ML19257B091
| ML19257B091 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 01/04/1980 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Groce R YANKEE ATOMIC ELECTRIC CO. |
| References | |
| NUDOCS 8001150234 | |
| Download: ML19257B091 (1) | |
Text
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
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REGION I 0
631 PARK AVENUE 9*****
,&g 44 KING OF PRUSSIA, PENNSYLVANIA 19406 Docket No. 50-29 JAN 4 1980 Yankee Atomic Electric Company ATTN:
Mr. Robert H. Groce Licensing Engineer 20 Turnpike Road Westborough, Massachusetts 01581 Gentlemen:
This Information Notice is provided as an early notification of a possibly significant matter.
It is expected that recipients will review the infor-mation 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 actions.
If you have questions regarding this matter, please contact this office.
Sincerely, J
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(,/BoyceH.Grier Director
Enclosures:
1.
IE Information Notice No. 80-01 2.
List of Recently Issued IE Information Notices CCNTACT:
D. L. Caphton (215-337-5308) cc w/encls:
H. Autio, Plant Superintendent L. E. Minnick, President 1749 081 80 0115e 2B4
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ENCLOSURE 1 g
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 assambly 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 trans-ferred 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.
1749 082 IE Information Notice No. 80-01 Date:
January 4, 1980 Fage 2 of 2 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 mechanisms intended for use on new fuel, which are not interlocked to prevent withdrawal froni 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 ap-propriate NRC Regional Office.
1749 083
ENCLOSURE 2 IE Information Notice No. 80-01 Date:
January 4, 1980 Page 1 of 1 RECENTLY ISSUED IE INFORMATION NOTICES Information Subject Date Issued to Notice No.
Issued 79-27 Steam Generator Tube 11/16/79 All Power Reactor Faci-Ruptures at Two PWR lities with an Operating Facilities License (OL) or Construc-tion Permit (CP) 79-28 Overloading of Structural 11/16/79 All Power Reactor Faci-Elements Due to Pipe Support lities with an OL or CP Loads 79-29 Loss of Nonsafety Related 11/19/79 A!1 Power Reactor Faci-Reactor Coolant System In-lities with an OL or CP strumentation During Operation 79-30 Reporting of Defects and 12/6/79 All Power Reactor Faci-Nancompliances, 10 CFR lities with an OL Part 21 or CP 79-31 Use of Incorrect Amplified 12/13/79 All Power Reactor Faci-Response Spectra (ARS) lities with an OL or CP 79-32 Separation of Electrical 12/21/79 All Power deactor Faci-Cables for HPCI and ADS lities with an OL or CP 79-33 Improper Closure of Primary 12/21/79 All Power Reactor Faci-Containment Access Hatches lities with an OL or CP 79-34 Inadequate Design of Safety-12/31/79 All Power Reactor Faci-Related Heat Exchangers lities with an OL or CP 79-35 Control of Maintenance 12/31/79 All Power Reactor Faci-and Essential Equipment lities with an OL or CP 79-36 Computer Code Defect in 12/31/79 All Power Reactor Faci-Stress Analysis of Piping lities with an OL or CP Elbow 79-37 Cracking in Low Presssure 12/31/79 All Power Reactor Faci-Turbine Discs lities with an OL or CP 1749 084