ML20168A737

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Final ASP Analysis - Three Mile Island 2 (LER 320-78-LTR)
ML20168A737
Person / Time
Site: Crane Constellation icon.png
Issue date: 06/16/2020
From: Christopher Hunter
NRC/RES/DRA/PRB
To:
Littlejohn J (301) 415-0428
References
LER 1978-LTR-00
Download: ML20168A737 (4)


Text

PRECURSOR DESCRIPTION AND DATA NSIC Accession Number:

141097 Date:

March 29, 1978

Title:

Safety Injection Occurs at TMI-2 The failure sequence was:

1. Alternate power source feeder breakers to vital bus 2-IV (120 V a-c) were tripped for test.
2. Frequency control module failed resulting in blown fuses in the DC input to invertor.
3. Vital bus 2-IV tripped on invertor failure, resulting in the PORV failing open.
4. Because of the reactor coolant pump configuration at the tine, a reactor trip also occurred.
5. The operators did not realize the relief valve had failed open because of lack of PORV position indication.
6. ECCS was initiated at 1650 psig.
7. Four minutes into the transient, vital bus 2-IV was re-energized, which closed the relief valve and terminated the transient.

Corrective action; 1.. A design change was initiated to change the failure position of the relief valve upon loss of power to closed in lieu of open.

2. Relief valve position indication was provided in the control room.

Design-purpose of failed system or component:

1. Provide 120 V a-c power for loads which require uninterrupted power.
2. The pilot operated relief valve provides overpressure protection for the RCS.

Unavailability of system per WASH 1400:

  • N/A Unavailability of component per WASH 1400: *solid state device, high power application:

3 x 10-6 /hr.

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

Testing with Invertor Pressure switch Pressure indi-Operator Vital bus reactor at failure &

failed closed cation powered intervention 2-IV zero power vital bus opening relief from vital bus successful reenergized 2-IV trip valve 2-IV available closing

& reactor to operator relief valve trip

& terminating CS blowdown Potential Severe Core Damage No No No No -reactor at power No No NSIC 141097 -

Actual Occurrence for Loss of Vital Bus and Relief Valve Opening at Three Mile Island 2

Small Reactor Aukiliary High Low Pressure LOCA Trip Feedwater and Pressure Recirculation Secondary jInjection and LPR/HPI Heat Removal Cross-connect Potential Severe Core Damage Sequence No.

2 3

4 5

6 7

NSIC 141097 -

Sequence of Interest for Safety Injection Occurs at Three Mile Island 2

  • failure requires operator error of failing to close the PORV isolation valve.

CATEGORIZAtTION OF ACCIDENT SEQUENCE PRECURSORS NSIC ACCESSION NUMBER:

141097 DATE OF~ LER:

June 27, 1978 DATE OF EVENT:

March 29, 19,78 SYSTEM INVOLVED:

120 V a-c vital power, ACS COMPONENT INVOLVED:

Vital bus invertor CAUSE:

Blown fuse, faulty invertor control module SEQUENCE OF INTEREST:

small LOCA -

stuck open PORV ACTUAL OCCURRENCE:

stuck open PORV REACTOR NAME:

Three Mile Island 2 DOCKET NUMBER:

50-320 REACTOR TYPE:

PWR DESIGN ELECTRICAL RATING:

906 MWe REACTOR AGE:

0.0+

yr VENDOR:

Babcock & Wilcox ARCHITECT-ENGINEERS:

Burns & Roe OPERATORS:

Metropolitan Edison Co.

LOCATION: 10 miles SE of Harrisburg, PA DURATION:

N/A PLANT OPERATING CONDITION:

Zero power physics testing SAFETY FEATURE TYPE OF FAILURE:

(a) inadequate performance; (b) failed to start; (c) made inoperable; G~)ailed inunafe position DISCOVERY METHOD:

incident during physics testing COMMENT:

Vital bus tripped because of invertor failure while alternate power source was removed for testing.