ML17308A238

Summary of 870604 Meeting W/Util in Bethesda,Md to Discuss Proposed Tech Spec Change to Raise Steam Generator Tube Plug Limit from 40% to 54%

ML17308A238
Person / Time
Site:	Saint Lucie
Issue date:	06/23/1987
From:	Tourigny E Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
TAC-64184, NUDOCS 8707020116
Download: ML17308A238 (99)

Text

Cy

~v 0

/p RfgIj P0 A.n0 g

• ++

UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 June 23, 1987 Docket No. 50-335 LICENSEE:

Florida Power and Light Company (FPAL)

FACILITY: St. Lucie Plant, Unit No.

1

SUMMARY

OF JUNE 4, 1987 MEETING MITH FPE(L AND NRC STAFF REGARDING THE PROPOSED TECHNICAL SPECIFICATION CHANGE ON STEAM GENERATOR TUBE PLUG LIMIT (TAC NO. 64184)

Introducti on NRC staff met with FPEL personnel on June 4, 1987 in Bethesda, Maryland to discuss the proposal-to raise the steam generator tube plug limit from 40%

to,54$ ;

The meeting w'a's chaired by the NRC Project Manager for St. Lucie.

The agenda for the meeting is contained in Enclosure 1.

Enclosure 2 identifies the meeting attendees.

Enclosure 3 contains a copy of FPSL's/CE's view graphs.

A summary of the meeting follows.

~Sunmar Mr. Moaba (FP8L) presented the St. Lucie Unit No.

1 steam generator history.

There are 8,519 tubes in each generator.

Four hundred and sixty-three tubes are plugged in generator lA (approximately 5X), and three hundred and fifty-eight tubes are plugged in generator 1B (approximately 4X).

The "as-determined" degradation history by inspection year was shown.

A sumary of pulled tube results was given.

Secondary chemistry related data was compared between the early operating history to recent operating history.

Mr. Moaba then presented the results of the February 1987 Eddy Current Testing (ECT) of the generators.

The areas of most concern to date are sludge pile region, eggcrate

regions, and drilled support plate regions.

FPSL believes that the as-found Intergranular Attack (IGA) and Intergranular Stress Corrosion Cracking (IGSCC) to date has been arrested (no apparent flaw growth between the 1985 and 1987 inspections and new flaw initiation is not occurring).

The meeting then focused on the technical basis for the technical specification change.

Mr. Heilker of Combustion Engineering (CE) made the presentation.

The CE/EPRI LOCA analysis experimental verification program was discussed.

The tube bundle LOCA and MSLB analyses were discussed.

The NRC staff criteria (delta P

margins) were discussed.

FP8L and CE believe that based upon the above work, a

54K tube plug limit can be technically justified.

Mr. Boyers (FPSL) gave an overview of the FP8L's ECT capability, and Mr. Moaba (FPSL) discussed growth rate of acidic IGA.

8707020iib 870623 (I

PDR ADDCII, 05000335,,

P PDR

June 23, 1987

~

2

~

Lastly, Mr. Moaba presented a summary of FPSL's and CE's work to support the technical specification change.

FPSL believes that the steam generator condition is well-defined and stabilized.

There is margin available to allow increased tube plugging criteria based upon structural analysis, ECT capability, and growth rate analysis.

Continued plugging at overly conservative criteria threatens the longevity of the steam generators and also results in increased personnel exposure and heat flux on the remaining tubes in service.

Followu l<ork A great deal of information was presented to the staff that must be reviewed in detail.

The staff plans on reviewing in more detail what was presented and has already determined the need for additional information.

The staff is planning to send a request for additional information (RAI) to FPSL as the next step.

In addition, a trip to the site may be necessary for a more in-depth review of FPSL's ECT capability.

The need for the trip will be determined after the staff reviews the responses from the planned RAI.

Enclosures:

As stated E.

G. Tourigny, Senior Project Manager Project Directorate II-2 Division of Reactor Projects-I/II cc:

See next page DISTRIBUTION E.M hy NRC POR K. Nchman Local PDR H. Conrad PD22 Rdg.

L. Rubenstein E. Tourigny OGC-Bethesda E. Jordan J. Partlow ACRS (10)

B. Troskoski 0'PD22 Tourigny:hc LRu stein

/y+87 6fg/87

0+

r+

II J

I

Mr. C. 0.

Woody Florida Power 5 Light Company St. Lucie Plant CC:

Mr. Jack Shreve Office of the Public Counsel Room 4, Holland Building

, Tallahassee, Florida 32304 Resident Inspector c/o U.S.

NRC 7585 S.

Hwy A1A Jensen Beach, Florida 33457 State Planning 8 Development Clearinghouse Office of Planning 5 Budget Executive Office of the Governor The Capitol Building Tallahassee, Florida.32301 Harold F. Reis, Esq.

Newman 5 Holtzinger 1615 L Street, N.W.

Washington, DC 20036 Norman A. Coll, Esq.

McCarthy, Steel, Hector and Davis 14th Floor, First National Bank Building Miami, Florida 33131 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Mr. Weldon B. Lewis, County Administrator St. Lucie County'300 Virginia Avenue, Room 104 Fort Pierce, Florida 33450 Mr. Charles B. Brinkman, Manager Washington - Nuclear Operations Combustion Engineering, Inc.

7910 Woodmont Avenue

Bethesda, Maryland 20814 Jacob Daniel Nash Office of Radiation Control Department of Health and Rehabilitative Services 1317 Winewood Blvd.

Tallahassee, Florida 32399-0700 Regional Administrator, Region II U.S. Nuclear Regulatory Commission Executive Director for Operations

101 Marietta Street N.W., Suite 2900 Atlanta, Georgia 30323

l 1 t)

P-Enclosure 1

AGXNDA PRPCQH)

TXCSMICALSPXCTflCATXM CHANGE FOR ST..LUCIXUNII' PLUGGING CRITXRIA MRC/J. ROASTS CQRRX)CT ST. LUCIXUXZf1 STATUS A

STR~ GE?CXRATOR MOORY 5,

RESULTS OF~ 1947 XCY J. i4OALA 3

REVS Of A

STRUCTURAL AXALYQS

5. " XCVCAPAXKITY C

ACIDICXrAGROWTH RATX T. KQLKXR CL SOYXRS J. QOABA J. BOAR@

g 1< P~~<ik REMMORY AM<ET FILE MPY

'P A.

P

Enclosure 2

NRC FPE(L MEETING Raising the Steam Generator Tube Plug Limit for the St. Lucie Plant, Unit No.

1 June 4, 1987 Name E. Tourigny G. Boyers J.

Moaba V. Looper S.

