ML20003A156

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Summary of 801212 Meeting W/Util Re Facility Steam Generator Insp Results.List of Attendees & Viewgraphs Encl
ML20003A156
Person / Time
Site: Millstone Dominion icon.png
Issue date: 01/08/1981
From: Conner E
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
TAC-43248, NUDOCS 8101290776
Download: ML20003A156 (42)


Text

{{#Wiki_filter:l {~' h p2 %9 \\ UNITED STATES / NCl.I AH REGULATORY COMMISSION f i 7 WASHINGTON, D. C.

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/ g Pt;d January 8,1981 e \\ j -~ Docket No. 50-336 -5 ~ Millstone Nuclear Power Station, Unit No. 2 (MNPS-2) FACILITY: LICENSEE: Northeast Nuclear Energy Company (NfiEC0)

SUBJECT:

SUMMARY

OF DECEMBER 12, 1980 MEETING WITH NNEC0 ON MNPS-2 STEAM GENERATOR INSPECTION RESULTS

== Introduction:== NNECO had requested this meeting to present the results of the recent steam generator (SG) eddy -current test (ECT) and profilometer inspection (PI) for the two MNPS-2 SGs. is a list of the NRC, NNECO and Combustion Engineering Company (CE) attendees. Summary: After opening remarks by the NRC (Conner), the meeting was turned over to NNEC0 and CE who presented and discussed the Enclosure 2 viewgraphs. P. F. Santoro (NNECO) covered the first 9 viewgraphs, J. M. Fackelmann (NNECO) the next 13 and W. J. Heilker the remaining 14 viewgraphs. Significant connients made in relationship to a certain viewgraph were: 2. The PI is supplementary to ECT and allows determinations of the ovality of dents at the egg crates; 7. No major changes seen at this one elevation. 8. The large jump in the number of tubes plugged in 1978 was preventive maintenance; 9. Highlighted the importance of the condensate polishing systems to reduce chlorides; 9. All volatile control since day one; 10. B&W profilometer probe has 8 fingers that contact the tube. Zetec probe gives same data without contacting tube (ECT type); 12. The present average of all dents is about 10 mills; 18. The calculated strain is greater at the inside surface than at the outside surface;

19. Viewgraph shows agreement between B&W and Zetec probes; 20.

The SG inspection program took a total of 3 days; 20. The profilometer measurements versus ECT data; 21. Data shows no change in the last year of measured dent size; 22. Important conclusions; 25. The analysis takes no credit for the vertical supports or partial detached grid plates; 30. The LOCA + SSE analysis results are conservative since the support provided by the vertical supports and partial detached grid plates is neglected; 81012 90 "l } Q J

Meeting Summary for l Millstone 33. The main steam line break + SSE analysis results are less than LOCA + SSE; and 37. Conclusion reached from analysis. In the concluding remarks, Mr. Santoro stated that profilometer inspection gives better definition of what is occuring at the egg-crate supports than ECT. The analysis results can be used in the selection of which SG tubes should be plugged. This is a considerable improvement over the go-no-go gage (ECT probe) presently used. NNECO intends to continue the use of PI along with ECT in future SG inspections. E. L. onner, Project Manager Operating Reactors Branch #3 Division of Licensing, NRR

Enclosures:

As stated cc: w/ enclosures

  1. ee next page 6

l MEETING SUfe%RY DISTRIBUTION Licensee: Northeast Nuclear Energy Company ) i o Copies also sent to those people on service (cc) list for subject plant (s). Docket File . NRC PDR L POR TERA HSIC ORB Rda NRR Rdg HDenton ECase OEisenhut RPurpl e RTedesco TNovak Glainas RReid TIppolito SVarga DCrutchfield RAClark ORB Project Manager Licensing Assistant OELD AE00 - JHeltemes IE-3 SShowe (PWR) or CThayer (BWR), IE RFraley, ACRS (16) Program Support Branch GZech .01shinski BGrimes, DEP Sheldon Schwartz, DEP FPagano, EPLB Steve Ramos, EPDB Mtg. Summary Dist. ERC Participants EConner RGamble JGrant EMurphy DHuang RAClark

