ENS 41896: Difference between revisions

v t e ENS Event
22:08 Aug 5, 2005
Title	Rps Actuation Due to Low Reactor Water Level Caused by Loss of Reactor Feed Pumps
Event Description	At 1708 on 08/05/2005, Unit 2 reactor scrammed from 100% power when reactor water level reached Level 3 Reactor Scram setpoint due to loss of 2C and 2B Reactor Feed Pumps. All rods inserted [fully]. Unit 3 was also at 100% power and was unaffected by this event. Reactor water level reached level 2 (-45) HPCI & RCIC initiation setpoint and was recovered by HPCI and RCIC injection. All expected PCIS isolations, Group 2 (RHR S/D cooling), Group 3 (RWCU), Group 6 (ventilation), and Group 8 (TIP) were received along with the auto start of CREV, 3 SGT trains, HPCI and RCIC with injection into Reactor Vessel. Recirc Pumps tripped at -45" as expected. Four MSRVs lifted momentarily to stabilize reactor pressure. This event is reportable at 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Non-Emergency Notification along with a 60 day written report in accordance with 10CFR50.72(b)(2)(iv)(A), 10CFR50.72(b)(2)(iv)(B), 10CFR50.72(b)(3)(iv)(A) and 10CFR50.73(a)(2)(iv)(A) as 'Any event or condition that results in a valid actuation of RPS and PCIS as described in (l) and (2) below.' Decay heat is being removed via steam to the main condenser using the bypass valves maintaining pressure at 895 psi. The licensee notified the NRC Resident Inspector. * * UPDATE PROVIDED BY HUNTER TO JEFF ROTTON AT 1524 ON 08/06/05 * * * Upon further evaluation by the trip investigation team, it has been determined that no MSRV's lifted during this event. Reactor pressure data indicated no increasing pressure spike during the transient. The post-scram pressure trends indicated the maximum reactor pressure was normal operating pressure at the start of the transient followed by a gradual decline. The initial report which stated that 4 MSRV's had lifted was in error. The licensee will notify the NRC Resident Inspector. Notified the R2DO (Landis).

ENS 41896 +/-
Where
Browns Ferry Alabama (NRC Region 2)
Reporting

10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge 10 CFR 50.72(b)(3)(iv)(A), System Actuation
Time - Person (Reporting Time:+-0.3 h-0.0125 days <br />-0.00179 weeks <br />-4.1094e-4 months <br />)
Opened:	Michael Hunter 21:50 Aug 5, 2005
NRC Officer:	Bill Gott
Last Updated:	Aug 6, 2005
41896 - NRC Website Loading map... {"minzoom":false,"maxzoom":false,"mappingservice":"leaflet","width":"350px","height":"250px","centre":false,"title":"","label":"","icon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"zoom":6,"defzoom":14,"layers":["OpenStreetMap"],"image layers":[],"overlays":[],"resizable":false,"fullscreen":false,"scrollwheelzoom":true,"cluster":false,"clustermaxzoom":20,"clusterzoomonclick":true,"clustermaxradius":80,"clusterspiderfy":true,"geojson":"","clicktarget":"","imageLayers":[],"locations":[{"text":"\u003Cb\u003E\u003Cdiv class=\"mw-parser-output\"\u003E\u003Cp\u003E\u003Ca class=\"mw-selflink selflink\"\u003EENS 41896\u003C/a\u003E - \u003Ca href=\"/Browns_Ferry\" title=\"Browns Ferry\"\u003EBrowns Ferry\u003C/a\u003E\n\u003C/p\u003E\u003C/div\u003E\u003C/b\u003E\u003Cdiv class=\"mw-parser-output\"\u003E\u003Cp\u003ERps Actuation Due to Low Reactor Water Level Caused by Loss of Reactor Feed Pumps\n\u003C/p\u003E\u003C/div\u003E","title":"ENS 41896 - Browns Ferry\n","link":"","lat":34.70418333333333,"lon":-87.11844722222222,"icon":"/w/images/c/ce/Tennessee_Valley_Authority_icon.png"}],"imageoverlays":null}
v • d • e

v t e Emergency Notification System
Browns Ferry with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge
WEEKMONTHYEAR2024-08-30T15:51:00 [Table view]
[ENS list for Browns Ferry]

@@ Line 16: / Line 16: @@
 | event date = 08/05/2005 17:08 CDT
 | last update date = 08/06/2005
-| title = Rps Actuation Due To Low Reactor Water Level Caused By Loss Of Reactor Feed Pumps
+| title = Rps Actuation Due to Low Reactor Water Level Caused by Loss of Reactor Feed Pumps
 | event text = At 1708 on 08/05/2005, Unit 2 reactor scrammed from 100% power when reactor water level reached Level 3 Reactor Scram setpoint due to loss of 2C and 2B Reactor Feed Pumps.  All rods inserted [fully].  Unit 3 was also at 100% power and was unaffected by this event.  Reactor water level reached level 2 (-45) HPCI & RCIC initiation setpoint and was recovered by HPCI and RCIC injection.  All expected PCIS isolations, Group 2 (RHR S/D cooling), Group 3 (RWCU), Group 6 (ventilation), and Group 8 (TIP) were received along with the auto start of CREV, 3 SGT trains, HPCI and RCIC with injection into Reactor Vessel.  Recirc Pumps tripped at -45" as expected.  Four MSRVs lifted momentarily to stabilize reactor pressure.
 This event is reportable at 4 hour and 8 hour Non-Emergency Notification along with a 60 day written report in accordance with 10CFR50.72(b)(2)(iv)(A), 10CFR50.72(b)(2)(iv)(B), 10CFR50.72(b)(3)(iv)(A) and 10CFR50.73(a)(2)(iv)(A) as 'Any event or condition that results in a valid actuation of RPS and PCIS as described in (l) and (2) below.'

v t e Unit 2
GE-4
Reactor critical	Critical
Scram	A/R
Before	Power Operation (100 %)
After	Hot Shutdown (0 %)

ENS 41896: Difference between revisions

Latest revision as of 21:20, 1 March 2018

Navigation menu

ENS 41896: Difference between revisions

Latest revision as of 21:20, 1 March 2018

Navigation menu

Search