ML18114A170

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Forwards Information on Operating History of Steam Generators
ML18114A170
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 06/01/1978
From: Robert E. Uhrig
Florida Power & Light Co
To: Reid R
Office of Nuclear Reactor Regulation
References
Download: ML18114A170 (22)
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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-335 REC:

REID R

W NRC ORG:

UHRIG R E FL PWR 5 LIGHT DOCDATE: 06/01/78 DATE RCVD: 06/06/78 DOCTYPE:

LETTER NOTARIZED:

NO COPIES RECEIVED

SUBJECT:

LTR 3 ENCL 3

RESPONSE

TO NRC LTR DTD 03/Oi/78... FORWARDING APPLICANT"S OPERATING HISTORY OF THE STEAM GENERATORS AT SUBJECT FACILITY'NDADVISING RESULTS OF THE FIRST UNIT 1

STEAM GENERATOR INSERVICE INSPEC CONDUCTED IN APRIL'S SCHEDULED FOR SUBMITTAL BY 07/31/78.

PLANT NAME: ST LUCIE 51 REVIEWER INITIAL:

XJM DISTRIBUTOR INITIAL:~

DI TRIBUTION OF THIS MATERIAL IS AS FOLI OWS 44+++<<<<+++<+++<+

'RESPONSES TO STEAM GENERATOR QUESTIONNARE (DISTRIBUTION CODE A023)-

FOR ACTION:

INTERNAL:

BR CHIEF ORBS@ BC>~M/7 ENCL REG FILETS

/ENCL ENCL HANAUER+4W/ENCL ENGINEERING BR+4M/ENCL PLANT SYSTEMS BR>+W/ENCL EFFLUENT TREAT SYS++W/ENCL NRC PDR++W/ENCL OELD++W/ENCL AD FOR OPER TECH>~W/ENCL REACTOR SAFETY BR<<W/ENCL EEB+4W/ENCL EXTERNAL:

LPDR S FT PIERCEi FL++W/ENCL TIC++W/ENCL NSIC>~W/ENCL RON GAMBLE44W/6 ENCL KEN HERRING~~W/6 ENCL ACRS CAT B<+W/16 ENCL DISTRIBUTION:

LTR 50 ENCL 50 SIZE:

1 P+13P THE END CONTROL NBR:

78157033

FLORIDA POWER 8( LIGHT COMPANY Office of Nuclear Reactor Regulation Attention:

Mr. R.

W. Reid, Chief Operating Reactors Branch 84 Division of Operating Reactors U.

S. Nuclear Regulatory Commission Washington, D.

C.

20555

Dear Mr. Reid:

June l, l978 L-78-l93 CD C()

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St. Lucie Unit 1

Docket No. 50-335 Steam Generator Information In accordance with our letter of March 1, 1978 (L-78-78), information on the operating history of the steam generators at St. Lucie Unit 1 is attached.

A followup report, containing more detailed information on the results of the first Unit 1

steam generator inservice inspection conducted in April, is scheduled for submittal to your office by July 31, 1978.

Very truly yours, Robert

. Uhrig Vice President REU/MAS/cpc Attachment cc:

Mr. James P. O'Reilly, Region II Harold F. Reis, Esquire 7gl570332 PEOPLE... SERVING PEOPLE

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ENCLOSURE 1

STEAM GENERATOR OPERATING HISTORY QUESTIONNAIRE NOTE:

All percentages should be, reported to four significant figures.

I BASIC PLANT INFORMATION

'I.

STEAM GENERATOR OPERATING CONDITIONS Normal 0 eration Temperature:

Tc=541 'F Th=585'F Flow Rate: 5.603 x 10 lb/hr Primary. Pressure:

2235 psig Secondary Pressure:

800 psig Accidents Design Base LOCA Max. Delta-P:

985 psi reverse dp Main Steam Line Break (MSLB) Sax. Delta-P:

1850 psi STEAM GENERATOR SUPPORT PLATE INFORMATION Allowable Leakage Rate:

1.0 gpm Material:

Carbon Steel Design Type:

Lower 8 - lattice/gridwork "egg crates";

upper 2 - drilled plates Design Code:

1965 ASME Section III for Class A vessels (including Winter 1967 Addenda)

Dimensions:

~12.5'iameter, 1" thick Flow Rate:

61 x 10 lb/hr Tube Hole Dimensions:

.765" Flow Hole Dimensions:

.250" Pl ant:

St.

