ML19309D513
| ML19309D513 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Dresden, Quad Cities, Zion, 02700047 |
| Issue date: | 02/22/1980 |
| From: | Peery W, Potter J, Woodruff R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19309D228 | List: |
| References | |
| 79-07A-01, 79-7A-1, NUDOCS 8004100408 | |
| Download: ML19309D513 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION III Special Report: WASTE PACKAGING INSPECTIONS OF LICENSEE-SHIPPERS REPORT NO.79-07A Licensee-Shipper:
Commonwealth Edison Company Quad-Cities (Shipments No. 017971 and No. 017990)
Zion Generating Station (Shipments No. 017995 and No. 017996)
Dresden Nuclear Power Station (Shipments No. 017988 and No. 018008)
Disposal Site:
Chem-Nuclear Systems, Inc.
P. O. Box 726 I
Barnwell, South Carolina 29812 Docket No. 15000039 Inspectors:
R. L. Woodruff, Radiation Specialist FF6MS Section, FF6MS Branch, Region II I
W. W. Peery, Radiation Specialist FF6MS Section, FF6MS Branch, Region II Approved By:
J. P. Potter, Section Chief FF6MS Section, FF6MS Branch, Region II
SUMMARY
Inspection Dates:
December 12-13, 1979, Visit to Chem-Nuclear Waste Disposal Site, Barnwell, South Carolina for Unannounced Inspection of Licensee-Shippers.
Areas Reviewed:
Each licensee-shipper vehicle was inspected for compliance 2
with Department of Transportation (DOT) and Nuclear Regulatory Commission (NRC) regulations as follows:
(1) shipping paper requirements; (2) DOT Placarding requirements; (3) radiation 1cvels; (4) removable' contamination (5) DOT marking and labeling requirements for packages; and (6) DOT and NRC require-ments for package external features.
Results: Of the six areas inspected involving 36 shipments, no items of noncompliance were identified.
i s o o 410 0'W15 1
DETAILS 1.
Persons Contacted Emory Williams, South Carolina Department of Health Richard J. Bluemle, South Carolina Department of Health David Ebenback, Health Physicist, Chem-Nuclear, Inc.
John Ott, Compliance Coordinator, Chem-Nuclear, Inc.
2.
General The NRC inspection consisted of a review of the shipping papers, radiation survey of the vehicle, contamination surveys and radiation level surveys of selected packages.
General surveys and observations were conducted to dete rmine if the vehicle had proper placards, proper seals, and if any obvious safety harzards 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 " shipment survey report numbers" (SSR No.), and were used by the inspectors to identify the licensee-shipper during this inspection.
3.
Shipments Inspected Thirty-six shipments were inspected during the period of December 12-13, 1979. A listing of the shippers inspected and their assigned SSR number is included as Attachment A.
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:
Material shipping name 49 CFR 172.100/172.200/172.202 Material class 49 CFR 172.200/172.202 Name sequence 49 CFR 172.200/172.202 Total quantity (volume) 49 CFR 172.200/172.202 Limited quantity 49 CFR 172.200/172.203 Name of each radionuclide 49 CFR 172.203 Physical and chemical form 49 CFR 172.203 Activity in curies 49 CFR 172.203 Category of label 49 CFR 172.203 Notation of NRC/ERDA package approval 49 CFR 172.203 Proper certification 49 CFR 172.204 7
r--
. s No items of noncompliance were identified.
5.
Each vehicle was inspected for conformance with DOT placarding requirements (49 CFR 172, Subpart F and 49 CFR 173.392). The vehicles were also inspected for compliance with the following:
Maximum transportation index of 50 -
(49 CFR 177.842)
Loaded so as to avoid spillage (49 CFR 177.842)
(49 CFR 392/177.843)
Properly blocked and braced (49 CFR 177.843)
LSA vehicle survey No items of noncompliance were identified.
6.
