L-76-438, Letter Transmitting Supplemental Information Regarding ECCS Reevaluation After re-calculation Using Tech Spec Rated Power Level of 2200 Mwt

Letter Transmitting Supplemental Information Regarding ECCS Reevaluation After re-calculation Using Tech Spec Rated Power Level of 2200 Mwt

ML18227C906
Person / Time
Site:	Turkey Point
Issue date:	12/30/1976
From:	Robert E. Uhrig Florida Power & Light Co
To:	Stello V Office of Nuclear Reactor Regulation
References
L-76-438
Download: ML18227C906 (38)

Text

NPQ FORM 195 U.S. NUCLEAR REGULATORV ASSIGN DOCKET NU ER (2.76)'RC 5 FILE NUMBER 25 251 DISTRIBUTION FDR PART 50'DOCI(ET MATERIAL TO: V. STELLO, JR. FROM:FLORDIA PWR ~ & LIGHT CO DATE OF DOCUMENT MIAMI, FLORDIA 12/30/76 R.E. UHRIG DATE RECEIVED 1/3/77 OLETTER ClNOTORIZED PROP INPUT FORM NUMBER OF. COPIES RECEIVED

@ORIGINAL %UNCLASSIFIED OCOP V )oo DESCRIPTION ENCLOSURE LTR. RE. THEIR 12/9/76 REVALUATION...TRANS REVISED CALCULATIONS AS,.A SUPPLEMENT TO THE ECC THE FOLLOWING........ REEVALUATE/., CONSISTING OF TABLES AND FIGURES.

g3 SIGNED CYS, RECEIVED)

( 24 PAGES)

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>OROT gggOV PLANT NAME! TURKEY PT. /I 3 & 0 ACgyO

~gg)g SAFETY FOR ACTION/INFORMATION SAB 1 6 77 ASSIGNED 'AD! ~ .

LEAR PR CT MANA E ELLIOTT PROJECT MANAGER!

L~CASST LIC ASST '0 INTERNAL D IST RI BUTION SYSTEMS SAFETY PLANT SYSTEMS S TE SAFE NRC PDR HEINEMAN TEDESCO I 6i E SCHROEDER 0 OELD GOSSICK & STAFF ENGINEERING IPPOLITO MIPC ERNST CASE KNIGHT BALLARD HANAUER SIHWEIL OPERATING REACTORS SPANGLER HARLESS PAWLICK STELLO SITE TECH PROJECT MANAG&IENT REACTOR SAFE OPERATING TECH GAMIIILL BOYD ROSS EISENHUT STEPP P, COLLINS NOVAK HULMAN HOUSTON ROSZTOCZY PETERSON CHECK B .E SITE ANALYSIS MELTZ VOLLMER HELTEMES AT6i I BUNCH SKOVHOLT SALTZMAN J COLLINS RUTBERG KRE GER EXTERNAL DISTRIBUTION CONTROL NUiVIBER LPDRi MIAMI FLORD A NAT LAB~

TIC! REG V,IE ULRIKSON OR Q g~.c'w j

NSIC! LA PDR 3i ASLB! CONSULTANTS!

ACRS 16 CYS >HOh5WC'/ E NRC FORM 195 I2-76)

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~0gglatorff Qg5gga"'. O. BOX 013100, MIAMI, FL 33101

~yMlg FLORIDA POWER & LIGHT COMPANY I

ember 30, 1976

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76-438 Office of Nuclear Reactor Regulat Attn: Victor Stello, Jr., Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Stello:

Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 ECCS Reevaluation Su lemental Information On December 9, 1976, Florida Power a Light Company forwarded the ECCS Reevaluation for Turkey Point Units 3 and 4 which was performed using a rated power level of 23.92 Mwt (L-76-419).

The calculations have been revised using the Technical Speci-fication rated power level of 2200 Mwt. The results of the

,revised calculations are forwarded herewith as a supplement to our earlier report.,

Very truly yours, Robert E. Uhrig Vice President REU/GDW/hlc Attachment cc: Norman C. Moseley, Region II Robert Lowenstein, Esq.

