ML17284A495

Revised Page 6 to Semiannual Effluent Rept,Jan-June 1988.

ML17284A495
Person / Time
Site:	Columbia
Issue date:	06/30/1988
From:	WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17284A494	List: ML17284A493 ML17284A495
References
NUDOCS 8809080010
Download: ML17284A495 (1)

Text

Total error estimates are propagated from individual error estimates of sample volume, sample activity and effluent flow rate measurements. The overriding uncertainty in all cases is in the measurement of the effluent and sample volumes. The estimated error was determined to be 36% at the 95% confidence levels The fission gas release rates during the first quarter were higher due to a fuel pin leak in the reactor core. The fuel bundle containing the leaking pin was removed from the reactor core during the scheduled 1988 refueling outage. The effluent gas release rates have returned to the pre-leak levels.

In addition to the reactor site, HNP-2 has a permanent laundry facility located approximately 0.75 miles from the site. Its ventilation system contains HEPA filters on the discharge and is continuously monitored for particulates. Also at this location is a backup chemistry lab within the EOF. The radiochemical hood containing HEPA filters is monitored for radioactive releases when in operation. Gamma spectrometry indicated no radioactive material present other than that attributable to natural background.

There were three limiting conditions for operations (LCO) which occurred during this reporting period.

NCR $~~~153: The LCO sampling period was missed for the reactor building effluent particulate and iodine. The reactor was in refuel mode and the reactor building ventilation was shut down for testing. The Standby Gas Treatment System was used to maintain building differential pressure. i)hen exhaust flow dropped below 17,000 cfm, sample flow to REA-SR-37 ceased. Chemistry was not informed that REA-SR-37 was out of service until it was returned to service, 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and 55 minutes later.

ttgp td\df This exceeded the LCO sampling period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

hh th building effluent particulate and iodine. The reactor was in refuel t

mode, and an electrical bus testing was being performed. Electrical power was lost to the portable, sampling equipment, that was temporarily substituting for REA-SR-37 which was out of service. Efforts to provide backup power required greater than four hours, as it had to be obtained from another floor level vi.a cable chases.

SJLNN- g: h g h Pt f hfd << t t't f th system is required every four (4) hours when the explosive gas monitoring ff g system is declared out of service. The normal grab sample station used to comply with this LCO became inoperable and a grab sample that was required could not be obtained until longer than one (1) hour past its required sampling time.

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