Kowkabany M. Torborg T. Patterson M. Schoppman J. Westhoven K. Craig S. Collard E. Weinkam R. Crlenjak E. Murphy K. Wichman H. Conrad Affiliation NRC PM/St. Lucie Plant FP&L/Juno Beach FPAL/Juno Beach NDE Technology/Jackson, MI GPUN GPUN GPUN FP8L Licensing CE FPAL/Juno Beach FPKL/Juno Beach FPSL NRC SRI/St. Lucie NRC/MTEB NRC/MTEB

'RC

its i

REACTOR COOLANT SYSTEM SURYEILLAHCE RE UIREHENTS Cont{nued S.

Defect means an {mperfect{on of such sever{ty that {t exceeds Me pTugg{ng l{m{t. i tube conta{n{ng a defect {s defect{ve.

Any tube wh{Ch dOeS nat perm{C the piSSage Of the eddy-current {nspect{on probe shall be deemed a defect{ve tube.

6.

Plu

{n L{m{tmeans the {mperfect{on depth at ar beyond cn the tu e shall 5e removed from serv{ce because {t may become uns rv{ceable ~r{or to the next {nspect{on and {s Sf 7o equal to Ov of the rom]mal tubs ua'll thlokosaa~

1.

Unserv{ceable descr{bes the cond{t{on of a tube {f{t leaks

~

d i i i ii i ii i ii i

{ntegr{ty {n the event of an Operat{np Sas{s Earthquake, a

losi-of-coolant ace{dent, or a steam

'l{ne or feedwater l{ne break as spec{f{ed {n 4.4.5.3.c, above.

e.

"Tube Ins ect{on means an {nspect{on of the steam generator t~."e rom the po<nt of entry (hot leg s{de) completely around the U-bend to the top support of the cold leg.

/

b.

The stea~ generator shall te determ{ned OPERNi.E after complet{ng the carr espond{ng act{ons (plug all tubes exceeding the plu99{n9 l{m{tand all tubes conta{r{n throu h-wall cracks) rahu{red b

Tibia 4.4-2.

Exes pr rp'gr ram pcudcru4 zrmrr is. +qua(,

7o 507'og c,orcurious 4F oA Adove'sa ToP pwmrrqz guprolr sacra'v russ zn~s zl7 a

iwcc usia'ollow{n each {nserv{ce )as ect an o

steam enerator tu es e

4.4,5.5 Number and extent of tubes

{nspected.

2.

Locat{on and percent of wall-th{ckness penetrat{on for each

{nd{cat{on ot'n {mperfect{on.

3.

Ident{f{cat{on of tubes plugged.

. aa 9

P g

a number of tubes plugged

{n each steam generator shill be reported.--

to the Corm{ss{on w{th{n 15 days.

b: 'he complete resulCs af the steam generator tube {nserv{ce {nspec-t{on shall be {ncluded {n the Annual Operat{ng Report far the per{ad {n which th{s {nspect{on was completed.

Th{s report shall

{nclude:

'Th{s 4

{s not appl{cable dur{ng the cycle 1 opere to June 30, l986. ff at any is per{ad t ers any Hades other thin Hades 1 and 2, or Hode 3

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, the un{C shall be placed

{n cold n

the tubes w{Ch {nd{ca Chan 40K throu h-rit{on shall be removed from serv{cc pr{or to ex ST.

LUCIE UN!T 1

3l4 4-8 Amendment No. 13

SYSTEM OVERVIEW o

2-Loop CE NSS, Series 67 Steam Generators o

Commercial Operation December 1976 o

AVT Chemistry since star tup OPERATING CONDITIONS Primary THot = 596oF 5 2250 PSI Secondary Saturated Steam 5 875 PSI Continuous Blovrdown 50 - 80 gpm -

I/2%%uo/gen CONDENSER o

Titanium Tubes o

Aluminum Bronze Tube Sheet o

Salt Water Cooling FEED TRAIN o

AllSS tubing o

Carbon Steel Piping HP5:2

Vertical U-tube. recirculating type

~

8519 Tubes each, lnconel 600 mill-anneal led

~ 0;750 O.D. x 0.048 wall

~ 6-fu 1 1 Eggcrates

~ 2-partial Eggcrates

~ 2-partial Drilled Supports See Figure 1 for General Arrangement

~ ~ ) )

U-SEHOS ROM l ROM 18 mBLK 904 890S ROM 19 - RN 144

~ ORILLED SUt 9 STARTS ROM 9l

DRILLS'SUP 10 STARTS RN ill TU8K SHEET KXPNGED'ULL LENGTH CE SERIES 67 S]g PSt.-)A PSL-1B

- DATA CODES IN.ET

(@+ $0 8M4)

SQ'N, y0t:

09H

. 0gc 088 0SC 07H OyC O6H 06'b5H 05C

8Ml, DSI1- '.-

059 EC8 E

ECe 04H 04C EC4 SM2SM I

Ii.

II fl mi t

Nt ilail II II Itlttll Il a tt ItllltlllIt

'2 22 39 BM5 1/2 I/2 03H 03C 02H 02C OIH 01C EC3 EC2 ECL-4

~

I II ttlllII II I I

tt ill Ilt I Il Ill ll t II 39 39 40 5/8 2

1/2

'I HENLEY (HL)

'OUTLET

'CL)'

Sr. LuclK I 5/6 ARSMEHENT Figure i

St. Lucie.Unit 01 j

. Plugging History Year S G1A S G1B Remarks Mfg 1977 1978 1979 j981 1984 1985 9

56 264 13 19 Shop Plugs Plugs for DS Rim Cut Tight Radius U-Bend Preventive U-Bend Pire Random Defects Ramkom Indicatiocm

tf I

~l

St. Lucio Unit 01

.I Steam Generator Estorical Data Year 20%

39%

1978 1979 1981 19810.

1984 1985 N/A N/A 26 25 201

~ L

~

- -286 N/A N/A 10 131 352 N/A N/A 60 71 Zad Ezaminati~ 1981 e

~ I

~

Pulled Tubes Results 3't-ubes, &wee~ &CefeetL 1 sludge pile defects 2 eggcrate defects 1 UDS' DSS Allhot Ieg of S/G A InitialLab Results (NDE)

J No visible defects No RT indications

~

~ 4

~

V Final Lab Results Patches ofIGAMth some IG/TG SCC Patches of multiple, overlapping axial cracks Patches typicaHy=-90o x-0.8 Tube cracks in eggcrate contact area Depth corresponded mell ~th ECT

~ ~

~,

~

Tube I.Q.

Location FPL Field ECT Measured Depth Defect Description 120-12-2 4.3" Above T.S.

(Sludge Pile) 120-12-3

¹3 eggcrate 41%

82%

30%

72%

IG/TG SCC. Parallel Axial cracks longest - 0.4" Most, over 90 degree Some 360 degree IG/TG SCC Parallel 3 axial cracks in land area longest

- 0.6" within 0.1' circum. length 79-91-2 79-91-2 1.4 above T.S..

(Sludge Pile)

'.4 above T.S.