Maximum Radiation Levels Each truck was surveyed for maximum radiation levels in the normally occupied 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 six feet from the sides of the vehicle where possible, and on the surface of a representative package. Shipping casks were surveyed at the surface.
No levels were in noncompliance with 49 CFR 173.393 limits.
7.
Contamination Smears Each vehicle and a representative sample package was surveyed for removable contamination by smearing over a 300 square centimeters area of the surface.
No more than two smears were taken f rom any package or vehicle. Smears were taken from areas that would most likely be contaminated. The smears were checked for gross Beta-gamma contamination at the site.
4 No smears were found to be contaminated in excess of 49 CFR 173.397 limits.
8.
Packaging A representative sampling of packages from each shipment was examined for conformance with DOT marking and labeling requirements. External features of the packages were examined for conformance with DOT and NRC requirements as noted below:
Low specific activity (LSA) packaging 49 CFR 173.392 Tight packages - Ltd. Qty., or 173.392 49 CFR 173.391 No release of material 49 CFR 173.392/173.393 Radicactive material markings 49 CFR 172.310 Security seals 49 CFR 173.393 Gross weight requirements 49 CFR 172.310 Proper shipping name 49 CFR 172.100/172.300 LSA Labeling 49 CFR 173.392 Cask design specifications 49 CFR 173.393(a)
No items of noncompliance were identified.
- i o t 9.
Verification of Package Contents Due to the lack of facilities for properly opening packages at the site, the criteria for opening packages was restricted to those packages containing solidified waste (to verify the absence of free-standing water) and/or where there was evidence of leakage.
No packages were selected for opening.
No items of noncompliance were noted.
10.
Interviews Interviews were not held during this inspection.
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ATTACHMENT A SSR No.
NRC Region Shipper 018107 I
Power Authority of The State of New York Fitzpatrick Plant 10 Columbus Circle New Ycrk, New York 10019 Docket No. 50-333 018105 I
consolidated Edison of New York, Inc.
4 Irving Place New York, New York Indian Point 2 Docket No. 50-247 018097 I
Maine Yankee Atomic Power Company 20 Turnpike Road Westboro, Massachusetts 01581 Docket No. 50-309 018082 I
Philadelphia Electric Company 018084 2301 Market Street 018096 Philadelphia, Pennsylvania 19101
)
Docket No. 50-277 018087 I
Jersey Central Power Light Company 018095 Madison Avenue Morristown, New Jersey 07960 Docket No. 50-219 018086 II Carolina Power and Light Company 018093 Atta:
J. A. Jones, Senior Executive Vice 018106 President and Chief Operating Officer 411 Fayetteville Street 1
Raleigh, North Carolina 27602 Docket No. 50-325 018101 II Duke Power Company Atta:
W. O. Parker, Jr.
Vice Presidant, Steam Production 422 S. Church Street 1
Charlotte, North Carolina 28242 Docket No. 50-269
- i.
SSR No.
NRC Region Shipper 018083 II Georgia Power Company Atta:
J. H. Miller, Jr, Executive Vice President 270 Peachtree Street Atlanta, Georgia 30303 Docket No. 50-321 018077 II Tennessee Valley Authority Attn:
H. G. Parris Manager of Power 500A Chestnut Street Tower II Chattanooga, Tennessee 37401 Docket No. 50-259 018098 II Southern Space, Inc.
Columbia, South Carolina 29205 018081 II Newport News Shipbuilding Company Newport News, Virginia 23607 018076 III Commonwealth Edison Company P. O. Box 767 Chicago, Illinois Zion Plant Docket No. 50-259 018089 III D. C. Cook Nuclear Plant P. O. Box 1178 Bridgeman, Michigan Docket No. 50-315 018100 III Monsanto Research Corporation Mound Facility P. O. Box 32 Miamisburg, Ohio 45342 018102 III Kerr McGee Chemical Systems 258 Ann Street West Chicago, Illinois 60185 e m e
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