IR 05000313/1981002
| 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: |
| 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 9/5'/
R. J. Everett, Radiation Specialist Date
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Ya 3l/9lP/
'. B.~ Ni-holag, Raidation Specialist Date
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Approved by:
h * O M,
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//t 13 J//'f/'7/
G.
0~. Brown, Chief', Technical Inspection Branch Date '
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,
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analytical orocedures and quality controls.
The Region IV mobile lacoratory was utili:ec for on site comparisons of samole results.
In addition, the
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- 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 1.
Persons Contacted (AP&L)
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- J.
P. O'Hanlon, ANO General Manager
^G. 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
- M. Frala, Assistant Radiochemistry Supervisor
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- 0. Wagner, Assistant Health Physics Supervisor
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- Denotes those present at the exit interview.
2.
Status of Previous Inspection Findings
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(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
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temperature control to maintain laboratory instrument performance.
The l
QC program and Procedure 1604.19 were reviewed and the radiochemistry
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counting laboratory has been moved to a location which is considered acceptable.
This item is considered closed.
3.
Significant Radiation Exposure
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A NRC inspector reviewed the circumstances surrounding the exposure of an
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AP&L employee to about 2.72 rem whole body on December 22, 1980.
An
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-scale.
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Suosequent reading of the engineer's TLD indicated a dose of about L
2.72 rem.
The NRC insoector's findings are as follows:
a.
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 area.
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b.
The health physics technician conducted the escort and insoection
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under a general RWP rather than an applicable S'wP.
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c.
The health physics technician was unfamiliar with the plant lay-out, in particular, the makeup tank rooms.
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The' postings at the access to these high radiation areas did not l
reflect the higher radiation levels in T-36A tank room.
i e.
There appears to be a need for guidance on what the term " escort"
means at the ANO site.
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The licensee conducted a' SRC management audit of the event on December 29,
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1980.
Several deficiences and proposed corrective actions were identified.
l The licensee has agreed to provide guidance on " escort" responsibilities.
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It was agreed that an escort would maintain visual contact with the person
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he is escorting in most cases.
However, the escort should consider his
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own exposure and take advantage of available shielding if possible.
Before
withdrawing from temporary visual contact, the escort should assure himself r
that all accessible areas and sources have been surveyed and that there
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has been effective communication with the person being escorted.
The NRC
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inspector stated that until such time as the corrective actions described
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.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 4.
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
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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 findings.
The regional office
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advised the recipient to open the box, survey the contents, and report l
the findings.
The box was found to contain radioactive waste (metal,
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plastic, and paper items) at levels up to 30 mR/h.
AP&L perscnnel aere
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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 site.
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
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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 3.0 mR/h at the vehicle external surface and 0.3 mR/h at 6 feet from the external surface of the vehicle.
The licensee stated that the shipment had been loaded on about December 16,
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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
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date of the shipment and signed the RSR certifing that all shipping
requirements had been met.
Since the radiation surveys in question were
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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 shipment.
i a.
Radiation surveys of radioactive shipment boxes and vehicles were not properly documented, b.
Boxes, crates, and other containers stored in the waste storage
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building were not identified properly as to their contents.
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 shipments.
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This is a Severity Level IV violation (Supplement V.D).
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5.
Radiochemistry Quality Control
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The NRC inspectors visited the radiochemistry counting laboratory facility
and reviewed the radiochemistry QC program.
Procedure 1604.09," Quality
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. 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).
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i Samples of health pnysics surveys, a plant gas decay tank, a plant liquid radioactive waste tank, and Unit 1 reactor coolant uere collected for
analysis by the Region IV mobile lacoratory.
Analytical comoarisons are reported in caragrapn 6.
l No items of /iolation were identified.
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6.
Analytical Measurements
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a.
Confirmatory Measurements
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Confirmatory measurements were performed on the following samples in the mobile laboratory at the ANO site during the inspection:
1.
Health Physics Particulate Filter 2.
. Health Physics Charcoal Cartridge'
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Gaseous Waste
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Liquid Waste
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5.
Reactor Coolant from Unit No. 1 6.
RESL Charcoal Cartridge Standard 7.
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)
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RESL's and the NRC's mobile laboratory measure-ments are referenced to the National Bureau of Standards by laboratory intercomparisons.
Confirmatory measurements are made only for
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those nuclides identified by the mobile laboratory or RESL as being present in concentrations greater than 10% of the respective isotopic
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values for liquid and gas concentrations as stated in 10 CFR Part 20,
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Appendix B, Table II, and above the Lower Limit of Detection (LLD)
for stack samples.
Stack charcoal cartridge and stack particulate
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i filter comparisons are based on established Lower Limits of Detection (LLD) for total activity per sample.
Attacnment No. 1 contains the criteria used to compare results.