Luci e Unit 1

Startup Date:

4-22-76 (Initial Criticality)

Utility:

Florida Power 8 Light Company.

Plant Location:

Hutchinson. Island, Saint Lucie County, Florida=

,Thermal Power Level:

2560 Mw Nuclear Steam Supply System (NSSS) Supplier:

Combustion Engineering Number of Loops:

Two Steam Generator Supplier, Model No. and Type:

Combustion Engineering;-

CE67508/

Number of Tubes Per Generator:

8485 Tube Size and Material:

3/4-inch OD,.048" Wall; Inconel composition Ni-Cr-Fe Alloy

IY.

STEAM GENERATOR BLOWDOHN INFORMATION Fr equency of Blowdown:

Continuous Normal Blowdown Rate:

~80 gpm Slowdown Rate w/Condenser Leakage:

~125 gpm Chemical Analysis Results (see attached sheet entitled Steam Generator Blowdown Information)

Resul ts Parameter Control Limits V.

WATER CHEMISTRY INFORMATION (see attached sheet entitled Hater Chemistry Information)

~Sd fl t Type of Treatment and Effective Full Power (EFP) Months of Operation:

Typical Chemistry or Impurity Limits:

Feedwater Typical Chemistry or Impurity Limits:

Condenser Coolin Water Typical Chemistry or Impurity Limits:

Demineralizers - Type:

Cooling Tower (open cycle, closed cycle or none):

'SI.

TURBINE STOP VALYE TESTING (applicable to Babcock 8 Wilcox (B&M) S.G. only)

Fre uenc of Testin Actual:

N/A Manufacturer Recommendation:

N/A Power Level At which Testin Is Conducted

'. Actual:

'N/A'anufacturer Recommendation:

N/A Testin Procedures (Stroke len th, stroke rate, etc.

Actu'al:

N/A Manufacturer Recommendation:

N/A VII.

STEAM GENERATOR 3'UBE DEGRADATION HISTORY.:..(Followup.report due July,'31, 1978)

,:,--- (The following is to be repeated for each scheduled ISI)

Inservice Inspection (ISI) Date:

Number of EFP Days of Operation Since Last Inspection:

(The following is to be repeated for each steam generator)

Steam Generator Number:

Percentage of Tubes Inspected At This ISI:

Percentage of Tubes Inspected At This ISI That,Had Been I'nspected At The Previous Scheduled ISI:

Percentage of Tubes Plugged Prior to This ISI:

Percentage of Tubes Plugged At This ISI:

Percentage of Tubes Plugged That Did Not Exceed Degradation Limits:

Percentage of Tubes Plugged As A Result of Exceedance of Degradation Limits:

Sludge Layer Material Chemical Analysis Results:

Sludge Lanci'ng (date):

Ave. Height of Sludge Before Lancing:

Ave. Height of Sludge After Lancing:

Replacement, Retubing or Other Remedial Action Considered:

(Briefly Specify Details)

Support Plate Hourglassing:

Support Plate Islanding:

Tube Hetalurgical Exam Results:

e

~

~

m

~

~

~

~

~

(Followup report'ue July 31, 1978)

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

AS OF ~4 Percentage of Tubes Plugged.

Other Preventive Heasures Was ta e/Cavi tati on Eros ion AS OF ~4

~Hot:Le':

{Repeat this information for the cold leg on Corabustion Engineering (C'.E.) and Westinghouse (W) S.G.)

Area of Tube Bundle (1)

X of Tubes Affected by Wastage/Cavitation Erosion X of Tubes Plugged Due to Exceedance of Allowable Limit (2)

X of Tubes Plugged That Did not Exceed Degradation Limit Location Above Tube Sheet (3)

Max. Wastage/Cavitation Erosion Rate for Any Single Tube (Tube Circum. Ave) (Hills/Honth)

Hax. Wastage/Cavitation Erosion in Any Single Unplugged Tube (Tube Circum. Ave) (Hills) b c

d e

Cracking Ag pF ~a Caustic Stress Corrosion Induced in C.E.

and W S.G.

