IR 015000039/1981002
| ML19350E944 | |
| Person / Time | |
|---|---|
| Site: | Crystal River, 015000039  |
| Issue date: | 04/30/1981 |
| From: | Macarthur T, Peery W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | FLORIDA POWER CORP. |
| Shared Package | |
| ML19350E924 | List: |
| References | |
| 15000039-81-02, 50-302-81-04, NUDOCS 8106230682 | |
| Download: ML19350E944 (3) | |
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UNITED STATES
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- NUCLEAR REGULATORY COMMISSION REGION 11 t,
a 101 MARIETTA ST N.W SulTE 3100
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Report Nos.
15000039/81/02 AND 50-302/81-04 Licensee:
Florida Power Corporation St. Petersburg, FL 33733 License No.
OPR-72 Inspection at:
Chem-Nuclear Systems, Inc., Barnwell, South Carolina
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Inspector: Mh&M NIA
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T. C. MacArthur, Date Signed
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Approved by:
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W. W. Peery, AA.ing Chief, Dite Signed Technical Inspection Branch Division of Engineering and Technical Inspection Inspection conducted on February 10, 1981 SUMMARY Areas Inspected
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Each licensee-shipper vehicle was inspected for compliance with Department of Transportation (DOT) and Nuclear Regulatory Commission (NRC)
regulations as follows: (1) shipping paper requirements; (2) DOT Placarding requirements; (3) radiation levels; (4) removable contamination; (5) 00T marking and labeling requirements for packages; (6) DOT and NRC requirements for external package features; and (7) prohibited articles or contents.
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Results: Of the seven areas inspected involving shipments, one item of noncom-pliance was identified.
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DETAILS
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Persons Contacted J. Purvis, CNSI
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J. Ott, CNSI 0. Eberhack, CNSI
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R. Sappington, DHEC
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General
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'The NRC inspection consisted of a review of the shipping papers, radiation survey of the vehicle, contamination surveys and radiation level surveys of
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selected packages.
General surveys and observations were conducted to determine if the vehicle had proper placards, proper seals, 'and if any
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obvious safety hazards existed. The contents of the vehicles were inspected for appropriate marking, labeling, tightness of seals, integrity of package construction or any evidence of leakage.
Chem-Nuclear assigns a control number for each shipment upon arrival at the site. These numbers were called " arrival survey numbers" (AS No.) and were used by the inspectors to identify licensee-shippurs during this inspec-tion.
3.
Shipments Inspected
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One shipment of waste material was received from the Crystal River Plant in'
trailer #027 on February 10, 1981. The shipment, carried by Chem-Nuclear Systems, Inc., (Trailer #24) identified b:, AS #24614, was found to be in violation of 49 CFR 173.392(j)(3) in that there were radiatiori-levels of 16 mR/hr at. two meters from the vertical planes projected by the outer lateral surfaces of the vehicle. This is a Severity Level HI. Violation (Supplement V.C.2).
4.
Shipping Papers The shipping papers were reviewed for completeness and to ascertain if the contents of the shipment were properly identified, and if emergency notifi-cation procedures and instructions were included as required under 49 CFR
.172, Subpart C.
Specific requirements for shipping papers were reviewed as follows:
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49 CFR 172.100/172.200/172.202 Material shipping name
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49 CFR 172.200/172.202 Material class
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49 CFR 172/200/172.202 Name sequence
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49 CFR 172/200/172.202 Total quantity (volume)
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49 CFR 172/200/172.203 Limited quantity
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49 CFR 172/203 Name of each radionuclide
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49 CFR 172/203 Physical and chemical form
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49 CFR 172/203 Activity-in curies
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In addition to the above, 49 CFR 177.817 requires carriers to maintain the above shipping papers readily available for inspection and recognfzable by-authorities in case of an accident.
No items of noncompliance were identified.
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Each vehicle was inspected for conformance with 00T placarding requirements (49 CFR - 172, Subpart F/173.392).
The vehicles were also inspected for
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compliance with the,following:
Maximum transportation index of 50
~(49 CFR 177.842).
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Loaded so as to avoid spillage (49 CFR 177.842)
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Properly blocked and braced (49 CFR 173.392/177.842)
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LSA v'ehicle survey (49 CFR 177.843)
No items of noncomplian.e were identified.
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Maximum Radiation Levels Each truck was surveyed for maximum radiation levels in the normally occu-pied portions of the vehicle, in a plane at the edge of the flat bed or at the surface of the closed vehicles, in a vertical plane two meters from the sides of the vehicle where possible, and on the surface of a representative package. Shipping casks were surveyed at the surfacte.
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One item of noncompliance was identified as described in paragraph 3 above.
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Packaging A representative sampling of packages from each -shipment was examined for
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conformance with DOT marking and labeling requirements-External features-of the packages were examined for conformance'with DOT ind NRC requirements as noted below:
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49 CFR 173.392 Low specific activity (LSA) packaging
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49 CFR 173'.391 or 173.392 Tight packages - ltd. Qty.
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49 CFR 173.392/173.393 No release of material
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Radioactive material markings
- 49 CFR 172.310
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49 CFR 173.393 Security seals
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49 CFR 172.310 Gross weight requirements
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49 CFR 172.100/172.300 Proper shipping name
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49 CFR 173.392 LSA labeling
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49 CFR 173.393a Cask design specifications
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No items of noncompliance were identified.
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