ML20168A742

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Final ASP Analysis - Turkey Point 4 (LER 251-74-LTR)
ML20168A742
Person / Time
Site: Turkey Point NextEra Energy icon.png
Issue date: 06/16/2020
From: Christopher Hunter
NRC/RES/DRA/PRB
To:
Littlejohn J (301) 415-0428
References
LER 1974-LTR-00
Download: ML20168A742 (5)


Text

PRECURSOR DESCRIPTION AN~D DATA N'SIC Accession Number:

93702 Date:

May 31, 1974

Title:

Two-Unit Trip at Turkey Point 3-and 4, Loss of Offsite Power at Turkey Point 4 The failure sequence was:

1. Units 3 & 4 were at full power, with unit 4 startup transformer electrically isolated for functional testing of protection system relays and for periodic maintenance on associated equipment.
2. After the transformer protective relays were tested, the transformer lockout relay was reset and current flowed through an unanticipated path (a "sneak circuit"t) and energized unit 4 generator breaker protection system relays, which opened the generator breakers for units 3 and *4.
3. Both unit 3 & 4 reactors automatically tripped when their turbine-generators tripped.

The instantaneous grid loss was 1443 MWe.

4. Since the unit 4 startup transformer was isolated, off-site power was lost to unit 4.(seadtoapg)

Corrective action;(seadtolpg)

1. Modifications were recommended to the startup transformer protective system to provide more complete isolation of the protection system relays during relay tests.
2. The stuck-open safety valve was closed by removing its manual lifting-device.

Design purpose of failed system or component:

1. Offsite electric power provides an alternative source of power to plant auxiliaries in the event the unit generator is inoperable.
2. The main steam safety valves provide over-pressure protection for the steam generators and main-steam piping.

Unavailability of system per WASH 140G:

  • Offsite power:

10-3 following trip Unavailability of component per WASH 1400:

  • Relief valves, failure to close:

10-2 /D Unavailabilities are in units of per demand D-1.

Failure rates are in units of per hour HR The failure sequence was:

(Continued)

5. Diesel-generators A & B started and assumed safety-related loads for unit 4.
6. Five minutes after reactor trip on unit 4, a main steam safety valve lifted and did not reseat.
7. Additional boron was added to the reactor coolant system to provide shut-down margin for the additional cooldown, resulting from the stuck-open safety valve.

Units 3 and 4 Transformer lockout Current flow through Diesel-generators Main steam Unit 4 boratlon at full power relay reset after a "sneak circuit" path A and B start to safety valve to compensate with unit 4 tesring energizes unit 4 genera-provide power to sticks open for cooldown startup trans-tor breaker protection unit 4 (unit 3 on unit 4 due to stuck former isolated system relays, opening offsite power open safety for functional the generator breakers available) valve testing for units 3 and 4 Potential Severe Core Damage 4

No -

additional boron injection available via safety injec-tion system if required

______________________________No J

No -

turbine driven ANW pumps available for R. cooling No No NSIC 93702 -

Actual Occurrence for Two-Unit Trip at Turkey Point 3 & 4

Loss of Turbine Erner-Auxiliary PORV PORV or High Long Offsite Generator gency Feedwater and Demanded PORV Isola-Pressure Term Power Runs Back Power Secondary tion Valve Injection Core and Assumes Heat Removal Closure Cooling House Loads Potenti Severe Core Damage

-No No Yes Yes Nes No Yeo Yes NSIC 93702 -

Sequence of Interest for Two Unit Trip at Turkey Point 3 & 4

  • Use of HPI following AFW failure not included in mitigation procedures.

al Sequence No.

2 3

4 5

6 7

8 9

10 11 12 13

CATEGORIZATION OF ACCIDENT SEQUENCE PRECURSORS NSIC ACCESSION NUMBER:

93702 DATE OF LER:

May 31, 1974 DATE OF EVENT:

April 25, 1974 SYSTEM INVOLVED: Electric power system, main steam COMPONENT INVOLVED:

Startup transformer protective relays,- main steam safety valve CAUSE:

Current flow in a sneak circuit during protective relay testing resulted in actuation of the Unit 3 & 4 generator breakers.

After reactor trip, a Unit 4 main of offsite power ACTUAL OCCURRENCE:

Reactor trip with loss of of~fsite power (Unit 4 only)

REACTOR NAME:

Turkey Point 4 DOCKET NUMBER:

50-251 REACTOR TYPE:

PWR DESIGN ELECTRICAL RATING:

693 INe REACTOR AGE:

.9 yr VENDOR:

Westinghouse ARCHITECT-ENLGINEERS:

Bechtel OPERATORS:

Florida Power & Light Co.

LOCATION:

.25.miles-south.of Miami, Fla.

DURATION:

N/A PLANT OPERATING CONDITION:

Both units at full power.

SAFETY FEATURE TYPE OF FAILURE:

(a) inadequate performance; (b) failed to start; (c) made inoperable; (0inadvertant-opprat-inn DISCOVERY METHOD:

During operation COMMENT:

This event and a previous event on March 1, 1974 resulted in the separation of both Turkey Point Units from the grid. However, only Unit #4 and only during this event lost of fsite power.