ML18228A480
| ML18228A480 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 04/04/1978 |
| From: | Robert E. Uhrig Florida Power & Light Co |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18228A480 (36) | |
Text
NRC 'L DOCTYPE:'ETTER
SUBJECT:
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL REC: SCHWENCER A ORG:
NOTARIZED: NO UHRIG R E PWR 8. LIGHT 50-250 DOCDATE: 04/04/78 DATE RCVD: 04/10/78 COPIES RECEIVED LTR 3 FORWARDlNG CONSIDERABLE INFO ON THE OPERATING HISTORY OF THE STEAM GENERATORS AT UNIT 3. IN ACCORDANCE WITH APPLICANT"S LTR DTD 03/01/78... W/ATT LISTING OF OTHER APPLICANT"S LTRS TO COMMISSION ON THE SAME SUBJECTS AND SUPPORTING ENCLS.
PLANT NAME: TURKEY PT 83 REVIEWER ENCL 3 INITIAL: XJM DISTRIBUTOR INITIAL:
DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS RESPONSES TO STEAM GENERATOR QUESTIONNARE (DISTRIBUTION CODE A023)
FOR ACTION: BR CHIEF~ -WENCER++W/7 ENCL INTERNAL: "REG FILE++W/ENCL NRC PDR++W/ENCL I h=-~~WZ~IWQ OELD+4W/ENCL HANAUER++W/ENCL E I SKNHUT+>W/ENCL SHAO~~~W/ENCL BAER4+W/ENCL BUTLER++M/ENCL GR IMES++M/ENCL J COLLINS<4~W/ENCL EXTERNAL: LPDR S MIAMIi FL++W/ENCL T I C~>+W/ENCL NS IC++W/ENCL RON GAMBLE44W/6 ENCL KEN HERRING++M/6 ENCL ACRS CAT B44W/16 ENCL DISTRIBUTION: LTR 50 ENCL 50 CONTROL NBR: 780100015 SIZE: 1 P+20P+3P THE END
. O. BOX 013100, MIAMI, FL 33101 FLORIOA POWER & LIGHT COMPANY April 4, 1978 L-78-117 ggt. g(m7<
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Office of Nuclear Reactor Regulation ,1,0 ll Attention: Mr. A. Schwencer, Chief Operating Reactors Branch gl RECOV fo Division of Operating Reactors APQ tp )y, U- S. Nuclear Regulatory Commission Washington, D. C..20555
Dear Mr. Schwencer:
~
CO~ISS Ctf Re: Turkey Point Unit 3 Docket No. 50-250 Steam Generator Information In accordance with our letter of March 1, 1978 (L-78-78),
considerable information on the operating history of the steam generators at Turkey Point Unit 3 is attached as Appendix A. A listing of other Florida Power & Light Company letters to the Commission on the same subject is attached as Appendix B.
Very ly yours, Robert E. Uhrig Vice President REU/MAS/ms Attachments cc: Mr. James P. O'Reilly, Region II Robert Lowenstein, Esquire 78OiOOOi5 PEOPLE... SERVING PEOPLE
f Re: Turkey Point Unit 3 Docket No. 50-250 Steam Generator Information APPENDIX A
STEAM GEHERATQP, OPERATING HISTORY (lUESTIONHAIRE NOTE: All percentages should be reported to four significant figures.
I. BASIC PLANT INFORMATION Plant Turkey Point Unit 3 (initial criticality)
'I Startup Date: October 20, 1972 Utility: Florida Power &, Light Company Plant Location: 8 miles east of Florida City, Florida Thermal Power Level: 2200 Mwt
'-
Nuclear .Steam SuPPly System (HSSS) Supplier Number of Loops:
Westinghouse Steam Generator Supplier, Model Ho. and Type.: Westinghouse 044 series, Number of Tubes Per Generator:
vertical steam 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 6 lb/hr Allowable Leakage Rate: 0.3 gpm Primary Pressure: 2235 psig Secondary Pressure: 770 psig Accidents Design Base LOCA Max. Delta-P: 1150 psig N Main Steam Line Break (MSLB) Sax. Delta-P: (to be suPPlied with III. STEN GENERATOR SUPPORT PLATE INFORMATION Unit 4 letter-5/1/78)
Material: carbon steel Design 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 6 lb/hr Tube Hole Dimensions: 0. 903" Flow Hole Dimensions: (to be supplied with Unit 4 letter-5/1/78)
'
IY. STEAM GENERATOR BLOMDOMN INFORMATION Frequency of Blowdown: continuous Normal Blowdown Rate: + l5 gpss/SG Blowdown 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 (closed cooling canal) .
