ENS 55821: Difference between revisions

v t e ENS Event
06:23 Apr 5, 2022
Title	Scram on LOW Level
Event Description	The following information was provided by the licensee via telephone and email: On 4/5/2022, at time 0223, during maintenance on Feedwater Level Control Valve 2FWS-LV10B, a Feedwater transient occurred resulting in an RPS Automatic Reactor Scram on Low Level (Level 3, 159.3 inches). Following the scram, reactor water level dropped below Level 2 (108.8 inches) resulting in a Group 2 Recirculation Sample System Isolation, Group 3 TIP [(Traversing Incore Probe)] Isolation Valve Isolation, Group 6 and 7 Reactor Water Cleanup Isolation and Group 9 Containment Purge Isolations. All control rods inserted as expected. High Pressure Core Spray and Reactor Core Isolation Cooling initiated and injected as expected. ECCS Systems have been secured and normal reactor pressure and level control has been established for hot shutdown. Nine Mile Point Unit 2 is stable in Mode 3. These 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and 8-hour non-emergency ENS [(Emergency Notification System)] reports are being made in accordance with 10 CFR 50.72(b)(2)(iv)(A), 10 CFR 50.72(b)(2)(iv)(B), and 10 CFR 50.72(b)(3)(iv)(A). The NRC Resident was informed. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: There was no impact on Unit 1.

ENS 55821 +/-
Where
Nine Mile Point New York (NRC Region 1)
Reporting

10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation
Time - Person (Reporting Time:+-0.25 h-0.0104 days <br />-0.00149 weeks <br />-3.4245e-4 months <br />)
Opened:	Roman Arnold 06:08 Apr 5, 2022
NRC Officer:	Ossy Font
Last Updated:	Apr 5, 2022
55821 - 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 55821\u003C/a\u003E - \u003Ca href=\"/Nine_Mile_Point\" title=\"Nine Mile Point\"\u003ENine Mile Point\u003C/a\u003E\n\u003C/p\u003E\u003C/div\u003E\u003C/b\u003E\u003Cdiv class=\"mw-parser-output\"\u003E\u003Cp\u003EScram on LOW Level\n\u003C/p\u003E\u003C/div\u003E","title":"ENS 55821 - Nine Mile Point\n","link":"","lat":43.52021388888889,"lon":-76.40656388888888,"icon":"/w/images/b/be/Constellation_icon.png"}],"imageoverlays":null}
v • d • e

v t e Emergency Notification System
Nine Mile Point 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
WEEKMONTHYEAR2024-03-04T00:42:00 [Table view]
[ENS list for Nine Mile Point]

@@ Line 9: / Line 9: @@
 | unit = 2
 | utype = GE-2, GE-5
-| cfr = 10 CFR 50.72(b)(2)(iv)(A)
+| cfr = 10 CFR 50.72(b)(2)(iv)(A), 10 CFR 50.72(b)(2)(iv)(B), 10 CFR 50.72(b)(3)(iv)(A)
 | emergency class = Non Emergency
 | notification date = 04/05/2022 06:08
@@ Line 16: / Line 16: @@
 | event date = 04/05/2022 02:23 EDT
 | last update date = 04/05/2022
-| title = SCRAM on LOW Level
+| title = Scram on LOW Level
 | event text = The following information was provided by the licensee via telephone and email:
 On 4/5/2022, at time 0223, during maintenance on Feedwater Level Control Valve 2FWS-LV10B, a Feedwater transient occurred resulting in an RPS Automatic Reactor Scram on Low Level (Level 3, 159.3 inches). Following the scram, reactor water level dropped below Level 2 (108.8 inches) resulting in a Group 2 Recirculation Sample System Isolation, Group 3 TIP [(Traversing Incore Probe)] Isolation Valve Isolation, Group 6 and 7 Reactor Water Cleanup Isolation and Group 9 Containment Purge Isolations.

v t e Unit 2
GE-5
Reactor critical	Critical
Scram	A/R
Before	Power Operation (100 %)
After	Hot Standby (0 %)

ENS 55821: Difference between revisions

Latest revision as of 16:02, 4 January 2024

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ENS 55821: Difference between revisions

Latest revision as of 16:02, 4 January 2024

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