REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)DISTRIBUTION FOR INCOMING MATERIAL 50-250

REC: SCHWENCER A ORG: UHRIG R E DOCDATE: 04/04/78NRC'LPWR 8. LIGHT DATE RCVD: 04/10/78

DOCTYPE:'ETTER NOTARIZED: NO COPIES RECEIVEDSUBJECT: LTR 3 ENCL 3FORWARDlNG CONSIDERABLE INFO ON THE OPERATING HISTORY OF THE STEAM GENERATORSAT UNIT 3. IN ACCORDANCE WITH APPLICANT"S LTR DTD 03/01/78... W/ATT LISTING OFOTHER APPLICANT"S LTRS TO COMMISSION ON THE SAME SUBJECTS AND SUPPORTINGENCLS.

PLANT NAME: TURKEY PT 83 REVIEWER INITIAL: XJMDISTRIBUTOR INITIAL:

DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS

RESPONSES TO STEAM GENERATOR QUESTIONNARE(DISTRIBUTION CODE A023)

FOR ACTION:

INTERNAL:

EXTERNAL:

BR CHIEF~ -WENCER++W/7 ENCL

"REG FILE++W/ENCLI h=-~~WZ~IWQHANAUER++W/ENCLSHAO~~~W/ENCLBUTLER++M/ENCLJ COLLINS<4~W/ENCL

LPDR SMIAMIi FL++W/ENCL

TIC~>+W/ENCLNS IC++W/ENCLRON GAMBLE44W/6 ENCLKEN HERRING++M/6 ENCLACRS CAT B44W/16 ENCL

NRC PDR++W/ENCLOELD+4W/ENCLE ISKNHUT+>W/ENCLBAER4+W/ENCLGR IMES++M/ENCL

DISTRIBUTION: LTR 50 ENCL 50SIZE: 1 P+20P+3P

CONTROL NBR: 780100015

THE END

. O. BOX 013100, MIAMI, FL 33101

FLORIOA POWER & LIGHT COMPANY

April 4, 1978L-78-117

g ggt.~ g(m7<

Office of Nuclear Reactor Regulation ,1,0 llAttention: Mr. A. Schwencer, Chief

Operating Reactors Branch gl RECOVfoDivision of Operating Reactors

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

Dear Mr. Schwencer:

APQ tp )y,

Ctf~CO~ISS

Re: Turkey Point Unit 3Docket No. 50-250Steam Generator Information

In accordance with our letter of March 1, 1978 (L-78-78),considerable information on the operating history of thesteam generators at Turkey Point Unit 3 is attached asAppendix A. A listing of other Florida Power & LightCompany letters to the Commission on the same subject isattached as Appendix B.

Very ly yours,

Robert E. UhrigVice President

REU/MAS/ms

Attachments

cc: Mr. James P. O'Reilly, Region IIRobert Lowenstein, Esquire

78OiOOOi5

PEOPLE... SERVING PEOPLE

f

Re: Turkey Point Unit 3Docket No. 50-250Steam Generator Information

APPENDIX A

STEAM GEHERATQP, OPERATING

HISTORY (|UESTIONHAIRE

NOTE: All percentages should be reported to four significant figures.

I. BASIC PLANT INFORMATION

Plant Turkey Point Unit 3'I

Startup Date: October 20, 1972 (initial criticality)Utility: Florida Power &, Light Company

Plant Location: 8 miles east of Florida City, FloridaThermal Power Level: 2200 Mwt

Nuclear .Steam SuPPly System (HSSS) Supplier WestinghouseNumber of Loops:

'-Steam Generator Supplier, Model Ho. and Type.: Westinghouse 044 series,

vertical steam generatorNumber of Tubes Per Generator:

Tube Size and Material: 0.875" 0-D-; 0.050 avg. wall. - Inconel.

II. STEAII GENERATOR OPERATING CONDITIONS

~Nl N

t'emperature: 516F

Flow Rate: 3.196 x 10 lb/hr Allowable Leakage Rate: 0.3 gpm6

Primary Pressure: 2235 psigSecondary Pressure: 770 psigAccidents

Design Base LOCA Max. Delta-P: 1150 psig N

Main Steam Line Break (MSLB) Sax. Delta-P: (to be suPPlied withIII. STEN GENERATOR SUPPORT PLATE INFORMATION Unit 4 letter-5/1/78)

Material: carbon steelDesign Type: (to be supplied with Unit 4 letter-5/1/78)"Design Code ESNE Boiler & Pressure Vessel Code, Section XXl.