(Sludge Pile)

UDS 57%

16%

42%

IGA patch (0.5'xial x 0.5'ircum)

IGA patch (0.8" axial x 0.3" circum) 59-95-+

¹1 eggcrate 59-95-5

¹2 eggcrate DSS 29 4/o 52%

13 /o IGA patch (0.7'xial x 0.3'ircum)

IGA patch (0.4'xial x 0.3" circum)

EDS SLUDGE DEPOSIT ANALYSIS SllX)GE DEPOSIT ANALYSIS 7E X

X X

Al Si X

X X

X X

X X

X Pb Ca Mn X

X X

X X

X X

X X

X X

X CI F

X X

X XX X XX X

X X'X X X+

K C hG~

h03 X

ORGANICS Fe, N3 and metallic coI~ found

~ l ~

120-'1 2 AI Si X

Zn Pb X

S Cl Mg 79-91 59-95 X

X X

X X

X X

I J

I 1 I

I 0

,S 120-12 59-95 79-91

%C 0.057 0.03 0.031 MCRO 201 HARDNESS DPH 177 185

~

~

. HUEYTEST 5.65 Mg2Dma/da 5.45 5.36 (No Sensitization)

EPR TEST C/Cm >

262.9 Sensitized 162.6 Partial 157.2 Partial reer.

IGSCC Susceptibility increases with increasing Carbon content

N

.NN SCNNN Q

48N III

~

II I

5 4

R 0

BT.Cucre (UNIT i)

EA LEAKS

I 7 1

f

Lucie Vnit 1 S G Tubes arl t

Hist 1

j e

o High Halogen Concentrations 93ue to Salt Water Leaks) o High Sulfur Concentrations ~marQy Due to Salt Water Leaks and %TP Operation) o High AirInleakage Values (15-30 SCPi4) o Acidic Crevice pH Values of 1-2 (From NWT Special Test Analysis inM~ 1980) o Acidic Crevice pH Values Ezhted VntQ 1984

> ~

Recent at His o

lKinimalSalt Water Inleakage o

Greatly reduced sulpher concentrations

- decreasing SOg hideout return o

pH values of crevices approximately neutral (MULTEQ) o Eddy Curreat Testing Result 1985:

. %o significant growth ocnared from 1984 to 1985 (based on 400 tubes sample).. Ihe subJect indications were present in 1981 in the majority of cases where data edsted h smaH number were tracked back to 1979.

1987:

1. No significant growth occurred froza 1985 to 1987 Increase in indicatioos arise froza better mxkrstanding of ECT signals and techniques.

2 RPC work confirms Iaeoeace of IGhpGSCC in eggcrates and sludge pQe Quoth hot and cold leg).

II St. Lucie Unit 41

>>uggi g Hi Year

~

S G1A S GIB Remarks Mfg.

1977 1978 1979 1981 1984 1985 1986

'987

, 56

~

~ 264 17 13 19 30 Shop Plugs Ptugs foe DS Rim Cut Tight Radius U"Bend Pr~entive U-Bend Plug Random Defects KbuMm Indications Post Review Plugs QGh/IGSCC)

IGA/IGSCC Total Plugged

~ 1 I

l I

~ St. Laciest 41 Ste Generate Histocical Data 20%

39%<

1978 1979 1981 19814'984 1985

'985+

1987 N/A NIA 25

., 201 286 441

'50 N/A N/A 10 131 352 559 N/A N/A 60

~

71 95 76 2nd Ezamhmticm 1981

+ Poet Revi~

IGA IGSCC METALLOGRAPHY SLUDGE PILE 4 TUBE SUPPORT CREVICE AREA ECT LOW PH MECHANISM ACID SULFATES WlTH CHLORIDES CERL MULTEQ SEAWATER HISTORY DEPOSIT ANALYSIS LITERATURE LAB WORK

FLORIDAPOWER h LIGHT ST. LUCIE UNIT 1 EDDY CURRENT PRESENTATION TO THE NRC JUNE 4, 1987 OUTLINE L

ECT DEVELOPMENT PROGRAM IL UPGRADE OF DATA ANALYSIS GUIDELINES AND DATA ANALYST TRAINING IIL 1987 ECT EXAMINATIONPROGRAM

'V.

1987 ECT FLAWDISTRIBUTION V

1985/1987 GROWTH STUDY VL INMENERATORFLAWCHAIMCTERIZATION VIL CONCLUSIONS MCI3:3 PROC.

DEVELOPMENTPROGRAM FOR PSL-I S/G ECT L

SLUDGE PILE REGION IL EGGCRATE REGIONS IIL DRILLIKlSUPPORT REGIONS MCI3:3 PROC.

1987 ECT DEVELOPMENTPROGRAM OMECTIVES L

FABRICATEIGAANDIGSCC SAMPLES IL CHARACTERIZE 1985 INMENERATORSIGNALS-FLA%S/DEP0 SITS IIL REPLICATE SIGNALS IN LAB IV'.

DEVELOP OPTIMUMTEST FOR EACH REGION

~

'4

~

MCI3:3 PROC.

I 0

OUT L I NE/ S UMh!A RY TECH.

SPEC.

CHANGE --

REG.

GUIDE l. 121 JUSTIFICATION INCREASE OF S

~ G.

TUBE PLUGGING LIMIT ST.

LUC I E, UNIT 1

I.

C-E/EPRI LOCA ANALYSIS EXP ERItiENTAL VERIFICATION I I.

TUBE BUNDI.E LOCA ANALYS I S.

III.

TUBE BUNDLE" MSLB ANALYSIS I V.

NRC STAFF CRITERIA (AP h1ARG INS)

V.

RESULTS:

REG.

GUIDE

1. 121 ANALYSIS ALLOWANCE FOR ECT ERROR ALLOWANCE FOR FLAW GROWTH 63K ALLOW.

DEGRADATI ON

-5r NET ALLOWABLE PLUG TUBES DEGRADED 535

/4o I

I

//0 l4 lh TYPICAL. TUBE BlPiKLE

I tl

Fp hP

~ Atubc

&'y Fy FLUID FORCES ACTIHO OH TUBE EXAGGERATED DFXLECTION TUBE RESPONSE TO RAREFACTION LOAD

RAREFACTION LOAD AUD STRESS IJS.

TILIE

~ lOADIN6 l

n h

I V

p DIRKI 5IRE55

/%

44 20 10 0

lEMDlN6STRESS'20 40 120 160 IlHE SEC x 10

~

~

4

PURPOSE OF THIS STUDY EXPERlNENTAi LY VERIFY:

CQNPUTER CODE "FLASH" NODELING TECHNIQUES ALSO STUDY EFFECTS OF'.

BRFAK OPENING TINE BREAK OPENING AREA BREAK LQCAI ION (PIPE LENGTH)

OPERATING PRESSURE, TENPERATURE, AND FLON RATE f'lIXED TUBE LENGTHS

k

~ I l

4~f tg f}f iw.

