RFGULATORY IN~ RtlATION DISTRIBUTION SYSTER'RIDS)

ACCE.'SS ION NBR: 7906050315 DOC, DATE: 79/05/30 NOTARIZED; NO

FACIL:50 335 ST ~ LUCIE PLANTP UNIT 1E FLORIDA POWER K LIGHT CO»

AUTH» NAME AUTHOR AFF IL'I ATIONUHRIGE R»E» FLORIDA POWER 8 LIGHT CO,,

RECIP ~ NAME RECIPIEN f AFFILIATIONREIDE R ~ W» OPERATING REACTORS BRANCH

DOCKET05000335

SUBJECT: NOTIFIES OF REDUCTION IN ALLOWABLE PEAK LINEAR HEAT RATE INACCORDANCE W/790526 8 790527 P ERICKSON TELCON,REDUCTIONNECESSITATES CHANGE EN TECH SPECS, REVISED FIGURES ENCL'

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Office of Nuclear Reactor RegulationAttention: Mr. R. W. Reid, Chief

Operating Reactors Branch 84Division of Operating Reactors

U. S. Nuclear Regulatory CommissionWashington, D. C. 20555

Dear Mr. Reid:

FLORIDA POWER II LIGHT COMPANY

May 3O, 1979L-79-148

Re: St. Lucie Unit 1

Docket No. 50-335C cle 3 ECCS Anal sis

In accordance with our conversation with your Mr. Peter Ericksonon May 26 and 27, 1979, we are reducing the allowable peak linearheat rate for St. Lucie 1 from 14.8 kw/ft to 14.68 kw/ft. Thishas the affect of reducing the fuel average temperature at thepeak linear heat rate from 2197 F (shown in Table 8-1 of the ReloadSafety Evaluation for Cycle 3) to '<2184 F which is the value usedin the reference ECCS analysis described in the Reload SafetyEvaluation for Cycle 2. With this reduction in kw/ft the referenceECCS analysis will envelope all of the input parameters applicableto Cycle 3.

The reduction in allowable peak linear heat rate requires revisionof Figures 3.2-1 and 3.2-2 of the proposed St. Lucie Unit 1

Technical Specifications submitted with the Cycle 3 Reload SafetyEvaluation. The revised figures are attached.

Very truly yours,

Robert E. UhrigVice President

'dvancedSystems & Technology

REU:TCG:cfAttachment

cc: Mr. J. P. O'Reilly, Region IIHarold Reis, Esquire

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Allowable Power Level per Specification 4.2.1.3

St. Lucie - Unit 3/4 2-4't4~~-

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STATE OP PLORXDA ))

COUNTY OP DADE )ss.

E. A. Adomat , being first duly,sworn, deposes and says:

*hLigh.. Company''-he Licensee herein;

of .Florida Power 6

That: he has executed -the foregoing document; that t.he st.at;e-ments made in this said document: are true and correct'o t.hebesh of hi knowledge, informat ion, anQ belie f, anQ that: he i"au'horized to execute the document on behalf of said Licensee

5

E. A. Adomat

Subscribed and sworn to before me this~oday or. ~~ 1a

75'OTARY

PUBLj:C in and for t.he County of Dade,Stat.e of Ploric

NOTA' ASLIC STATR OP FLORIDA at tARGeI 1Y COlAMlSS,ON EXr RES MARCll 27~ 188Z

eely COmmiSSiOn eXpireS GDNDED THRU MAYNARD BONDlNG AGENGY4

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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS>

REC: DAVIS D KNRC

ORG: UHRIG R EFL PWR 8( LIGHT

DOCD ATE: 02f 0 i/78DATE RCVD: 02/06/ 78

I(

DOCTYPE: I ETTER NOTARIZED'O COPIES RECEIVEDSUBJECT: LTR 3 ENCL 3SUPPL TO INITIALRESPONSE RE: LONG TERM COOLING MODES OF OPERATION. fgggg)

PLANT NAME: ST. LUCIE — UNIT i REVIEWER INITIAL: XBTDISTRIBUTOR INITIAL:

«~~+««+~~«««~ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS «««««~~«~«~GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.(DISTRIBUTION CODE A00i)

FOR ACTION:

INTERNAL:

EXTERNAL:

BRANCH CHIEF DAVIS«W/7 ENCL

EG FILE+ W/ENCLI h k«W/2 ENCLHANAUER«W/ENCLE ISENHUT«W/ENCLBAER«W/ENCLGR IMES~~W/ENCLJ. MCGOUGH«W/ENCL

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DISTRIBUTION:SIZE: iP+2P

LTR 25 ENCL CONTROL NBR: 7803703 8

THE END

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P. O. BOX 013100, MIAMI, FL 33101

II)IhIIIIg(IR'II (IIV'fI'flcm< m'

FLORIDA POWER 8( LIGHT COMPANY

February 1, 1978L-78-36

Office of Nuclear Reactor. RegulationAttention: Mr.. Don K. Davis, Acting Chief

Operating Reactors Branch N2Division of Operating Reactors

U. S. Nuclear Regulatory CommissionWashington, 'D.C. "

20555,'ear

Mr. Davis:

i, '(./pPPJ~ ~78~A~~>ISS~>~10~ g

Re: St. Lucie Unit 1Docket No. 50-335Lon Term Coolin (ECCS)

A reply to your September 27, 1977 letter regarding long termcooling modes of operation is attached. Xt supplements ourinitial response of November 2, 1977 (L-77-342) .