Flow Induced Vibration Caused in 88M S.G.

(Followup report due July 31, 1978) a b

~Crackin (Con't)

~ROt Le:

Lnepeat this information for the cold leg on C.E.

and M S.G.)

Area of Tube Bundle (1) c d

e "X of Tubes Affected By Cracking 5 of Tubes Plugged Due to C.racking I of Tubes Plugged That Did Not Exceed Degradation Limit-Location Above '( 3)

Tube Sheet Rate of Leakage From Leaking Cracks (gpm)

~Dentin (Rot applicab'le to 88M S.G.} AS OF ~4

~o~

Le<O:

(Re'peat this information for the cold Ieg on C.E.

and M S.G.)

Area of Tube Bundle (1) c d

A of Tubes Affected by Denting I of Tubes Plugged Due to Exceedance of Allowable Limit (2) 5 of Tubes Plugged That Did Not Exceed Degradation Limit Rate of Leakage From Leaking Dents (gpm)

Max. Denting Rate for Any Single Tube

{Tube Circum. Ave) (Mills/Month)

Max. Denting in Any Single Unplugged Tube (Tube Circum. Ave) {Mills)""'s

L,

ne<<ee

~

~

{Fo11owup report due July 31, 197S)

Denting Support Plate Level s (Con't)

Max. Denting in Any Single Tube in Bundle Area (Tube Ave) (Mills) (1) c d

X of Tubes Affected By Denting in Bundle Area c

5 6

7 8

9 10 ll 12

(Followup report duluiy 31, 1978)

TABLE KEY NOTE:

All percentages refer to the percent of the tubes within a given area of the tube bundle.

Area of the Tube Bundle No. of Tubes Within the Area a.

Periphery of Bundle (wi/20rows for BInW; wi/10 rows for C.E. =and W) b.

Patch Plate (wi/4 rows) c."- Hissing Tube Lane (BSW only)

(wi/5 rows)

Flow Slot Areas (C.E.

and W only) wi/10 rows) d.

Wedge Regions (C.E.

and H only)

(wi/8 rows) e.

Interior of Bundle (remainder of tubes)

(2)

Allowable Limit for Wastage/Cavitation Erosion:

Allowable Limit For Denting:

1.

Specifies area between the tube sheet and-the first support plate 2.

Specifies in the following locations: (list the additional locations)

Wastage/Cavitation Erosion:

Cracking:

(4)

Specify the date of'he inspection for which results have been tabulated.

~

~"

~ ~

'I VIII.

SIGNIFICANT STEAM GENERATOR ABNORMAL OPERATIONAL EVENTS

SUMMARY

(Include event descri'ption; unscheduled I'5I results, if

  • performed; and subsequent remedial actions)

None CONDENSER INFORMATION (see attached sheet entitled Condenser Informati.on)

Condenser Material Tube Leakage Date Rate (gpm)

Detectable Limit Detection Method

.001 gpm Aluminum Brass 70/30 Copper-Nickel (Air Removal, Section)

Cati.on Conductivity Chloride Analysis X.

RADIATION EXPOSURE HISTORY bfITH RESPECT TO STEAH GENERATORS Date Exam Dosage (Han-Rem)

Repair Dosage (Han-Rem)

Comnents 3/78+4/7 12.455 None None

XI.

DEGRADATION HISTORY FOR EACH TYPE OF DEGRADATION EXPERIENCED FOR TEN REPRESENTATIVE, UNPLUGGED TUBES FOR MHICH THE RESULTS OF TMO OR MORE ISI 'S ARE AVAILABLE

'If the results for ten tubes are not available, specify this infor-mation for all those tubes for which results are available.

(repeat the following information for each tube and degradation type)

Steam Generator No:

'=

Tube Identification:

Type of,Degradation:

.(specify denting, wastage,.cavitation erosion,

~ -.;-.... caustic stress corrosion cracking, or flow ---

induced vibration cracking)

(repeat the following information chronologically for each IS'I for which re ults are available)

ISI Date:

Amount of Degradation:

(specify amount and units)

EFP Months of Operation Since Last ISI for Mhich Results are Given:

NOTE:

Only 1 S/6 ISI has been performed to date at St. Lucie Unit l.

XV.

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