ML19211C845
| ML19211C845 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 01/04/1980 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Papay L SOUTHERN CALIFORNIA EDISON CO. |
| References | |
| NUDOCS 8001150080 | |
| Download: ML19211C845 (1) | |
Text
DC pa arog 4,
UNITED STATES 8 '}* 3., c ' j NUCLEAR REGULATORY COMMISSION 3
.C REGION V 0, '-
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1990 N. CALIFORNIA BOULEVARD
,e" SUITE 202, WALNUT CREEK PLAZA
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WALNUT CREEK CALIFOHNIA 94596 January 4,1980 Docket Nos. 50-206, 50-361, 50-362 Southern California Edison Company P. O. Box 800 2244 Walnut Grove Avenue Rosemead, California 91770 Attention: Dr. L. T. Papay, Vice President Advanced Engineering Gentlemen:
This Information Notice is provided as an early notification of a possibly significant matter.
It is expected that recipients will review the information for possible applicability to their facilities.
No specific action or response is requested at this time.
If further NRC evaluations so indicate, an IE Circular or Bulletin will be issued to reconmend or request specific licensee actions.
If you have questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
Sincerely,
,~,a GL---
R. H. Engelken Director
Enclosures:
1.
IE Information Notice No. 80-01 2.
List of Recently Issued IE Information Notices cc w/ enclosures:
J. M. Curran, SCE R. Dietch, SCE 1744 204 800115005'O
UtilTED STATES SSI!!S f!O.:
6370 fiUCLEAR REGULATORY COMfilSSI0il Accessions flo.:
0FFICE OF If4SPECTI0tl Att0 EtlFORCEMEllT 7910250523 WASHIllGT0tl, D.C.
20555 January 4,1980 IE Information flotice flo. 80-01 FUEL HA!!DLIflG EVEilTS Description of Circumstances:
Two recent fuel handling events at the Pilgrim fluclear Station have been reported to the flRC wherein there were no interlocks to control or limit the movement of nuclear fuel in the reactor building.
The first event occurred on December 11, 1979 when a spent fuel assembly was inadver'ently raised high enough in the fuel pool to activate area radiation alarns. The reactor building overhead crane was being used to nove new fuel from the inspection rig to the high density storage racks in the fuel pool.
After the release of a new fuel element, the lif ting hook became caught between the lifting bail and the assembly channel of a spent fuel assembly. The operating personnel were unaware of the fact that the spent fuel assembly was being raised until radiation alarms sounded. The operators quickly lowered the assembly to clear the radiation alarms and ultimately placed it in a storage position. Tha licensee subsequently increased the administrative controls on fuel handling activities by assigning more personnel and limiting concurrent duties.
On December 17, 1979, the second fuel handling event occurred at Pilgrim iluclear Station when a new fuel assembly was dropped while it was being transferred to its storage location in the spent fuel pool. The assembly was being transported with the reactor building overhead crane when it struck the too edge of the high density fuel racks and the latching device on the auxiliary hook failed to retain the fuel assembly lifting bail in the hook. The assembly fell, striking the lifting bails on four spent fuel elements, then coming to rest on the top of the fuel racks.
It has since been moved to a spent fuel preparation stand; an inspection of the assembly will be made at the site and then it will be returned to the supplier for further evaluation. A visual inspection of the four spent assemblies was performed and there was no apparent damage.
Sanples of the fuel pool water wer e analyzed and no change in activity levels was detected. The licensee has terninated the use of contract personnel and will use members of the plant operating staff for future fuel handling operations; a licensed fluclear Plant Operator ('lPO) will be responsible for proper alignment of the crane before fuel movement and a Reactor Engineer will suoervise all fuel movement. All fuel movement will be limited to the minimum speed of the crane.
The events described above occurred at a boiling water reactor, however, the potential for raising a spent fuel element with the new fuel elevator may also exist at some pressurized water reactors.
flovement of spent fuel by cranes or 1744 205
IE Information Notice No. 80-01 January 4, 1980 Page 2 of 2 mechanisms intended for use on new fuel, which are not interlocked to orevent withdrawal from the pool, have the potential for producing extrenely hich dose rates or resulting in fuel damage.
This IE Information Notice is provided as an early notification of a possibly significant ratter that is still under review by the NRC staff.
It is expected that recipients will review the information for possible applicability to their facilities.
No specific action or response is requested at this time.
If NRC evaluations so indicate, further licensee actions may be requested or required.
No written response to this IE Information Notice is required.
If you have any questions regarding this matter please contact the Director of the appropriate NRC Regional Office.
1744 20u6
IE Information flotice No. 80-01 Enclosure January 4,1980 RECENTLY ISSUED IE INF0PPATION NOTICES Infornation Subject Date Issued To Notice No.
Issued 79-37 Cracking in Low Pressure 12/28/79 All power reactor OLs Turbine Discs and cps 79-36 Conputer Code Defect in 12/31/79 All power reactor OLs Stress Analysis of Piping and cps Elbow 79-35 Control of Maintenance 12/31/79 All power reactor facilities and Essential Equipment with an OL or CP 79-34 Inadequate Design of 12/27/79 All holders of power reactor Safety-Related Heat OLs and cps Exchangers 79-33 Improper Closure of 12/21/79 All power reactor facilities Primary Containment holding OLs and cps Access Hatches 79-32 Separation of Electrical 12/21/79 All power reactor facilities Cables for HPCI and ADS holding OLs and cps 79-31 Use of Incorrect Amplified 12/13/79 All holders of power reactor Response Spectra (ARS)
OLs and cps 79-30 Reporting of Defects and 12/6/79 All power reactor facilities Noncompliance, 10 CFR Part 21.
holding OLs and cps and vendors inspected by LCVIP 79-29 Loss of MonSafety-Related 11/16/79 All power reactor facilities Reactor Coolant System holding OLs or cps Instrumentation During Operation 79-28 Overloading of Structural 11/16/79 All power reactor facilities Elements Due to Pipe Support with an OL or CP Loads 79-27 Steam Generator Tube 11/16/79 All oower reactor facilities Ruptures At Two PWR holding OLs and cps Facilities79-12A Attempted Damage To "ew 11/9/79 All Fuel Facilities, Fuel Assemblies research reactors, and power reactors with an OL or CP 1744 207