05000333/LER-1979-096-03, /03L-0:on 791028,during Normal Operation,Reactor Water Conductivity Exceeded Spec Limit.Power Reduction Initiated.Caused by Leakage from Radwaste Concentrator to Main Condenser.Shell to Tube Side Leak Exists.Study Ongoing

/03L-0:on 791028,during Normal Operation,Reactor Water Conductivity Exceeded Spec Limit.Power Reduction Initiated.Caused by Leakage from Radwaste Concentrator to Main Condenser.Shell to Tube Side Leak Exists.Study Ongoing

ML19210E103
Person / Time
Site:	FitzPatrick
Issue date:	11/27/1979
From:	W. Verne Childs POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19210E102	List: 05000333/LER-1979-096, Forwards LER 79-096/03L-0 05000333/LER-1979-096-03, /03L-0:on 791028,during Normal Operation,Reactor Water Conductivity Exceeded Spec Limit.Power Reduction Initiated.Caused by Leakage from Radwaste Concentrator to Main Condenser.Shell to Tube Side Leak Exists.Study Ongoing
References
LER-79-096-03L, LER-79-96-3L, NUDOCS 7911290328
Download: ML19210E103 (3)

LER-1979-096, /03L-0:on 791028,during Normal Operation,Reactor Water Conductivity Exceeded Spec Limit.Power Reduction Initiated.Caused by Leakage from Radwaste Concentrator to Main Condenser.Shell to Tube Side Leak Exists.Study Ongoing

Event date:
Report date:
3331979096R03 - NRC Website

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4 POWER AUTH0P.iTY OF THE STATE OF NEW YORK JAMES A. FITZrATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 ATTACHMENT TO LER 79-096/03L-0 Page 1 of 2 During normal operation, reactor water conductivity exceeded the Technical Specification limit as a result of leakage from the radwaste concentrator to the main condenser.

Operai! ions personnel were transferring concentrated effluent from the radwaste concentrator which caused contamination of the concentrator's condensate receiver with concentrated waste by tube or gasket leakage. The condensate receiver was lined up to return condensate to the main condenser and thereby resulted in the addition of an e timated 50 gallons of concentrated waste with a c.onductivity of between 10,000 and 20,000 pmho/cm to the main condenser.

Operations personnel noted the rapid increase in reactor vessel conductivity at approximately 2:30 AM. A power reduction was initiated immediately and conductivity exceeded the limits of Technical Specifications, Appendix A, Paragraph 3.6.C. approximately 5 minutes later.

Included in this attachment is a complete tabulation of the conductivity trar.sient and other parameters from prior to the event until return to normal following the event.

The FitzPatrick Plant Staff has thoroughly reviewed the transient and NE00-10899, titled " Chloride Control in BWR Coolants" which indicates that while high conductivity due to the presence of high neutral salt solutions is undesirable, no damage to the reactor fuel or the reactor coolant pressure boundary should result because both the chloride and dissolved oxygen con-centrations remained low throughout the transient. Therefore, the event did not represent a significant hazard to the public health and safety.

To preclude recurrence, operation of the waste concentrator was reviewed and it was determined that a shell to the tube side leak exists which allows contamination of the steam condensate when the shell side is pressurized to complete effluent transfer operations of the unit.

Until the precise location of the leak can be determined and repaired, the condensate receiver return line will be routed to the waste collector and the line to the main condenser is isolated and tagged.

Further, until the unit's condensate receiver is modified by the addition of continuous conductivity measuring equipment operation in this manner will be continued.

NOTE: LER 79-076 is a related event.

102 %0

i POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 ATTACHMENT TO LER 79-096/03L-0 PAGE 2

of 2 REACTOR WATER CHLORIDE CONDUCTIVITY DATE TIME (PPB)*

(MI C ROMH0/CM)

• REMARKS 10/26'79 1800 50 1.05 Reactor water grab sample at clean-up system influent.

10/28/79 0230 Rapid increase in clean-up system influent noted and power reduction initiated.

10/28/79 0235 5.0 Clean-up system influent cc iductivi ty indication exceeds technical speci fication limi t.

10/28/79 0400 320 23.0 Reactor water grab sample at clean-up system influent.

10/28/79 0600 19.0 10/28/79 0745 230 15.0 10/28/79 0840 13.0 10/28/79 0950 12.0 10/28/73 1105 9.1 10/28/79 1145 180 8.3 10/28/79 1415 6.0 Clean-up system influent conduc-tivity indication.

10/28/79 1530 5.3 10/28/79 1650 190 4.8 Reactor water grab sample at clean-up system influent.

10/28/79 1950 90 4.3 10/28/79 2355 76 2.3 10/29/79 0400 60 1.7 10/29/79 0830 40 0.95

• Technical specification limits for chloride and conductivity dre 500 ppb and 5.0 micromho/cm respectively.

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