ENS 52000: Difference between revisions

v t e ENS Event
00:13 Jun 13, 2013
Title	Technical Specification Required Shutdown and Reactor Trip
Event Description	At 2013 EDT on 6/12/16, Millstone Unit 3 commenced a Technical Specification (TS) required shutdown due to excessive Reactor Coolant System leakage from the "A" Reactor Coolant Pump (RCP) third stage seal. The leakage from the third stage seal was approximately two gpm which is greater than the Technical Specification (TS) limit of less than one gpm. During the shutdown, oscillations developed in the Main Feedwater which required the operator to initiate a manual reactor trip. Unit 3 is currently stable in Mode 3. Decay heat is being released via the Steam Dumps to the Main Condenser. Normal offsite power is available and the unit is in a normal shutdown electrical line-up. The cause of the Main Feedwater oscillations is being investigated. The licensee notified the NRC Resident Inspector. The licensee notified State and local government agencies. * * UPDATE FROM WALTER ORF TO DONALD NORWOOD AT 0129 EDT ON 6/13/2016 * * * The following clarifies Feedwater isolation vs. Feedwater oscillation: At 2337 EDT on 6/12/16, a manual reactor trip was initiated on Unit 3 following feedwater isolation. As expected, Aux Feedwater system (AFW) initiated on the reactor trip. The trip was uncomplicated and the plant is currently in Mode 3 with a normal electric line-up and decay heat is being removed via steam dumps to the condenser. This is reportable under 10 CFR 50.72(b)(2)(iv)(B) - RPS Actuation - Critical and 10 CFR 50.72(b)(3)(iv)(A) - Valid Specific System Actuation." The Feedwater isolation occurred due to high Steam Generator water level. The licensee notified the NRC Resident Inspector. Notified R1DO (Arner).

ENS 52000 +/-
Where
Millstone Connecticut (NRC Region 1)
Reporting

10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation
Time - Person (Reporting Time:+-0.37 h-0.0154 days <br />-0.0022 weeks <br />-5.06826e-4 months <br />)
Opened:	Walter Orf 23:51 Jun 12, 2013
NRC Officer:	Daniel Mills
Last Updated:	Jun 13, 2016
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v • d • e

v t e Emergency Notification System
Millstone 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)(i), Tech Spec Required Shutdown
WEEKMONTHYEAR2023-05-30T08:46:00 [Table view]
[ENS list for Millstone]

@@ Line 16: / Line 16: @@
 | event date = 06/12/2013 20:13 EDT
 | last update date = 06/13/2016
-| title = Technical Specification Required Shutdown And Reactor Trip
+| title = Technical Specification Required Shutdown and Reactor Trip
 | event text = At 2013 EDT on 6/12/16, Millstone Unit 3 commenced a Technical Specification (TS) required shutdown due to excessive Reactor Coolant System leakage from the "A" Reactor Coolant Pump (RCP) third stage seal. The leakage from the third stage seal was approximately two gpm which is greater than the Technical Specification (TS) limit of less than one gpm.
 During the shutdown, oscillations developed in the Main Feedwater which required the operator to initiate a manual reactor trip. Unit 3 is currently stable in Mode 3. Decay heat is being released via the Steam Dumps to the Main Condenser. Normal offsite power is available and the unit is in a normal shutdown electrical line-up. The cause of the Main Feedwater oscillations is being investigated.

v t e Unit 3
W-4-LP
Reactor critical	Critical
Scram	Yes, Manual Scram
Before	Power Operation (100 %)
After	Hot Standby (0 %)

ENS 52000: Difference between revisions

Latest revision as of 20:44, 1 March 2018

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ENS 52000: Difference between revisions

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