Very truly yours,

Robert E. UhrigVice President

REU/MAS/lah

Attachment

cc: Mr. James P. O'Reilly, Region XXRobert Lowenstein, EsquireEd Reeves

'l~780370338

PEOPLE... SERVING PEOPLE

ATTACHMENT

Re: St. Lucie Unit 1Docket No. 50-335Long Term Coolin (ECCS)

Answers to Questions 1, 2, 6 3

These questions do not apply. St. Lucie Unit 1 does not usethe "hot leg suction",method.

Answer to Question 4

Two procedures are used at St. Lucie 1 to assure adequate flowof 'water through the core during a LOCA. Both provide neces-sary cooling as well as sufficient flushing to prevent boronprecipitation. These methods are described in detail inAppendix 6C of the FSAR (pages 6C-4 through 6C-12), and areapproved in Section 6.3.5 of Supplement 2 to the Safety Eval-uation Report. The primary procedure provides for core flushingby low head injection into the shutdown cooling suction line,which is connected to'he hot leg. Hot leg injection in con-junction with existing cold leg injection will establish coreflushing flow for both hot leg and cold leg breaks. The ECCSre-alignment flow path establishes flow from the containmentsump and low pressure safety injection pump to the shutdowncooling bypass (recirculation) line into the shutdown coolingsuction line and hot leg.The alternate or backup procedure is to establish flow intothe hot leg via the pressurizer auxiliary spray line. Coreflushing is provided by diverting a portion of the highpressure safety injection flow through the pressurizer auxil-iary spray line. This occurs in conjunction with existingcold leg injection.Both the primary and the alternate procedures will provideadequate flow for either a hot or cold leg break. The FSARdescribes the procedures, valve line-ups, flow characteristics,and monitoring methods in detail.

Answer to Question 5

The primary or alternate procedure for flushing the core toprevent boron precipitation (as described in Appendix 6C ofthe FSAR) could be used during cooldown and depressurizationof the core after a small LOCA.

After a small LOCA, normal safety injection would cool downthe core until post LOCA recirculation could be established(FSAR Section 6.3). The cooldown would be continued untilsystem conditions were established which would allow hot leg

a~'L 0

~ ~ '. i Attachment 0injection either by the primary or alternate procedure asdiscussed in Appendix 6C of the FSAR, pages 6C-l0 through6C-12a. When the flushing has reduced the boron concentra-tions throughout the core', normal shutdown cooling could beestablished. The temperature and pressure of the system wouldthen be lowered until the vessel head could be removed.

RECEIVED 00CUHFg~CPS I'PPI r ESq

PpN FLg 6 Nn l0 ~8

'.S..',RCDISTBIBIjflOH SEA VICES

BRANCH

NRC FORM 195(2.76)

U.S. NUCLEAR REGUI.ATOR i,iiiiVIISSION)g l

NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL

DOCKET NUMBER50-335

FILE NUMBER

TO: Mr..V. Stello

I7ILETTERI3OR IGINALCleam

Im NOTOR I2 E D

SUNC LASS IF I E D

PROP INPUT FORM

F ROTI: PPLMiami, Pla.

R.E, Uhrig

DATE OF DOCUMENT

7 9-76DATE RECEIVED

7-15-76NUMBER OF COPIES RECEIVED

3 signed 37 CC

DEscRIPTloN Ltr notarized 7-9-76 requests oramdt to Agp. JL fo OL/DPR-67 & trans thefollowing:

ENCLOSURE er ormanceLucie Unit 1,. ~ ~ ~

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(40 cys'encl rec,'d) '

esu s o

PLANT NAME: St. Lucie Unit,l w ~

SAPETYASSIGNED AD:

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DHL 7«16~'l6FOR ACTION/INFORMATION"ASSX NED

D'NQjWQI55i i

~ - i BRANCH CHEEP:~PROACT MANAGER:LIC~ ASST

~ ~1 ~ 'P 0 NA T) hT PTi Xfi. i'i7

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SCHROEDER

ENGXNEERINGMACCARRYKNIGHT'',SIHIJEILPAMLICKX~

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OPERATING REACTORS

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PROJECT MANAGEMENTBOYDP COLLINSHOUSTON .,

PETERSON? IELTZHELTEMESSKOVHOLT

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REACTOR SAPE'EY

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EXTERNAL DISTRIBUTION+AT LAB:

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OPERA+:NCH'ISENII

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BROOKHAVEN NAULRIKSON ORNL

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CONTROL NUMBER

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July 9, 1976

gegIIletoryocket filf Qg)

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Director of Nuclear Rea gulationAttn: Mr. Victor Stello, Director

Division of Operating ReactorsU. S. Nuclear Regulatory CommissionWashington D. C. 20555

' ~crrAe +oorArogy,U.e.

COMI~Iee IOII+oII goalog

Dear Mr. Stello:Re: St. Lucie Unit No. 1 — Docket. No. 50-335

Pro osed Amendment to Facilit 0 crating License DPR-67

In accordance with 10 CFR 50.30, Florida Power 6 LightCompany submits herewith three (3) signed originals and forty(40) conformed copies of a request to amend Appendix A ofFacility Operating License DPR-67.

This proposal is 'being submitted in response to provisions(1) and (2) of the Office of Nuclear Reactor Regulation'sJune 17, 1976, Order for Modification of License in thematter of Florida Power 6 Light Company. A reanalysis ofSt. Lucie Unit No. 1 ECCS performance has been performed,using the corrected version of the STRII(IN-II computer code.The analysis demonstrates that the allowable peak linear heatgeneration rate (PLHGR) that meets the NRC Acceptance Cri-teria published in the Federal Register on January 4, 1974,is 14.8 kw/ft. The analysis was performed for full poweroperation using reduced system flow (134.06 x 10 lb/hrcorresponding to 354,000 gpm). A summary of the analysis isattached in support of the requested Technical Specificationchange.

