 '

Cs 1.29E-01 uti/ml 1.75E-01 uCi/ml 'Possible Agreement 241 '

Am 3.19E-02 uCi/ml Not Reported Disagreement (2) Analytical results as reported by the health physics counting facilit No items of violation were identifie i Previous Confirmatory Measurements Confirmatory measurements were performed on samples of gaseous waste and liquid waste during an inspection (Report Nos. 50-313/79-18 and 50-368/79-16) conducted in August 1979. The following tables show the_various sampie comparisons: Gas (collected 1130, August 15, 1979)

Nuclide NRC Measurement Licensee Measurement (1) Decision

Kr 1.5010.01E-02 uCi/cc 1.9010.02E-02 uCi/cc Agreement (1) Analytical results as reported by the radiochemistry counting facilit . Liquid (collected 0925, August 14, 1979)

Nuclide NRC Measurement Licenste Measurement (1) 01 cision gross ceta 4.4+0.20E-04 uCi/ml 5.S+0.10E-04 uCi/ml Agreement tritium 3.7+0.02E-03 uCi/mi 3.7:0.06E-03 uCi/mi Agreement o0

" Sr 1.5+0.10E-07 uCi/ml 7.7 2.50E-08 uCi/mi Disagreement

Mn 2.4:0.10E-05 uCi/mi 3.5:0.08E-05 uCi/mi Possible Agreement

Co 2.3 0.01E-04 uCi/ml 3.210.02E-04 uCi/ml Possible Agreement no

~~Fe 7.3+1.70E-06 uCi/ml 5.7+1.20E-06 uCi/ml Agreement

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Agreement

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Zn 1.9r .15E-05 uCi/ml Not Reported Disagreement ;

Zr 1.5+0.14E-05 uCi/ml 2.1+0.12E-05 uCi/mi Agreement ;

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110m Ag 1.8+0.12E-05 uCi/ml 2.3+0.10E-05 uCi/ml Agreement f 124 Sb 2.1+0.40E-06 uCi/ml 3.3+0.40E-06 uCi/ml Agreement 125 Sb 3.3+0.20E-05 uCi/mi

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'1.2+0.20E-05 uCi/ml 7.5+0.50E-06 uCi/ml Agreement 134 Cs 3.3+0.20E-05 uCi/ml 3.8+0.09E-05 uCi/ml Agreement f 137 Cs 5.1+0.30E-05 uCi/ml 5.9+0.07E-05 uCi/ml Agreement !

(1) Analytical results as reported by the radiochemistry counting facilit L No items of violation were identifie . Exit Interview .

At the conclusion of the inspection on January 15, 1981, the inspection findings were discussed with the AP&L personnel denoted in paragraph !

The NRC inspectors reviewed the scope of the inspection and the inspection i finding '

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ATTACHMENT NO. 1

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Criteria for Ccmoarine Analytical .'tessurements The following is the criteria used in comparing the resuits of capabili:y l tests and verification measurements. The criteria are based :n an emciricai '

relationship established tnrough prior experience and this program's analyt-ical requirement .

In these criteria, the judgement limits vary in relation to the c moarison  :

of the resolutio .

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Resolution = NRC Value NRC Uncertainly

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Ratio = Licensee Value NRC Value Comparisons are made by firs; determining the resolution and :nen reading across the same line to the corresponding ratio. The following table shcws the acceptance value ,

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1 RESOLUTION I

RATIO

Poss1 ole '

.-os s i o l e Agreement Agreemen: A Agreement B 3 0.4 - .3 - No comparison [

4-7 0.5 - .4 - .3 - :

3 - 15 0.5 - 1.56 0.5 - .4 - lo - =0 0...fo - 1,3 l 0.0 - . o. - 1.c..o .

51 - 200 0.20 - 1.25 0.75 - 1.33 0.6 - 1.55 '

200 0.35 - 1.18 0.30 - 1.25 0.75 - 1.33 i

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i i"A" criteria are acclied :: me followina anaivses:

3amma "cectrome ry wnere princi:al gamma aner;y ;sec f:r ::en ;#3:3 ::n is

"reater '.n3C 23C (s "

~ritium anaIyses Of liquiC Sam 0les, i

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Cine On Ics;r er "3" r.r7". aria tre a 0'lec ~ "'s

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1. ll:Wi"O inal/Se!:

- - .r. ., , ~2 -wer . - *er..'r wnere OrinCi"al Oamma energ? USIC '0I ' 230~

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595r and iOSe :e:ermina:i:n '

Gr:ss 5e:a wnere samoles are ::un ac :n :na 3ame :a e ;-i-- ,e 33:e r?ference nuCli; '

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ATTACHMENT NO. 2

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LL0s for Nuclides on Particulate and Char: cal Filter ,

Y Nuclide LLD (uCi/samole) '

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i 51C r lE-04 -

54Mn- 1.5E-05 !

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58Co 1.5E-05 1

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59Fe 3E-05 57Co 2E-05 !

60Co 3E-05 55Zn 3E-05 395 r lE-05 90S r 2E-07 i 131 I 2E-05 i 134 Cs 2E-05 ,

137Cs 2E-05 i idOBa 2E-05 l 140La dE-05 :

idice 2E-05 !

ladCe lE-04

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