Dimensions: (to be supplied with Unit 4 letter-5/1/78)Flow Rate: '33.8 x 10 lb/hr6

Tube Hole Dimensions: 0. 903"

Flow Hole Dimensions: (to be supplied with Unit 4 letter-5/1/78)'

-2-IY. STEAM GENERATOR BLOMDOMN INFORMATION

Frequency of Blowdown: continuousNormal Blowdown Rate: + l5 gpss/SGBlowdown Rite w/Condenser Leakage: 25 30

, Chemical Rnalys>s Results (to be supplied with Unit 4 letter-5/l/78)

Results Parameter Control Limits

V. NTER CHEMISTRY INFORMATION

Secondar Mater

Type of Treatment and Effective Full Power (EFP) Months of Operation:AVT after October 1974; EFPH not. calculated.Typical Chemistry or Impurity Limits:

(separate Table attached)Feedwater

Typical Chemistry or Impurity Limits:(separate, Table attached)

Condenser Coolin Mater .

.Typical Chemistry or Impurity Limits:(separate Table attached)

Demineral izers - Type: none

Cooling Tower (open cycle, closed cycle or, none): none (closedcooling canal) .

TABLE 1

Chemistr Information

T ical S/G Chemistr

pH 8.96Cation cond. 1.0~hoFree OH 4,.13 ppm as OHNH> .29 ppmNa+ .Ol ppmCl <.05 ppmHydrazine- .030 ppm

T ical Feedwater Chemistr

pH 9.15Cond. 3.5 ~mho (total conductivity)Hydrazine .020 ppm-Cl 4'.05 ppmFe <.010 ppmCu <.005 ppm

TABLE 2r

Turke Point Coolin Hater Chemistr

Total ~4, ppm CaCO3p„~op., ppm CaCO

~ g1.carbonate> ppm@~de. ppm.Calci~, ppm"

I 'I

Carbonate, ppm'ipon Dioxide~ ppmG3.oriole, ppmCopper, ppmFluoride, ppm

~ree Hydroxy.de, ppmIodide, ppm

'Iron,ppm"'.

Lead, ppmLitMLXR~ pp m

2700

32980

596r

06

X7;000CQ.Z.

~ -.

';45'.1

0.214

Hag; esi~, ppm.~ P~ganese, ppm

'

'itrateNitrogen~ ppm'it&te Nitrogen~ ppm'b~~en~ ppm r

phosphate, ppmPotassium, 'pm

'-Silica, ppmSodi~, ppm

'ulfate,ppm

Sulfide, ppmSu1fite, ppmT.D.S., ppmConductivity, ~osfcmTurbidi typH

1s3754 0.05

Q. 1850. 001

~ 0.05

0.19 $ 2002sMO

<Q. 1C0.1

31,300

4.3 (NTU}6.4-s

3

VI. TURBINE STOP VALVE TESTING (applicable to Babcock 5 Milcox (BPA) S.G. only)

Fre uenc of TestinActual:Manufacturer Reco(rmendation:

Power Level At Mhich Testin Is Conducted

Actual:Manufacturer Recommendation:

Testin Procedures {Stroke len th, stroke- rate, etc.Actual:Manufacturer Reconmendation:

VII. STEW GENERATOR 'TUBE DEGRADATION HISTORY

(The following is to be repeated for each scheduled ISI)Inservice Inspection (ISI) gate: io/T4

Number of EFP Days of Operation Since Last Inspection: gp 7

The followin is to be re eated fo'r each steam generator )( g P

Steam Generator Number: 8h, SB, sc .

Percentage of Tubes Inspected At This ISI: >A-7.449%, 38- '7,o49 /o 3c, 3./9g%Percentage of Tubes Inspected At This ISI That.Had Been Inspected At

The Previous Scheduled ISI: FIesY'sI idspac.viowpercentage of Tubes Plugged Prior to This ISI:3A-a Ps'z log 36 op> 3Q-z 79! Ie

Percentage of Tubes Plugged At This ISI: gA-.s'aug /Percentage of Tubes Plugged That Did Not Exceed Degradation Limits:ggg

Percentage of Tubes Plugged As A Result of Exc cdance of Degradation

Limits: ALL

Sludge Layer Material Chemical Analysis Results: AoT pagFg~<>

Sludge Lancing (date): REFEP ~ f'RBQI«s L<l~ w dR~. CA~blgg)Ave. Height of Sludge Before Lancing: g~ m ~p~p<y. g I

Ave. Height of Sludge After Lancing: Ra~ Te pap~>,v. ~Replacement, Re+ubing or Other Remedial Action Considered: (Briefly

Specify Details) A~we.