The proposed amendment is as described below, and as shownon the attached Technical Specification page bearing the dateof this letter in the lower right, hand corner.

Pa e 3/4 2-3

Figure 3.2-1 is revised to show a new allowable peaklinear heat generation rate of 14.8 kw/ft.

The proposed amendment has been reviewed and the conclusionreached that it does not involve a significant hazard con-sideration, therefore, prenoticing pursuant to 10 CFR 2.105

'7IXS

HELPING BUILD FLORIDA

I~ I

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I

i

~ ~

To: Mr. Victor StelloRe: St. Lucie Unit No. 1

Docket No. 50-335

July 9, 1976Page -2-

should not be required. The St. Lucie Unit, 1 ECCS Perfor-mance Results are attached in support of the proposed change.

Very truly yours,

obert E. UhrigVice President

REU/NR/hlc

Attachment

cc: Norman C. Moseley, Region IIJack R. Newman, Esq.

I

C)~ MPl 16

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'

r

St. Lucie Unit 1 ECCS Performance Results

I. Introduction

This reanalysis of the St. Lucie Unit 1 ECCS Performance has been performed

with the corrections made to the STRIKIN-II computer code (Reference 3). This

reanalysis supercedes the ECCS evaluations Ahich appear in'eferences 4 and 5.-\

I

The analysis documented herein consists of a six-break spectrum analyzed ata peak linear heat generation rate '(PLHGR) of'14.8 kw/ft for a core-average

burn-up greater than 500 jgmpm. This analysis was performed using the reduced

system flow of 134.06x10 lb/hr. The most limiting break was identified as the*

0 8 DES/PD at a PLHGR of 14.8 kw/ft.

The results of this analysis demonstrate that the ECCS for St. Lucie Unit 1

meets the NRC Acceptance Criteria published in the Federal Register on

. January 4, 1974. Conformance is summarized as follows:l

Criterion (1) Peak Clad Tem erature., "The calculated maximum fuel element

cladding temperature shall not exceed 2200 F."I

The analysis yielded a peak clad temperature of2181 F for' 'he 0.8 DES/PD break.

t C

Criterion (2) Maximum Claddin Oxidation. "The calculated total oxidation~ of the cladding shall nowhere exceed 17~ of the total cladding

thickness'before oxidation."~,,

I

The analysis yielded a local peak clad oxidation percentage

of 13 A for the 1.0 DEG/PD break.

*0.8 DES(PD = 0.8 Double-EndedSlot At the Pump Discharge

Criterion (3) Maximum H dro en Generation. "The calculated total amount

of hydrogen generated from the chemical reaction of thecladding with water or steam shall not exceed 15 'of the

.hypothetical amount that would be generated if all of themetal in the cladding cylinders surrounding the fuel,excluding the cladding surrounding the plenum volume, were

to react".

The analysis yielded a peak core-wide oxidation percentage,of <0.855 for the 0.8 DEG/PD break.

The statements in Reference 5 demonstrating compliance with Criterion 4

(eoolable geometry) .and Criterion' (long term cooling) are unchanged.

III. Lar e Break S ectrum Anal sis

A. Method of Calculation

The C-E large break evaluation model which was used is documented inReferences 1 and 2 and is the same as that used in the spectrum analysis reportedin Reference 5. 'he only differences between this analysis and

that in Reference 5, besides the use of the corrected STRIKIN-II version, arethe incorporation of new refill information and the use of the PARCH (Reference 6)computer code to generate steam cooling heat transfer coefficients., The

description of the procedure used with the PARCH code is detailed in SectionS.III.D.6.b of Referen=e l.

~ = The analyses reported in References 4 and 5 used a minimum convective heattransfer coefficient of 5.0 BTU/hr- F-ft duting the steam cooling portion of thetransient, for the rupture elevation and above. Due to the importance placed on

the rupture location by the corrected STRIKIN-II code, the PARCH code was

employed to generate more realistic time-dependent steam cooling heat transfercoefficients. The PARCH heat transfer coefficients were then used in STRIKIN-IIonly for the rupture location. For elevations above rupture, the minimum value .

of 5.0 BTU/hr- F-ft was still used.o 2

" ~W'A >~1 ~Y

B. Emer enc Core C in S stem Assum tionsr )

The ECCS assumptions are the same as those stated in Reference 5.

Incorporation of updated ECCS system hardware data necessitated

performing a COHPERC-II analysis to find new refill characteristics. tlost

significant of the changes was a 'reduction in the safety injection line loss

coefficient. Reflood behavior was not affected by the changes and is the same as

'sed in the earlier analyses (References 4 and 5).C. Core, S stem, and Containment Parameters

I

The parameters are the same as those given in Reference 5 with the~ exception of the .parameters which are related to PLHGR and core 'flow. The

parameters which have changed are shown in Table- III-.1.

0. Break S ectrum

All of the breaks analyzed in References 4 and 5 have been repeated ata PLHGR-of- 14.8-kw/ft. The plant has already undergone a core average burn-up

« 500 ->>/l~. ITherefore, the'orst radiation enclosure was chosen -from(I)

those which occur after this burn-up. -Calculations have been performed for both „

1.. '

guillotine and slot breaks at the pump discharge over a range of break sizes

varying frcm 60/ to 100K of the double-ended cold leg pipe area.4 j,.

