ML19323E287
| ML19323E287 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Oconee, Pilgrim, Brunswick, Surry, FitzPatrick, 02700047 |
| Issue date: | 03/28/1980 |
| From: | Brown R, Potter J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | AFFILIATION NOT ASSIGNED, DUKE POWER CO. |
| Shared Package | |
| ML19323E282 | List: |
| References | |
| NUDOCS 8005230341 | |
| Download: ML19323E287 (4) | |
Text
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/p recog'b't UNITED STATES o
' NUCLEAR REGULATORY COMMISSION
. e REGION il o
101 MARIETTA ST., N.W., SUITE 3100 o
ATLANTA, GEORGIA 30303 Special Report: WASTE PACKAGING INSPECTIONS OF LICENSEE-SHIPPERS
Reference:
TI 2840/1, (Rev. 1), " Waste Packaging Inspections", 10/10/79 Licensee-Shipper:
See Attachment A Disposal Site:
Chem-Nuclear Systems, Inc.
P. O. Box 726, Barnwell, South Carolina 29812 Docket o.
15000 39 Inspector:
b R.[F&MS. Brown, Radiatfdrf Specialist, D5teAigned F
- ti S Branch Approved by:
Ih J. P.f otter, Chief, FF&MS Section, FF&MS Branch yate[ Signed
SUMMARY
Inspection Dates:
March 13-14, 1980 visit to Chem-Nuclear Waste disposal site, Barnwell, South Carolina for unannounced inspections of licensee-shippers.
Areas Reviewed: Each licensee-shipper vehicle was inspected for compliance with Department of Transportation (DOT) and Nuclear Regulatory Commission (NRC) regu-lations as follows: (1) shipping paper requirements; (2) DOT Placarding require-ments; (3) radiation levels; (4) removable contaminction; (5) DOT marking and labeling requirements for packages; (6) DOT and NRC requirements for external package features, and (7) prohibited articles or contents.
Results:
Of the seven areas inspected involving 15 shipments, no items of noncompliance were identified.
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DETAILS 1.
Persons Contacted R. Sappington, South Carolina DHEC W. House, South Carolina DHEC D. Ebenhock, Chem-Nuclear Systems, Inc.
L. Reynolds, Chem-Nuclear Systems, Inc.
C. Hathaway, Chem-Nuclear Systems, 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 determine if the vehicle had proper placards, proper seals, and if any 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 " shipment survey report numbers" (SSR No.)
and were used by the inspectors to identify licensee-shippers during this inspection.
3.
Shipments Inspected Fifteen shipments were inspected during the period of March 13-14, 1980. A listing of the shippers inspected and their assigned 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
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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 or label 49 CFR 172.203 i
Notation of NRC/ERDA O
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- package approval 49 CFR 172.203 Proper certification 49 CFR 17L.204 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)
Properly blocked and braced (49 CFR 173.392/177.842)
LSA vehicle survey (49 CFR 177.843)
No items of noncompliance were identified.
6.
Maximum Radiation Levels Each truck was surveyed for maximum radiation levels in the normally occupied rm tions 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 cask were surveyed at the surface.
No levels were in noncompliance with 49 CFR 173.393 limits.
l 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 uore than two smears were taken from 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.
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 requirments as noted below:
Low specific activity (LSA) packaging 49 "FR 173.392 Tight packages - ltd. Qty.,
49 CFR 173.391 or 173.392 No release of material 49 CFR 173.392/173.393 Radioactive material markings 49 CFR 172.310 Security seals 49 CFR 173.393 Gros & weight requirements 49 CFR 172.310 e
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' Proper shipping name 49 CFR 172.100/172.300 LSA labeling 49 CFR 173.392 Cask design specifications 49 CFR 173.393a No items of noncompliance were identified.
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 items of noncompliance were noted.
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APR -71880 Docket No. 1500039 ATTACHMENT A NRC SSR NO.
Region CARRIER TRAILER NO.
LICENSEE-SHIPPER 019104 I
HITTMAN 72233 Philadelphia Electric Company 019110 I
Tri-State 72485 2301 Market Street 019119 I
Hittman 72237 Philadelphia, PA 19101 Peach Bottom Plant Docket No. 50-277 019113 I
Chem-Nuclear 049 Power Authority of the State of New York 10 Columbus Circle New York, NY 10019 Fitzpatrick Plant Docket No. 50-333 019114 I
Chem-Nuclear 044 Niagara Mohawk Power Corporation 300 Erie Boulevard West Syracuse, NY 13202 Nine Mile Point Plant Docket No. 50-220 019122 I
Chem-Nuclear 040 Boston Edison Company 800 Boylston Street Beston, MA 02199 1
Px1 grim Plant Docket No. 50-293 019108 II Chem-Nuclear 022 Virginia Electric & Power Company Atta:
J. H. Ferguson Executive Vice President-Power E. O. Box 26666 Richmond, VA 23261 Surry Plant Docket No. 50-280 Report No. 80-07 019111 II Chem-Nuclear 050 Carolina Power & Light Company 019117 II Chem-Nuclear 007 Atta:
J. A. Jones, Senior Executive Vice President and Chief Operating Officer 411 Fayetteville Street Raleigh, NC 27602 Brunswick Plant Docket No. 50-325 Report No. 80-13 019100 II Mason-Dixon 41661 Tennessee Nuclear Specialties P. O. Box 158 Jonesboro, TN 37659 4
APR - 71980 o r s
NRC SSR NO.
Region CARRIER TRAILER NO.
LICENSEE-SHIPPER 019115 II Chem-Nuclear 033 Westinghouse Electric Corporation Atta:
M. D'Amore, Manager Columbia Plant Columbia, SC 29205 Report No. 80-07 019116 II Home 018 Neoplastic Diseases Dr. Weisman 740 Magnolia Avenue Orlando, FL 019107 II Chem-Nuclear 026 Duke Power Company Attn:
W. O. Parker, Jr.
Vice President, Steam Production 422 South Church Street Charlotte, NC 28242 Oconee Plant Docket No. 50-269 Report No. 80-I0 019118 III Hittman 72230 Commonwealth Edison Company Dresden Nuclear Power Station RR #1 Morris, IL 60450 Docket No.50-010 019105 III Hittman 72484 Commonwealth Edison Company P. O. Box 767 Chicago, IL 60690 Quad-Cities Plant Docket No. 50-254 4
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