IR 05000335/1979004
| ML17206A808 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/08/1979 |
| From: | Earnestine Clay, Todd G, Gerald Williams NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17206A806 | List: |
| References | |
| 50-335-79-04, 50-335-79-4, NUDOCS 7905240069 | |
| Download: ML17206A808 (5) | |
Text
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UNITEDSTATES NUCLEAR REGULATORYCOMMISSION
REGION II
101 MARIETTA STREET, N.W.
ATLANTA,GEORGIA 30303 MAR 15 1979 Report No.:
50-335/79-04 Licensee:
Florida Power and Light Company Advanced Systems and Technology P. 0.
Box 529100 Miami, Florida 33152 Facility Name:
St. Lucie
Docket No.:
50-335 License Nos.:
DPR-67 Safeguards Group No.:
IV Inspection at St.
cie County, Florida Inspectors:
G. A.
od E. L.
'\\
Approved by:
G. H. Williams, Section Chief, MCUS D
e i ed
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ate Signed ate Signed SUMMARY Inspection on February 7-9, 1979 This routine unannounced inspection involved 38 inspector-hours onsite in the areas of facility organization and operation, measurement and controls, ship-ping and receiving, storage and internal control, inventory, records and reports and management of the material control system.
Results Of the seven areas inspected, no apparent items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Em lo ees
- C. M. Wethy, Plant Manager
+J.
H. Barrow, Operations Superintendent
+A, W. Bailey, QA Operations Supervisor-G.
M. Vaux, Quality Control Supervisor-J.
E. Bowers, Maintenance Superintendent
"R. R. Jennings, Technical Supervisor
>R. K. Ryall, Reactor Engineer Supervisor
- N. G. Roos, Quality Control Engineer
- C. A. Pell, Reactor Engineer J.
P. I,ewis, Senior Plant Technician-Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on February 9,
1979 with those persons indicated in Paragraph 1 above.
3.
Licensee Action on Previous Ins ection Findin s Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Facilit Or anization and eration The licensee has prepared and is maintaining and utilizing, on a current basis, adequate procedures covering the nuclear material control and accounting system for the nuclear power plant.
Written statements of responsibility and authority have been established for those positions having responsibility for special nuclear material (SNM) receiving, shipping, inventory, storage, transfers, burnup related measurements, and records and reports.
The control functions of the program are organizationally separate from the operational functions with seperation such that independence of action is assured.
The licensee has confined possession and use of SNM to the location and purpose authorized by license and has established and described item control areas in such a manner to assure that physical and administra-tive control of SNM is maintaine "
6.
Measurement and Controls Data for computing burnup for each fuel assembly in Unit 1 reactor core is routinely collected on site and transmitted to the corporate office in Miami, Florida.
The corporate office performs burnup calculation using a computer program that was furnished by Combustion Engineering and later changed by Florida Power and Light Company (APL). All input to this computer program is taken from a daily Nuclear Power Operating Data log.
This daily operations data is sent to the Miami office for a bimonthly update of the core isotopic depletion record.
This daily operating data is also used by the Miami office of FPL to prepare the semiannual Material Status Reports (MSR's).
All MSR's are sent to the St. Lucie site for review prior to being dispatched.
Since the Unit 1 reactor has completed Cycle 1 of operations and is in the second report period of Cycle 2, the inspector used a sampling of Cycle 1 operating data to predict the reported burnup during the first report period of Cycle 2.
For the operating period of June 1 to September 30, 1978, the licensee reported a total burnup for Unit 1 core of 224,451 grams U-235.
The difference in the licensee's reported value and the Region II calculated value is considered reasonable.
7.
Shi in and Receivin Review of shipment documentation retained on site revealed that actual receipts of nuclear fuel at the reactor site are promptly confirmed. by verification of component serial numbers'he licensee reports to the Central Accounting Office at the completion of the shipment all pertinent information relative to the fuel.
Incoming material transaction docu-ments (NRC 741's)
are receipted within ten days and a complete record is maintained of the location, idenfity and SNM content of each fuel assembly received and stored.
8.
Stora e and Internal Control The licensee utilizes and internal transfer form to document the move-ment of fuel assemblies at the site.
A transfer form is prepared for each assembly as it is moved from the shipping container to storage.
Subsequent moves are similarly documented and up-dated on the fuel status record and location mapping.
For core loading an alternate documenting record of fuel movement is utilized.
A step by step loading procedure has been prepared documenting final core location of each assembly including confirming initials of an assigned employe.
Tnventornr The special nuclear material inventory of Unit 1 consisted of 12 fuel assemblies in the new fuel storage racks, 217 fuel assemblies loaded in the reactor vessel, 60 irradiated fuel assemblies in the spent fuel pool, plutonium-beryllium neutron sources and several in-core fission detectors, In each case the licensee is in compliance with license possession limits.
The licensee maintains schematics of the new and spent fuel storage'reas and the reactor core.
The new fuel schematic was compared with the actual location of each fuel assembly.
The spent fuel schematic was compared by pool location and item piece count.
The reactor core schematic was compared to Cycle 2 fuel status records and material transfers.
No discrepancies were identified and all 289 fuel assemblies were accounted for.
Sources and fission detectors were installed in the reactor vessel and were not amenable to physical inventory.
10.
Records and Re orts Audit= of NRC-741's (material transaction reports)
issued during the period February 20, 1976 through January 30, 1979 revealed no signi-ficant errors.
Receipts acknowledged within ten days and 741's documenting shipments were dispatched the day the material was shipped.
Processing of the 741's was as described in plant procedures.
NRC-742's (material status reports)
issued during the period under review were examined and revealed no significant errors.
ll.
Mana ement of Material Control S stem Licensee management conducts an annual review of their nuclear material control and accounting program.
Evidence of the results of this review is based on appropriate procedure up-dates and implementation of an improved measurement and control data base.