E. Results

The blowdown and reflood results are unchanged and can be obtained from

References 4 and 5. Table III-2 contains a list of the STRIKIN-II variablest

'lotted for each break. The times of interest for each of the breaks are

reported in'able III-3..Table III-4 contains a summary of the peak clad

, temperatures and oxidation percentages for the break spectrum. Figure III-13shows peak clad temperature plotted versus break size and type, indicating

that the worst break is the 0.8 DES/PD rupture;

F. Com uter Code Version Identification

The following code versions were used in this analysis:

COHPERC-II

STRIKIN-IIPARCH

Version 75097

Version 76161

Version 75206

Cff

IY. Concl us ions

Based on the considerations of this reanalysis of the St. Lucie Unit 1

ECCS performance, we have concluded that:

1) because the changes do not involve a significant increase inthe probability or consequences of accidents previously con-sidered and do not involve a significant decrease in a safetymargin, the changes do not involve a significant hazards con-

sideration;

2) there is reasonable assurance that the health and safetyof the public will not be endangered by operation in theproposed manner; and

3) such activities will be conducted in compliance with the'ommission's regulations and the issuance of this amendment

will not be inimical to the cordon defense and security,or to the health and safety of the public.

O.

w r.

REFERENCES

1. CENPD-132, "Calculative Methods for the C-E Large Break LOCA Evaluation

Model", August, 1974 (Proprietary).

CENPD-132, Supplement 1, "Updated Calculative Methods for'the C-E Large

Break LOCA Evaluation Model",,December, 1974 (Proprietary).

2. CENPD-132, Supplement 2, "Calculational Methods for the C-E Large Break

LOCA Evaluation Model", July, 1975 (Proprietary).H

3. CENPD-135, Supplement 4, "STRIKIN-II, A Cylindrical Geometry Fuel Rod

Heat Transfer Program, (June, 1976 Modification)",June, 1976, (Proprietary).P

4.'etter, R. E. Uhrig (FPL) to Y. Stello (NRC), "St. Lucie Plant Unit 1,

Docket No. 50-335,Proposed Amendment to Facility Operating License DPR-67",

May 14, 1976.

5. Safety Injection System Analysis of St. Lucie Unit 1 for FSAR, Section 6.3.3.6as amended by Revision No. 55, February 9, 1976.

6. CENPD-138, "PARCH-A FORTRAN IV Digital Computer Program to Evaluate Pool-

Boiling Axial Rod and Coolant Heatup", August, 1974 (Proprietary).

TABLE II I-1

General System Parameters

uantit

~ Peak Linear Heat Generation Rate (PLHGR)

=Gap Conductance at PLHGR

Fuel Centerline Temperature at PLHGR

Fuel Average Temperature at PLHGR

System Flow Rate (Total)Core Flow Rate

'Ya1ue .

14.8

760.4

3882.5

2573.6

134.06xl0129.4xl0

- kw/ft. "'TU/hr-ft - F

0F

0F

1 bs/hr1 bs/hr

TABLE III-2

St. Lucie Unit 1

Large Break Spectrum Plots

Break Size, T e and Location PlotFigureNumber

1.0 x Double-Ended Slot Break inPump Discharge Leg (1.0 x DES/PD)

0.8 x Double-Ended Slot Break inPump Discharge Leg (0. 8 x DES/PD)

Peak Clad Temperature

Peak Clad Temperature

Local Clad Oxidation

Hot Spot- Gap Conductance

Clad, Fuel Centerline, FuelAverage and Coolant Temper-ature for the Hottest Node

III-1

III-2

III-3III-4

III-6Hot Spot Heat TransferCoefficient

Hot Spot Heat Transferefficie t Durin Reflood

III-7Co n g

Hot Rod Internal Gas Pressure III-80.6 x Double-Ended Slot Break inPump Discharge Leg (0.6 x DES/PD)

1.0 x Double-Ended Guillotine Breakin Pump Discharge Leg (1.0 x DEG/PD)

0.8 x Double-Ended Guillotine Breakin Pump Discharge Leg (0.8 x DEG/PD)

0-6 x Double-Ended Guillotine Breakin Pump Discharge Leg (0.6 x DEG/PD)

Peak Clad Temperature

Peak Clad Temperature

Peak Clad Temperature

Peak Clad Temperature

III-9

III-10

III-ll

III-1 2

~,

1

TABLE III-3Times of Interest for Each Large Break (PLHGR = 14.8 kw/ft)

(Seconds)

Break

1.0 x DES/PD

0.8 x DES/PD

0.6 x DES/PD

Hot Rod~Ru ture

10.1

9.9

10. 5

SI Tankson

17.3

17. 6

19.3

,Start ofRef lood

~ 35.4

35.8

37.5

SI Tanks~Em t

~63.0

~63.4

~65. 2

1.0 x'EG/PD

0.8 x DEG/PD

0.6 x DEG/PD

10.2

10.1

29.1

17.4

17.9

20.1

35.5

36.1

38.4

&3.1n 63.7

~66.0

.4TABLE III-4

Peak Clad Temperatures and Oxidation Percentages

for the Break Spectrum at a PLHGR of 14.8 kw/ft

BreakPeak Clad

Tem erature F

Clad Oxidation'ALocal . Core-Mide

1.0 DES/PD

0.8 DES/PD

0.6 DES/PD

2148

*2181 .

2080

13.1 '"

12.3 .

<.803 ~

. <..795.

<..727'

1.0 DEG/PD

0.8 DEG/PD

0.6 DEG/PD

2139

2129

1937

1,3.413.3

'.6

. <.828'..

