ML19257C519
| ML19257C519 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 01/04/1980 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Nichols T SOUTH CAROLINA ELECTRIC & GAS CO. |
| References | |
| NUDOCS 8001290297 | |
| Download: ML19257C519 (1) | |
Text
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'o, UNITED f,TATES 8
NUCLEAR REGULATORY COMMISSl" 3
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$4
)aE REGION 11 o,, Yp' 6 f~
- 101 MARIETTA ST., N.W., S'JtTE 3100 o
ATLANTA, G EORGI A 30303 JAN 4 1980 In Reply Refer To:
Rll:JP0 60-395
)
Souta Carolina Electric and Gas Company Attn:
T. C. Nichc1s, Jr., Vice President Power Production and System Operations Post Office Box 764 Columbia, South Carolina 29218 Gentlemen:
This Infor. nation Notice is,rovided as an early notification of a possible 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 recommend or request specific licensee A
actions.
If you have questions regarding this matter, please contact the Director of the appropriate hTC Regional Office.
Sincerely, 1
%. _-s.w
[
James P. O'Reilly Director
Enclosures:
1.
IE Information Notice No. 80-01 2.
List of Recently Issued IE Information Notices 1841 016 8001290 2N 0
UNITED STATES SSINS NO.:
6870 NUCLEAR REGULATORY COMMISSION Accessions No.:
OFFICE OF INSrECTION AND ENFORCEMENT 7910250523 k'ASHINGTON, D.C.
20555 c,
January 4, 1980 b :du 1: du H m
IE Information Notice No. 80-01 FUEL HANDLING EVENTS Description of Circumstances:
Two recent fuel handling events at the Pilgrim Nuclear Station have been reported to the NFO 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.
Af ter 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 tF4t the spent fuel assembly was being raised until radiation alarms sounded. lie operators quickly lowered the assembly to clear the radiation alarms and ultimately placed it in a stor age 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 Cperator (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 potenticl for raising a spent fuel element with the new fuel elevator may clso exist at some pressurized water reactors. Movement of spent fuel by cranes or 1841 017
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 prevent withdrawal from the pool, heve 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 possiblo 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.his IE Information Notice is required.
If you have any questions regarding t- :s matter please contact the Director of the appropriate NRC Regional Office.
1841 018
IE Information Notice No. 80-01 Enclosure January 4,1980 RECENTLY ISSUED IE IFIORMATION NOTICES Information Subject Date Issued To Notice No.
Issued 30-01 Fuel Handling Events 1/4/80 All power reactor OLs and cps 79-37 Cracking in Low Pressure 12/28/79 All power reactor OLs Turbine Discs and cps 79-36 Computer 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 12/21/70 All power reactor facilities Cables for HPCI and ADS holding OLs and cps 79-32 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 NonSafety-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 I.pe Support with an OL or CP Loads 79-27 Steam Generator Tube 11/16/79 All power reattor facilities Ruptures At Two PWR holding OLs and cps Facilities79-12A Attempted Damage To New 11/9/79 All Fuel Facilities, Fuel Assemblies research reactors, and 4