ML19339A468
| ML19339A468 | |
| Person / Time | |
|---|---|
| Site: | 07001201 |
| Issue date: | 09/19/1980 |
| From: | Coryell G, Kahle J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19339A464 | List: |
| References | |
| 70-1201-80-11, NUDOCS 8011040051 | |
| Download: ML19339A468 (5) | |
Text
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'b UNITED STATES
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8' NUCLEAR REGULATORY COMMISSION o
E REGION 11 b[
g 101 MARIETTA sT., N.W., sulTE 3100 o
ATLANTA, G EORGIA 30303 SEP 191980 Report No. 70-1201/80-11 Licensee: Babcock and Wilcox Company Commercial Nuclear Fuel Plant Lynchburg, VA 24505 Facility Name: Commercial Nuclear Fuel Plant Docket No. 70-1201 License No. SNM-1168 Inspector:
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9 G.P.Coryell]
9 //5!74 Approved by:
L J. B. Ka e, Acting Section Chief, Safeguards Branch
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SUMMARY
Inspection on August 26-29, 1980.
Areas Inspected This routine, unannounced inspec:. ion involved 22 inspector-hours on site in the areas of operations review, training, facility changes and modifications, procedure control and followup of IE Circulars and Information Notices.
Results Of the five areas inspected, no apparent items of noncompliance or deviations were identified in four areas; one apparent item of noncompliance was found in one area - Infraction - Failure to maintain baffling in place around service water piping in the pelletizing area (80-11-01).
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DETAILS 1.
Persons Contacted
- W. F. Heer, Manager, Virginia Operations
- D. W. Zeff, Manager, Health, Safety and Licensing
- R. L. Vinton, Jr., Health Physicist
- P. A. Cure, Associate Health Physicist K. E. Shy, Supervisor, Health and Safety J. P. Watters, Licensing Engineer S. E. Carter, Supervisor, Fuel Assembly and Fabrication G. Johnson, Supervisor, Pelletizing Area B. Lacks, Supervisor, Pelletizing Area Other licensee employees contacted included several technicians and operators.
- Attended exit interview.
2.
Exit Interview The inspection scope and findings were summarized on August 29, 1980, with those persons indicated in Paragraph I above.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Facility Changes and Modifications a.
Facility chane -~ quests, health and safety evaluations and review and approval reco additional fuel assembly storage racks, resintering furnace installat.'on and a proposed waste water flocculation unit were reviewed.
Documentation showed that appropriate safety reviews had been accomplished as required by the conditions section of the license application.
b.
Verification was made that approved procedures were being developed and that a pre-operational audit must be completed prior to initial use or operation of the facility modifications. The inspector was informed that final approval of the fuel storage racks was heldup pending completion of an SRB review of potential accident conditions.
SRB review records will be examined on a future inspection.
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6.
Safety Committees.
p The Safety Review Board (SRB) met on May 13, July 18-and July 28-29, 1980,
- with the assigned members in attendance. Meeting minutes verify SRB review of powder unloading operations, fire safety practices, fuel assembly rack safety review, audit and inspection reports, facility modifications review and review of proposed license amendments. SRB activities met the require-l ments of the. license and the administrative procedure, AS-AD-1120, CNFP i
Safety Review Board.
7.
Operations I
a.
Current operating procedures were available in the work areas. Discus-sions with operators indicate that they had read the procedures and were aware of nuclear and radiation safety limits. Operators stated that they review procedures if they are assigned to a work station j-they do not operate routinely. Verification was made. that operating personnel had attended retraining sessions in the last twelve month period.
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b.
- The inspector observed that SNM was stored in approved arrays and within posted safe mass limits. The pelletizing area is a designated moderation control area.
On August 26, 1980, it was-noted that a section of a sheet metal baffle was not in place over service water
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lines in the pelletizing area as required by a license condition,Section V, Subsection 7.4.3.1.
Area supervision corrected the specific j.
condition immediately.
Licensee representatives were informed that i
failure to maintain the water line baffling in place was ' considered to be an item of noncompliance (80-11-01).
I 8.
Training i
1 Personnel training records for 1980 were checked for conformance with a.
license conditions defined in the license - application,Section V, Subsection 6.3 and the licensee's administrative procedure AS-AD-1101.
The records confirm that new hires receive instruction in radiation and nuclear safety that includes coverage of 10 CFR 19 requirements.
Radiation workers have received safety retraining in the last _ twelve
_ month _ period. One hundred and fifty five employees were retrained on i
plant emergency procedures in' July 1980. Employees also participated
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t in the practice evacuation drill conducted, by shift, on June' 23, 24, 4
and 26,1980. Selected employees were trained on current regulations l.
and procedures for shipment of radioactive material in March 1980.
J-The inspector.was informed that additional training has been provided i
b.
to the plant Emergency' Response Team for familiarization with site specific fire control and other emergency response procedures. The inspector had no further questions.
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Procedure Control 1
a.
Each functional component of the licensee's organization has the responsibility for preparing, obtaining approvals, issuing, distribution l
control and revision of procedures. All components must comply with I
the requirements of procedures PC-1300, Rev. - 2, "CNFP Procedure Numbering System" and PC-1330, Rev. 1, " Preparation and Approval of CNFP Admini-strative and Operative Procedures."
b.
The procedure system is divided into Administrative Procedures that define systems for control of manufacturing service functions and Operative Procedures that direct manufacturing operations.
c.
Selected procedures were reviewed for conformance with the basic procedures noted in "a" above and with the appropriate component j
procedures as follows:
(1) AS-1124, Rev. 4, " Preparation, Distribution and Control of Health, Safety and Licensing Procedures."
(2) QC-1421, Rev. 1, " Review and Approval of Drawings, Specifications and Procedures."
(3) QC-1425, " Distribution of CNFP QC Documents."
(4) MA-1200, " Manufacturing Document Control."
d.
Verification was made that the current revision of procedures were in and that document control records were up to date. Procedures use MA-312, Rev. 4, " Blender Loading and Operation," and MA-AD-1800, " Safety During Maintenance Activities," were audited for conformance to admini-strative requirements and no deficiencies were identified.
e.
Verification was made that Health, Safety and Licensing Procedures have been reviewed and updated in the past year.
10.
IE Circulars and Information Notices a.
Circulars (1) 80-14, issued 6/24/80, " Radioactive Contamination of Plant Demin-eralized Water Systems and Resultant Internal Contamination of Personnel." Use of plant supplied demineralized water for human consumption is prohibited.
There are no connections with any other system.
(2) 80-20, " Changes in Safe-Slab Tank Dimensions." The one slab tank at the facility handles liquid effluents with only trace quantities of SNM. The tank is supported by a framework of steel bracing.
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1 b.
Information Notices (1) 80-24, " Transportation and Commercial Burial of Radioactive Material." Confirmation made that correct criteria and latest requirements are known.
(2) 80-25, " Transportation of Pyrophoric Uranium." The licensee does not possess or handle uranium in a metallic or pyrophoric form.
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