'<.850,<.565 .

-z.z.a 0

Frauen I II-3sv ncrF. t4

j.,O x DOUBLE ENDED SLOT BREAK IN PUf'JP DISCHARGE LEG

PEAK CLAD TB'IPERATURE

P000

3.800

3.600 r ~

4

3.40 0

~ p

\ ~

rr

'2.00

.'

~

l000

800

4'

rI

- L. 'r

600

'% h

~ — I

4000 30010 0 .2.0 0

TIr<E, SECONDS

400 500 600

'

2.2.0 0

2000

1800

3600

3400

12.0 0

i'al00 0

800

600

4000

FIGURE III-7sr Luc|E 4

0,8 x DOUBLE ENDED SLOT BREAK IN PUNP DISCHARGE LEG

PEAK CLAD TPlPERATURE

~ r

~ I

~ 4 1 ' '

~ ',i I

r ew ~,

~ ~

\r

~ J,

r

r ~ ~~ ~ '

r ~

'.4

00200 '00TINE, 'ECONDS

300 500 600

5

70(

FreuaE lI1-3

~ ST LUCtE~.0,8 x DOUBLE EldDED SLOT BREAKTi9 PUl'lP DISClIRGE LEG

LOCAL CLAD OXIDATION

~'

h h ~

100 2.00 300TINE, SECONDS

500 800

'j.8 0 0

~ 0

~ Ftsuna III'T

LUCIE0.8 x DOUBLE ENDED SLOT BREAK IN PVNP DISCHARGE LEG

HOT SPOT GAP CONDUCTANCE

1800

1400

1P 00

~.10000

h

800

I=

8>, ~,

800zC>

~~-~ oo

2.0 0

00 100... 200 . 300

TIf'lE, SECONDS

400 500 600

4500

4000

Fr6unc II -5ST LUCI-

0,8 x DOUBI E ENDED SLOT BREAK IN PUi']P DISCHARGE LEG

CLAD TENPERATURE, CENTERLINE FUEL TEI'JPERATURE. AVERAGE

FUEL TEMPERATURE AND COOLANT TEJ'CPERATURE FOR HOTTEST NODE

3500

3000

'

~ ~

2.50 0

FUEL CEi jTERLINE

~Z000~l

I

. 1500AYERAGE .F EL

CLAD

1000

'COOLANT

500

0100 200 300

,-, TINE, SECONDS

400 500 600

,0 ~

360

F<eunE III-6~ ST LUCIE

. O,8 x DOUBLE ENDED SLOT BREAK IN PUHP DISCHARGE LEG

HOT SPOT HEAT TRANSFER COEFFICIENT

j 2.0

j00

LU

U

UJCD

80

BO

40

00 100 200 300

TIt'lE, SECQNQS

400 500 600

~ FIsui:c III-7ST LUCIE I

0,8 x DOUBLE ENDED SLOT BREAK IN PUHP DISCHARGE LEG .

HOT SPOT HEAT TRANSFER COEFFICIENT DURING REFLOOD

60

O

50l

00

30'

20

10

00 100 200 300 400

TINE, SECONDS

500 600 700

1000

FIGURE III"8ST LUCIE I

0,8 x DOUBLE ENDED SLOT BREAK IN PUYIP DISCHARGE LEG

HOT ROD INTERNAL GAS PRESSURE

1200 INITIAL

1000

RUPTURE=9,93 SEC

e

600

e

200

00 20 00. .60 80 j.00

TILL', SECONDS

2200

~ Froude III-9QST LUCIE I

0,6 x DOUBLE ENDED SLOT BREAK IN PUJ'JP DISCHARGE LEG

PEAK CLADTEMPERATURE'00

j.80

4

l60

10C

120

1000

600 3.00 200 300 400

TIr<E, SECONDS

500 600 700

'","2.2.'D 0

FIGURE IIX-3.0

ST LUCIE

1.0 x DO LE ENDED GUILLOTINE BREA IN PUPlP DISCHARGE LEG

PEAK CLAD, TEHPERATURE

2.0 00

3800

h

h

h

1600

3.4 00

'

~P

~j 2.00

h ~

y j000'00

SOO

400F00 200 300

TINE, SECONDS

400 500 600.

22.00

2000

3.600

1.4 00

g12.0 0

i.ol

~>000

O

800

800

4000

t ~

FrGuRE IIIST LUCIE

0,8 x DOUBLE ENDED GUILLOTINE BREAK II'> PUf]P DISCHARGE LEG

PEAK CLAD TEMPERATURE

t

~ ~ ~hh

I'"

yJ'

t,

t

f

~'I~ ~ It ~ ", ~~,',

) ~h

t ~ ~ ~

J

4- *t ~

t

h

400 500200 300TIf'lE, SECONDS

100 600

2200

FIGURE I I I-12 ~r ST LUCIE I

0. 6 x DOUBLE ENDED GUILLOTINE BREAK IN PUf<jP DISCHARGE LEG

PEAK CLAD TEf']PERATURE

2000

j.800

~ ~

- j.600

u j000CtCC

'

i~

*~

3.200

j.000

800

6000 j.00 200 500 400

i If'iE, SECONDS

500 600 700

E

Fr|'uRc III-15 " .'

ST LUCIE IPEAK CLAD TEMPERATURE vs BREAK AREA

2200 0Q

2000

1800.

1600

~ - 0 -DISCHARGE LEG SLOTS

C3 DISCHARGE LEG GUILLOTINES

1000 —..

12000 2.

