ML19254E860
| ML19254E860 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse |
| Issue date: | 09/18/1979 |
| From: | Coryell G, Gillespie F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19254E858 | List: |
| References | |
| 70-1151-79-13, NUDOCS 7911020422 | |
| Download: ML19254E860 (4) | |
Text
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
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,c REGION 11 0
101 MARIETTA ST N.W.,SulTE 3100 g*
ATLANTA, GEORGIA 3o3o3 SEP 191979 Report No.
70-1151/79-13 Licensee: Westinghouse Electric Corp.
Nuclear Fuel Division Drawer R Columbia, South Carolina 29205 Facility Name-Columbia Nuclear Fuel License No. SNM-1107
.7 Inspector:
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Date Signed Approve by:
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lespie, Chief, MC&A Section, D(te Signed Safe ards Branch Inspection on September 4-7, 1979 Areas Inspected This routine unannounced inspection involved 26 inspector-hours onsite by one NRC inspector in the areas of facility changes due to plant expansion, operations, safety committees, previous inspection findings and unusual occurrences.
Results Of the five areas inspected, no apparent items of ranccepiance or deviations were identified.
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REPORT DETAILS 1.
Persons Contacted
- E. M. Philpot, General Supervisor
- W. L. Goodwin, Regdatory Compliance Manager
- C. F. Sanders, R&E Manager H. T. King, Nuclear Criticality Engineer
- E. K. Reitler,it&E Engineer L. Coco, R&E Engineer R. O. Noe, Chemical Development Engineer B. F. Garrett, Facilities Engineer J. B. Spangler Facilities Engineer D. H. Logan, Supervisor, Chemical Manufacturing Other licensee employees contacted included four construction craftsmen and four operators.
- Denotes those present at the exit interview.
2.
Exit Interview The inspection scope and findings were summarized on September 7, 1979 with those persons indicated in Paragraph I above. The facility expansion status and schedule were discussed and corrective actions for outstanding items were reviewed. Licensee management provided available information regarding the minor chemical release on September 6, 1979.
3.
Licensee Action on Previous Inspection Findings (Closed) Noncompliance item (79-08-01) Failure to store SNM in ac-a.
cordance with posted instructions.
Corrective action to assure proper spacing was verified (paragraph 7.b).
b.
(Closed) Noncompliance item (79-10-01) Failure to adequately evaluate the refresher training program. A revised examination and an expanded monitoring proge m for training are now in use (pargraph 7.b).
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Facility Changes and Modifications a.
Plant Expansion The inspector toured the construction area and inspected equipment installation in the company of the Chemical Development Engineer, Nuclear Criticality Engineer and assigned Facility Engineers. The h))"O
( solvent extraction and incinerator units are greater than 90% com-plete. The Manufacturing Development Laboratory is an assigned area only. No equipment has been installed.
b.
Solvent Extraction The solvent extraction system is inctalled except for transfer of the prototype extraction column and strip column from the pilot plant in the licensed facility. Installed equipment includes a scrap dissolver system such as in use in the operating area, feed and adjustment tanks, product storage and blending tanks, a uranyl nitrate concen-trator, a nitric acid recovery cnit and necessary piping, instru-mentation, vent system, ventilation equipment and utilir,i supplies. No deviations from the licensee's description were identificc.
c.
New Incinerator System The controlled air, dual chambered, gas fired incinerator and auxiliary equipment including quench tower, absorber tower heat exchanger, condenser, and motor control center are installed. Exhaust sv, tem units were being installed during the inspection period and installation is scheduled for completion by September 15. The Facility Engineer verified installation of the safety mechan.sms as described in Section 1.9.7.7 of the amendment application. It was noted that the process water supply line is equipped with a backflow preventer valve as well as dual check valve at the equipment inlet.
d.
Review and Approval Construction blueprints and material and equipment specifications have been reviewed and approved as specified in Section 2.3.2.3 " Radiation Protection and Nuclear Criticality Safety Administration" of the license application and the implementing procedures RC-202 and RC-300.
No deviations from the amendment application description or Nuclear Safety Analysis assumptions were identified in the areas inspected.
6.
Safety Committees Regulatory Compliance Committee Meeting minutes for June 20, July 5 and August 7, 1979 meetings were examined. Designated commit *2e members were present as required by license condition 19. Meeting frequency greatly exceeds the semi-annual requirement. Discussion topics include internal audit findings, ALARA Task Force program developments, license amendment actions and review of NRC inspection reports. The draft ALARA report for January-June 1979 was reviewed. Records verify operation of the Safety Policy Committee to identify plant safety trends and review corrective actions. To items of noncompliance or deviations wer'e identified.
- t 7.
Operations During tours of the operating areas, the inspector found that oper-a.
ating procedures were available at work locations or control room.
Operations logbooks were checked to verify that conductivity monitors and liquid level detectors in the UF6 vaporization area were tested and calibrated.
b.
The licensees correctise actions regarding previously identified items of noncompliance were reviewed. The storage shelf separation in the QC Laboratory cabinet is greater than 16 inches and criticality safety requirements are posted. The refresher training examination has been revised to cover major topics in the training agenda. Training program effettiveness is evaluated by use of tests in addition to questionnaires and internal safety inspection findings. The inspector had no further questions on these items.
c.
No items of noncompliance or deviations were identified.
8.
Nonroutine Event The chemical process area ras evacuated at 3:00 p.m. on September 6, a.
1979 due to a visible release of ammonium diuranate fines from an offgas scrubber vent on one line. The licensee, per procedure, shut-down the affected area and evacuated the area until air samples were evaluated. Personnel entering the area wore full face masks.
b.
The maximum uranium concentration in the area near the scrubber was ten times the 10 CFR 20,' Appendix B concentration limit for a e-stricted area. Room air reached normal background level and normal operations resumed by 3:40 p.m.
Preliminary investigation findings show no contamination of workers c.
and no elevated stack releases. Room air exhausts through the normal HEPA filter bank exhaust system.
Initiating cause appears to be failure of a level control on the offgas scrubber and faulty instal-lation of a temporary vent from the scrubber.
d.
The licensee's evaluation and corrective actions will be reviewed on a subsequent inspection.
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