IR 05000006/1987003
| ML20236N491 | |
| Person / Time | |
|---|---|
| Site: | Battelle Memorial Institute, 07000008 |
| Issue date: | 11/09/1987 |
| From: | France G, Greger L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20236N459 | List: |
| References | |
| 50-006-87-03, 50-6-87-3, 70-0008-87-03, 70-8-87-3, NUDOCS 8711160188 | |
| Download: ML20236N491 (6) | |
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U. S. NUCLEAR REGULATORY COMMISSION
REGION III
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Reports No. 70-008/87003(DRSS);50-006/87003(DRSS)
Docket Nos. 07000008; 05000006 Licenses No. SNM-7; No. R 4
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Licensee Name:
Battelle Columbus Division Inspection At: West Jefferson Facilities Inspection Conducted: October 19-23, 1987 Inspector:
George M. France, III
//- 9-87
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Date Approved By:
L. R.
reger, Chief
//- 9-87 Facilities Radiation Protection Date
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Section Inspection _ Summary No. 50-006/B70'OMDKST)T-~~~~Qeports No.
Inspection on October 19-23, 1987 70-008/87003(DRSS);
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Freas Inspected:
Routine unannounced health and safety inspection, including: nuclear criticality safety; radiation protection, including exposure contral, surveys, and reports; spent fuel handling, including transportation activities; management organization and control; and a review of survey results conducted around the retired Battelle Research Reactor.
Results:
The licensee was found to be in compliance with NRC requirements within-the areas examined.
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8711160188 871110 PDR ADOCK 05000006 G
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1.
Persons Contacted T. Emswiler, Transportation Specialist (Part Time Employee)
l E. Fromm, Supervisor, Quality Assurance
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- G. Kirsch,' Supervisor, Operational Health Physics l
A. Lawrence, Supervisor, Hot Cell Operations
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- D. McKown, Radiological Safety Officer (Part Time Employee)
A. Parscns, Maintenance Operations
- V Pasupathi, Manager, Nuclear Technology D. Stewart, Research Technician L.-Stickel, Master Technician E. Swindall, Master Technician P. Tomlin, Master Technician
- H. Toy, Manager, BCL Nuclear Service Group
Interviews were also conducted with other members of the licensee's i
staff. Discussions on the preparation and shipment of spent fuel bundles were held with representatives from DOE, EG&G Idaho', Inc.,
Transnulcear, Inc., and Tristate Shipping.
- Denotes those present at the exit meeting on October 23, 1987.
2.
General This inspectioil of onsite licensee activities, which began at 1:30 p.m.
on October 19, 1987, was conducted to examine activities at the West Jefferson site under Materials License No. SNM-7. During the course of this inspection, the licensee was observed preparing three spent fuel bundles for shipment to DOE's Idaho Operations site.
Representatives
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from EG&G Idaho, Inc., DOE's Idaho Operations, DOE's Chicago, Illinois and j
Washington, DC offices, Transnuclear, and Tristate Shipping were also J
observers of these preparations.
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f 3.
Management Organization and Controls
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The inspector reviewed the licensee's management organization and controls i
for radiation protection and operation, including changes in the
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organizational structure.
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Organization j
I There were no new assignments of personnel to the licensee's radiation protection program. The licensee continues to use the consultant services of retired workers in order to support radiological health and safety, instrument maintenance, transportation, and/or environmental sampling programs.
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Procedures l
Ir preparing for the transport of loose rods and spent fuel l
t assemblies from Battelle Columbus Division (BCD) to DOE's Idaho Operations, the licensee followed a comprehensive written procedure.
i (BCD Spent Fuel Transfer Statement of Work / Field Work Package
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Proposal / Agreement No. 6MC4).
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The inspector noted that essential elements of the task were performed and sign-offs were recorded in compliance with Agreement l
No. 6MC4. BCD's QA Supervisor observed the packaging of fuel bundles and verified the appropriate sign-off signatures as each
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task was completed.
No violations or deviations were identified.
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4.
Radiation Protection
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The inspector reviewed the licensee's internal and external exposure control programs including the required records, reports, and notifications. The inspector also observed the licensee's health
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physics work routines during preparation of the spent fuel shipments.
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a.
Internal Exposure Control Whole body counts for mixed fission products, and isotopes of
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cesium, cobalt, plutonium and uranium were scheduled for the week of October 25, 1987. Bio-assay records for the third quarter 1987 disclosed that the 40 MPC-hour intake limit for uranium and plutonium had not been exceeded.
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External Exposure Exposure levels to any one employee was less than 300 mrem; this may increase due to the recent handling of spent fuel. Throughout
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this inspection, health physics technicians monitored workers
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perfreming the transfer of fuel bundles to a shipping cask. The
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licensee noted that no exposure involving hot particles had been
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identified in recent memory.
This discussion was expended during the exit meeting.
c.
Surveys _and_ Con _tamination Control
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Records of surveys conducted for the May through September 1987 operating period disclosed that there have been no significant
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contamination or exposure problems.
Dry mopping with chemically treated yellow-wipes / wet mopping of high count locations reduced the spread of contamination.
While performing fuel transfer (to cask) maneuvers, the licensee provided protective covering (anti "C" clothing) for workers and/or observers. Additionally, paper covering was used around the
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I perimeter of'the spent fuel pool ~.
Because of the licensee's precautions, there were no incidents of contamination' detected by the monitor among personnel exiting the hot cell.
d.
