ML20155H032
| ML20155H032 | |
| Person / Time | |
|---|---|
| Site: | 07001113 |
| Issue date: | 02/17/1986 |
| From: | Winslow T GENERAL ELECTRIC CO. |
| To: | Kahle J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20155H020 | List: |
| References | |
| FOIA-86-169 NUDOCS 8605120083 | |
| Download: ML20155H032 (3) | |
Text
GENERAL $ ELECTRIC NUCLEAR FUEL MANUFACTURING DEPARTMENT eENonat stscraic courAny - e. o. som reo - w Luimeroes nonin canotana pe4or February 17, 1986 c
Mr. J. B. Kahle Q
U. S. Nuclear Regulatory Commission, RII m'
101 Marietta Street, N.W. - Suite 2900 Atlanta, Georgia 30323 3
co
Dear Mr. Kahle:
.c.
References:
(1) HRC License SNM-1097, Docket 70-1113 (2) Letter, TP Winslow to JN Grace, 1/27/86
Subject:
INTERNAL INVESTIGATION COMPLETION On January 22, 1986, General Electric Company Nuclear Fuel &
Components Manufacturing (NFECM) experienced an elevated stack discharge and a minor process upset which did not require formal reporting pursuant to federal regulations or license conditions.
However, as a matter of courtesy, the NRC Region II was notified.
(See Reference 2.)
The discharge was identified by NFECM as Class II and investigated pursuant to internal procedures.
The investigation was completed on February 14, 1986.
As requested, please notify Messrs. Ken Barr and Phil Stoddard (who performed an inspection of the subject incident on February 3-5, 1986) that the investigation report is on file at NFECM_.
If you have any questions regarding this matter, please contact me.
Very truly yours, GENERAL ELECTRIC COMPANY h-s T.
Preston Winslow, Manager Licensing & Nuclear Materials Management M/C J26 TPW:bsd Ps
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Air flow through openings in these containment devices
(
is measured monthly, at a minimum, to assure adequate
)
system performance as necessary for protection of personnel.
When air flow through any point of the opening approaches the minimum requirement of 80 LFPM, action is instituted to correct the problem.
Additionally, there are differential pressure indicators across exhaust system filters to assure system performance.
When a differential pressure is observed to have reached four inches of water, the effectiveness of the filter is investigated.
Notwithstanding the monthly checks of differential pressure, the filters are changed when they are unable to allow the airflow necessary for the system which they are designed to serve.
3.2.2.3 Effluent Air Duct Design Effluent air ducts and air flow velocities are designed to minimize radioactive dust accumulations.
3.2.2.4 Exhaust System Exhaust systems in potentially contaminated airborne effluents are equipped with filter media which are selected to maintain its integrity when subjected to chemicals, solvents and abnormal operations of the processes.
These filters are at least 99.97% efficient for removal of 0.3 micron particles.
All HEPA filters (both primary and secondary) in the exhaust system are equipped with a device for measuring differential pressure.
LICENSE SNM-1097 DATE 5/14'/84 PAGE DOCKET 70-1113 REVISION 3
I-3.9
Filter effectiveness is investigated when the pressure differential across the filter exceeds four inches of water.
A filter is replaced following evidence of the inability of the filt:
or the exhaunt system to perform its function 9roperly.
In no case will filters oe operated at A P values which exceed the manufacturer's ratings for the filter.
Water scrubbers or other appropriate devices are provided where necessary to treat effluents before filtration.
Such scrubbers are installed so that effectiveness of filters is maintained.
3.2.2.5 Air Recirculation Room air may be recirculated within the uranium processing areas after being filtered.
i 3.2.3 Instrumentation i
3.2.3.1 General Appropriate radiation detection instruments are available to ensure adequate radiation surveillance can be accomplished.
Selection criteria of portable and laboratory counting equipment is based on the types of t
radiations detected, maintenance requirements, ruggedness, interchangeability-and upper and lower limits of detection capabilities.
The radiation safety function annually reviews the appropriateness of the types of instruments being used for each monitoring function.
[
k LICENSE SNM-1097 DATE 5/14'/84 PAGE DOCKET 70-1113 REVISION 3
I-3.10 l
_