ML20203F277
| ML20203F277 | |
| Person / Time | |
|---|---|
| Issue date: | 07/28/1986 |
| From: | Abbate C, Jocelyn Craig NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | |
| Shared Package | |
| ML20203F270 | List: |
| References | |
| REF-QA-99901049 99901049-86-01, 99901049-86-1, NUDOCS 8607300243 | |
| Download: ML20203F277 (10) | |
Text
{{#Wiki_filter:- ORGANIZATION: CHEM-NUCLEAR SYSTEMS, INC. BARNWELL, SOUTH CAROLINA REPORT INSPECTION [NSPECTION NO.: 99901049/86-01 DATE: 3/24-27/86 )N-SITE HOURS: 94 CORRESPONDENCE ADDRESS: Chem-Nuclear Systems, Inc. ATTN: Mr. Michael Jump President 220 Stoneridge Drive Columbia, South Carolina 29210 ORGANIZATIONAL CONTACT: Mr. Clarence Hathaway TELEPHONE NUMBER: (803) 256-0450 NUCLEAR INDUSTRY ACTIVITY: CNSI is a Certificate of Compliance holder and registered user for a number of Type A and B transportation casks and provides services for the shipping and disposal of radioactive material. ASSIGNED INSPECTOR: b6 k. h( dT! [t) C. M. Abbate, Sp'ecial Projects inspection Date Section (SPIS) OTHERINSPECTORf):r R. L. Cilimberg, SPIS ( f W. D. Sch field, EG&G APPROVED BY: c W 7 5 (o ,J hn W. Craig, Chief, SPIS, Vendor Program Branch Da t'e INSPECTION BASES AND SCOPE: A. BASES: 10 CFR Part 71,10 CFR Part 21. B. SCOPE: Observe the maintenance and repair of transportation casks, review the Chem-Nuclear Systems, Inc. (CNSI) Quality Assurance (QA) pro-gram and its implementation, and review compliance with the NRC require-ments of 10 CFR 71 and 10 CFR 21 during the maintenance of transportation casks. PLANT SITE APPLICABILITY: All nuclear power facilities who are registered users of the casks for which CNSI is the Certificate of Compliance (C of C) holder. l l 8607300243 860728 01N99EMVC
ORGANIZATION: CHEM-NUCLEAR SYSTEMS, INC. BARNWELL, SOUTH CAROLINA REPORT INSPECTION N0.: 99901049/86-01 RESULTS: PAGE 2 of 6 A. VIOLATIONS: None. B. NONCONFORMANCES: None. C. UNRESOLVED ITEMS: None. D. STATUS OF PREVIOUS INSPECTION FINDINGS: Not applicable. E. INSPECTION FINDINGS AND OTHER COMMENTS: 1. Entrance and Exit Meetings An entrance meeting was conducted on March 24, 1986, at the Chem-Nuclear Systems, Inc. (CNSI) corporate office in Columbia, South Carolina, during which the purpose and scope of the inspection was discussed. During the exit meeting, conducted on March 27, 1986 at the CNSI low level disposal site, near Barnwell, South Carolina, the inspection findings and observations were summarized. 2. Description of Activities at Barnwell, S.C. Site This inspection was the first in a trial inspection program to review the fabrication, maintenance and repair of transportation casks. There are several different organizations involved in the manufacturing, maintenance and use of transportation casks. These organizations are: (1) the cask manufacturer, (2) the Certificate of Compliance (C of C) holder and (3) the registered user. CNSI is the Certificate holder and registered user for a number of Type A and B transportation casks. CNSI also provides services for the shipping and disposal of radioactive material. During the in-spection, the NRC inspectors observed the handling procedure for transportation cask number CNSI 14-195H, C of C Number 9094. Hand-ling Procedure TR-0P-008, Revision H, dated January 30, 1986 was
