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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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VI. TURBINE STOP VALVE TESTING (applicable to Babcock & Mi]cox (B&M) S.G. only),
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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'lI. TURBINE STOP YALVE TESTING {applicable to Babcock & Milcox {8&M) S.G. only)
Fre uenc of TestinActual:Manufacturer Reco(rrrendation:
Power Level At Which Testin Is Conducted
Actual:' Manufacturer Recommendation:
Testinq Procedures {Stroke len th; stroke rate, etc.)Actual:Manufacturer Recoamendation:
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,
Percentage of Tubes Plugged At This ISI: 3A-Z.c WVb,35-4817'f 3c,-(77'g '7,
Percentage of Tubes Plugged That Did Not Exceed Degradation Limits:SA-I.I II.'l.; 38-4.Sit %; Sc- f.I I4 l.Percentage of Tubes Plugged As A Result of Exc cdance of Degradation
Limits: 3A 8894'1> 3Q, oplg~7
y3' QQ2
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Sludge Lancing (date): %4Ave. Height of Sludge Before Lancing:BA-,)$ 5 3Q-Q,I83
- Ave. Heioht of Sludge After Lancing: EFrici~cQ eF. R~ovAL- 3A,"733 /by39 ~,Q 7o 'C 57,(o 'go,
R'eplacement, Re<ubing or Other Remedial Action Considered: (Br>efly
Specify Oetails) sl/P
Support Plate Hourglassing: SBa ApF~g~y 8. Support Plate IsIanding: ~~ gpp~y<g l3,
Tube Metalurgical Exam Results: A/g
t
Fretting or Yibration in U-Bend Area {not applicable to BKM S.G.)
Percentage of Tubes Plugged . Other Preventive Heasures
Masta e/Cavitation Erosion
X of Tubes Affected byMastage/Cavitation Erosiorr
. ~ of Tubes Plugged Due toExceedance of AllowableLimit
5 of Tubes Plugged That-- Did not Exceed Degradation
Limit
.'f'ta E,3'l Pf
L
I.643
Location Above TubeSheet
Max. Mastage/Cavitation ErosionRate for Any Single Tube{Tube Circum. Ave) {Hills/Month)
'lo Nax. Mastage/Cavitation Erosionin Any Single Unplugged Tube
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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)