Support Plate Hourglassing: ~/p,

Support Plate Islanding:g/ATube Netalurgical Exam Re usit :s N/p

Fretting or Yibration in U-Bend Area (not applicable to BEM S.G.)-

Percentage of Tubes Plugged Other Preventive Measures

~/A

Masta e/Cavitation Erosion

38

X of Tubes Affected byMastage/Cavitation Erosion

~ of Tubes Plugged Due toExceedance of AllowableLimit '

5~$,~ of Tubes Plugged Tnat

Did not Exceed DegradationLimit

Location Above TubeSheet

Nax. Mastage/Cavitation ErosionRate for Any -Single Tube(Tube Circum. Ave) (Mills/Month)

/i Nax. Mastage/Cavitation Erosionin Any Single Unplugged Tube

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Fre uenc of TestinActual:Manufacturer Recommendation:

Power Level At Nich Testin Is Conducted

Actual:'anufacturer Recoamendation:

Testing Procedures (Stroke len th, stroke rate, etc.)Actual:Manufacturer Recommendation:

VII. STEAl1 GENERATOR TUBE DEGRADATION HISTORY

(The following is to be repeated for each scheduled ISI)Insenvice Inspection (ISI) Date: ln/7rNumber of EFP Days of Operation Since Last. Inspection: $ 83,5

(The following is to be repeated fo'r each steam generator)

Steam Generator Number: 3A, 58,3CPercentage of Tubes Inspected At This ISI:3A-IZ.S'l lo ~

36-9.floe ~3c - t3.83 la

Percentage of Tubes Inspected At This ISI That Had Been Inspected AtThe Previous Scheduled ISI:34- 0;8857o

~3s-'Z.395'7O

g 3c z 395'Vo

Percentage of Tubes Plugged Prior to This ISI:3A-3.435K;38-.zi47V.~ac -3.o37 7,

Percentage of Tubes Plugged At This ISI:3A-.W42,'l.; 88".I%%7'p,q 3c-,3o47'p.

Percentage of Tubes Plugged That Did Not Exceed Degradation Limits:<dopa

Percentage of Tubes Plugged As A Result of Exceedance of Degradation

L1mlts: ALL,

Sludge Layer Material Chemical Analysis Results: po> pgp~L p,>~Sludge Lancing (date):Ao> AVAILABLE

Ave. Heigh of Sludge Before Lancing- Coy- AyntiASWAve. Height of Sludge After Lancing: gow AVAlLA,GLw

Replacement, Re+ubing or Other Remedial Action Considered: (Briefly

Specify Deteiis) A/A

Support Plate Hourgl assing: $p, -g3% .

Support Pla e Islanding: AoAE. osaagvcoTube 'Metalurgical Exam Results: W/p,

Fretting or Vibration in U-Bend Area'(not applicable to 8EW S.G.)

Percentage of'ubes Plugged Other Preventive Measures

Wasta e/Cavitation Erosion

S+~ SEhl<P AY'6035

X of Tubes Affectedby'astage/CavitationErosion

~ of Tubes Plugged Oue toExceedance of AllowableLimit $ o /,

X of Tubes Plugged That*

Did not Exceed DegradationLimit

Location Above TubeSheet

Max. Mastage/Cavitation ErosionRate for Any Single Tube(Tube Circum. Ave) ('fills/tlonth)

7oNax. Wastage/Cavitation Erosionin Any Single Unplugged Tube

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Actual:' Manufacturer Recommendation:

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AA

VII. STDW GENERATOR TUBE DEGRADATION HISTORY

(The following is to be repeated for each scheduled ISI)Inservice Inspection (ISI) Gate: li/q(Number of EFP Days of Operation Since Last Inspection: Z77. 8

(The following is to be repeated fo'r each steam generator)

Steam Generator Number: 5$ ,38, 3c .

Percentage of Tubes Inspected At This ISI:34-9.877~; 38-2,4b7Vb~ 3c-(.534 lb

Percentage of Tubes Inspected At This ISI That.Had Been Inspected AtThe Previous Scheduled ISI:3A-<,Li37, ~ 3g- l.olz7. ~ 3~

Percentage of Tubes Plugged Prior to This ISI:3A-Cuts'L 35-.pqgag gc-3,g7$ 7,

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Tube Metalurgical Exam Results: A/g

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Data from the December 1977 Steam Generator inspectionsis being processed and will be forwarded at a later date.A schedule for submitting supplemental information of thistype will be provided with the Unit 4 letter (5/1/78).'

