ML19249B181
| ML19249B181 | |
| Person / Time | |
|---|---|
| Site: | 07001201 |
| Issue date: | 07/08/1979 |
| From: | Coryell G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19249B169 | List: |
| References | |
| 70-1201-79-07, 70-1201-79-7, NUDOCS 7909040050 | |
| Download: ML19249B181 (4) | |
Text
pn nuou
~
'o, UNITED STATES
+
8'
' 7, NUCLEAR REGULATORY COMMI'ISION
- /
REGION 11 fo, k '" ' #
h 101 MARIETTA sT., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 g '.w. e,e
.+
Report No. 70-1201/79-7 Licensee:
Babcock and Wilcox Company Lynchburg, Virginia Facility Name:
Commercial Nuclear Fuel Plant Docket No. 70-1201 License No. SNM-1168 Inspection at Commercial Nuclear Fuel Plant near Lynchburg, Virginia 7/k
/
Inspector:
L
./
G. P. Coryell
~
D$te Signed Approved by-M
!/9 J. P. Pot
,' Section Chief, FFMS Branch Date ' Sign
SUMMARY
Inspection on June 19-22, 1979 Areas Inspected This routin-unannounced inspection involved 28 inspector-hours onsite in the areas of organization, operations, training, internal audits, safety committees and SNM packaging and shipping.
Results Of the six areas inspected, no apparent items of noncompliance or deviations were identified in five areas; one apparent item of noncompliance was found in one area (incorrectly labeled package of radioactive material - Paragraph 10.b).
7 9 0 90 4 0 0 5c>
-a o n $ ;6]. ~. t
- s) v
DETAILS
~
1.
Persons Centacted Licensee Employees
- W. F. Heer, Plant Manager R. A. Alto, Manager, Manufacturing
- D. W. Zeff, Manager, Safety Licensing and Safeguards R. L. Vinton, Jr., Health Physicist K. E. Shy, Health and Safety Superviso; J. P. Watters, Licensing Engineer L. T. Lee, General Foreman, Shop Operations G. Johnson, Foreman, Pellet Plant T. L. Wilcox, Supervisor, QC Inspection J. M. Moore, Accountability Representative Other licensee employees contacted included two technicians and four operatcrs.
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on June 22, 1979 with those persons indicated in Paragraph I above.
Licensee representatives acknowledged the findings and stated that review of shipping records would be included in internal audits.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved items Unresolved items were not identified during this inspectica.
5.
Organization The Nuclear Materials Division, in June, 1973, became the Nuclear Materials and Manuf acturing Division.
Division production facilities include the Mt. Vernen plant and CNFP. Mr. W. F. Heer, former Apollo pl. ant manager, has been appointed the CNFP Plant Manager.
Mr. D. W. Zef f is now manager of the Safety, Licensing and Safeguards Section.
Total plant employment has increased to about 200 personnel.
6.
Safety Committees The inspector examined Safety Review Board meeting minutes for four meetings conducted between December 20, 1978 and May 22, 1979. Review items include internal audit results, NRC inspection findings, proposed license amendments oar) m.o s
s,J L e
and equipment or procedural changes. The minutes verify conformar.ce to meeting frequency and quorum requirements. No items of noncompliance or deviations were identified.
7.
Internal Review and Audits An examination of the audit files showed that the nuclear criticality safety and health physics audits had been performed on a quarterly basis by independent auditors as required by the conditions of the license. The results had been reported to the plant manager and the documentation showed that corrective actions had been taken when necessary. Weekly and monthly audits were performed in accordance with the requirements of the license and the licensee's procedures. Audit records confirm inspection and preopera-tional acceptance of the recently installed ultrafiltration system. The inspector had no further questions.
8.
Operations The inspector observed operations and verified that current operating procedures were available at work stations and that Nuclear Safety limits were posted.
Plant housekeeping was satisfactory and no apparent fire hazards or unsafe conditions were observed.
No items of noncompliance or deviations were identified.
9.
Training Training program recordr and tests were reviewed for conformance with a.
requirements of License Conditions identified in Section V, paragraphs 6.3 and 15.0 and in administrative procedure AS-1101.
New hires receive basic radiation safety and nuclear safety training and cover requirements of 10 CFR 19 and 21. Radiation workers receive retraining on at least an annual basis. Six retraining sessions have been conducted this year, total attendance has been 112. Training tecords are documented and signed, written tests are on file.
b.
Special training for health-safety monitoring personnel has been provided as described in Section V, paragraph 6.3.2 of the license application. The inspector was informed that additional training for the ten member Emergency Response Team was scheduled for June 25, 1979 to provide familiarization and training for emergency response to on-site personnel.
No items of noncompliance or deviations were identified.
10.
Packaging and Transportation of Radioactive Material The licensee has established operating procedures to assure (1) that a.
preliminary and routine determinations are accomplished and (2) that regular and periodic container inspections are performed. Inspection and SNM receiving and shipping records were reviewed and compared with requirements of manufacturing procedure MA-332, Rev. 1, " Packaging and Shipping," and Health and Safety procedure AS-AD-1111, Rev. 2, " Shipment and Receipt of Radioactive Material."
eqw q vt u,..
b.
Records covering procurements of 15 new UNC-2901 containers including acceptance and release QC records were examined, in addition to inspec-tion and shipping records for BB-240-2, LA-36 and BU-7 containers.
One deficiency in shipping papers was identified. On May 14, 1979, a UO Pellet shipment in a BU-7 container measuring 0.7 millirem per 2
hour at the package surface was shipped using a Radioactive White-I
- label. 49 CFR 172.403(c) requires a Radioactive Yellow-II label for packages with surface readings above 0.5 millirem per hour and not more than 50 millirem per hour.
c.
The licensee possessed a copy of the Certificate of Compliance and referenced documents for each type of container roted in the shipping records as required by 10 CFR 71.12(b)(1)(i).
Verification was made that the licensee had a copy of each transferee's license or written certification that authorized the type, form and quantity of material shipped.
- 11. Nonroutine Events No items of this category were identified in dicussions with licensee representatives or by examinat ion of log books and records.
ii
//
//
</
9003T
//
/