IR 05000333/1981022
| ML20040F623 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 01/06/1982 |
| From: | Clemons P, Knapp P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20040F621 | List: |
| References | |
| 50-333-81-22, NUDOCS 8202090423 | |
| Download: ML20040F623 (4) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-333/81-22 Docket No. 50-333 License No. OPR-59 Priority
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Category C
Licensee:
Power Authority of the State of New York P. O. Box 41 Lycoming, New York 13093 Facility Name:
James F. Fitzpatric) Nuclear Power Plant Inspection At:
Barnwell, South Carolina-M
/ ML Report Prepare
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'5.'Clemons, adiation Specialist
'dats signed Approved By:
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P.AKnapp, ChTeT, Facility RQiological date signed Protection Section, Technical Inspection Branch Inspection Summary:
Inspection on September 24, 1981 by a representative of the South Carolina Department of Environmental Control The Power Authority of the State of New York was the originator of a waste shipment which was inspected at the Chem-Nuclear Systems, Inc. burial site at Barnwell, South Carolina.
Results: One apparent item of noncompliance was identified (transfer of byproduct material in a form the recipient was not authorized to receive).
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l 8252090423 820108 PDR ADOCK 05000333
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DETAILS On September 22, 1981, the Power Authority of the State of New York dispatched a shipment of licensed material, consisting of 13.47 curies of LSA radioactive waste. as solidified evaporator bottoms, to the Chem-Nuclear Systems, Inc.
bur;al site at Barnwell, South Carolina.
The shipment was made in a Chem-Nuclear Systems Model No. 14-195-H cask.
On September 24, 1981, a representative of the South Carolina Department of Health and Environmental Control inspected the' shipment.
The inspection consisted of a review of shipping papers, placarding, marking and labeling, radiation measurements, and examination of the packages and the tractor-trailer.
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A copy of the report, without attachments, prepared by the representative is attached. The report states that several holes were drilled in the liner of the cask. Sixty gallons of liquid were drained from the liner.
Urea formaldehyde had been used as the solidification medium.
Condition No. 27 of the Chem-Nuclear Systems, Inc. Agreement State License, South Carolina License No. 097, states:
"The licensee aay receive aqueous liquids solidified with one of the following solidification media provided the requirements of other conditions as specified in this license are met:
(a) Dow media (b) Cement (c) Urea Formaldehyde (d) Asphalt-(e) Delaware Custom Media (f) Solidification media and processes reviewed and approved by the U.S.N.R.C. Office of Nuclear Reactor Regulation, subject to final approval by the S. C. Department of Health and Environmental Control, Bureau of Radiological Health."
Condition No. 26 of License No. 097 states that solidified radioactive
. waste shall have no detectable free standing liquid.
License No. 097 defines "no detectable free standing liquid" as follows:
"(a) One percent (1*4) liquid by waste volume until December 31, 1980.
(b) Effective January 1,1981, one-half percent (0.5*4) by waste volume or one gallon of non-corrosive liquids per container, whichever is less.
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In lieu of the requirements of sub paragraph (b) above, solidified waste containing liquids in excess of one-half percent (0.5%) by waste volume, but less than one percent (1%) liquid by waste volume, may be
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received and disposed of in approved high integrity containers."
In an October 19, 1981, telephone conversation with P. Clemons, a State of-South Carolina representative reported that the liner used in this shipment had been designated as a high integrity container. He noted-that the 1.0 percent license limit is applicable. The 60 gallons of. liquid radioactive waste drained from the liner corresponds to 4.1 percent of the waste volume.
10 CFR 30.41 prohibits _ transfer of byproduct material unless it is in a form authorized by the recipient's NRC or Agreement State license. As-noted above, South Carolina License No. 097 prohibits the receipt of solidified waste with " detectable free standing liquid," which is defined in this case as liquid in excess of 1.0 percent by waste volume for high integrity containers.
This represents noncompliance with 10 CFR 30.41 (81-22-01).
The James F. Fitzpatrick Nuclear Power Plant Assistant to the Superintendent of Power was informed of this apparent item of noncompliance with NRC requirements in a telephone conversation with P. Clemons on October 21, 1981.
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EPARTMENT OF HEALTH AND ENVIRONM
\\L CONTROL Sg.h 1799-672.4 ow-Lival Rrdiocctiva Shipment In rection
.A. G:nnrcl Information:
D:ta In;p;ct:d 8/r/T. E4- /98/
j, gg 1. Name of-Shipper: / 4- < A/ /
Type Package / Cask Model:
Address:
L V 6/#/,J /t A/, E
/// -/96-//-/
2. Carrier:
C A/_6 /
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Cask containing: Nu._ L/s4/2 Tractor #
Trailer #
d69 Type l
B. Shipping Documentation:
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l. SSR#
O23 550 Vol. Allot.# O C/ 8 / -C3 /
RSR#
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l 2. Shipping Name and Class: Radioactive Material /E rjApo/2,4 rf,fl._ d y;r7af ts, (172. 202 (a'
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3. Total Volume:
/96 ft$(172.202(c)) Total Curies:
/ 'T., 4L'J Z4L 9 (172.203(f 4. Radionucl-ides:
Labels -
(172.203(f
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5. Description (chem /phy/ media):JoL,off,Ay> u. F. 6 t/ Aro/24 rrvL (do-Tra/-fs, (172.203(4 6. Shippers Certification: State (48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />)
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(172.204)
7. Exclusive Use M structions (173.392(c))(173.393(j))or Total T.I.
(177.842(e
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8. Check for:(a) Radiation Survey (173.393(i)(j)) Contamination levels (173.397)
9. Compare: Radionuclides w/ resin analysis Radiation / Contamination levels w/CNSI/BRH L C. Shipment Inspection Check List:
Packaging: Ltd. Qty / devices 173.391,LSA 173.392, General 173.393,Special form 173.394, Normal form 173.395, Fissile 173.396 Ex lusive Seals (173.393(b))
ds (D..., '; =, cask) secure (173.393(n)(6))
_ hi ment Bra ced/ Blocked (173. 392.(c) /177. 842 (d) ) dj,s ib le Dama ge (173. 393 (d) )
_ i ible Leakage (173.392(c)/173.393(d))
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Ca k Defects / Missing parts (173.398)
ackn e LabeHne/Wh I, Ye1 II,III (172.403)
diation Survey (173.393(j))
-or (' Radioactive LSA' (173.392(c))
-Cab / sleeper, trailer / truck (173.310)LSA Ex.use Exempt _Co amination Levels (173.397)
, Cross Weight ma e F Tv e A/ Type B package marked (173.310)
_ ehicle Placards (173.392(c))/172.512)
t railer / Tractor Defects Tiedowns secure / adequate
[Packagesbanded/ reinforced.palletized Offloading Discrepancies
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D. Radiation / Contamination Survey:
(MR/HR)
Surface:
/3.O 2 meters:
Surface:
Cab / sleeper Surface:
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2 meters:
2 meters:
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Surface:
/C. C 2 meters:
Highest Contamination Detected: Arrival adpm/100cm2 Release adpm/100cn l
Sydpm/100cm2 Sydpm/100cn
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E. Results of Inspection l
1. Cpements and/or Discrepancies Found:
$ /4-A bity /.o& / CAL - l 1 N oD rd w its Tfz-- e LJHLJ rHL Aba.1$_ H i c_
I-/ U ft/L -
cd A ~5 b /2-* LL4-b,
31 y 1-Y (& O \\ 6m,(J OF Lt L? Jo b D /2-Aiel 40 0a T~
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i 2. Persons Contacted (if discrepancies):
d, t.(_
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