ML19260D222
| ML19260D222 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 01/04/1980 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Millen C PUBLIC SERVICE CO. OF COLORADO |
| References | |
| NUDOCS 8002080130 | |
| Download: ML19260D222 (1) | |
Text
CENTRAL "ILES PDR:HQ UNITED STATES LPDR
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NUCLEAR REGULATORY COMMISSION TIC J
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. J' Januarf 4, 1980 Docket No. 50-267
?ublic Serrice Company of Colorado AT"'N :
Mr. C. K. Millen Senior Vice President
?. O. Box 840 Denver, Colorado 80201 Gentle =en:
This II Infor=ation Notice is provided as an early notification of a possibly significan: =atter.
It is expected that recipients will reviev the infor=ation for possible applicabili:y to their facilities.
No specific action is requested at this ti=e.
If further NRC evaluations so indicate, an IE Circular or Bulletin vill be issued to recommend or request specific licensee ac: ions.
If you have questions regarding this =atter, please contact the Director of the appropriate NRC Regional Office.
Sincerely,
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KarlI.Seyfrit/f Director
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Inclosures:
1.
II Infor=ation Notice No. 80-01 2.
List of Recently Issued II Infor=ation Notices cc:
D. W. Ware = bourg, Nuclear Production Manager For: St. Vrain Nuclear Station P. O. Box 368 Platteville, Colorado 80651 L. Brey, Manager, Quality Assurance 1943 126 8002080 130
UNITED STATES SSINS NO.:
6870 NUCLEAR REGULATORY COMMISSION Accessions No.:
OFFICE OF INSPECTION AND ENFORCEMENT 7910250523 WASHINGTON, D. C.
20555 IE Information Notice No. 80-01 Date:
January 4, 1980 Page 1 of 2 FUEL HANDLING EVENTS Description of Circumstances:
Two recent fuel handling events at the Pilgrim Nuclear Station have been reported to the NRC 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 inadvertently raised high enough in the fuel pool to activate area radiation alarms.
The reactor building overhead crane was being used to move 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 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.
The 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 Nuclear 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 top 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.
Samples 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 Nuclear Plant Operator (NPO) will be responsible for proper alignment of the crane before fuel movement and a Reactor Engineer will supervise 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.
Movement of spent fuel by cranes or i943 127
IE Information Notice No. 80-01 Date:
January 4, 1980 Page 2 of 2 mechanisms intended for use on new fuel, which are not interlocked to prevent withdrawal from the pool, have the potential for producing extremely high dose rates or resulting in fuel damage.
This IE Information Notice is provided as an early notification of a possibly significant matter 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.
1943 128
IE Information Notice No. 80-01 January 4, 1980 LISTING OF RECENTLY ISSUED IE INFORMATION NOTICES Information Subj ect Date Issued To Notice No.
Issued 79-32 Separation of Electrical 12/21/79 All power reactor Cables for HPCI and ADS facilities holding Operating Licenses (OL) and Construction Permits (cps) 79-33 Improper Closure of 12/21/79 All power reactor Primary Containment facilities holding Access Hatches Operating Licenses (OL) and Construction Permits (cps) 79-34 Inadequate Design of 12/27/79 All holders of of Safety-Related Heat power reactor Exchangers Operating Licenses (OLs) and Con-struction Permits (cps) 79-35 Control of Maintenance 12/31/79 All power reactor facilities and Essential Equipment with an Operating Licenses (OLs) and Construction Permits (cps) 79-36 Computer Code Defect 12/31/79 All holders of power reactor Stress Analysis of Piping Operating Licenses (OLs)
Elbow and Construction Permits (cps) 79-37 Cracking in Low Pressure 12/28/79 All holders of power reactor Turbine Discs Operating Licenses (0Ls) and Construction Permits (cps)
Enclosure 1943 129