ORGANIZATION: CHEM-NUCLEAR SYSTEMS, INC. BARNWELL, SOUTH CAROLINA REPORT INSPECTION NO.: 99901049/86-01 RESULTS: PAGE 3 of 6 used by CNSI staff members and provided for a dimensional check of the cask, tool and material requirements, acceptance criteria, pro-cedures for loading and unloading, the removal and installation of the cask from the trailer, and requirements for reports and records. 3. Maintenance and Repair Activities After the contents of the CNSI 14-195H cask had been unloaded at the trench area, the NRC inspectors observed the CNSI QA staff visually inspecting the primary and secondary lid gaskets for cracks, tears or areas where the gaskets had come unglued. The secondary lid is a smaller diameter lid which fits inside the primary lid and provides access when material is loaded into the liner of the cask. Ordinarily, the secondary lid gasket is inspected only if the seal has been broken or if the seal is not a CNSI seal, while the primary lid is inspected whenever it is removed. Onthe14-195Hcask,bothgasketshadareaswhichhadcomeunglued,f therefore, the lids were removed in the Cask Maintenance Building (CMB). A radiation sirear was taken and both gaskets were repaired per " Gasket / Seal /0-Ring Replacement / Repair Procedure for CNSI Cask Fleet," TR-MN-005, Rev. D, dated January 30, 1985. The procedure observed by the inspectors included"a worker scraping off the old sealant on the primary gasket with a metal scraper and applying new sealant to the area. Acetone was used to remove the old cement on the secondary lid gasket before regluing. Both repairs were inspected by the CNSI QA personnel and were done in accordance with the written procedures. 4. Quality Assurance Records The NRC inspectors reviewed the data package which contained the QA records furnished by Richmond Engineering Company (RECO), a cask manufacturer, for the CNSI 14-190H, Series A Transportation Cask, serial number NS-2551 for CNSI PO 436776. Each data package in-cludes certificates of compliance which state that the cask meets the purchase order and specification requirements for certification of personnel qualifications, gamma scanning and leak testing, non-conformance reports, welder qualification tests, welding procedure specifications, lead filling, and drawings.
) ORGANIZATION: CHEM-NUCLEAR SYSTEMS, INC. BARNWELL, SOUTH CAROLINA REPORT INSPECTION NO.- 99901049/86-01 RESULTS: PAGE 4 of 6 The NRC inspectors determined that the QA records in the data package met the requirements of specification number 24505-186-01, Revision 0 and Purchase Order (P0; 436776 as well as section 17.0, " Quality Assurance Records" of the CNSI Quality Assurance Program, QA-AD-001, Rev. E, dated January 20, 1986. 5. Procurement Document Control The NRC inspectors reviewed CNSI P0 number 436776, dated July 8, 1985, to REC 0. This P0 was issued for the fabrication of trans-portation cask CNSI 14-190H, Series A. CNSI specification number 24505-186-01, " Procurement Specification for Transport Cask CNSI 14-190H Series A," Revision 0, dated June 11, 1985, provides the technical requirements for the cask and is referenced by P0 436776. This specification identifies NRC C of C number 9159 for the above cask and imposes the QA requirements of 10 CFR 71, Subpart H on REC 0, the cask f abricator. k The inspectors also reviewed P0s 439471, 439599, and 439598 for replacement gaskets and the corresponding Inspection / Rejection Reports (IRRs) written by CNSI. Replacement gaskets are supplied to CNSI by Charleston Rubber & Gasket and are receipt inspected. An IRR was filled out for each P0 and contained a checklist of items to be inspected during receipt inspection. The receipt inspector could check satisfactory or unsatisfactory on these items in addi-tion to describing problems found during the inspection. The NRC inspectors determined that the procurement documents were in accordance with Section 4.0, " Procurement Document Control" and that the receipt inspection of replacement gaskets was performed in accordance with Section 7.4, " Receiving Inspection" of the CNSI QA Program. 6. Personnel Qualification l l Auditors CNSI has a formal training and testing program for personnel quali-fica tion. The NRC inspectors determined by review of selected per-sonnel files that six auditors are currently qualified in accordance with CNSI procedure number QA-AD-009, " Quality Assurance Department c Training," Revision B, dated January 14, 1986.
