ML19344E127
| ML19344E127 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 05/06/1980 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | William Jones OMAHA PUBLIC POWER DISTRICT |
| References | |
| NUDOCS 8008260689 | |
| Download: ML19344E127 (1) | |
Text
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CENTRAL FILES UNITED STATES POR:HQ
,pa %,,'o, NUCLEAR REGULATORY COMMISSION LPD,R f
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STATE May 6, t.to Dock t No. 50-285 Omaha Public Power District ATTN:
W. C. Jones, Division Manager -
Production Operations 1623 Harney Street Omaha, Nebraska 68102 Centlemen:
Enclosed is IE Bulletin No. 80-10 wlich requires action by you with regard to your power reactor facility with an operating license.
For facilities with a construction permit, no action is required; the Bulletin is providing information only.
Should you have questions regarding this Bulletin or the actions required of you, please contact this office.
Sincerely, r
- r'*)[
Karl V. Seyfrit j/,
Director
/
Enclosures:
1.
List of Recer.tly Issued IE Bulletins cc:
S. C. Stevens, Manager Fort Ci.1houn Station Post Office Box 98 Fort Calhoun, Nebraska 68102 8e08260G49
1 SSINS No.: 6820 UNITED STATES Accessions No.:
NUCLEAR REGULATORY COMMISSION 8002280677 0FFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Bulletin No. 80-10 Date: May 6, 1980 Page 1 of 2 CONTAMINATION OF NONRADI0 ACTIVE SYSTEM AND RESULTING POTENTIAL FOR UNMONITORED, UNCONTROLLED RELEASE OF RADIOACTIVITY TO EN!IRONMENT Description of Circumstance At the Brunswick Nuclear Facility, the auxiliary boiler was operated for an extended period of time with radioactively contaminated water in the boiler 2
at levels up to 2 x 10 mi.crocuries per milliliter. A tube leak in the firebox of the oil fired auxiliary boiler resulted in an unmonitored, uncon-trolled release of radioactivity to the environment.
The initial contaminating event was caused by the use of a temporary heating hose from the auxiliary boiler to a radioactive waste evaporator concentrate tank.
Upon cooling and condensation of the steam in the temporary hose, contam-inated water siphoned from the concentrate tank back to the auxiliary boiler.
Due to additional, continuing leaks in the heat exchanger of the waste evaporator (to which the auxiliary boiler also provides process steam), the licensee's efforts to decontaminate the auxiliary boiler feedwater had been ineffective.
Maintenance of proper boiler chemistry was difficult because blowdown options were severely restricted due to the contamination. As a result, a boiler tube failure caused on the order of 100 millicuries of radioactive material to be released off-site via the auxiliary boiler fire box and smokestack in the form of steam. This resulted in increased environmental levels of cesium and activa-tion products being detected as far as eight miles downwind from the site bounda ry.
Action to be Taken by Licensee with an Operating License 1.
Review your facility design and operation to identify systems that are considered as nonradioactive (or described as nonradioactive in the FSAR), but could possibly become radioactive through interfaces with radioactive systems, i.e.,
a nonradioactive system that could become contaminated due to leakage, valving errors or other operating conditions in radioactive systems.
In particular, special consideration should be given to the following systems:
auxiliary boiler system, demineralized water system, isolation condenser system, PWR secondary water clean-up system, instrument air system, and the sanitary waste system.
l 2.
Establish a routine sampling / analysis or monitoring program for these j
systems in order to promptly identify any contaminating events which could lead to unmonitored, uncontrolled liquid or gaseous releases to the environment, including releases to on-site leaching fields or retention ponds.
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IE Bulletin No. 80-10 May 6, 1980 RECENTLY ISSUED IE BULLETINS Bulletin Subject Date Issued Issued To No.
J 80-05 Vacuum Condition Resulting 3/10/80 All PWR povnr reactor In Damage To Chemical facilities holding Volume Control System Operating Licenees (OLs)
(CVCS) Holdup Tanks and to those with a Construction Permit (CP) 80-06 Engineered Safety Feature 3/13/80 All power reactor facilities (ESF) Reset Controls with an Operating License (OL)79-03A Longitudinal Weld Defects 4/4/80 All power reactor facilities In ASME SA-312 Type 304 with an Operating License Stainless Steel Pipe (OL) or Construction Permit (CP) 80-07 BWR Jet Pump Assembly 4/4/80 All GE BWR-3 and BWR-4 Failure facilities sith an Operating License (OL) 80-08 Examination of Containment 4/7/80 All power reactors with a Liner Penetration Welds Construction Permit and/or Operating License (OL) 80-09 Hydramotor Actuator 4/17/80 All power reactor Deficiencies operating facilities and holders of power reactor construction permits Enclosure i
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