ML20058G432
| ML20058G432 | |
| Person / Time | |
|---|---|
| Site: | 07001201 |
| Issue date: | 07/13/1982 |
| From: | Mcalpine E, Troup G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20058G416 | List: |
| References | |
| 70-1201-82-08, 70-1201-82-8, NUDOCS 8208030324 | |
| Download: ML20058G432 (4) | |
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'o, UNITED STATES 8~
NUCLEAR REGULATORY COMMISSION g
a REGION 11 o
101 MARIETTA ST., N.W., SUITE 3100 Y
ATLANTA, GEORGIA 30303 g
o Report No. 70-1201/82-08 Licensee:
Babcock & Wilcox Company P. O. Box 800 Lynchburg, VA 24505 Facility Name:
Commercial Nuclear Fuel Plant Docket No. 70-1201 License No. SNM-1168
_e Inspector:
7 g 2__
G. L. Troup Date' Signed Approved by:
&fT(\\' (11 7// 3 /7 L E. J. McAlpine, Section thief Date Signed Technical Inspection Branch Division of Engineering and Technical Programs
SUMMARY
Inspection on June 16-18, 1982 Areas Inspected This routine, unannounced inspection involved 12 inspector-hours on site in the areas of organization, facility changes and modification, safety committees, operations and previously identified items.
Results Of the areas inspected, no violations or deviations were identified.
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4 8208030324 820715 PDR ADOCK 07001201 C
3 REPORT DETAILS 1.
Persons Contacted Licensee Employees
- R. A. Alto, Plant Manager
- D. W. Zeff, Manager, Materials Management
- L. T. Lee, Manager, Manufacturing Operations
- C W. Speight, Manager, Facilities Control R. L. Vinton, Health Physicist
- J. T. Ford, License Administrator Other licensee employees contacted included two operators.
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on June 18, 1982, with those persons indicated in paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Safety Committees The inspector reviewed the agenda and minutes for the Safety Review Board meetings on March 16 and June 16, 1982.
Attendance at the meetings and topics considered were in accordance with the board's charter. Meeting frequency was in accordance with Section V, Subsection 6.1 of the license application. The inspector had no further questions.
6.
Organization a.
Effective April 1,1982 a major reorganization of the plant organiza-tion was ef fected to a consolidate compatible functions and improve operational flexibility.
The new organization was approved by the Plant Manager with the concurrence of the Manager, Nuclear Fuel Services. The new organization was incorporated into License SNM-1168 by Amendment No.16, dated May 7,1982.
b.
D. W.
hff was appointed Manager, Materials Management with responsi-bility for license administration, safety review board, safeguards and production control.
C. W. Speight was appointed Manager, Facility
S 2
Control with responsibility for health physics, health safety, security and facility engineering. No management changes were made in Manu-facturing Operations or Manufacturing Engineering.
c.
Due to the Corporate reorganization in March 1982, the " responsible officer" for 10 CFR 21 reports had changed.
This was identified as open item 82-04-01, pending designation of the new official.
As an interim measure, the plant manager issued a memorandum on May 13, 1982 stating that the " responsible officer" is the Vice President, Nuclear Power Generation Division pending completion of the review of proce-dures by a division task force. The inspector had no questions on the interim policy but stated that this item would remain open pending completion of the task force actions.
7.
Operations a.
During a tour of the pellet area the inspector observed four plastic containers containing liquids within the moderation controlled area.
The containers were affixed with labels for a commercial product and were marked with "BH-38" or "SD-20."
Subsequent investigation by licensee representatives determined that these materials were in-dustrial cleaners and were not flammab7e. The volume of the containers was less than the limit for liquid moderators specified in Section V,-
Subsection 7.4.3.1 of the license application. Management representa-tives stated that the containers were used to transfer the cleaners from the bulk shipping containers to the area of use, and that excess containers would be remeved from the area as a housekeeping measure.
The inspector had no further questions.
b.
The inspector observed that the baffles on one side of a sintering furnace had been rearranged and one baffle was askew to permit temporary installation of a dew point monitor. Further investigation revealed that the Daffles in question were not required for water i
moderation control as no water lines were installed on that side of the furnace.
The baffles were removed and reinstalled in the proper configuration and an access hole provided for installation of the dew l
point monitor. The inspector had no further questions.
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c.
The inspector verified during plant tours that operating procedures and health safety procedures were available in the work areas and that current r(visions were in use. General safety requirements were posted in various areas of the plant.
l-d.
No apparent fire or industrial safety hazards were observed. General housekeeping conditions were satisfactory.
8.
Facility Changes and Modifications i
a.
Section V, Subsection 7.1.4 of the application states the requirement i
for the approval of modifications.
Procedure AS-1170, "CNFP Safety Review Board" implements these requirements.
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b.
The inspector reviewed the records for the approval of the installation of scrap containers near the granulator. The inspector verified that the modification had been evaluated for nuclear safety (with an independent review of the evaluation) and had been reviewed and approved by the Safety Review Board.
Installation of the containers has not been accomplished. The inspector had no further questions at thi s time.
9.
IE Information Notice 82-15 Information Notice 82-15
" Notification of the Nuclear Regulatory Commis-sion" provides an alternate telephone number for contacting the NRC Opera-tions Center. As the licensee had not received the notice, the inspector provided copies to management. After reviewing the notice, licensee re-presentatives stated that it would be included in the plant emergency procedures, which are presently being revised. The inspector had no further questions concerning the licensee's actions.