ML20168A459

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Final ASP Analysis - Dresden 2 (LER 237-70-LTR)
ML20168A459
Person / Time
Site: Dresden Constellation icon.png
Issue date: 06/16/2020
From: Christopher Hunter
NRC/RES/DRA/PRB
To:
Littlejohn J (301) 415-0428
References
LER 1970-LTR-00
Download: ML20168A459 (4)


Text

PRECURSOR DESCRIPTION AND DATA NSIC Accession Number:

47814 Date:

June 5, 1970 -

Title:

Depressurization Incident at Dresden 2 The failure sequence was:

1. A spurious-signal in. the reactor pressure control system occurred causing the turbine control valve to open from 75% to 80% and turbine bypass valve to open 100%.
2. The reactor scrammed and the water level began to drop.

The pen in the water level stuck on the low water level mark.

Due to this incorrec-t signal the operator took manual control of the feedwater system and began to increase flow to the reactor.

3. After no change in water level indication the operator realized the pen was stuck.

He tapped the pen, however water was already blowing through the relief valves.

4. The feedwater flow was throttled back.

Corrective action:

The plant was shutdown for an extended period for repair of and inspection.

minor damage Design purpose of failed system or component:

The reactor water level instrumentation indicates the water level in the reactor vessel.

Unavailability of system per WASH 1400:

Unavailability of component per WASH 1400:

Unavailabilities are In units of per demand D-1.

Failure rates are in units of per hour HR-1.

A Spurious Signal The Reactor Tripped Due to an Erroneous Signal Feedwater Was Throttled Potential Initiates a Feed-the Operator Took Control Back and the Reactor Severe Water Transient of the Feedwater Controls Placed in Cold Shutdown Core

____and Overfilled the Vessel Damage No MSLB initiator No ATWS NSIC 47814 -

Actual Occurrence of the Depressurization Incident at Dresden 2

Excessive Coolant Inventory Reactor Scram Reactor Vessel Or Turbine Isolate Reactor Coolant Overflows Into Steam Lines, Is Dis-charged Through Relief Valves, Which Stick Open Steam Line Break Due To Turbine Missiles, etc.

Long Term Core Cooling Success Potential Severe Core Damage o

Small LOCA Initiator I

No r~No I

e5l'71YWý0%%

-Yes y R A I

No Yes NSIC 47814 -

Sequence of Interest for-the Depressurization Incident at Dresden 2

CATEGORIZATION OF ACCIDENT SEQUENCE PRECURSORS NSIC ACCESSION NUMBER: 47814 DATE OF LER:

July 6, 1970 DATE OF EVENT:

June 5, 1970 SYSTEM4 INVOLVED:

Feedwater COMPONENT INVOLVED:

Reactor Water Level Indicator.

CAUSE: Component failure SEQUENCE OF INTEREST:

Excessive Coolant Inventory ACTUAL OCCURRENCE:

Depressurization Incident REACTOR NAME:

Dresden 2 DOCKET NU~!BER: 50-237 REACTOR TYPE:

BWR DESIGN ELECTRICAL RATING:

794 MJ e REACTOR AGE:

0.4 yr VENDOR: General Electric ARCHITECT-ENGINEERS:

Sargents and Lundy OPERATORS:

Commonwealth Edison LOCATION:- Nine miles from Morris, Ill.

DURATION:

N/A PLANT OPERATING CONDITION:

75%

SAFETY FEATURE TYPE OF FAILURE:

(ainadequate performance; (b) failed to start; PC) made inoperable; (d)____________

DISCOVERY METHOD: operational event COMM*ENT: