ML18081A902
| ML18081A902 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek  |
| Issue date: | 01/04/1980 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Martin T Public Service Enterprise Group |
| References | |
| NUDOCS 8001150226 | |
| Download: ML18081A902 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA 19406 JAN 4 7980 Public Service Electric and Gas Company ATTN:
Mr. F. W. Schneider Vice President - Producti-0n 80 Park Place Newark, New Jersey 07101 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.
Enclosures:
Sincerely, 11.U!,~~
j J.1./ Boyce H. Grier C/
1f' - Di rector
- 1.
IE Information Notice No. 80-01
- 2.
List of Recently Issued IE Information Notices CONTACT:
D. L. Caphton (215-337-5308)
- cc w/encl s:
F. P. Librizzi, General Manager - Electric Production E. N. Schwalje, Manager - Quality Assurance R. L. Mittl, General Manager - Licensing and Environment H. J. Midura, Manager - Salem Generating Station
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8001150 2;2G;
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FUEL HANDLING EVENTS ENCLOSURE 1 UNITED STATES
- NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 SSINS NO.: 6870 Accessions No.:
7910250523 IE Information Notice No. 80-01 Date:
January 4, 1980 Page 1 of 2 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 s~cond 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 evaluatio.n.
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.
IE Information Notice No. 80-01 Date:
January 4, 1980 Page 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 from the pool, havethe potential for producing extremely high dose rates or resulting in fuel damage.
lhis IE Information Notice is provided as an early notification of a possibly significant matter that is still under review by the NRC sta,ff. 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.
Information Notice No.
- 79-27 79-28 79-29 79-30 79-31 79-32 79-33 79-34 79-35 79-36 79-37 ENCLOSURE 2 IE Information Notice No. 80-01 Date:
January 4, 1980 Page l of 1 RECENTLY ISSUED IE INFORMATION NOTICES Subject Steam Generator Tube Ruptures at Two PWR Facilities Ove~loading of Structural Elements Due to Pipe Support
- Loads Loss of Nonsafety Related Reactor Coolant System In-Date Issued to Issued 11/16/79 All Power Reactor Faci-lities with an Operating License (OL) or Construc-tion Permit (CP) 11/16/79 All Power Reactor Faci-lities with an OL or CP 11/19/79 All Power Reactor Faci-lities with an OL or CP strumentation During Operation Reporting of Defects and
.* Noncompliances, 10 CFR Part 21 Use of Incorrect Amplified Response Spectra (ARS)
Separation of Electrical Cables for HPCI and ADS Improper Closure of Primary Containment Access Hatches Inadequate Design of Safety-Related Heat Exchangers Control of Maintenance and Essential Equipment Computer Code Defect in Stress Analysis of Piping Elbow Cracking in Low Presssure Turbine Discs 12/6/79 All Power Reactor Faci-liti es with an OL or CP 12/13/79 All Power Reactor Faci-lities with an OL or CP 12/21/79 All Power Reactor Faci-lities with an OL or CP 12/21/79 All Power Reactor Faci-lities with an OL ~r CP 12/31/79 All Power Reactor Faci-lities with an OL or CP 12/31/79 All Power Reactor Faci-lities with an OL or CP 12/31/79 All Power Reactor Faci-1 ities with an OL or CP 12/31/79 All Power Reactor Faci-lities with an OL or CP