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t Attachment No. 2 lists the LLD's for stack samoles.
I The following tables show tne various sample comoarisons:
3.
Health Physics Particulate Filter (collectec 3157, January 14,
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1981, curing tne neaa puli on Unit No. 1)
Nuclide concentrations identified by Regicn IV mobile lacoratory e
were less than LLDs.
No comparison made.
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b.
Health Physics Charcoal Cartridge (collected 0157, January 14,
1981, during the nead pull on Unit No. 1)
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Nuclide NRC Measurement Licensee Measurement (1)
Decision f
f I
1.7510.14E-10 uCi/cc 2.02+0.20E-10 uCi/cc Agreement ( ) Analytical results as reported by the health physics counting facility, f
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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 UXe 3.00+0.10E-02 aCi/cc 3.00 0.12E-02 uCi/cc Agreement 85 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
facility.
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d.
Liquid (Monitor Tank, T-16A, collected 1450, January 14, 1981)
Nuclide NRC Measurement Licensee Measurement (1) Decision
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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
895r (2)
1.40+0.02E-06 uCi/ml (3)
90Sr (2)
1.37+0.35E-07 uCi/ml (3)
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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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l SCo 2.97+0.01E-04 uCi/ml 3.31:0.03E-04 uCi/ml Disagreemen
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o' Fe 2.35+0.09E-05 uCi/mi 3.77+0.25E-05 uCi/mi Possible I
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Agreement l
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Co 7.9710.09E-05 uCi/mi 1.04:0.02E-04 uCi/mi Possible i
Agreement
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i-7-j 99Zr 3.1210.61E-06 uCi/ml 5.34+1.66E-06 uCi/ml (4)
95Nb 9.7610.44E-06 uCi/mi 9.4910.99E-06 uCi/ml (4)
97Nb 4.8010.35E-06 uCi/ml Not Reported (4)
99Mo 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)
110mAg 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 134Cs 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 facility.
(2) Analytical results were not available at time of report.
Formal documentation of these analyses will appear in the next radiological inspection report.
(3) Analytical results were not available at time of report; therefore, no comparison is made.
( ) 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, e.
Reactor Coolant Licuia from Unit No.1 (collected 08 5, January 14, 1981)
Nuclide NRC Measurement Licensee Measurement ( )
Decision
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51Cr 5.5011.06E-03 uCi/ml 3.51 2.01E-03 uCi/mi Agreement 54Mn 1.00:0.12E-03 uCi/mi 7.25:1.41E-04 uCi/ml Agreement
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Co 2.45+0.68E-04 uCi/ml Not Reported Disagreement i
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-8-58Co 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
97Nb 3.49+0.16E-03 uCi/ml 2.41+0.18E-03 uCi/ml Possible
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Agreement
f Mo 2.05+0.10E-02 uCi/ml 2.69+0.16E-02 uCi/ml Agreement 99*Tc 6.20+0.03E-02 uCi/ml 9.5010.07E-03 uCi/mi Disagreement 109Cd 2.01+0.51E-02 uCi/mi 2.85+0.46E-02 uCi/ml Agreement 110m I
Ag 3.06+0.16E-03 uCi/ml 2.33+0.19E-03 uCi/mi Agreement 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
134Cs 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 Possible i
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Agreement i
137 Cs 1.62+0.01E-01 uCi/ml 1.73+0.01E-01 uCi/ml Agreement 139Ba Not Reported 6.36+1.05E-02 uCi/ml (2)
I 140Ba 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 made.
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RESL Charcoal Cartridge Hemocenous Standard (standardized 0900, f
March 19, 1980)
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'Nuclide NRC Measurement Licensee Measurement (1) Decision 57Co 2.28+0.09E-02 uCi/mi 1.76+0.01E-02 uCi/ml Agreement
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60 Co 1.73+0.07E-01 uCi/ml 1.37+0.01E-01 uCi/ml Agreement 85Sr 7.54+0.30E-02 uCi/ml 5.42+0.16E-02 uCi/ml Possible
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Agreement 88Y 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 Disagreement
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137Cs 1.29+0.05E-01 uCi/ml 9.48+0.03E-02 uCi/ml Possible
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Agreement 241Am 3.19+0.13E-02 uCi/ml Not Reported Disagreement
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(1) Analytical results as reported by the radiochemistry counting facility.
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RESL Particulate Filter Standard (standardized 0900, March 19, 1980)
Nuclide NRC Measurement Licensee Measurement (1) Decision 57 Co 2.28t0.09E-02 uCi/ml 2.73+0.05E-02 uCi/ml Agreement 60Co 1.73t0.07E-01 UCi/mi 2.04+0.02E-01 uCi/ml Agreement
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85Sr 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 Agreement
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241Am 3.1910.13E-02 uCi/ml Not Reported Di sagreement (1) Analytical results as reported oy the radicchemistry counting facility.
