ML041890338
| ML041890338 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 04/19/2004 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| 40682, 40684, FOIA/PA-2004-0243 | |
| Download: ML041890338 (2) | |
Text
NRC:FJvent Notification Report for April 19, 2004
- Page, any contamination occurred. At 2125 EDT, the HazMat responders reported that no radiation above normal background was found at the site, and they were following up with the operator of the device to check for personal contamination.
At 2208 EDT, the team reported that no contamination was found on either the Individual who operated and transported the device, or his clothing.
4 of 5 Power Reactor Event Number: 40682 Facility: VOGTLE Notification Date: 04/18/2004 Region: 2 State: GA Notification Time: 15:31 [ET]
Unit: [ ] [2] [ ]
Event Date: 04/18/2004 RX Type: [1] W-4-LP,[2] W-4-LP Event Time: 12:38 [EDT]
NRC Notified By: THOMAS PETRAK Last Update Date: 04/18/2004 HQ OPS Officer: JAMIE HEISSERER Emergency Class: NON EMERGENCY Person (Organization):
10 CFR Section:
STEPHEN CAHILL (R2) 50.72(b)(3)(iv)(A) - VAUD SPECIF SYS ACTUATION SCRAM Current Unit Code RX CRIT Initial PWR Initial RX Mode PWR Current RX Mode 2
N N
0 Hot Standby 0
Hot Standby Event Text AUXILIARY FEEDWATER SYSTEM ACTUATION DUE TO MAIN FEED PUMP TRIPS "An Auxiliary Feedwater [AFW] actuation occurred with the plant In Mode 3, Main Feedwater out of service and a cooldown In progress. An AFW actuation was received when both main feed pumps tripped due to low condenser vacuum. AFW was already In service with both motor-driven pumps running and discharge valves throttled to maintain steam generator level. A surveillance to test AFW actuation on the trip of main feedwater pumps was In progress. The main feed pump trip signal was generated when condenser vacuum was broken prior to completing the test and blocking the actuation signal from the main feed pumps to AFW. Steam generator blowdown and sample valves Isolated and MDAFW [Motor Driven AFW] discharge valves opened as expected. Operators took action to throttle AFW feed to the steam generators. No adverse affects on the plant occurred. The AFW actuation signal from the trip of main feed pumps has been blocked as allowed by plant conditions."
The licensee notified the NRC Resident Inspector.
A rop Power Reactor Event Number: 40684 Facility: NINE MILE POINT Notification Date: 04/18/2004 Region: 1 State: NY Notification Time: 23:45 [ET]
Unit: [ ] [2] [ ]
Event Date: 04/18/2004 RX Type: [1] GE-2,[2] GE-5 Event Time: 18:30 [EDT]
NRC Notified By: DAVE RICHARDSON Last Update Date: 04/18/2004 HQ OPS Officer: ARLON COSTA Emergency Class: NON EMERGENCY Person (Organization):
10 CFR Section:
BRIAN MCDERMOTT (R1) 50.72(b)(3)(lv)(A) - VALID SPECIF SYS ACTUATION
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NRC: Event Notification Report for April 19, 2004 Page 5 of 5 NRC-Event Notification Report for April 19, 2004 Page 5 of 5 Event Text RESIDUAL HEAT REMOVAL SYSTEM ISOLATION DUE TO A RISE IN REACTOR PRESSURE "At 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br /> on 18 April 2004, Nine Mile Point Unit 2 was restoring from reactor pressure vessel leakage test.
"Reactor pressure was -82 psi, temperature "178 degrees, reactor level was solid with both reactor recirculation pumps running in slow speed per the leak test procedure.
"'B' residual heat removal system was being warmed up in preparation for going In to service. Reactor water cleanup reject from the vessel was secured to maintain RPV [Reactor Pressure Vessel] pressure stable In order to provide driving head for flow through the residual heat removal discharge line to radwaste. The line is warmed up from the reactor, back through the Shutdown cooling isolation valve, to radwaste prior to placing shutdown cooling in service.
When warm-up criteria are met, the operating procedure directs securing flow.
When flow was secured, this effectively Isolated the solid reactor vessel, resulting in a rise in reactor pressure. Pressure peaked at -146 psi before operators established reactor water cleanup reject flow.
"When RPV pressure reached 128 psi, the residual heat removal system isolation was automatically initiated as designed. The shutdown cooling Injection valve, which was open to support piping warm-up, closed as designed. All other shutdown cooling valves were closed prior to the event per the warm-up lineup."
RPV is currently depressurized with shutdown cooling in service. All systems are functioning as expected.
The licensee notified the NRC Resident Inspector.
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