.u ORGANIZATION: CHEM-NUCLEAR SYSTEMS, INC. BARNWELL, SOUTH CAROLINA REPORT INSPECTION NO.- 99901049/86-01 RESULTS: PAGE 5 of 6 Nondestructive Exam' nation (NDE) The NRC inspectors reviewed the qualifications of three Level II NDE personnel at REC 0 and determined that their accreditations were in compliance with the guidelines of practice number SNT-TC-1A recommended by the American Society for Nondestructive Testing. Welder The NRC inspectors reviewed the qualification tests for one REC 0 employee and determined that he had qualified for Shielded Metal Arc Welding (SMAW) and Gas Tungsten Arc Welding (GTAW) in accor-dance with Section IX of the ASME Boiler and Pressure Vessel Code 1983 Edition, Summer 1984 Addendum, as required in CNSI specifica-tion number 24505-186-01. Brokers 7 The inspector reviewed a list of brokers used by CNSI. Brokers are' personnel who are authorized and qualified to make radioactive shipments. Training records and programs were reviewed and found in compliance with CNSI's procedure number RA-TN-001, Revision B, " Procedure for Training and Certification of Chem-Nuclear Systems, Inc. Radioactive Materials Brokers," dated April 11, 1985, and with the Code of Federal Regulations, Title 49 CFR, Parts 100-199. 7. Internal Audits The NRC inspectors reviewed CNSI procedure number QA-AD-011, " Quality Assurance Internal Audit Procedure," Revision B, dated August 20, 1985. This procedure is based on operating experience and provides guide-lines for items to be checked in various parts of the program such as areas of previous and potential nonconformances. The NRC inspectors reviewed the following four CNSI internal audit reports: QAB-84-216-02, " Liner Operations ~," dated August 3,1984, CAB-84-04-01, " Maintenance and Trench Operations," dated February 14, 1984, and QAB-84-256-02, " Purchasing," dated September 12, 1984, and RA-0464-5, the internal radiological audit for 1985. The NRC inspectors determined that the audits were performed and the reports written in accordance with the requirements of CNSI QA manual number QA-AD-001 and CNSI procedure number QA-AD-011. The audits are conducted once every 12 months and provide an independent verification
ORGANIZATION: CHEM-NUCLEAR SYSTEMS, INC. BARNWELL, SOUTH CAROLINA REPORT INSPECTION NO.- 99901049/86-01 RESULTS: PAGE 6 of 6 4 1 of the CNSI quality system practices, procedures, and effectiveness. Audit findings are written in detail and require follow-up to achieve corrective action which must be accepted and approved by the QA orga-nization. 8. Transportation Trip Reports A Transportation Trip Report accompanies each cask on a trip. Each package contains records and reports pertaining to the truck, cask, and material being transported. The NRC inspectors reviewed four such reports. Included in the package were a report from the driver which covered his inspection of the truck, a safety inspection report of the truck performed by the CNSI staff, and repair work performed on the truck as a result of incoming and outgoing inspections. Also included was a QA Cask Radioactive Shipment Inspection Form which was a checklist of items inspected at the site gate, cask maintenance bifilding, and trench. The trip order stated where and what (drums, or pallets) was being shipped. The Isotopic Analysis report and a F description of where the waste was coming from was found in the Ra
- dioactive Waste Shipment and Disposal Manifest (RSM). The package also contained the Arrival Release Form which was the radiation sur-vey and dose rates of the shipments upon arrival.
F. PERSONS CONTACTED
- D. Ebenhack, Vice President, Regulatory Affairs
- C. Hathaway, Director, Quality Assurance L. Poppe, Director, Licensing S. Kintner, Document Control
- R. Byars, Manager, Quality Assurance
- C. Ross, Audit Supervisor, Quality Assurance A. B. Bonifacio, Quality Assurance Representative, Avon, CT
- D. Hartzog, Quality Assurance Department
- J. Zawacki, General Manager, Barnwell Site
- M. Benjamin, Health Physics Manager, Barnwell Site M. Ryan, Director, Regulatory Affairs L. Toner, Assistant General Manager, Transportation Services M. Grubbs, Quality Assurance B. Gainey, Site Supervisor M. Lewis, Broker Supervisor
- Attended Exit Meeting
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