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Nuclide NRC Measurement Licensee Measurement (2) Decision 57 Co 2.22E-02 uCi/ml 3.31E-02 uCi/ml Possible Agreement 50Co 1.73E-01 uCi/ml 2.34E-01 uCi/ml Possible Agreement
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-10-I 85Sr 7.54E-02 uCi/ml 1.16E-01 uCi/mi Possible Agreement
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Y 2.92E-01 uCi/ml 3.80E-01 uCi/ml Agreement 113
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Sn 5.75E-02 uCi/ml 5.26E-02 uC1/ml Agreement 137
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'Possible Cs 1.29E-01 uti/ml 1.75E-01 uCi/ml Agreement 241
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Am 3.19E-02 uCi/ml Not Reported Disagreement (2) Analytical results as reported by the health physics counting facility.
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No items of violation were identified.
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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:
1.
Gas (collected 1130, August 15, 1979)
Nuclide NRC Measurement Licensee Measurement (1) Decision 85 Kr 1.5010.01E-02 uCi/cc 1.9010.02E-02 uCi/cc Agreement (1) Analytical results as reported by the radiochemistry counting facility.
2.
Liquid (collected 0925, August 14, 1979)
Nuclide NRC Measurement Licenste Measurement (1)
0 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 54Mn 2.4:0.10E-05 uCi/mi 3.5:0.08E-05 uCi/mi Possible Agreement 08 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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60Co 3.3+0.09E-04 uCi/ml 4.9+0.02E-04 uCi/ml Possible
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Agreement
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65 Zn 1.9r.15E-05 uCi/ml Not Reported Disagreement
95Zr 1.5+0.14E-05 uCi/ml 2.1+0.12E-05 uCi/mi Agreement
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Ag 1.8+0.12E-05 uCi/ml 2.3+0.10E-05 uCi/ml Agreement f
110m 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 4.5+0,20E-05 uCi/ml Possible
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Agreement
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'1.2+0.20E-05 uCi/ml 7.5+0.50E-06 uCi/ml Agreement Cs 3.3+0.20E-05 uCi/ml 3.8+0.09E-05 uCi/ml Agreement f
134 137 Cs 5.1+0.30E-05 uCi/ml 5.9+0.07E-05 uCi/ml Agreement
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(1) Analytical results as reported by the radiochemistry counting facility.
L No items of violation were identified.
7.
Exit Interview
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At the conclusion of the inspection on January 15, 1981, the inspection findings were discussed with the AP&L personnel denoted in paragraph 1.
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The NRC inspectors reviewed the scope of the inspection and the inspection i
findings.
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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
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relationship established tnrough prior experience and this program's analyt-ical requirements.
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In these criteria, the judgement limits vary in relation to the c moarison
of the resolution.
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Resolution = NRC Value NRC Uncertainly Ratio = Licensee Value
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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 values.
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1 RESOLUTION RATIO I
Poss1 ole
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Agreement Agreemen: A Agreement B
0.4 - 2.5 0.3 - 3.0 No comparison
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4-7 0.5 - 2.0 0.4 - 2.5 0.3 - 3.0
3 - 15 0.5 - 1.56 0.5 - 2.0 0.4 - 2.5 l
lo - =0 0...fo - 1,3a.
0. o. - 1.c..o 0.0 - 2.0
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51 - 200 0.20 - 1.25 0.75 - 1.33 0.6 - 1.55
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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 (sv.
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~ itium anaIyses Of liquiC Sam 0les, r
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Cine On Ics;r ers.
"3" r.r7". aria tre a 0'lec ~
"'s # ll:Wi"O inal/Se!:
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r..,, ~2 -wer.
er..'r wnere OrinCi"al Oamma energ? USIC '0I '
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230~
3 "i C iS
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less. nan 250 'eV.
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595r and iOSe :e:ermina:i:ns.
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Gr:ss 5e:a wnere samoles are ::un ac :n :na 3ame :a e ;-i--
,e 33:e r?ference nuCli;e.
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ATTACHMENT NO. 2
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LL0s for Nuclides on Particulate and Char: cal Filters.
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Y Nuclide LLD (uCi/samole)
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i 51 r lE-04
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C 54Mn-1.5E-05
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58 o 1.5E-05
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C
59 e 3E-05
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F 57Co 2E-05
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60 o 3E-05 C
55 n 3E-05 Z
39 r lE-05
90 r 2E-07 i
S 131 I 2E-05 i
134 2E-05 Cs
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137Cs 2E-05 i
idOBa 2E-05 l
140 a dE-05
L idice 2E-05
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ladCe lE-04
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