Instruments The licensee located neutron criticality detectors and ganna I
radiation monitors in accordance with 10 CFR 70.24 while monitoring
fuel transfer activities.
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' Airborne Releases No'MPC-hour assignment exceeding regulatory requirements was noted.
No violations or deviations were identified in this program area.
5.
Operations Review The inspector observed the licensee's preparation, cask off-loading operation, and transfer of three bundles to the TN-8 shipping cask. The
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three spent fuel assemblies represent the -last remaining bundles stored at-BCD.
During this inspection the licensee was engaged in a project that required the transfer of the remaining spent fuel assemblies and loose rods and rod sections from Battelle Columbus Division (BCD) in Ohio to the DOE / Idaho National Engineering Laboratory (INTEL) for interim storage.
The project also included the design of a fuel basket to hold loose encapsulated rods and rod sections. Out of a total of 131 loose
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rods, it was noted that 29 loose rods contained NRC-owned material obtained from H. B. Robinson, Oconee, and Maine Yankee reactor programs.
EG&G Idaho arranged for the delivery of the TN-8 shipping cask to BCD, wFile Transnuclear, Inc. provided the onsite technical assistance required for cask loading. By the end of the onsite inspection (October 23,1987)
the TN-8 cask was loaded and ready for transport by Tristate Shipping.
No problems were noted during the period of observation.
The inspector reviewed the requirements of the Reactor License and the
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licensee's records for the May through September 1987 surveillance period.
In accordance with Amendment 13 to Reactor License No. R-4, the licensee is required to monitor radioactivity in the water released from a basement sump to the storm sewer, conduct periodic radiation surveys, and maintain barriers preventing access to the retired reactor.
The' inspector concluded that all the above requirements (technical specifications) of Amendment 13, License No. R-4 were satisfactorily met.
No violations or deviations were identified.
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Maintenance Surveillance A review of the licensee's general maintenance operations was conducted to determine specifically whether systems pertinent to cask handling are properly maintained.
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p A review of. maintenance records disclosed that the Ohio Crane and Hoist.
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' Company conducted a quarterly maintenance inspection on the 50-ton crane.
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The licensee performed specific operational checks on the 50-ton crane such asihooked and' unhooked,-up and down, and left and right movement.
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addition,'all cranes, lif_ ting chains and cable slings were checked for i
operability. No problems'were observed with crane ~and hoist equipment l-during fuel transfer operations.
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l No violations'or' deviations.were identified.
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7.
Training I
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-All. training observed during this. inspection supported fuel transfer cask'.
loadirg requirements. 'A'Transnuclear, Inc. representative provided
' technical assistance and training.for crane hookup and placement, and
. ca s.k loading activities. The. inspector observed a classroom training i
session that introduced four BCD workers to the care, and_ handling of operating:' equipment:for the TN-8 cask.. Additionally, the Transnuclear'
representative provided-technical assistance, while BCD workers
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off-loaded the TN-8 cask.from the carrier platform into the fuel storage
pool.
The licensee noted that eight workers completed annual qualification
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requirements:to certify personnel to perform overhead crane operations on the following equipmenti
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Hot lab b'idge crane /10-ton auxiliary crane r
Pool bridge 1-ton monorail crane jl Truck dock cranes-
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The eight workers :(after qualifying for crane operations) are paired into two-man teams (operator and crane rigger). Under this program each team
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must demonstrate ability in performing specific crane maneuvers using
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the 50-ton crane.
No problems were reported.
No violations or deviations were identified.
8.
Criticality Safety The inspector reviewed the licensee's documentation ? facility changes requiring criticality considerations, including determination of whether
'the licensee has positive management controls to ensure that facility operations are conducted within nuclear criticality safety limits.
The inspector reviewed the criticality concerns relative to the spent H
fuel shipment scheduled for DOE Idaho from BCD. The configuration of the TN-8 shipping cask was acceptable for the three shipping baskets in storage at BCD. The BCD design for loose rods and rod sections required a basket wfth the same envelope dimensions as a standard 15 x 15.
Westinghouse PWR fuel assembly. The final fuel information and shipping configuration to support criticality analysis was performed by EG&G Idaho.
No problems were noted.
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No violations or deviations were identified.
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'9.! 1r_ansportation and Radioactive Waste' Generation
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The inspector. reviewed the.. licensee's transportation activities to '
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determine.whether the'licens'ee is maintaining an adequate program to
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' assure. radiological safety in the receipt,. packaging, and delivery of:
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LMcensed radioactive materials.
No discrepancies were found in the licensee'sLshipping records;
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The licensee noted that no failed fuel was present among the 131 loose
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rods encapsulated.for. shipment to DOE Idaho Operations., The encapsulated rods and rodfsections were placed in a basket' designed similar.tola Westinghouse PWR. fuel. assembly.
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.No violations.or deviations were. identified.
1 10.-. Exit Meeting
'The inspector met with li~censee -representatives (denote'd in Section 1)' at.
, the conclusio'n of the onsite inspection on October 23, 1987. The u
inspector summarized the scope and findings of the. inspection.
In response to:certain items discussed by the inspector, the licensee:
Acknowledged that ;the.information notice od hot particles had been
- discussed. However, no problems recent memory had involved hot
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m During the course of the inspection and the exit meeting, the licensee
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.did not identify any. documents or inspector comments and references to
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- specific processes as proprietary.
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