TABLE 1 Chemistr Information T ical S/G Chemistr pH 8.96 Cation cond. 1.0~ho Free OH 4,.13 ppm as OH NH> .29 ppm Na+ .Ol ppm Cl <.05 ppm Hydrazine- .030 ppm T ical Feedwater Chemistr pH 9.15 Cond. 3.5 ~mho (total conductivity)
Hydrazine .020 ppm-Cl 4'.05 ppm Fe <.010 ppm Cu <.005 ppm
TABLE 2 r
Turke Point Coolin Hater Chemistr Total ~4, ppm CaCO3 270 p~op., ppm CaCO 0
~ g1.carbonate> ppm 329
@~de. ppm. 80 Calci~, ppm" 596 I 'I r Carbonate, ppm 0
'ipon Dioxide~ ppm 6 G3.oriole, ppm X7;000 Copper, ppm CQ.Z.
Fluoride, ppm ~ -.
';45'.1
~ree Hydroxy.de, ppm Iodide, ppm
'Iron, ppm"'.
Lead, ppm 0.214 LitMLXR~ pp m Hag; esi~, ppm. 1s375 P~ganese, ppm 4 0.05
'
~
Nitrogen~ ppm Q. 185
'it&te
'itrate Nitrogen~ ppm 0. 001
'b~~en~ ppm r phosphate, ppm ~
0.05 Potassium, 'pm
'-Silica, ppm 0.1 Sodi~, ppm 9 $ 200 ppm'ulfate, 2sMO Sulfide, ppm <Q. 1 i
Su1f te, T.D.S., ppm ppm 31,300 C0.1 Conductivity, ~osfcm Turbi di ty 4.3 (NTU}
pH 6.4-s
3 VI. TURBINE STOP VALVE TESTING (applicable to Babcock 5 Milcox (BPA) S.G. only)
Fre uenc of Testin Actual:
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 following is to be re P eated fo'r each steam generator )
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.viow percentage 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/A Tube 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 by Mastage/Cavitation Erosion
~ of Tubes Plugged Due to Exceedance of Allowable Limit 5~$ ,
'
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Sheet 3 Nax. Mastage/Cavitation Erosion Rate for Any -Single Tube (Tube Circum. Ave) (Mills/Month)
/i Nax. Mastage/Cavitation Erosion in 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 Testin Actual:
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/7r Number 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, 58,3C Percentage 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 At The 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- AyntiASW Ave. 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. osaagvco Tube '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 35 S+~ SEhl<P AY'6 0 X of Tubes Affected Erosion by'astage/Cavitation
.95o't,2,7 Gl .39PR ,3374
~ of Tubes Plugged Oue to Z.as'3o47 Exceedance of Allowable Limit $ o /, 12%7
- X of Tubes Plugged That Did not Exceed Degradation Limit 0 Location Above Tube ufo TS Sheet I Max. Mastage/Cavitation Erosion Rate for Any Single Tube (Tube Circum. Ave) ('fills/tlonth) 7oNax. Wastage/Cavitation Erosion in Any Single Unplugged Tube bio TE 2. loop
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'lI. TURBINE STOP YALVE TESTING {applicable to Babcock & Milcox {8&M) S.G. only)
Fre uenc of Testin Actual:
Manufacturer Reco(rrrendation:
Power Level At Which Testin Is Conducted Actual:
'
Manufacturer Recommendation:
AA Testinq Procedures {Stroke len th; stroke rate, etc.)
