ML13308B508
| ML13308B508 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 04/25/1974 |
| From: | Haynes J SOUTHERN CALIFORNIA EDISON CO. |
| To: | Burger A US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8103060668 | |
| Download: ML13308B508 (3) | |
Text
Regulatory Docket File Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD, CALIFORNIA 91770
/#AY April 25, 1974 19GLA74 MU a Directorate of Licensing Regulation U.S. Atomic Energy Commission Washington, D.C.
20545 Attention: Mr. A. Burger Operating Reactors Branch No. 1 Gentlemen:
Subject:
Docket No. 50-206 Provisional Operating License DPR-13 Input Data Required for Analysis of Steam Generator Tube Rupture and Steam Line Break Accidents San Onofre Nuclear Generating Station Unit 1 Enclosed is the information that was requested by members of your staff during the March 13, 1974 meeting concerning plans for Addition of Onsite Power and ECCS Modi fications.
This information consists of input data required for analysis of Steam Generator Tube Rupture and Steam Line Break Accidents.
If you have any questions concerning the en closed material, please contact me.
Very truly yours, J. G. Haynes Chief of Nuclear Engineering Services Enclosure t391
ATTACHMENT PLANT NAME SAN ONOFRE UNIT 1 INPUT DATA REQUIRED FOR ANALYSES OF STEAM GENERATOR TUBE RUPTURE AND STEAM LINE BREAK ACCIDENTS.
Reactor Power Rating Mwth = 1347 Number of Steam Generators 3
Supplier of Steam Generators Westinghouse Primary Coolant Mass (lb) 250,811 Average operating temperature (OF). = 575.1 Average operating pressure (psig) = 2085 Operating primary to secondary leakage (gpm) = normal < 1 gal/day (limit of detection)
Amount of primary coolant that leaks through double-ended tube rupture (lb) = The FSA assumes that following a steam generator tube rupture there is maintained a 200 psi difference between the primary and secondary systems during cooldown and that the cool down lasts for 4.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (tube diameter is.63").
For conservation, the FSA assumes all activity in the primary coolant would be transferred into the turbine cycle.
Approximate mass of metal in contact with primary coolant (i.e., reactor vessel, internals, pumps, Etc.).
This parameter is used for ECCS calculations.
(lb) = 2x10 Safety injection water temperature (OF) = 40 to 90 Letdown rate (lb/min) = 560 (full design purification) 1120 (maximum letdown)
Secondary Coolant Mass of water in SG at time of accident (lb) total mass normal pratinq Q-600/.SG Mass of steam in SG at time of accident (lb) = total mass no oad =
.70,491/SC Total SC secondary side volume (ft3) =2351/SG
Secondary Coolant (ctd.)
Secondary side operatinq temperature (OF) = 534 (no load), 504 (full, load)
Secondary side operating pressure (psig) = 903 (no load), 694 (full load)
SG safety valve set point pressure (psig)
Number of Safety Valve 2
2 2
2 2
Set Point Pressure 985 1000 1020 1030 1035 Total secondary system water and steam mass (IL) 850.000 Total steam flow rate at rated power (lb/hr) = 5.698 x 106 Turbine bypass capacity (%) = 10 (considering valves CV 3 & 4 only)
Auxiliary feedwater temperature (OF) 40 to 90 SG blowdown rate (operating conditions) (gpm) = 15 SG blowdown tank capacity (1b)=2600 (no load conditions), 2300 (operating conditions)
Air ejector flow rate (cfm) = 33.75 Condenser hot well capacity (gallons) =
55,650 (normal operating level) 190,660.,(full capacity)
Cooling rate after isolation of failed SG with no offsite power (OF/hr) =
No Steam Time required for isolation of SG following tube Generator rupture accident (min)
Isolation Time required for isolation of SG following steamj line break accident (min) =
Auxiliary Feedwater rate 300 gpm Site Characteristics X/Q (sec/m 3) =
.ixlG-4 Distance to site boundary (meters) = 800 Wind speed (m/sec) = 1.8