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Event Notification Report for July 18, 2008

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
07/17/2008 - 07/18/2008

** EVENT NUMBERS **


44252 44352 44354

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 44252
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: JOE BENNETT
HQ OPS Officer: PETE SNYDER
Notification Date: 06/01/2008
Notification Time: 17:33 [ET]
Event Date: 06/01/2008
Event Time: 11:48 [CDT]
Last Update Date: 07/17/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
MALCOLM WIDMANN (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation

Event Text

LUBE OIL MOISTURE CONTENT GREATER THAN ACCEPTABLE LIMIT

"A sample was taken of the lubrication/control oil from the Unit 1 High Pressure Coolant Injection (HPCI) System for moisture content analysis. The results of this analysis concluded that the moisture content in the oil exceeded acceptable levels. As a result of this condition the Browns Ferry Nuclear Unit 1 HPCI system was declared inoperable at 11:48 on 6/1/08.

"This event is reportable within 8 hours in accordance with 10 CFR 50.72 (b)(3)(v) as event or condition that at the time of discovery could have prevented the fulfillment of a safety function. It also requires a 60 day written report in accordance with 10 CFR 50.73 (a)(2)(vii).

"Unit 1 remains at 100% power.

"Unit 1 has entered Technical Specification LCO 3.5.1 and is performing the required actions. Troubleshooting of the moisture intrusion condition is in progress, and a corrective action plan is being developed.

"The NRC Resident inspector has been notified."

* * * RETRACTION AT 1239 EDT ON 7/17/08 FROM BAKER TO HUFFMAN * * *

"ENS Event Number 44252, made on June 1, 2008, is being retracted.

"NRC Notification 44252 was conservatively made to ensure that the Eight-Hour Non-Emergency reporting requirements of 10 CFR 50.72 were met when an oil sample indicated the Unit 1 High Pressure Coolant Injection (HPCI) System turbine oil system contained excessive amounts of water.

"An evaluation performed in response to this report concluded that the Unit 1 HPCI System was capable of performing its intended safety function with the turbine oil system containing more water than recommended in the TVA Lubrication Oil Analysis and Monitoring Program. TVA found through an engineering evaluation that the amount of water contained in the turbine oil system would not impact the HPCI operation during its mission time for the Design Basis Loss-of-Coolant Accident.

"As such, the circumstances discussed in the report did not result in any condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to remove residual heat, or mitigate the consequences of an accident. Thus, there was no impact on nuclear safety. Therefore, this event is not reportable under 10 CFR 50.72(b)(3)(v)(B) or 10 CFR 50.72(b)(3)(v)(D).

"TVA's evaluation of this issue is documented in the corrective action program (PER 145517).

"The licensee has notified the NRC Resident Inspector. "

R2DO (Haag) notified.

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Power Reactor Event Number: 44352
Facility: CATAWBA
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BERT ANDERSON
HQ OPS Officer: JOHN KNOKE
Notification Date: 07/17/2008
Notification Time: 10:48 [ET]
Event Date: 06/09/2008
Event Time: 16:31 [EDT]
Last Update Date: 07/17/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
ROBERT HAAG (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Cold Shutdown 0 Cold Shutdown

Event Text

60 DAY REPORT - INVALID ACTUATION OF MAIN STEAM ISOLATION SYSTEM

"This 60-day optional report, as allowed by 10 CFR 50.73 (a)(1), is being made under the reporting requirement in 10 CFR 50.73 (a)(2)(iv)(A) to describe an invalid actuation of a specified system, specifically the Main Steam (SM) System. On June 9, 2008, at 1631 with Unit 1 in Mode 5, an invalid signal was generated on Train B of the SM system during Engineered Safety Features testing. During the performance of returning the Solid State Protection System (SSPS) to 'normal', the SSPSB mode selector switch was placed to operate. A Unit 1 Feedwater and Main Steam isolation occurred. Part of the 'return to normal' sequence is to place the SSPS Input Error Inhibit switch to the inhibit position. The technician failed to insure the inhibit switch 'snapped' into position and trip signals were generated when the Output Test relay switch was placed to Operate. The SM system was returned to standby readiness. This was considered a partial system/train actuation. During this event, the SM system performed as expected. This event was entered into the site specific corrective action program for resolution."

The licensee has notified the NRC Resident Inspector, and will be notifying the State, local and other government agencies.

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Power Reactor Event Number: 44354
Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RYAN FRUTH
HQ OPS Officer: BILL HUFFMAN
Notification Date: 07/17/2008
Notification Time: 19:53 [ET]
Event Date: 07/17/2008
Event Time: 11:41 [CDT]
Last Update Date: 07/17/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
JULIO LARA (R3)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation
2 N Y 100 Power Operation 100 Power Operation

Event Text

DEGRADED CONTROL ROOM VENTILATION ENVELOPE

"At 1141 on Thursday, July 17, 2008, Braidwood Station determined that the Control Room Envelope (CRE) boundary had a degraded condition based on data obtained during performance of differential pressure testing performed in accordance with Technical Specification (TS) 5.5.18, 'Control Room Envelope Habitability Program.' Degradation of the CRE boundary was identified that could have prevented the Control Room (VC) Ventilation Filtration System from performing its safety function due to the potential for a greater amount of unfiltered inleakage into the CRE than assumed in the licensing basis analysis for Design Basis Accident consequences. The differential pressure test results identified slightly negative pressures as compared to outside air in some areas of the CRE that do not include spaces that control room occupants inhabit during accident conditions.

"In accordance with the requirements of TS 3.7.10, 'VC Filtration System,' Condition B, mitigating actions have been implemented to lessen the effect on CRE occupants from the potential hazards of a radiological or chemical event or a challenge from smoke. Actions are in progress to resolve the CRE degraded condition.

"This event is being reported under 10CFR50.72(b)(3)(v)(D) as an 8-hour report as a condition that at the time of discovery could have prevented the fulfillment of the safety function of a system needed to mitigate the consequences of an accident. A Licensee Event Report will be submitted under 10CFR50.73(a)(2)(v).

"The licensee informed the NRC resident."

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Thursday, March 29, 2012