Re: Turkey Point Unit 3Docket No. 50-250Steam Generator Information

APPENDIX B

FPL Correspondence with NRC Concerning Steam GeneratorIns ections — Turke Point Units 3 & 4

September 30, 1975.(L-75-475), R. E. Uhrig (FPL) to GeorgeLear (NRC), Turkey Point Units 3 & 4, "Integrity of SteamGenerator Tubes". (exten'sive eddy current test data)

October 26, 1976 (L-76-369), R. E. Uhrig (FPL) to GeorgeLear (NRC), Turkey Point Units 3 & 4, "Steam Generator'Inspection Program". (integrity of small'end radius tubes)

November 24, 1976 (L-76-403), R. E. Uhrig (FPL) to George =

~ 'ear (NRC), Turkey Point. Unit 4,. "Steam Generator InspectionResults". (integrity of small bend radius tubes)

November 30, 1976 (L-76-409), R. E. Uhrig (FPL) to GeorgeLear (NRC), Turkey Point Unit 4, "Steam Generator InspectionResults — Supplemental Information".

December 20, 1976 (L-76-428), R. E. Uhrig (FPL) to GeorgeLear (NRC), Turkey -Point Units 3 & 4, "Steam GeneratorSurveillance".

December 21, 1976 (L-76-431), R. E.'hrig (FPL) to George„Lear (NRC), Turkey Point Unit 3, "Steam Generator InspectionResults". (integrity of small bend .radius tubes)

December 22, 1976 (L-76-432), R. E. Uhrig (FPL) to GeorgeLear (NRC), Turkey Point Units 3 & 4, "Steam Generator-TubeIntegrity". (response to 12/10/76 NRC Request for Information)

I

December 30, 1976 (L-76-434), R. E. Uhrig (FPL) to GeorgeLear (NRC)," Turkey Point Units 3 & 4, "Steam Generator TubeIntegrity — Supplemental. Information".

January 3, 1977 (L-77-3), R. E. Uhrig (FPL) to George Lear(NRC), Turkey Point Units 3 & 4, "Steam Generator TubeIntegrity — Supplemental Information".

January 21, 1977 (L-77-29), R. E. Uhrig (FPL) to George Lear(NRC),, Turkey Point Unit 4, "Steam Generator Operation".

February 2, 1977 (L-77-40), R. E. Uhrig (FPL) to George Lear(NRC), Turkey Point Units 3 & 4, "Steam Generator Tube Integrity—Supplemental Information".

April ll, 1977 (L-77-112), R. E., Uhrig (FPL) to %'ictor Btello(NRC), Turkey Point Unit 4, "Steam. Generator InspectionProgram".

'FPL CorrespondencePa e Two

April 20, 1977 (L-77-117), R. E. Uhrig (FPL) to Victor Stello(NRC), Turkey Point Unit 4, "Steam Generator Inspection Program—Supplemental Information".

June 9, 1977 (L-77-173), R. E. Uhrig (FPL) to Victor Stello(NRC), Turkey Point Unit 4, "Steam Generator Inspection Results".(results of S/G'.inspections performed during the reload outage)

June 16, 1977 (L-77-179); R. E. Uhrig (FPL) to Victor Stello(NRC), Turkey Point Unit 3, "Steam Generator Inspection Program".

June 28, 1977 (L-77-198), R. E. Uhrig (FPL) to Victor Stello(NRC), Turkey Point Unit 4, "Steam Generator Inspections".(followup to L-77-173 of June 9, 1977) *

August 30, 1977 (L-77-267),, R. E. Uhrig (FPL) to. George Lear(NRC), Turkey Point Unit 3, "Steam Generator Inspection Program".(S/G inspection plan for reload outage)

December 29, 1977 (L-77-393), R. E. Uhrig (FPL) to Victor Stello(NRC), Turkey Point Unit. 3, "Steam Generator Inspection'.

January 18, 1978 (L-78-24), R. E.'hrig (FPL) to Victor Stello(NRC), Turkey Point Unit 3, "Steam Generator Inspection Results".

January 31, 1978 (L-78-34),; R E. Uhrig (FPL) to George Lear(NRC), Turkey Point Unit 4g "Steam Generator Inspection Program".(S/G inspections planned for February, 1978)

March 1, 1978 (L-78-82), R; E. Uhrig (FPL) to Victor Stello(NRC), Turkey Point Unit, 4, "Steam .Generators Inspections".(results of February, 1978 inspections)