ML19323B352
| ML19323B352 | |
| Person / Time | |
|---|---|
| Site: | 07001201 |
| Issue date: | 03/20/1980 |
| From: | Coryell J, Kahle J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19323B346 | List: |
| References | |
| 70-1201-80-05, 70-1201-80-5, NUDOCS 8005120269 | |
| Download: ML19323B352 (4) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION O
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101 MARIE TTA ST N.W 5UITE 3100 o
'g ATLANTA, GEORGIA 30303 l
MAR 211980 i
j Report No. 70-1201/80-5 i
License No. SNM-1168
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Licensee:
Babcock and Wilcox Company Lynchburg, VA 24505 Facility Name:
Commercia1 oclear-F 1~ Plant Inspector:
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B G.P.Coryell~[
"[ ' ~ l Zfate ' Signed Approving Section Chief:
O'}Nd la 3/N A J. B.
snle,' Acting Chief, SFGS Branch Dat( Signed Dates of Inspection: March 4'-7, 1980 Areas Inspected: This routine, unannounced inspection involved 24 inspector-hours onsite in the areas of Facility Changes and Modifications,10 CFR 21 Implementation, Safety Committees, Operations, Training and Transportation.
Results: Of the 6 areas inspected, no apparent items of noncompliance or deviation were identified.
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DETAILS i
1.
Persons Contacted 4
i Licensee Employees i
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- V. F. Heer, Manager, Virginia Operations
- D. W. Zeff, Manager, Health Safety and Licensing i
- W. Powers, Manager, Safeguards
- J. P. Watters, Licensing Engineer
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R. L. Vinton, Jr., Health Physicist j
K. E. Shy, Health and Safety, Supervisor P. A. Cure, Associate Health Physicist L. T. Lee, General Foreman, Shop Operations Other licensee employees contacted included 4 technicians, and four operators.
i Other Organizations i
- J. W. Bates, NRC, RII I
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on March 7, 1980 with those persons indicated in Paragraph I above.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items i
Unresolved items were not identified during this inspection.
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5.
10 CFR 21 The licensee has approved policies and procedures that assign responsi-a.
l bilities, provide for evaluation of safety concerns, establish reporting criteria and to impose 10 CFR 21 provisions on procurement documents for basic components. The following procedures were examined.
i (1) 1716-A1, Reporting of Defects and Noncompliance Concerning Safety (10 CFR 21) l (2) NPG-1707-01 (Rev. 5) Processing of Safety Concerns I
(3) QC-AD-1433 Reporting of Defects and Non-conformance l
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(4) AD-Il28 (CNFP) Reporting of Defects and Noncompliance 10 CFR 21 b.
Purchase orders were examined and 10 CFR 21 requirements were included j
for licensee identified basic components. Verification was made that j
posting requirements were met.
c.
The licensee's evaluation of possible deviations concluded that no items requiring a 10 CFR 21 evaluation have occurred in the past year.
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Facility Changes and Modifications Selected change request records were audited for compliance with require-a.
me_ats of license application,Section V " Conditions", subsection 7.1.4 b.
Change request records for a grinder sludge collection receptacle and l
a new resintering furnace installation verify review by the Manager, Health Safety and Licensing, nuclear safety evaluation by the Nuclear Criticality Safety function and review by the Safety Review Board as required by license conditions.
c.
The grinder sludge collection unit is in service. Verification was made that approved procedures and criticality control signs were posted and that a pre-operational safety audit was performed prior to operational use.
The resintering furnace has not been accepted for use.
Pre-operational audit and safety interlock test records will be reviewed on a subsequent inspection.
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Safety Committee i
The Safety Review Board meeting minutes for 1979 confirm meetings at least quarterly and with required management members in attendance. Discussion 1
topics included evaluation of change requests, proposed process inodifications, proposed license amendments, NRC and internal audit reports and corrective actions.
8.
Operations 4
a.
The inspector verified during plant tours, that operating procedures were available in the work areas and that current revisions were in use.
Criticality safety. limits were posted for work stations and arrays.
General safety requirements were posted in various areas of the plant.
b.
Discussions with operators and techniciant indicate a good working j
knowledge of industrial and nuclear safety criteria and confirmed performance of safety retraining in 1979.
No apparent fire or industrial safety hazards were observed and genrral f
c.
housekeeping conditions were satisfactory.
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Training a.
Training program records for 1979 were reviewed for conformance with license conditions identified in Section V, Subsection 6.3 and CNFP procedure AS-1011.
Personnel training records confirm that new hires received initial radiation, nuclear and industrial safety training I
including requirements of 10 CFR 19 and 21.
Radiation workers receive additional health and safety retraining on at least an annual frequency.
i b.
Records verify performance of special training for health physics monitors as described in Section V, subsection 6.3.2.
In 1979 one training course was provided the plant Emergency Response team.
A practice " Nuclear Emergency" drill that included off-site assistance and hospital participation was perforced on December 13, 1979. No deficiencies in the area of training were identified.
10.
Transportation Program The in pector discussed the revised Radioactive Material Transportation a.
prograa and procedures with licensee representatives.
The recently revis -d pr<scedure AS-1111, " Shipment and Receipt of Radioactive Material" and
- r. ocedure NM-1610, " Documentation of Scrap Shipments" delineate rer. esibility for SNM shipping activities.
b.
The loading and QC inspection of two fuel assembly shipping containers I
were observed. Activities were in conformance with procedures QC-R-224, Rev. 8, " Assembly Loading Checklist" and QI-FA-815 " Fuel Assembly -
Shipping Container Loading & Shipping Inspection".
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