0

~

+Y

~'

f

>>v$

f f

~

~

"h

~ J

~

t

\\ff p

~ ~

5 5 ~

.)

P $

4-

~5k'tip,,

+

Pg p

5 FIGURE D.l EPRI/CE PROGRAM S144-1 LOCA 8LOWDOWN SIt1ULATION TEST STAND D.2

I ~

I

P1 06 P1 07 P105 Dl, Al KISTI ER GAUGE LVDTAND/OR ACCELEROMETER 0

SYSTEM PRESSURE Cl STRAIN GAUGE PAIR Lcl SG1 P118 P108 SG2 SG3 0

THERMOCOUPLE 8

LOAD CELL REACTOR VESSEL SIMULATEDVOLUME Pill P119 Q SG4 P104 LC2 P R ESSUR IZE R Tpl Psl PL1 P103 Pl '12 P102 PUMP Pl TC5 QOV P 113 I

TC3 P101 I

ATKOMATIC VALVE BREAK Tl ORIFICE P117 PD1 COLD PLENUM P2 LOOP HEATERS HOT PLENUM P116 P115 P114 T2 Figure 3-2.

Steam Generator LOCA Blowdown Loop Schematic

- Base Line Tests 3-3

I P107

'108 P106 9

10 ll 12 13 8

P105

'P109 14 15 16 P110 Pill 17

~

~

N:IIODE NUIIGEG PXXX KISTLER GAUGE 10 6

P104 P112-19 30 2

PRESSURI2ER 31 29 4

P103 20 P 113 21 22 26 I

I r-33 27 28 I

38

~

Q9 37 RV SIMULATOP, 35

$34~-

36 ELECTRIC HEATERS P

45 I OI

~IPI 2

INLET PLENUM OUTLET PLENUM P

14 23 P115 24 25 46 47 ~48

TO VENT PIPIIIG P116

=P117 BREAK PIPING 0

42 41.

PUMP FIGURE 2

CEFLASH Model for Steam Generator Blowdown Simijl<ition Loni>

?t.

I

); n.

r>:

L L 3 I

i Baseline Test (A09)

C Q. I c g tat e" l>l>o ca'ted 3'""

C l

a~l

~l)

Ck Vi (P

~

'28 0

l S~;0 n

I

~.

I )

~

C 0

n ID

~ J I

\\

)

\\

I II

~

)

)

)

I I

I I

I/

I I

I I

)

g

)

I

~ ~

I

~

/

)

I

' \\

- ibG t')

c C) e C)

C'J C)

C)

C),

C)

C)

FIGUR E 5.

A Comparison of 'the Calculated and the Measured Pressure Di fference Across the Hori zontal Tuhe Span

TA 1

SUMMARY

OF INDEPENDENT PARAMETERS. AND RESULTS Baseline (1)

Break Opening Time Break Opening Tine t.wg Ttvk 1 L4 0 p Flow Rate 2-3 9.27 (4.20) 16 ~s~c, 9.44 ibm/sec.

(2(.28 Kg/sec)

Cold Plenum

~Tem 598oF (314.4oC) 600 (315.6) 208.2 psi 283. 7 (1.96j:

193.8 psi

~ (1.34 HPa)

I 231.8 (1.60)

I Bor)~o A~) 'o~5>oem)

Span hP, Span hP, Measured Calculatecl'ifference

- 6.9

-18, 3 Area Rati CEFLASM/Te 1.02

l. 06 Break Opening Time Break Opening Time Flow Rate Flow Rate Cold Plenum Temp.

Break Opening Area (2)

Break Opening Area (3)

Maixed Length Tube Bundle 27 45 17 17 19 17 16 24 ft 14,4 9:25 (4.20) 9.46 (4.29) 4.15

(-1. 80) 9.77 (4.43) 9.32 (4.23}

9.41 (4.27) 9.10 (4.13) 602 (316.7) 601 (316. 1) 598 (314.4)

'00 (315.6) 546 (285.6) 597 (313. 9) 597 (313.9) 601 (316.1) 185.7 (1.28) 168. 9 (1.16) 201.9 (1.39)

~

196.4 (1.35) 247.7 (1.71) 187.8 (1.29) 193.2 (1.33) 196 (1.35).

164.4 (1:13) 148. 1 (1.02) 183.0 (1.26) 180.1 (1.24) 214.1 (1.48) 185.3 (1.28) 185.9 (1.2e) 190.7 (1.31)

~

-411. 5

-12. 3 9.4

- 8.3

-13

~ 6

- 1.3

- 3.8 2

~ 7 1.05 1.17

l. 14 1.04 1.16 1.14 0.96 12 ft

( 1)

Break Area 3.64 x 10 ft (3.381 x

(2)

Break Area 2.43 x 10 3 ft2 (2.261 x

3)

Break Area 4.86 x 10 ft (4.515 x

.r)

Area under the AP (P105-Pl(i)

curve 212 (1.46)

-4 2

10 m ) unless noted otherwise 10-4 m2) 10 4 m2) 220. 9 (1.52)

+ 4.2 1,26

g ~

FIGUR LOCA THERMAL-HYDRAULICMODEL 21 22 20 23 19 2$

IB D

Secondary

)2 D

34 Secondary 81 25 17 26 16 27 15 11 12 13 13 12 15 14 26 30 33 30 33 S. I. Tank fl'.

I. Tank f2 S. I. Tank t3 Fill Systea 10 5

6 35 H

Hade 31 32 31 32 29 37 29 51 55 H

Flow Path

FIGURE B.3 LOCA THERMAL-HYDRAULICMODEL STEAM GENERATOR DETAIL)

Primary System 41 42 43 40 41 42 43 44 40 39 45 39 46 46 25 47 22 47 20 21 49 49 19 36 24 17 27 15 14 30 26 29 B.4

FIGURE 8.4

'LOCA NET FORCE VS.TIME Tube Row 0 140

. -80 70 60 50 40 Vl O

4 30 20 10

-10

-20

0. 02

0. 04 0; 06 0.'08 0

I 10; 0.>12 0.]4';16':18 0.20 Time, Seconds

TABLE C.1 LOCA AND SSE SEISMIC STRESSES MAXIMUM LOCA MODEL ROW STRESS KSI REDUCED LOCA SSE STRESS KSI NODE

.2 3

s 5

10 12 13 14 15 16 17 18 19 25.9 24.0 20.8

".19.9 18.7 16.8 16.2 18 '

22.2 23.7 37.72 34.6 28.7 21 F 9 20.7 21.9 22.4 22.1 23.0 19.43 18.0 15.6 14.93 14.03 12.6 12.15 14.1 16.65 17.78 28.28 25.95 21.53 16.43 15.53 16.43 16.8 16.58 17.25 2.8 5.7 4.9 4

7.

