ML19345H181
| ML19345H181 | |
| Person / Time | |
|---|---|
| Site: | 07001201 |
| Issue date: | 03/27/1981 |
| From: | Coryell G, Kellogg P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19345H177 | List: |
| References | |
| 70-1201-81-02, 70-1201-81-2, NUDOCS 8105010176 | |
| Download: ML19345H181 (5) | |
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101 MARI.4TA S.
V.,%JI(E 3100 jg ATLANTA,GEoHGl/ 30303 Report No. 70-1201/81-02 Licensee: Babcock and Wilcox Compan;'
Comme.rcial Nuclear Fuel Plant Lynchburg, VA 24505 Facility Name: Commercial Nuclear Fuel Plant (CNFP)
Occket No. 70-1201 License No. SNM-1168 Inspector:
G. P. Cory Date Signed T!27!P/
Approved by:
h
~T ~ ident and R[M4ef, Division of ell Wiw Date 51sn68 P. J.
actor Project Inspection
SUMMARY
Inspection on March 17-20, 1981 Areas Inspected This routine unannounced inspection involved 24 inspector-hours on site in the areas of Organization, 10 CFR 21 implementation, Operations, Internal Review and Audit, Safety Committees, Nuclear Criticality Safety and followup on corrective actions.
Results Of the seven areas inspected, no violations or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- R. A. Alto, Manager, Virginig Operations
- D. W. Zeff, Manager, Health Safaty and Licensing W. Powers, Manager, Safeguards
- R. L. Vinton, Health Physicise "J. T. Ford, Licensing Engineer K. E. Shy, Foreman, Health and Safety P. A. Cure, Associate Health Physicist W. E. Cyrus, Supervisor, Pellet Area R. Harper, QC Technician J. E. Cregar, Puchasing Agent Other licensee employees contacted included two technicians, four operators, and two mechanics.
- Attended exit interview 2
Exit Interview The inspection scope and findings were summarized on March 19, 1981, with those persons indicated in Paragraph 1 above. The revised NRC enforcement criteria was discussed with licensee representatives.
3.
Licensee Action on Previous Inspection Findings (Closed) Violation (70-1201/30-11-01) Failure to maintain enclosure of service water piping in a moderation control area.
The licensee now provideIpositive identification of waterline baffles and enclosures and j
provided additional training for plant maintenance personnel. The inspector verified these corrective actions.
7 4.
Unresolved Items j
f Unresolved items were not identified during this inspection.
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5.
Organization a.
R. A. Alto was appointed Manager, Virginia Operations in January 1991.
W. F. Heer, former manager transferred to the B&W Barberton facility as Production Manager Mr. Alto currently remains acting production j
manager as well as Manager, Virginia Operations.
l b.
J. T. Ford has recently been appointed as Licensing Engineer. There has been no other significant changes in the Health, Safety and Licensing staff.
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2 6.
10 CFR Implementation a.
The licensee has approved policies and procedures for discharging 10 CFR 21 requirements. The procedures assign responsibilities, establish reporting and review requirements and impose 10 CFR 21 provisions on procurement documents for safety-related components.
The following Corporate and Division policies and procedures were reviewed:
(1) 1716-A1, Reporting of Defects and Noncompliance Concerning Safety (10 CFR 21)
(2) 1208-A5, Government Aspects of Procurement (3) AS-1128: Rev. 2, Reporting of Defects and Noncompliance (Nuclear Materials and Manufacturing Division)
(4) QC-AD-1433, Rev. 2, Reporting of Defects and Nonconformance b.
Examination of the 10 CFR 21 file showed that one equipment defect was evaluated and judged to not be reportable. There has been no report-able events in the last t welve months.
c.
Purchase orders wer examined and 10 CFR 21 requirements were specified for licensee ident'.fied basic components and services.
d.
Section 206 of the Energy Reorganization Act of 1974 and notices are properly posted on the facility bulletin boards.
7.
Safety Committees The inspector examined Safety Review Board meeting minutes for 1980 and the first quarter of 1981. The Board has met quarterly with required members in attendance. Meeting topics verify conformance with the committee's charter l
to review and determine acceptability of new or modified processes, review l
license amendments, audit findings, health physics trends, nuclear safety evaluations and control criteria, procedures and to arrange reviews where multiple disciplines or functions are involved.
8.
Internal Review and Audits a.
Confirmation was obtained that the nuclear criticality safety and health physics audits had been performed on a quarterly basis by independent auditors as required by license conditions. The audit file had two inspection reports missing but reports were obtained prior to i
the inspector leaving the site.
b.
The Health, Safety and Licensing staffs monthly and weekly area inspections were completed in accordance with the licensee's procedures i
and schedules.
Records verify that the annual interlock tests were completed in August 1980.
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3 c.
Reports of audit fin fings are provided the plant manager as required by license conditions. Records include reaudit findings and confirmation of completed corrective actions.
9.
Nuclear Criticality Safety a.
The inspector reviewed safety evaluation and preoperational inspection records for the new fuel element storage racks and independently verified that structural rigidity and spacing met previously approved criteria.
b.
SNM storage, transport and processing operations were observed.
Material was in approved arrays and locations, SNM scrap is handled in safe volume containers. No deviations from posted safety criteria was identified.
c.
Adherence to the following special criticality control limits was verified by observation and review of audit records:
(1) Liquid containers in the pelletizing area were limited to 3.5 gallons. Flammable solvents were limited to 2 gallons.
(2) Unsafe geometry containers are marked and covered.
(3)
Independent calculations were made of the H/U ratio prior. to release of powder for the blending operation.
(4) Batch records verify conformance to posted mass and H/U limits.
(5) Service water lines in the moderation control area are shielded and baffled to preclude spraying in the event of a ruptured line.
(6)
The total SNM inventory is less than the license limit of 20,000 kgs of U-235.
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Criticality monitoring system test records verify completion of anpual calibration and monthly source functional tests.
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- 10. Operations l
a.
Observations made during plant tours and dicussions with plant personnel confirm completion of corrective actions to prevent i
recurrence of uncovered service water liner in a moderation ~ control area.
(Item 80-11-01).
Line cavers are stenciled for positive i
identification and maintenance personnel attended additional nuclear l
safety training as stated in the licensee's response dated October 9, l
1980. This item is closed.
b.
Current approved operating procedures are available in the work areas and work stations and storage arrays are posted with applicable criticality safety limits. Operators stated that they routinely review I
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procedures when they are assigned to a work station they do not operate routinely.
c.
General housekeeping conditions are excellent. No fire or industrial safety hazards were observed during tours of the facility.
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