ML20214E205

Forwards Semiannual Radioactive Effluent Release Rept,Jul- Dec 1985. Changes to Offsite Dose Calculation Manual, Process Control Program & Rept Corrections Included. Operational & environmentally-related Events Discussed

ML20214E205
Person / Time
Site:	Rancho Seco
Issue date:	03/03/1986
From:	Reinaldo Rodriguez SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20214E208	List: ML20214E205 ML20214E215
References
RJR-86-087, RJR-86-87, TAC-64735, NUDOCS 8603070196
Download: ML20214E205 (3)

Text

p hSMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT C 62o1 S Street. P.o. Box 15830, Sacramento CA 95852-1830.(916) 452-3211 RJR 86-087 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA March 3, 1986 J B MARTIN ADMINISTRATOR U S NUCLEAR REGULATORY COMMISSION REGION V 0FFICE OF INSPECTION AND ENFORCEMENT 1450 MARIA LANE SUITE 210 WALNUT CREEK CA 94596 DOCKET NO. 50-312 OPERATING LICENSE OPR-54 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT The Sacramento Municipal Utility District hereby transmits the Semiannual Radioactive Effluent Release Report for the period of July 1, 1985 through December 31, 1985 in compliance with Technical Specification 6.9.2.3.

The format of this report follows that found in Appendix 8 of Regulatory Guide 1.21.

In addition, changes to the Offsite Dose Calculation Manual and to the Process Control Program are included as required by Technical Specification 6.9.2.3.

Corrections, if any, to previous reports are also included.

Doerational Events Rancho Seco was not operating during the period of July 1, 1985 to September 28, 1985 for plant modifications.

On September 28, 1985, the reactor achieved criticality and was brought to 40%

power on September 30, 1985 for physics testing.

The power level was reduced to 15% on October 1, 1985 to perform the turbine overspeed trip test. The reactor tripped on high coolant pressure following the turbine trip.

The plant was brought to hot shutdown, where it remained until November 2, 1985.

Criticality was achieved on November 2, 1985. The 220 KV breakers were closed on November 3, 1985 and power was leveled at 42%.

Power was reduced to 15%

and the turbine overspeed trip test performed on November 7, 1985. The breakers were reclosed on November 8, 1985 and the reactor power was brought to 42%.

The power level was increased to 75% on November 17,1985 and to 91%

on November 19, 1985. Power level remained at approximately 91% to December 5, 1985.

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B603070196 060303 PDR ADOCK 05000312 M

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RJR 86-087 J B Martin March 3, 1986 The reactor tripped on reactor coolant system high pressure on December 5, 1985.

The reactor was brought to hot shutdown for control system maintenance until December 12, 1985.

The reactor was brought back on line on December 12, 1985.

Power was gradually increased to near 100% on December 15, 1985 and remained at 100% until December 22, 1985. On December 22, 1985, the plant was brought to hot shutdown to repair a leaking pressurizer sampling isolation valve. The reactor was brought back on line on December 24, 1985.

The plant tripped on December 26, 1986 due to loss of power to the Integrated Control System.

The plant was brought to cold shutdown for the remainder of December.

Environmentally Related Events An abnormal release occurred on July 24, 1985 associated with recirculating the "A" steam generator. Approximately 1.6 uC) of Cs-134 and 3.5 pCi of Cs-137 were released to a plant drain which discharges directly to the plant efEluent. Samples of the plant effluent indicated no detectable activity.

The carbon adsorber trays in the reactor building's exhaust air system were replaced in August 1985. The replacement became necessary due to spray painting in the reactor building.

A sample for the regenerate hold-up tank release 85-137 was taken for composite but was not included in the August composite A separate area in the hot laboratory has been set aside for storing composites to reduce confusion.

A release of noble gases occurred through the secondary steam relief valves on the December 26, 1985 plant trip. A description of the event was transmitted to your office by District letter RJR 86-075 dated February 19, 1986.

Approximately 30 gallons of tritiated water were released to the ground on the south side of the protected area on December 28, 1985.

No radiological impact is expected due to dispersion and evaporation in the soil. Samples taken at the fenceline indicated no detectable activity.

Water samples were collected in October 1985 from the regenerate hold-up tanks and the retention basins onsite at Rancho Seco for purposes of the ongoing Lawrence Livermore National Laboratory (LLNL) Rancho Seco Environmental Studies program.

The results of the analysis of these samples are included in LLNL report UCID-20641 Part I, February 6,1986 and Part II, January 23, 1986 which have been already transmitted to you.

Radionuclides were detected in these samples but at concentrations less than the Technical Specifications

RJR 86-087 J B Martin March 3, 1986' 4.21 Lower Limits of Octection requirements. However, the District will prepare a special report which will reevaluate the 1985 radiological liquid

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effluent source term and submit this report to you by August 31, 1986.

This report was prepared by R. G. Oesterling and R. L. Gardner of United Energy Services Corporation under the review and direction of E. W. Bradley, Supervising Health Physicist in the Nuclear Engineering Department.

1 If there are any questions concerning this report, please contact Mr. Bradley j

a(the,0istrictoffice.

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R. J. RODRIGUEZ ASSISTANT GENERAL MANAGER, NUCLEAR Attachment I

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