ML20168A731

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Final ASP Analysis - St. Lucie 1 (LER 335-77-026)
ML20168A731
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 06/16/2020
From: Christopher Hunter
NRC/RES/DRA/PRB
To:
Littlejohn J (301) 415-0428
References
LER 1977-026-00
Download: ML20168A731 (4)


Text

PRECURSOR DESCRIPTION AN~D DATA NSIC Accession Number:

125563 Date:

May 16, 1977

Title:

Offsite Power Lost at St. Luicie 1 The failure sequence was:

1. Fifteen minutes after a manual reactor trip due to grid system undervoltage condition occurred which caused the pumps to trip.

disturbances, a reactor coolant

2. Both diesel-generators started and loaded.
3. The reactor was cooled down using natural circulation until off-site power was restored (approximately 20 minutes).
4. One hour later, off-site power was again lost and natural circulation cool-down was used until off-site power was restored (one to one-and-a-half hours later).

Corrective action; None Design purpose of failed system or component:

1. Off-site power provides the preferred source of electric power to safety-related equipment when the unit generator is not in operation.

Unavailability of system per WASH.140G:

loss of offsite power:

2 x 10-5 /hr Unavailability of component per WASH 1400:*

i*Unavailabilitie are in units of per demand D-1.

Failure rates are in units of per hour HR-

Reactor manually Loss of off-Two of two diesel-Two of two motor-Turbine-driven tripped due to site power generators start driven AFW pumps AFW pump provides grid disturbances and assume safety-provide AFW flow AFW flow to steam related loads to steam generators generators Potential Severe Core Damage No No Yes No NSIC 125563 -. Actual Occurrence for Off-Site Power Lost at St. Lucie 1 specific pumps providing AFW flow not specified.

Loss of Turbine Emer-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 Potential Severe Core Damage No Sequence No.

2 3

4 5

6 7

8 9

10' 11 12 13 NSIC 125563 - Sequence of Interest for Off-Site Power Lost at St. Lucie 1 not included in mitigation procedures.

CATEGORIZATION OF ACCIDENT SEQUENCE PRECURSORS NSIC ACCESSION NU~MBER:

125563 DATE OF LER:

June 16, 1977 DATE OF EVENT:

May 16, 1977 SYSTE'M INVOLVED:

off-site power COIMPONIENT INVOLVED:

unknown CAUSE:

unknown SEQUENCE OF INTEREST:

loss of offsite power ACTUAL~ OCCURRENCE:

reactor trip with loss of off site power REACTOR NAkEE:

St. Lucie 1 DOCKET NUMBER:

50-335 REACTOR TYPE:

pWR DESIGN ELECTRICAL RATING:

802 MWe REACTOR AGE:

1.1 yr VENDOR:

Cbmbustion Engineering ARCHITECT-ENGINEERS:

Ebasco OPERATORS:

Florida Power & Light Co.

LOCATION:

12 muilea. SEA,f.J.ort. 1ierce, Fla.

DURATION:

N/A PLANT OPERATING CONDITION:

tripped prior to loss of off-site power SAFETY FEATURE TYPE OF FAILURE:

(a) inadequate performance; (b) failed to start; 0

made inoperable; (d)

DISCOVERY METHOD:

during operation COMMENT:

LER does not specify which AFW system components were used to provide core cooling.