4.5 4.3 3.7 1.3 7.4 6.7 7.1 5.3 4.0 3.0 2.4 1.7 1.7

.7 4.1 505 32 55 80 105 130 164 682 213 238 259 284 309 334 859 884 909 934 964 The LOCA Stresses are reduced by 25% per Appendix D.

C.2

SECOIGlARY FUN AXD TUBE IlfFERACTZON PORCES ACTINO ON TUBE 1?XAGGERATO) DEFLECTION TtR DEFTZCTfON DUI: TO kSIS ACC]blued VliN

FIGURE 8.16 MSLB THERMAL-HYDRAULICMODEL Secondary System 25 1

1 5

me g

floe Path

~ ~

~

25 22 20 20 6

6 24 23 23 26 PlLL 19 19 I

5 18 10 10 12 13 16 15 16 15 16 8.17

NSLB I

FIGURE B. 17 BEND REGION PRESSURE DIFFERENCE.VS 30 (u

25 uC C7 S

20 IC)P'5 o.

10 C

-10

~ 0

~

I 0.2 0.4 I

, '0;6 0.8

~ i~ ';

I

':I':, '~

)

'.Time, Seconds 1.:0

~ J g

,I)

~

~

I

IX.

NRC STAFF CRITERIA FOR MINIMUM ACCEPTABLE TUBE WALL THICKNESS 1.

Tubes with detected acceptable defects will not be stressed dur-ing the full range of normal reactor operation beyond the elastic range of tube material.

2.

The.factor of safety against failure by bursting under normal operating conditions is not less than three at any tube location where defects have been detected.

3.

Crack-type defects that could lead to tube rupture either during normal -oper ation or under postulated accident conditions would not'be acceptabl e.

These criteria are from Reference 1 and are in addition to the fault-ed allowables of Section III.

Figure E. 1 presents the minimum re-quired thicknesses for tubes based on the above criteria.

20

1.

NORMAL OPERATION 2.

NORMAL OPERATION 3.

STEAM LINE BREAK o

S

= 27.9 KSI, 600 F

3 a

< S= 80.0 KSI, 600 F

a

<.7 S= 56.0 ksi, 600 F

NORMAL OPERATING PRESSURES R

r S-05P

+P 3aP R

r S

+

P U

~P Ri r

0.7S

-0.

P

+P U

P>

= 2250 psia P2

= 815 psia aP

= 1435 psi STEAM LINE BREAK 1.435

.327 r

27.

-.5 3.065 t

= 0.0178 in.

r I Al low. Degradation

(.048 -.0178)

X 100

.048 3(1. 435) (. 327 1

8 -.

30

)

t

= 0.0179 in, r

/ Allow. Degradation, 0

I 100 2.25 (.327

. r t'

0.0134 in.

X 'Al 1 ow.

Degrada tion P2=0 Pi

= 2250 psia

= 63

= 63

= 72 FIGURE E. 1 EVALUATION PER NRC REG.

GUIDE 1.121

~

~

4

80 70 60 NRC STAFF CRITERIA'OCA

+ SSE EVALUATION

/

50 C) 40 30 UJ 20.

ACCEPTABLE REGION 10 0

0 20 40 60 80 100 120 140 TUBE ROW NUMBER I

FIGURE E.3 ALLOWABLE'UBE LIALL DEGRADATION FOR TOTAL TUBE BUNDLE

~

I

~ I 0

DEPTH OF GENERAL ATTACK A.

j t

I

~

~

h.~

2 ~

< ~

DEEP ISOLATED PENETRATION

"--<<-n>>.~

~..-

tX p

~

~-

~

W FIGURE C2-1 IGA ATTACK - TUBE SAMPLE 78110, 50X MAX PENETRATION - 56K, 1 to 3 VOLTS DEPTH OF GENERAL ATTACK

~.-..'..-..'-

~

".'."'-~ ':

~

~

~

~

~

1 4

~

~

~

P 4

w. '.

~

~

~

~

g'

w. a

",~"

'e'~'Pa

'y e

~~,

I

~ ~.~,

~

~'

FIGURE C2-2 IGA ATTACK -

TUBE SAMPLE 78109, 50X AVG PENETRATION - 25K,

0. 1 to 0.4 VOLTS

~ l I

SCHEMATIC. OF CE El Wl TUK= BURG i AhJD LE'AK. RAT'2.

3 EST I=A.CIL,li'Y T'Q CQUDF hJSER.

T.%ST MODEI-P.R.ESSURE T'~Mba&DUC:K,~ xaam I=IT%I%&

TUBE eI ECImaN l{OQED FI OW'RII=ICE F'LA~

T~ TEST' OOP'OMAGE,R.

WEAOER FROM T2 ST' QO P HE.ADKR

~ I I

I

IGA TUBE DEFECTS-CORRELATION WITH BURST PRESSURE FPBL ST.

LUCIE 1 S.G.

TUBE BURST TEST DATA - SUPP.

2 TABLE C1-1 Tube Sampl e I.D.

Defect Dimensions Axial Circum.

Length Extent (In.)

(Deg.)

Tested Burst Pressure (P>>)

Standard ECT Basis Defect Predict.

PTest Burst Prdt.

De th P

P (5 Wall)

(psi)

Metallography Basis (Max. Depth)

Defect Predict.

PTTest Depth PB t

Pp

(% Wall)

(psi)

Testing Conducted at 600 2-1 2-4 2-5 2-6 2-~

2-8 2-12 2-13 2-14 2-17 2-21 2-23 1.0 7.5 1.0 7.5 1.0 7.5 1.0 7.5 1.0 7.5 1.0 7.5 1.0 7.5 1.0 7.5 1.0 7.5 1.0 7.5 1.0 7.5 1.0 7.5

>9150 6400 7750

>4200

>8500

>4600 4800 6600 7250 4100 7800 4700 65 48 56 55 28 56 61 45 50 58 40 53

~

V 4007 5882 5005 5115 8031 5005 4452 6208 5664 4785 6749 5335 NA 33 1.09 59 1.55 41 NA 46 NA 35 NA 54 1.08 68 1.06 54 1.28 63 0.86 74 1.16 65 0.88 66 7499 NA 4674 1.37 6641 1.17 6100 NA 7285 NA 5225 NA 3672 1.31 5225 1.26 4230 1.71 2996 1.37 4007 1.95 3895 1.21 The above twelve samples comprise all burst test data.

missing numbers represent unsuccessful IGA flaw implementation.

Maximum safe test vessel pressure'as reached.

The data are plotted since they represent lower bound burst pressure.

These samples developed small through wall leaks and could not be pressurized to burst.

While the data are not

plotted, they are meanin'g ful in that they demonstrate "leak before break" behavior.

~ l

IGA TUBE DEFECTS-CORRELATION WITH BURST PRESSURE FPSL ST.

LUCIE 1 S.G.

TUBE BURST TEST DATA - SUPP.

1 TABLE C1-2 Tube Sampl e I.D.

Defect Dimensions Axial Circum.

