ML19257B772
| ML19257B772 | |
| Person / Time | |
|---|---|
| Site: | 07001201 |
| Issue date: | 11/21/1979 |
| From: | Coryell G, Gillespie F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19257B770 | List: |
| References | |
| 70-1201-79-14, NUDOCS 8001180301 | |
| Download: ML19257B772 (5) | |
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o UNITED STATES 8"
~,1, NUCLEAR REGULATORY COMMISSION
$,W).,.,j ;[E REGION II o,
101 MARIETTA ST., N.W., SUITE 3100
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ATLANTA, GEORGIA 30303 NOV 2 31979 Report No. 70-1201/79-14 Licensee:
Babcock and Wilcox Company Lynchburg, Virginia Facility Name: Commercial Nuclear Fuel Plant (CNFP)
License No. SNM-1168
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9 Inspector:
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g G. P.
ell ~/
f-Dite Signdd Approved by:
///fp7d il/A//77 F. P. Gillespie,'Se ion Chief, Safeguards Branch Date Signed Date of Inspection: November 6-9, 1979 Areas Inspected This routine, unannounced inspection involved 27 inspector-hours onsite in the areas of facility changes and modification, procedure control, nuclear criticality safety, operations review, safety committees, and previous enforcement matters.
Results Of the six areas inspected, no apparent items of noncompliance or deviations were identified.
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e DETAILS 1.
Persons Contacted Licensee Employees W. F. Heer, Manager, Virginia Operations R. A. Alto, Manager, Manufacturing
- D. W. Zeff, Manager, Health Safety and Licensing
- Wm. Powers, Manager, Safeguards P. A. Cure, Associate Health Physicist K. E. Shy, Health and Safety Supervisor W. E. Cyrus, Supervisor, Pellet Area K. H. Campbell, Maintenance Supervisor S. E. Carter, Supervisor, Fuel Assembly Fabrication J. T. Anderson, MBA Custodian Other licensee employees contacted included two technicians and six operators.
- Attended exit interview.
2.
Exit Interview The inspection scope and findings were summarized on November 9, 1979 with those persons indicated in Paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings (Closed) Noncompliance Item (79-07-01) use of an incorrect radioactive a.
label on a type B container.
Corrective actions completed include further training, revised procedures and internal audits of shipping records.
b.
(Closed) Unresolved Item (79-12-01) method of determining sample size of vegation samples. Revised procedure requires a weight determination to verify sample size.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Safety Committee The Safety Review Board (SRB) met on April 27, May 22 and August 23, a.
1979 with all members in attendance. Meeting minutes confirm review of internal audit findings, NRC inspection results, proposed facility modifications, procedure revisions and discussion of licensing actions and Federal Regulations.
1770 I19 b.
SRB activities met requirements of license conditions and procedure AS-AD-1120, "CNFP Safety Review Board" conditions.
6.
Facility Changes and Modifications Facility change requests, nuclear safety evaluations and review and approval documentation for two facility changes were reviewed. The installation of a centrifuge ahead of the ultra-filter in the liquid waste cleanup system and for a grinder sludge collection recepcacle (proposed) verify completion of safety evaluations and management approvals as required by the conditions section of the license application. No items of noncompliance were identified in this area.
7.
Criticality Safety The inspector observed that SNM was stored and transported in compliance a.
with procedural requirements.
Scrzp SNM is handled in safe volume containers and material is placed in safe arrays and at designated locations. No deviations from approved safety criteria were identified.
b.
Criticality monitoring system calibration and test records verify performance of annual calibration and monthly source functional tests.
The inspector verified by e.'oservation and by review of internal audit c.
records that the following special criticality control criteria is maintained:
(1) Independent calculations verify UO2 Powder H/U ratio prior to blending.
(2) Water lines are baffled in the moderation control area.
(3) Areas are properly posted as required by license conditions.
(4) Plant audits for criticality control are performed on a quarterly schedule.
(5) Fire fighting agents are limited to nonhydrogenous material in the moderation control areas.
(6) Unsafe geometry containers in the pellet production area are marked and covered.
d.
Material control and accounting records show that the total quantity of SNM is substantially below the license limit of 20,000 kgs. of U-235.
No items of noncompliance or deviations were identified.
8.
Operations Review Operating procedures are available at work stations and nuclear criti-a.
cality limits and controls are posted. Discussions with operating 1770 120
. personnel indicate familiarity with safety limits, procedural require-ments and expected emergency responses.
b.
General housekeeping was excellent and no industrial safety hazards were apparent. No items of noncompliance or deviations were identified.
9.
Procedure Control Each functional component of the licensee's organization has the a.
responsibility for preparing, obtaining approvals, issuing, distribution control and revision of procedures. All components must comply with requirements of procedure PC-1300, Rev. 2, "CNFP Procedure Numbering System" and PC-1330, Rev. 1, " Preparation and Approval of CNFP Administrative 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 procedures as follows:
(1) AS-1124 - Health and Safety Procedures Temporary Procedure Revisions (2) QC-R508 - Document Control (Operative)
(3) QC-R509 - Document Control (Administrative)
(4) QC-1421 - Review and Approval of Drawings, Specifications and Procedurer (5) QC-1425 - Distribution of CNFP QC Documents (6) QC-1432 - Temporary Procedure Revisions (7) MA-1200 - Manufacturing Document Control (8) MA-1206 - Preparation and Approval; Manufacturing Procedures d.
Verification was made that the correct revision of procedures were in use and that document control records conform to administrative control requirements.
The inspector noted that the procedure format does not identify pre-e.
requisites, where applicable.
Procedure No. MA-308, " Sintering of UO2 pellets in the Walking Beam Furnace," for averple, does not. include safety interlock test requirements.
Interlock tests are required prior to startup. Tests are performed by maintenance and are covered 1770 121
f
. in a maintenance instruction.
Licensee representatives stated that the need for prerequisite information will be considered in the pro-cedure review program. This will be reviewed on future inspections.
f.
The inspector examined records that confirm that health and safety procedures had been reviewed and updated in the past year. No items of noncompliance were identified in this area.
10.
The licensee's response to IE Bulletin No. 79-19, " Packaging of Low Level Radioactive Waste for Transport and Burial" was timely and addressed each action item. The inspector performed an onsite review on October 18, 1979.
b.
All CNFP low-level radioactive waste is buried at the Chem-Nuclear Services, Barnwell site. Verification was made that current copies of DOT (49 CFR 100-199), NRC (10 CFR 71) Regulations and Chem-Nuclear license requirements were available.
Management approved operating procedures for shipping anu receiving of c.
radioactive material are presently available.
Training on DOT require-ments was given in April and June 1979. Additional training on all pertinent requirements is to be completed by the end of December. An audit of the transportation program was completed in September 1979.
d.
Several partially filled low-level waste packages were examined. All material was dry, shipping records verify that no liquid low-level radioactive waste was generated in the last 18 months.
No items of noncompliance or deviations were noted within the scope of e.
the inspection.
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