DISCHARGE LEG BREAKS

0,6 DE, 0,8 DE . 1,0 DE .

6

BREAK AREA, FT2~ ~

I

p ~

STATE OF FLORXDA ))

COUNTY OF DADE )

ss

Robert E. Uhrig, being first duly sworn, deposes and says:

That he's 'a Vice President of Florida Power E Light Company,the Licensee herein;

That he has executed'he foregoing document; that the state-ments made in this said document are true and correct,to thebest of his knowledge, information and belief,'nd that. he isauthorized to execute the document. on behalf of said Licen'see.

Robert E. Uhrig

Subscribed and sworn to before me

this day of 1976

ary Public, in aSt'ate of Florida

,'" g)'a

< My, commission expires:

for the County of Dade,tVOIART PU8LfC STATE OF FI.ORIDA AT EAA EARGE

R

Y COMMISSION EXPIRES NOV. 3ONDED THRU CANER>l INS. UNDERWRITERS

e.. I 4 ~ 0

I'

NRC D . IBUTION FOR PART GO DOCKE TEBlAL(TEMPORAIEY FORM)

CONTROL NO:

FILE

FROM: Flordia Power 6c Light Co.Miami, Fla. 33101

. ~ 1- 2-76 1-33-76

DATE OF DOC DATE R EC'D LTR TWX RPT OTHER

TO:

Mr. 0. D. ParrCLASS UNCLASS PROP INFO.

XXX

ORIG

3 si nedINPUT

CC OTHER

37NO CYS REC'D

40

SENTNRC PDR

SENT LOCAL PDR

DOCKET NO:

. 50-335

DESCRIPTION: Ltr trans the following:

DISTRIBUTION PER H. ROOD 1«23 "76

ENC LOSU R ES: St. Lucie Unit 1 ECCS PerformanceResults 6c Isolated Safety In)ection'-Tank

Study N ~ ~ ~

(40 cys encl rec'.d)

PLANT NAME: St. Lucie Unit. 1-

SAFETY

ASSIGNED AD DEYOUNG L,

ARANCH CIIIEF PARR

/'AROJE('T MANAGER

FOR ACTION/INFC:RMATIOASSIGN'ED BRANCH CHIEF

PROJECT MANAGER

LIC ASST.

MIIo~hgDHL 1-24-76

IlI/ ACRS

FLIC, ASST, GOULBOURNELWR

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INTERNAL ISTRIBUTION(EG FILESRC

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PROJECT MANAGEMENTBOYO

P. COLLXNSHOUSTONPETERSONMELTZHELTEMES

SYSTEMS SAFETYIE INEIAN

SCHROEDER

ENGlNEERlNGMACCARYKNIGIITSXHME'ILPAIi'LICKX

REACTOR SAFETYaAOSSSLOVAK$%0SZTOCZY+HECK

PLANT SYSTEMSTEDESCOBENAROYALAXNASIPPOLITO

OPERATING REACTORS+TELLO

SXTE SAFETY 6 ENVlRO ANALYSISDENTON MULLER

ENvlRO TECH.ERNSTBALLARDSPANGLER

SXTP TECH.

S1TE ANALYSISVOLLMERBUNCHJ. COLLINSKREGER

,~ATMSALTZMAN.RUTBERG

OPERATlNG TECH. GiQ!MILL+ISENHUT sTEPP

SHAO HULMANySAER

S CElxENCER flSCELLANEOUSGRIMES e Hzah eEXTEr(NALDISl'R I BUTION

tlat.OCAL PDR Ft ~ Pierce, Fla.TICNSICASLB

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FLORIDA POWER 8E UGHT COMPANY

January 12, 1976L-76-8

'

Director of Nuclear Reactor ReATTN: Mr. Olan D. Parr, Chief

Light Mater ReactorsProj ect Branch 1-3

Division of Project ManagementU. S. Nuclear Regulatory Commissionwashington, D. C. 20555

Dear Mr. Parr:

geguiatary D00iIet .il

cn

efg ((g"~AND@ ty6,

Re: St. Lucie Unit No. 1 - Docket No. 50-335Technical S ecifications

Our letter L-75-482 dated October 7, 1975 at item 29 requestedchanges to the proposed Technical Specifications which wouldallow power operation with one Safety Injection Tank (SIT)isolated. Discussions with your Staff indicated that an ECCSFAC analysis would be required to support our request. The

'equisiteanalysis has been performed and is submitted herewith.The analysis, which was performed utilizing more recent modelsthan the original, indicates (1) an allowable peak linear heatrate of 15.8 kw/ft (revised technical specification figure 3.2-1is also attached) and (2) that full power operation with one SITisolated is acceptable. Accordingly, we request that the technicalspecifications be revised to reflect the results of the ECCS analysis.

Very uly yours,

Robert E. UhrigVice President

REU: nchAttach.cc: Jack R. Newman, Esq.

HELPING BUILD FLORIDA

tE

IIf

"1tt@

~ "4 - ~ ~'-'

~/NRC. TRIBUTION FOR PART 50 DOCK ATERIAL

(TEMPORARY FORM)CONTROL NO:

FILE'ROM

Florida Powex C; Light Co.lliami, Fla,.Robert E. Uhri

DATE OF DOC DATE REC'D LTR rwx RPT OTHER

Olan D.PaxrORIG

3 SignedCC OTHER SENT NRC PDR

SENT LOCAL PDR

CLASS UNCLASSZnXX

PROP INFO INPUT NO CYS REC'D DOCKET NO:

50-335DESCR IPTION:Ltx xe our ltr of 6-3-75 6 7-3-75 and theirltx. of 6-i7-75...Advising info xequested con

corning ECCS analysis will be furnished duxinweel: of 8-l1.»75 as an amd' t:o St. Lucie 0 1.