Length Extent

( In. )

(Deg. )

Tested Standard ECT Basis Burst Defect Predict.

PTTest Pressure DePth Burst prdt (psi)

(I Wall)

(psi)

Metallography Basis (Max. Depth)

Defect Predict.

PTTest Depth PB PP d

(% Wall)

(psi)

Testing Conducted at Approx.

565 F

1-2 1-3 1-6 1.0 1

~ 0 1

~ 0 1.0 1.0 1.0 90 90 90 90 90 90

>9600

>8500 6600

>8000 3500 4650 15 35 45 50 65 85 9396 NA 18 7285 NA 20 6208 1.06 69 5664 NA 40 4007 0.87 74 1742 2.67 78 9083 NA 8873 NA 3559 1.85 6749 NA 2996 1.17 2542 1.83 1-7 1-8 1-9 1-10 1.0 180 1.0, 180 1.0 180 1.0 180

>8500

>8000 6650 3450 20 40 50 90 8873 NA 6749 NA 5664 1.17 1166 2.96 13 42 63 75 9603 NA 6533 NA 4230 1.57 2883 1.20 1-12 1-13 1-14 1.0 360 1.0 360 1.0 360 1.0 360

>8500

>8500 5900 5550 25 40 50 70 8348 6749 5664 3447 NA NA 1.04 1.61 32 17 58 63 7606 NA 9187 NA 4785 1.23 4230 1.31

IGA TUBE DEFECTS-CORRELATION WITH BURST PRESSURE CPC PALISADES S.G.

TUBE BURST TEST DATA TABLE Cl-3 Tube Sampl e I ~ D.

Defect Dimensions Axial Circum Length Extent (In

)

(Deg

)

Tested Standard ECT Basis Burst Defect Predict.

PTTest Pressure Depth PD t

PP Burst Prdt.

(psi)

(% Wall)

(psi)

Metallography Basis (Max. Depth)

Defect Predict.

PT Depth PB t

PP dt.

(% Wall)

(psi)

P-1 P-12 P-13 P-14 2 Sampl es T

3 0 II On 3.0" 3 0" 0tt Uniform Circumferential 360

" ~

4625 53 360 4125 56 360 5950 43 360 6000 45 360 450 IGA Tested at 600 F (1974) 4535* "

1.02 58 4255*

0.97 58 5461*

1.09 46 5277*

1.14 43 100 4067*

1.14 4067*

1.01 5185*

1.15 5461*

1.10 0

N/A P-39 P-40 P-42 3 Samples Local 20%

0.5" 75 0.5" 75 0.5" 75 0.5" 75 Wall Thinning + IGA Tested at 600 F (1974) 7500 49 5773 1.29 54 6500 55 5115 1.27 77 5300 50 5664 0.94 70 2400-100 3300 5225 1.44 2656 2.45 3447 1.54 0

NA A-1 A-2 A-3 A-4 A-5 B-1 8-2 NA NA NA NA NA NA NA Nondegraded Tubes NA 9550 NA 9600 NA 9850 NA 10,150 NA 10,150 NA 10,200 NA 10,350 Tested at 600 F (1975) 9300*

1.03 9300*

1.03 9300*

1.06 9300*

1.09 9300*

1.09 9300" 1.10 9300*

1.11 NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA ote* - Based on General Surface Attack (Corrected for Tube Swelling)

~ I I

I

IGA TUBE BURST TEST DATA -

LABORATORY DEFECTS DEFECT KEY: 0 ST.

LUCIE IGA Q.

'ST.

LUCIE IGA (UHBURSTED) 0 PALISADES WASTAGE

+

IGI' PALISADES CIRCUM.

IGA CE NOHDEGRADED 0.048 In.

!~ALL GEOMETRY:

TUBE O.D.

= 3/4 INCH WALL t

= 0.048 INCH MATERIAL:

IHCONEL 600 ANNEALED CE SPEC.:

55 KSI

> a>

> 35 KSI MILL TEST:

90 KSI 9 6000F:

a 80 KSI I

I

":I '.

e i

1 '

"I I !-'- t - -"I"'"'"'

I 12

~ ~

~

e ~

REFERENCE BURST PRESSURE FOR LOCAL TUBE WALL DEGRADATION

~ ~ ~

10

~

~

.i l:i!i!iiii!

i:!i I!

.:: ~ I:

~

~ I

~.::e

~ I

~

F 1 '

1 eI';I e

!.Ii

~

~

CA 8

~M Ill'. elle

~ I:l aery

~

~

~

~

'::I 'r:

'.:: ~.".

~

Ii):::

~ ~

REF.

BURST PRESSURE FOR UNIFORM TUBE WALL THINNING 6

~ ". "."..'.I: I:.

.:p

~

~ I

~

~

i:

I I'.

~

4 I

.....l..:.

I...

~

~

REGION OF OPERATION FOR 40K TUBE PLUGGING LIMIT REGION FOR 54%

IMIT I

~ ~

~ ~

~

~

~:.I

~ ~

I e

0 10 20 30 40 50 60 70 80

'10 X TUBE WALL DEGRADATION BY ECT

~ ~ I

~

I';,

"I:

1

~

~

e*

i

. ~ 1 0

100

~ /

lt

1.0 0.8 Q

o.6 0

a. CI~0.4 UNCONSERVATIVE

~

~

~ ~ ~

0

~ ~

~

~

~ 1

~

~

~

~

~ ~

~ '

0.2 CONSERVATIVE

~ i ~

O.E, 0:0 0.2 O.4 0 8 (ACTUAL) hPp 0.8 1.0 FIGURE Cl-2 Comparison of Predicted and Actual Burst Pressure Parameters for All EDH Slot Specimens EOM MOI~

IIIBE SIZE

~ O.Bh a O.OQ iiEAI 8 E II

~ 0 hO a 0.0:I ~EAI Ci 0, hO

~ 0 DAC iHEAi Dl

~ 0 IZB a 0 OII i"EAIDI M Al U'IDEEECIEO f

~ ~

$0 U

l0 EO

!0 i

0 I0 EO IO AO 50 00 IO BO l00 ACIIIALOEIECI DE PlH A siIII FIGURE Cl-3 Eddy-Current Indicated Defect Depth Versus Actual Depth for EDM Slot Specimens

OfIfC I LLh'4IIL 10 Lc'cOIILCILO Of IKCI Of PIH

< LYALL LCI ALLASuILLO I C IUAL 7

e I/l CD 4

CD 0

0.25 0.50 0.75 1.00 1.25 1.50 OEFECT LENGTH (incIIOSl FIGURE C1-4'urst Pressure Versus Defect Length for EDN Slot Heat 8 {0.875 x 0.050) Tubing

'90 SO 70 laJo 60 40 Cb 30 Z

I CJ 20 10 P

P,I 0

~ P I

~ ~

~

~

4

" REGION OF-1978 PLUGGIl'tG PRACTICE

~ 0

~

~ ~ r

~

P

~

g C

~

0

~

~

g~o

~

o,

~

L

~

~

~

~

~

~, Pa

~ 'C'o

~l P

~\\

~ ~

~ ~

~

~

~

~

~

~~j

~

~ 0

~ ~ 0 1

2 3,

4 5

fc 7

8 9

10 11 12 BUAST PAESSUAE (Icsil FIGURE Cl-5 ECT Indicated Flaw Depth Versus Burst Pressure for Various Flaw Types, Ref.