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TABLE 1 LARGE BREAK TIME SEQUENCE OF EVENTS STEAM GENERATOR 10Ã TUBE PLUGGING DECL (CD=0.4)

(sec)

START 0.0 REACTOR TRIP SIGNAL 0.595 S.I. SIGNAL 0.67 ACC. INJECTION 16.3 END OF BYPASS 27.52 END OF BLOWDOWN 27.66 BOTTOM OF CORE RECOVERY 46.'59 ACC EMPTY 61.02 PUMP INJECTION 25.67

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TABLE 2 LARGE BREAK STEAM GENERATOR 10/ TUBE PLUGGING DECL (CD=0.4)

RESULTS PEAK CLAD TEMP oF 2190 PEAK CLAD LOCATION FT. 6.0 LOCAL "Zr/H20 Reaction (max)X 11.922 LOCAL Zr/H20 LOCATION Ft. 6.0 TOTAL Zr/H20 Reaction 'A <O. G HOT ROD BURST TIME Sec 22. 8 HOT ROD BURST LOCATION Ft. 6.0 CALCULATION CORE P01'1ER Mwt 102% of 2200 PEAK LINEAR POWER kw/ft 102Ã of 12.61 PEAKING FACTOR 2.22 ACCUMULATOR ttATER VOLUME (ft ) 875 (per accumulator)

FUEL REGION + CYCLE ANALYZED CYCLE REGION Units 3 and 4

TABLE 3 LARGE BREAK CONTAINMENT DATA (DRY CONTAINMENT)

NET FREE VOLUME 1.55 x 10 Ft INITIAL CONDITIONS Pressure 14.7 psia Temperature gO oF RWST Temperature 39 oF Service Hater Temperature 63 oF Outside Temperature 39 oF SPRAY SYSTEM Number of Pumps Operating 2-Runout Flow Rate 1450 gpm Actuation Time 26 sec SAFEGUARDS FAN COOLERS Number of Fan Coolers, Operating Minimum Post Accident Initiation Time for Fan Coolers 26 secs

LARGE BREAK TABLE 3 (Continued)

CONTAINMENT DATA (DRY CONTAINMENT)

STRUCTURAL HEAT SINKS I

TH CKNESS In AREA Ft STEEL 0.03 31,400 STEEL 0.063 107,158 STEEL 0.1,, 56,371 STEEL 0.2 57,185 STEEL 0.24 9,931 STEEL 0.2898) 136,000 CONCRETE 24.0 STEEL 0.4896 23,677 STEEL 0.6396 6,537 STEEL - '.8904 4,915 STEEL 1.256 27,802 STEEL 1.56 5,307

. STEEL 2.0 668 STEEL 2.75 1,268.7 STEEL 5.5 1,277.4 STEEL 9.0 260.4 STAINLESS 0.14 14,392 CONCRETE 24.0

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STAINLESS 0.44 768 STAINLESS 2.126 3,704 STAINLESS 0.007 102,400 CONCRETE 24.0 59,132

TABLE 4 REFLOOD MASS AND ENERGY RELEASES FOR LIMITING CASE DECLG (CD=0 4) AND 10/o STEAM GENERATOR TUBE PLUGGING TIME TOTAL MASS FLOWRATE .TOTAL ENERGY FLOl<RATE (Sec) (LBm/Sec) (10 BTU/SEC) 46.589 0.0 0.0 48.714 0.0415 0.0005 54.286 35.50 0.4614 l

64,436 95.65 1.189 77.136 98.17 1.219 92.136 103.9 1.,280 107.936 220. 9 1. 603 124.236 263. 2 1.678 159.236 274.8 1.607 197.536 281.5 1.514

TABLE 5 BROKEN LOOP ACCUMULATOR FLOW TO CONTAINMENT FOR LIMITING CASE DECLG (CD=0. 4) 10% STEAM GENERATOR TUBE PLUGGING TIME (Sec) MASS FLOWRATE (LBm/Sec) 0.0 0.0 0.02 2723.5 2.00 2276.0 4.00 1994-9 6.00 1793.1 8.00 1645.5 10.0 1526.4 15.0 1302.5 20.0 1137.8 25.0 1034.6 30.0 954.2 35.0 887.0 38.9 842.6

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