FSARe ~ ~ e ~ e

ENCLOSURES

PLANTNAME: St. Lucie 0 iFOR ACTION/INFORMATION

BUTLER (L)W/ Copies

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E TERNAL DISTRIBUTION

~1 —LOCAL PDR ~

~'l.—TIC (ABERNATHY) (1)(2)('IO) —NATIONALLABS 1 —PD R-SAN/LA/NY~1. —NSIC (BUCHANAN) 1 —W. PENNINGTON, Rm E-201 GT 1 —BROOKHAVEN NAT LAB

1-RSVP B ,1 —CONSULTANTS 1 —G. ULRIKSON ORNL1 —Newton Anderson ~ i ~ NEWMARK/BLUME/AGBABIAN

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Mr. Olan D. Paxr, ChiefLight Water Reactors

'Proj ect Branch 1-3Division of Reactor LicensingOffice ofNuclear Reactor RegulationU ~ S. Nuclear Regulatory CommissionWashington, D. C. 20555

Dear Mr. Parr:

CrrBErorBEO+Q 0 IBg00I,013100 MIAMI 330010A 03101

~ =:.5eFLORIOA POWER 83 LIGHT COMPANY

August 1, 1975-'5-382

bocerroIrsrrrrC

»Ge ~stQ3E,

rroCIBE Cr g 8

Re: ECCS InformationSt. Lucie Unit No. 1Dock'e't'o". " '50'.-'3'3'5'

Your letter of June. 3," 1975, reques'ted additional informationconcerning the ECCS analyses'ox St.'ucie Unit No. 1. My letterof June 27, 1975, advised you that, with 'the exception of informationpertaining to idle 'loop operation, all information requested wouldbe furnished during the''week of July 14. It now 'appeaxs that thisinformation wi'll be 'furnished to you as an amendment (Rev'. 48) tothe St, Lucie Unit No. 1 FSAR during the week of August ll, 1975

'ourletter. of July 3, 1975, requested that FPL rev'iew'he attachedinformation criter'ia and advise you if we'onsidered our submittalto be complete,'r, if necessary, our schedule for submittal ofadditional information. The status of the information indicatedis as follows:

l. 'reak 'S''ctrum an'd'a'rtia'1''oo 0 'e'x'a'ti'on — This information wille'comp ete wx.t t e su mx:tta o ev. , which will xeference

the Millstone 'Application, during the week of August ll, 1975.1

2.-'ote'ntial Eo'ro'n Pr'e'ci''itation — See response to 1above.'.

" S'i'n'e Fai.'1'ure''Anal 'sis - Thi;s 'information wi'll be completewxt t e su mitta o ev.,48 during the 'week of August ll, 1975.

4. 'ubm'e'r 'e'd'a'1ves'-'- This information is complete.'ee Rev. 47 tot e t. ucz.e Unit No. 1 FSAR, dated July 9, 1975.

HELPING BUILD FLORIDA~

I

I A

I

I

'0cg

, II'lIE 4

.l

C

Ar. Olan D, Pagr, August 1, 1975

5. 'Conta'inm'e'nt'r'e's'sure '- Information concerning the parameters usedzn t e containment pressure analysis was "previously submitted inRev'. 27 to the FSAR, dated June 26, 1974,. in response to Staffquestion 6,26. The's'e 'paramet'ers are believ'ed to have 'beensufficiently conser'vative 'with 'res'pect 'to the "ECCS 'analysis.In response to your information request 'of June 3, 1975, revisedcontainment parameter's for St', Lucie 'Unit No. 1 will be providedin Rev', 48 to the St, Lucie Unit No, 1 FSAR. The 'effects of anychanges in thes'e "par'ametexs upon the 'containment pressure analysiswi,ll be"'.ev'aluated and wi;11 also be 'addressed in Rev. 48. In viewof the consexvative 'manner in whi.'ch this analysis was previouslyperfoxmed, it is not exp'ected that'hanges'n the'se 'containmentparameter's will alter'he'onclusions of the prev'ious.-analysis.This information wi;11 be complete with 'the submittal of Rev. 48during the 'week of August ll, 1975,

\ f

Yours, pery truly,

/w A~Robert E, UhxigVice Pxesident

REU:nch

c'c: Jack 'R., New'man, Esquire "-

F

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0- ~NRC DISTRIBUTION FOR PART 50 DOCKFT MATERIAL

(TEMPO BAR Y FO RM)

CONTROL NO: ~ Z 5 ~FILE

FROM ~ Florida Power 6 LightMiami, FlaR-E Uhri

''ATE OF DOC

. 6-27-75

DATE R EC'D

7-8-75

LTR

XX

TWX RPT OTHER

Mr Parr

CLASS UNCLASS

DESCR IPTION:

PROPINFO

ORIGone signed

INPUT

CC OTHER

NO CYS REC'D

1

ENCLOSURES:

SENT bRC PDR

SENT LOCAL PDR

~ DOCKET NO:

50-335

. Ltr re our 6-3-7 ltr....advising thatthey will submitt ECCS analysis by theweek of 7»14-75......

