ML20147A545

From kanterella
Jump to navigation Jump to search
Final ASP Analysis - Duane Arnold (LER 331-80-054)
ML20147A545
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 04/23/1982
From: Christopher Hunter
NRC/RES/DRA/PRB
To:
Littlejohn J (301) 415-0428
References
LER 1980-054-00
Download: ML20147A545 (4)


Text

PRECURSOR DESCRIPTION AND DATA NSIC Accession Number:

174073 Date:

April 23, 1982

Title:

Stuck Open Relief Valve at Duane Arnold The failure sequence was:

1. With the reactor at 7% power during a startup, an operator noticed a higher than normal discharge line temperature from a Target Rock Model 67F-6XI0 main steam relief
valve, which indicated a small steam leakage from the reactor coolant system (RCS).
2.

An operator manually cycled the valve at rated pressure to attempt a better valve seating.

3.

The valve stuck open and remained open for 7.5 min, resulting in RCS depressurization to <880 psig.

4.

The MSIVs closed on low RCS pressure and an automatic reactor scram occurred.

5.

The vessel water level fell 7.5 in.

below instrument zero level (150.5 in.

above the active fuel).

6.

ECCS initiation was not required and ECCS was not employed in the recovery (water level and pressure were above ECCS actuation set point.

7.

One train (group 3 channel A) of the containment isolation actuation logic failed to actuate on low vessel water level as required.

A wiring error made during a design change and not detectable by postinstallation testing or normal surveillance tests was discovered.

One valve in a number of pairs of isolation valves failed to close.

Channel B did actuate and the containment was isolated.

8.

The reactor was placed in cold shutdown until repairs were completed.

Corrective action:

The valve was replaced.

The cause of the closure failure could not be determined.

Design purpose of failed system or component:

The relief valve provides over-pressure protection for the RCS during a transient event.

Operator manually cycles MSIVs close Automatic reactor [ Reactor Containment relief valve to seat it; on low steam scram due to MSIV inventory A isolation valve sticks open pressure closure is maintained logic fails Potential Severe Core Damage No No Yes Yes No No Yes Yes NSIC 174073 - Actual Occurrence Tree for Stuck Open Relief Valve at Duane Arnold

Small Reactor Standby High Automatic LPCI Long Potential Sequence Loss of Scram Liquid Pressure Depressuri-or CS Term Severe No.

Coolant Control Cooling zation

Response

Core Core Accident Initiated Provided System Adequate Cooling Damage

_Operates No 1

Yes 2

No 3

Yes 4

Yes 5

Yes 6

No 7

Yes 8

Yes 9

Yes 10 NSIC 174073 -

Sequence of Interest Tree for Stuck Open Relief Valve at Duane Arnold

CATEGORIZATION OF ACCIDENT SEQUENCE PRECURSORS NSIC ACCESSION NUMBER:

174073 LER NO:

80-054/01X-i DATE OF LER:

April 23, 1982 DATE OF EVENT:

January 11, 1980 SYSTEM INVOLVED:

Over-pressure protection system COMPONENT INVOLVED:

Main steam relief valve CAUSE:

Unknown SEQUENCE OF INTEREST:

Small break LOCA ACTUAL OCCURRENCE:

Small break LOCA REACTOR NAME:

Duane Arnold DOCKET NUMBER:

50-331 REACTOR TYPE:

BWR DESIGN ELECTRICAL RATING:

538 MWe REACTOR AGE:

5.8 years VENDOR:

General Electric ARCHITECT-ENGINEERS:

Bechtel OPERATORS:

Iowa Light and Power LOCATION:

8 miles NW of Cedar Rapids, Iowa DURATION:

7.5 min PLANT OPERATING CONDITION:

7% full power (starting up)

TYPE OF FAILURE:

Failed to close DISCOVERY METHOD:

Operational event COMMENT:

This event could have occurred at full power.

Note:

LER Rev.

0 for this event was filed as NSIC 161716.