C1-6.

1.0 0.8 h/t = 0.25 0.6 hP

'o 0.4 0.2 ST.

LU 1

S.G.

TUBE h/t 1.00 h/t = 0.50 4/t = 0.63 h/t = 0.75 0.0 0

~

W

~

2 4

6 8

10 12 L// Rt

~

P L

(PREDICTED) = 1 We 0 373 ~t hPo t

14 16 1

FIGURE Cl-G Burst Pressure Parameter Prediction Curves for EOM Slot Specimens - Length Parameter Variation

OUT L I NE/S UNt.PRY TECH.

SPEC.

CHANGE --

REG.

GUIDE l. 121 JUSTIFICATION INCREASE OF S.G.

TUBE PLUGGING L ltlIT ST.

LUC I E, UN IT 1

I.

C-E/EPRI LOCA ANALYSIS EXPERIMENTAL VERIFICATION

~ b

~

I I.

TUBE BUNDLE LOCA ANALY5IS-I I I.

TUBE BUNDLE tdSLB ANALYSIS I V.

NRC STAFF CRITERIA (AP t1ARGINS)

V.

RESULTS:

REG.

GUIDE

1. 121 ANALYSIS ALLOWANCE FOR ECT ERROR ALLOWANCE FOR FLAW GROWTH 63K ALLOW.

DEGRADATION NET ALLOWABLE PLUG TUBES DEGRADED 53/.

54%

1987 ECT DEVELOPMENT PROGRAM RESULTS L

SLUDGE PILE DEPOSTIS WERE REPLICATED WlTH BRASS IL SLUDGE PILE DEPOSITS COULD BE SUPRESSED BY MIXING IIL EGGCRATE NOISE CAN BE DISCRIMINATEDFROM SMALL AMPLITUDEFLAWS DRILLEDSUPPORT FLAWS CAN BE CONFIRMED ON OTHER FREQUENCY CHANNELS V.

THE OPTIMUMTEST IS THE.580" SF/RM PROBE

\\

VL THE ROTATINGPANCAKE COIL BEST CHARACTEEUZES FLAW GEOMETRY AND DEPTH MCI3:3 PROC.

ECT EVALUATIONCURVE 4.1 vs 3 POINT FIT CURVE 88

'r.

58

'8 r

c "~

F" 18 18 28 38 48 58 68 78 88 98 188 118 128 138 148 158 i TlNOUGH l4LL VSo RASE Q4kE <DEGREES)

DEO CH~EL 4 1

112 68 49 188 155 28 8

8 28 58 DEO48 188 183 68 147 17 8

8 28 58 MCI3:3 PROC,

~

~

1985 'A'/G PULLED TUBE DATA DEFECT DEPTH BY EDDY CURRENT AND METALLOGRAPHY ECT DEPTH DETERMINED USING *1 CURVE AND 3 PFC TUBE LOCATION ET DEPTH (1) 4.1 CURVE ET DEPTH (3) 3 P F C MET DEPTH REMARXS L 120/1Z-2 120/12-7 SLUDE PILE O3 EGG CRATE 41%

82%

33%

79%

30%

72%

IG/TG SCC IG/TG SCC IIL59/95M 59/95-5

~ i ~

41 EGG CRAGE 42 EGG CRATE

'L 79/91-2 SLUDGE PILE NDD 57%

62%(2)- --

Z9%

NDD 47%

56%

18%

16%

42%

52%

13%

IGA IGA IGA IGA 5 PULLED TUBE DATAPOINTS ANALYSIS CURVE MEAN OVERCALL STANDARD DEVIATION 3 PF

+12.4

+ 2.9

+

9 NQ NOT QUANTIFIABLE (1) EDDY CURRENT RESULTS BASED ON FIEXZ) ECT DATA (2) PER CENT THROUGH WALLASSIGNED AFTER TUBE PULL (3) ECT DEPTH DETERMINED BYTIIRIKPOINT FIT CURVE MCI3:3 PROC.

1985 PSL - 1 PULLED TUBES COMPARISON OF 4.1 CURVE AND 3 POINT FIT CURVE 100 CONSERVATIVE 80 E

C T

D E

P T

H 70 30 h

+

3 PF CURVE IS MORE ACCURATE AND STILLCONSERVATIVE 20 10 NONCONSERVATIVE 10

'20 30 40 50 60 70 80 90 100 4 1 Curve 3 PF Curve

+

MCI3:3 PROC.

4 UP-DATE PSL 1 INTERPRETATION GUIDELINES AND TRAININGPROGRAM FOR DATAANALYSIS 100 KHs ABSOLUTE RESPONSE IN EGGCRATE REGION CAN BE USED FOR FLAWCONFIRMATION.

~ I USE OF 400/100 KHx MIXDATAAND 600 KHxTO CONFIRM FLAWS IN DRILLEDSUPPORTS.

3.

USE OF 600/100 KHx MIXDATA'TOSCREEN SLUDGE PILE AT TOP OF TUBE SHEET FOR FLAWS.

4.

A MIXOF 600/100 KHx IS EFFECTIVE FOR SUPPRESSING DEPOSITS AND USING 400 KHz OR MDQNG 400/100 KHx CAN BE USED FOR QUANTIFICATION.

5.

EVALUATIONCURVE CHANGED TO 3 POINT FIT CURVE.

MCI3:3 PROC.

1987 ECT EXAMINATIONPROGRAM PSL-1 1.

NO CHANGE IN DATAACQUISITIONEQUIPMENT FROM 1985 2.

EXAMGREATLYIMPROVED FROM DEVELOPMENTVORE.

3.

DDA-4 DATAANALYSISEQUIPMENT OPTXhGZES ANALYSIS.

4.

SPECIAL TEST INMENERATOR A

MRPC TO CEQQMCTERIZE AND CONFIRM HL/CLBOBBIN RESULTS B.

DENT SUPPRESSION ADJACENT TO STAY RODS.

C.

PROFILOMETRY A S/G HL MCI3!3 PROC.

ST LUCIE UNIT 1 FLAWDISTRIBUTIONBY PERCENT THROUGH WALL 20-39%

559 (323/236)

~187 4095 OR GREATER 76 (47/29) 1985 103 (74/29) 519 (356/163) 950 (582/368) 1585 458 (ZZ1/237 1080 o

GENERAK SHIFT OF FLAWS TO LESS SEVERE CATEGORY DUE TO USE OF 3 POINT FIT CURVE.

o OVEEVQL INCREASE IN FLAWS DUE TO IMPROVED TEST AND ANALYSISCRITERIA AND IMPROVED EXPERIENCE LEVELIN DATA ANALYSIS.

