ML19211C847
| ML19211C847 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 01/04/1980 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| References | |
| NUDOCS 8001150083 | |
| Download: ML19211C847 (1) | |
Text
7/C jaa a'coq'o, UNITED STATES
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g NUCLEAR REGULATORY COMMISSION
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1990 N. CALIFORNIA BOULEVARD
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U SUITE 202, WALNUT CetEEK PLAZA o
- ,,,e WALNUT CREEK. CALIFORNIA 94596 January 4,1980 Docket No. 50-312 Sacramento Municipal Utility District P. O. Box 15830 Sacramento, California 95813 Attention: Mr. John J. Mattimoe Assistant General Manager 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 recomend or request specific licensee actions.
If you have quest'sns regarding this matter, please contact the Director of tha appropriate NRC Regional Office.
Sincerely,
/ M m d d,+.____
R. H. Engelken Director
Enclosures:
1.
IE Information Notice No. 80-01 2.
List of Recently Issued IE Information Notices cc w/ enclosures:
R. J. Rodriguez, SMUD L. G. Schwieger, SMUD 1744 197 80 011 50 Og3
s UflITED STATES SSIfts fl0.:
6370 flUCLEAR REGULATORY COMf11SSI0fl Accessions flo.:
0FFICE OF IllSPECTI0fl Afl0 EflFORCEfiErlT 7910250523 WASHIfiGT0!!, D.C.
20555 January 4,1980 IE Information flotice flo. 80-01 FUEL HA!iDLIriG EVErlTS 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 inadvertent 1.,.a', sed high enough in the fuel pool to activate area radiation alarms.
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 lifting 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 assenbly was being raised until radiation alams sounded. The operators quickly lowered the assembly to clear the radiation alarms and ultimately placed it in a storage position. The licensee subsequently increased the administrative controls on fuel handling activities by assigning more oersonnel and limiting concurrent duties.
On December 17, 1979, the second fuel handling event occurred at Pilgrim fluclear Station when a new fuel assembly was dropped while it was being transferred to it.; 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 d2nsit' fuel racks and the latching device on the auxiliary hook failed to retain the fuel assembly lifting bail in the hook. The assenbly fell, striking the lif ting 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 perfcrmed and there was no apparent damage.
Sanples of the fuel pool water were analyzed and no change in activity levels was detected. The licensee has terminated the use of contract personnel and will use members of the plant operating staff for future fuel handling operations; a licensed fluclear Plant Operator (flP0) will be responsible for proper alignment of the crane before fuel moverent 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 198
a IE Inforration flotice flo. 80-01 January 4, 1980 Page 2 of 2 n'echanisms intended for use on new fuel, which are not interlocked to orevent withdrawal fran the pool, have the potential for producing extremely high dose rates or resulting in fuel damage.
This IE Inforration flotice is provided as an early notification of a possibly significant matter that is still under review by the f;RC staff.
It is expected that recipients will review the infornation for possible applicability to their facilities, flo specific action or response is requested at this time.
If flRC evaluations so indicate, further licensee actions may be requested or required.
flo written response to this IE Information ?!otice is required.
If you have any questions regarding this matter please contact the Director of the appropriate f!RC Regional Office.
1744 199
i IE Infomation flotice flo. 80-01 Encl osure January 4,1980 RECEilTLY ISSUED IE IflF0PFATION NOTICES Information Subject Date Issued To flotice 40.
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 Equipnent 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 tioncompliance,10 CFR Part 21.
holding OLs and cps and vendors insnected by LCVIP 79-29 Loss of flonSafety-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 200