Actual:
Manufacturer Recoamendation:
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 At The Previous Scheduled ISI:3A-<,Li37, 3g- l.olz7. 3~
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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 y 3' QQ2 Sludge Layer Material Chemical Analysis Results: go~ AgA~LpgI ~
Sludge Lancing (date): %4 Ave. Height of Sludge Before Lancing:BA-,)$ 5 3Q-Q,I83 Ave. Heioht of Sludge After Lancing: EFrici~cQ eF. R~ovAL- 3A,"733 /by
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39 ~,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 L
X of Tubes Affected by Mastage/Cavitation Erosiorr I.643
. ~ of Tubes Plugged Due to Exceedance of Allowable Limit .'f'ta E,3'l Pf 5 of Tubes Plugged That
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/'I I ~~:j 0 I Q ~ ~ ~ I I t~-" I I: t-+ :l ~ Y! I I i:7 >>:>>Z r ~ ~ ~ p, l ~V. ~~@ I ~t ~ ~ r /i!-- - '!a-I-m .L I.3 wl Xq4-Q' i0 I--I--I+g --.i I- ~ I I I I ~ I I'+L -T I I I I->> f I L ~ r ~ -l" I ~ sC 'r I I jl-- I r g-t ii~ '=ll f~ l3 'CP ) I p I Y ~ ~ ~ ~ ~ I :c:J5. IO . ,,-!L>>t+, I'. ~ ~ 1" -H l t-Id I"I \~ ~ ~ ~ ~ Ilf, tJ I 'wI = 7 +I e L. I-I- r". I I '-i I 3 ltI, W I ~ I I -fq-I-I I" I f -I- <<~ CJ >>:K-I+I-I t ~ Iff r I I ' T :f:: W J-I-1"" I I .g.Jgq.k ..G I 3 y I sr~ r>>r>>w ROwS e Data from the December 1977 Steam Generator inspections is being processed and will be forwarded at a later date. A schedule for submitting supplemental information of this type will be provided with the Unit 4 letter (5/1/78).' Re: Turkey Point Unit 3 Docket No. 50-250 Steam Generator Information APPENDIX B FPL Correspondence with NRC Concerning Steam Generator Ins ections Turke Point Units 3 & 4 September 30, 1975.(L-75-475), R. E. Uhrig (FPL) to George Lear (NRC), Turkey Point Units 3 & 4, "Integrity of Steam Generator Tubes". (exten'sive eddy current test data) October 26, 1976 (L-76-369), R. E. Uhrig (FPL) to George Lear (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 Inspection Results". (integrity of small bend radius tubes) November 30, 1976 (L-76-409), R. E. Uhrig (FPL) to George Lear (NRC), Turkey Point Unit 4, "Steam Generator Inspection Results Supplemental Information". December 20, 1976 (L-76-428), R. E. Uhrig (FPL) to George Lear (NRC), Turkey -Point Units 3 & 4, "Steam Generator Surveillance". December 21, 1976 (L-76-431), R. E.'hrig (FPL) to George Lear (NRC), Turkey Point Unit 3, "Steam Generator Inspection Results". (integrity of small bend .radius tubes) December 22, 1976 (L-76-432), R. E. Uhrig (FPL) to George Lear (NRC), Turkey Point Units 3 & 4, "Steam Generator-Tube Integrity". (response to 12/10/76 NRC Request for Information) I December 30, 1976 (L-76-434), R. E. Uhrig (FPL) to George Lear (NRC)," Turkey Point Units 3 & 4, "Steam Generator Tube Integrity Supplemental. Information". January 3, 1977 (L-77-3), R. E. Uhrig (FPL) to George Lear (NRC), Turkey Point Units 3 & 4, "Steam Generator Tube Integrity 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) (NRC), Turkey Point Unit 4, "Steam. Generator to %'ictor Btello Inspection Program". 'FPL Correspondence Pa 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)