PLANT NAME: St Lucie Ol

~5.ACKNOWLEDGED

50 50T REMOXR

FOR ACTION/INFORMATION ~ 7-8-75 'h'fBUTLER (L)

W/ CopiesCLARK (L)

W/ CopiesPARR (L)< W/'ICopiesKNIEI (L)

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SCHWENCER (L)W/ Copies

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YOUNGB LOODW/ Copies

REGAN (E)W/ Copies

LEAR (I.) .W/ Copies

SPXESW/ Copies

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INTERiXALDISTRIBUTION

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. PLANSMCDONALDCHAP IVIANDUBE {Ltr)E. COUPEPETERSONHARTFIELD (2)KLECKEREISENHUTWlG G I k'TON

EXTERNAL DISTRIBUTION~1 —LOCAL PD R Ed~ca c c ir 1 —TIC (ABERNATHY) (l)(2)(10) —NATIONALLABSr1 —NSIC (BUCHANAN) ~ 1 —W. PENN(NGTON, Rrn E-201 GT

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~ /- ACRS I%94E~/SENTVc7 a, g. uJ /s > ~

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P. O. BOX 013100, MIAMI, FLORIDA 33101

FLORIDA POWER 8L UGHT COMPANY

June 27-, 1975L-,75.-319

Mr. Olan D. Parr, Chi;efLight Water Reactors

Pxoject Branch 1;3Division of Reactor LicensingOffice of Nuclear Reactor RegulationU. S. Nuclear Regulatory CommissionWashington, D. C. 20555

Dear Mr. Parr:

ayftt)~ ', .

'il% ~

t11 /j~t tt Eg~&+

Re: Submittal of Additional ECCS Information'St. Lu'c'ie'n'i:t'o'. "1 (D'ocket'0-'3'3'5') ''

Your letter of June 3, 1975, requested that Florida Power 6Light Company advise you of the date by whi;ch we propose tosubmit additional information regarding the ECCS analysisfor St. Lucie Unit No. 1 if we could not provide 'it byJuly 3, 1975.

We have been advised by our NSSS, vendor and thearchitect-'ngineerthat the information requested cannot be developed

in time 'to support a July. 3, 1975 submittal. With the excep-tion of information item 6.30, all information requested willbe submitted prior to ox during the week of July 14. Item 6.30of your letter requests idle 'loop ECCS calculations and requiresadditional'odel development. It is being treated as a genericissue and we 'have not yet been advised of a schedule by. ourvendor.

You very truly,

Robert E. UhrigVice President

REU:WHR:nc,h'c:

Jack R. Newman, Esquire

id't0CKETtO

QPIIRc

JUL 5'1975mQ U.S. UAKhR ttfGUlAT

COMMlaa~ttMalt

7255

HELPING BUILD FLORIDA

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ROM. Florida Power 6 Light Co DATE OF DOCMiami, FlaR E Uhri 3-25-75

DATE R EC'D

4-l-75LTR TWX RPT OTHER

TO:

CLASS

Mr Parr

UNCLASS PROP INFO

ORIGone singed

INPUT

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DESCRIPTION ENCLOSURES:

Ltr re our 3-20-75 ltr....furnishing schedulinfo with regard to ECCS analysis....—

ng

I@0 ~R|I P„'@IVtG~E

PLANT NAME: St Lucie 1 6 2

FOR ACTION/INFORMATION 0-X-75 ehfBUTLER (L)

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SCHWENCER (L)W/ Copies

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INTERNALDISTRIBUTIONt

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COUPEPETERSONHARTFIELD (2)KLECKEREISENHUTWlG G I N TONVAR("4

EXTERNAL DISTRIBUTION

wl —LOCAL P D R Pk~vc.4 q F a~1 —T!C (ABERNATHY) (1)(2)(10) —NATIONALLABS~1 —NSIC (BUCHANAN) 1 —W. PENNINGTON, Rm E-201 GT

1 —ASLB 1 —CONSULTANTS1 —Newton Anderson NEWMARK/BLUiVlE/AG GAB IAN

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C(/1 —P D R.SAN7LA/NY1 —BROQKHAVEN NAT LAB1 —G. ULR IKSON, ORi~IL1 —AGMED (RUTH GUSSMAiN)

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Mr. Olan D. Parr, Chi'ef'ight'aterReactors

Project Branch 1.-3'ivisionof Reactor Licensing

Office "of Nuclear Reactor RegulationU. S. Nuclear Regulatory CommissionWashington, D. CD 20555

P 0 BOX 013100~ MIAMI~ FLORIDA 33101

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C3FLORIDA POWER 8L LIGHT COMPANY

March '25; 1975L-75-148

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Dear Mr. Parr:

Re ''Sub'mi't't'a'1''o'f ECCS''An'al''si's'o'r St." Luc'ie Units''1'nd '2

We 'are 'in'- receipt of your let'ter of March '20, 1975, requestingsubmittal 'dates 'for the 'subj'.ect analyses'. Florida Power 6 'LightCompany's schedule for submittal of the ECCS analysis req'uix'edby; 10 'CFR, 50,46 for St; Lucie Units '1 and 2 has bein reevaluatedin light'f the current status of analytical model approvaldiscussions with 'the''Staff. On thi;s basis, we''presently foreseesubmittal of the requisite 'analytical res'ults as follows;

Unit 1 - Week of April 7, 1975Unit 2 - Week of May 26, 1975

The information for Unit No. 1 regarding techniques'or monitoringpower distribution and evaluating setpoint 1'imits will be submittedapproximately two (2) weeks after submittal of the 10 CFR 50.46analysis.

Your ery truly,

Robert E. UhrigVice President

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cc: Jack R. Newman, Esq.Norman A. Coll, Esq.Mr. Martin H. Hodder

gQRIHELPING BUILD FLOR IDA

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