MCI3:3 PROC.

1985 1987 GROWTH STUDY

'A'TEAMGENERATOR NO OF DATAPOINTS 114 MEAN

-12B33 STANDARD DEVIATION

+/-8.654 o

RESULTS. OF COMPARING 1985 VS 1987 DATA FOR INDICATIONS 20-3g% IN.BOTH YEARS AND MATCHINGLOCATION.

o RESULTS INDICATE ESSENTltALLY NO GROWTH WHEN THE -12 333 MEAN IS ADJUSTED TO ACCOUNT FOR THE DIFFERENCE. IN THE 4.1 AND 3 POINT FIT CURVES.

NOTE:

1. INDICATIONSOF LESS THAN 20% WERE NOT USED IN STUDY

2. IN THE DEPTH RANGE OF 20% TO 40% THE DIFFERENCE OF THE 4.1 CURVE AND THE 3 POINT FIT CURVES IS 12%.

MCI3:3 PROC.

A S/G MRPC EXAMINATION L

MRPC 27 BOBBIN COIL INDICATIONSTO CONFIRM AND CHAIMCTERIZE BOBBIN RESULTS IL MRPC CONFIRMED BOBBIN RESULTS IIL BOBBIN TEST MORE CONSERVATIVE THAN MRPC TEST IV.

MRPC RESULTS CONFIRMED THATINMENERATORHL/CLINDICATIONS ARE CONSISTENT %XTH PULLED TUBE OBSERVATIONS MCI3:3 PROC,

~

~

CONCLUSIONS L

THE3 POINTFITCURVEISMOREACCURATE IL EXAMINATIONTECHNIQUESHAVEBEENOPIIMIZED IIL NEW FLAWINXIIATIONIS NOT OCCURRING IV.

NO APPARENT GROWTH IN EXISTING FLAWS FROM 85/8?

V.

NO ACTIVE CORROSION MECHANISM IS OCCURRING IN THE STEAM GENERATORS r

~

1 VL,HL/CLIN GENERATOR FLAWS ARE CONSISTENT WZTH PULLED TUBE OBSERVATIONS MCI3:3 PROC.

N

~

o lCAJOKRY C% R 4, D AQCND AT CAQSTI Kkk

~

HK SCXLRR TRNTItOR AND% XkAs TRST DURATXM h

~

~ 4

~

""SO 40 yyea e

c

110 ST.

LUCIE UNIT NO.

1 170 150 130 16

~'

00%

9'Sc 1987 ECT REVIElKD FOR 20%.JQ GAUNT T IONS lFE'H

= 178 110 QO 70 1.

INDIChT IONS SHOVING NO APP&&NT GROWI'H 50.

2.

INDI ChT IONS SHOVING hPP&KN'I'ROVI'H 40 30 3.

INDICATIONS SHOVING APPhRENT DECREASE 20 io 0

2.

3.

160 140 100%

'5m 88m ST.

LUCIE UNIT 1

1987 ECT INDICATIONS NOT REPORTED IN 1985 130 120 M

100 9P R

80 128 L

80.5m.

S/G A 20m AND GIGSTER = 159 70 60 50'0 30 20 15 10 5

0 2.

12 1.

IMPROVED DETECTION/ SIZING AND ANALYSIS CAPABILITY

,'.'ISTORTED SIGNAL 1985 3.

UNKNOVÃ 1985 4.

INDICATION NOT PRESENT 1986

~ l l

0

>a LL 1985 1987 HISTORICALREVIEW OF ECT DATA-PSL-1

'OR NEW FLAWINI'HA'DON J

~

HISTORICALREVIEW CONSISTED OFc 1.

ALLFL'AWS 40% AND GREATER A 8c B S/G.

2.

SLUDGE REGION - 30 INDICATIONS20 - 39'Yi h S/G.

3.

EGGCRATE INTERSECTIONS - 30 INDICATIONS20 - 39'5 A S/G.

~ 5.

DRILLEDSUPPORTS - 30 INDICATIONS20 3~ A S/G.

~ l ~

LOVER BATWINGASSEMBLY.-5 INDICATIONS20 - 39%%uo A S/G.

6.

MID-SPAN ELEVATION-5 INDICATIONS20>> 39'5 A S/G.

DISCUSSION THE 100 20 - 39%

INDICATIONSELECTION PROCESS IS BIASED TO TUBES WHICH HAVE THE HIGHEST PROBABILITY OF CONThQGNG NEW FLAW INDICATIONSFOR THE FOLLOWINGREASONS:

1.

INDICATIONS WERE CHOSEN FROM THE A STEAM GENERATOR WHICH HAS HISTORICALLY CONTAINED INDICATIONS IN GREATER NUMBERS AND SEVERHV.

APPROXIMATEL

. 80%

OF INDICATIONS CHOSEN WERE NOT REPORTED IN 19 5.

30 THE INDICATIO WHEN~

CONTAIN RELATQTELY HIGH AMPLITUDESIGNALS TO THE TOTALPOPULATION.

1 87 ECT RXVIRVCONCLUSIONS o

NO SIGNIPICANT GROWTH OCCURRED PROM 1945 TO 1947~

SMALL NUMBER OP INDICATIONS(12lgC) WHICH VARKDWII'HINECT TOLERANCES 1 86 ECT KIEVCONCLUSION o

iGNTRVED OVER 100 TUBES (UDS, DSS, CALLEDPLAVS, ETC~ POLLOVING RESULTS OP TUBE PULL o

~

NO SIGNIPICANT GROWTH OCCUiutED PROi4 1984 TO 1985.

THE SUBJECT INDICATIONSVERE PRESENT IN 1981 IN THE llAJORZIV OP CASES WHERE DATAEXISTED.'

SMALLNUMBER VERE TRACKED BACKTO 1929.

SUMMARY

1.

STEAM GENERATOR CONDITIONWELL-DEFINED& STABILIZED 2.

MARGINAVAILABLETO ALLOWINCREASED TUBE PLUGGING CRITERIA A.

STRUCTURAL B.

ECT CAPABILITY C.

GROWTH RATE 3.

CONTINUED PLUGGING AT OVERLY CONSERVATIVE CRITERIATHREATENS LONGEVITYOF STEAM GENERATORS. IT ALSO RESULTS IN:

A.

INGREASED EXPOSURE B.

INCREASED HEATFLUX ON REMABGNGTUBES C.

INCREASED PLUGGING ALLOWED IN ANALYSIS RESULTS IN DECREASED OPERATIONALMARGINS ELSEWHERE

~ E MCI4:2

~

II E

4