Northeast Nuclear Energy Company cc: Mr. John Shedlosky William H. Cuddy, Esquire Resident Inspector / Millstone Day, Berry & Howard c/o U.S. NRC j Counselors at Law P. O. Drawer KK ) One Constitution Plaza Niantic, CT 06357 Hartford, Connecticut 06103 Anthony Z. Roisman Mr. Charles B. Brinkman l Natural Resources Defense Council Manager Washington Nuclear j 917 15th Street, N.W. CjP Washington, D.C. 20005 Po r stems k"e le -1 Mr. Lawrence Bettencourt. First Selectnan el Bethesda, Maryland 20014 ~i at g eg d - 200 Boston Post Road Waterford, Connecticut 06385 Northeast Nuclear Energy Company ATTN: Superintendent Millstone Plant Post Office Box 128 Connecticut Energy A Waterford, Connecticut 06385 ATTN: Assistant Dir cto, Research and Policy Development Department of Planning and Energy Director, Criteria and Standards Division Policy Office of Radiation Programs (ANR-460) 20 Grand Street U.S. Envirorinental Protection Agency Hartford, Connecticut 06106 Washington, D.C. 20460 U. S. Environmental Protection Agency Region 1 Of fice ATTN: EIS COORDINATOR John F. Kennedy Federal Building Boston, tussachusetts 02203 WaterfoM Public Library Rope Ferry Road, Route 156 Waterford, Connecticut 06385 Northeast Utilities Service Company Mr. James R. Himmelwright ATTN: Nuclear Engineering and Operations P. O. Box 270 Hartford, Connecticut 06101 .p MILLSTONE - 2 STEAM GENERATOR TUBE INSPECTION MEETING - DECEMBER 12, 1980 NAME POSITION _ NRC-0RB#3 E. Conner NUSCO P. Santoro J. Fackelmann NUSCO W. Heilker CE-Component Eng. NUSCO-Generation Engineering G. Johnson NUSCO-Generation Engineering L. Starner NRC-ORB #3 R. Clark Florida Power & Light Co. R. Acosta Florida Power & Light Co. T. Grozan CE E. Kennedy CE-Bethesda C. Brinkman R. Gamble NRC-MTEB NRC-MTEB J. Grant NRC-MTEB E. Murphy NRC-MTEB D. Huang NUSCO M. Cass CE R. Jacques A. Sudduth Duke Power Co. J. Jandovitz Consumer Power Co.

1 MILLSf0NE UNIT NO. 2 STEAM GENERATOR REVIEW INTRODUCTION -- NUSCO PROFILOMETER INSPECTION -- NUSCO STRUCTURAL ANALYSIS -- CE SUMi1ARY -- NUSC0 l I l 1 1. l

k CliRON0 LOGY OF EVENTS DECEMBER 1975 COMMERCIAL OPERATION MAY 1977 CONDENSER RETUBING DENTING DETECTION TSPL'S IMPROVED CHENISTRY NOVEf1BER 1977 EGG CRATE INl>ICATIONS BY ECT RIM CUT PREVENTATIVE TUBE-PLUGGING CONDENSATE POLISHING f1 ARCH 1979 PROFIL0 METER f1EASUREt1ENTS, 2 TUBES AUGUST 1980 PROFIL0t1ETER INSPECTION, 300 TUBES 1 i 2

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ECT DATA h DENT / PLUGGING PROGRESSION MILLSTONE UNIT NO. 2 STEAM GENERATORS 1 & 2 l 'T / I DENT SIZE g, TSPL'S NOS.10-11 HL & CL (794) (799) (800) 8. g goo j ,s PLUGGED TUBES h 2_ 7. g w m !S o [ 6. P O 5 0 O e 5. 3 c E o 4 600 e n ~ 2 3 DENT SIZE EGG CRATE 2 too NOS.1-9. HL 1. O-- y o 1977 1978 1979 1980 YEAR

l { l f MILLSTO.NE. UNIT N0. 2 l STEAM GENERATOR INSPEC110N AUGUST 1980 OUTAGE l l l VISUAL INSPECTION l f ESSENTIALLY UNCHANGED l RIM cut CLEARANCE INTACT l l l EDDY CURRENT TEST

SUMMARY

l f 140% TSPL, 13% EGG CRATES ONE (1) BLOCKED IUBE l ONE (1) IUBE PLUGGED NO DENT PROGRESSION

  • NO DEFECTS l

l CORRECTIVE ACTIONS STABILIZED DENTING CONDENSER RETUBING - MAY 1977 RIM Cur, NOVEMBER 1977 PREVENTATIVE TUBE PLUGGING, NOVEMBER 1977 CONDENSATE POLISHING, NOVEMBER 1977 CHEMISTRY CONTROL: 0.6 PPM CHLORIDE (12/75 TO 5/77) 0 (N.D.) CHLORIDE ~ (5/77 TO PRESENT) l

  • WITHIN IEST ACCURACY l

STEAM GENERATOR PROFIL0 METER INSPECTION l MILLSTONE UNIT N0. 2 l AUGUST 1980 OUTAGE f OBJECTIVES DEFINE EGG CRATE INDICAT. IONS ESTABLISH DATA BASE FOR IMPROVING IUBE PLUGGING CRITERION IMPROVE DEFINITION OF DENT EFFECTS TEST PROGRAM i STEAM GENERATOR NO. 1: 157 TUBES (B&W PROBE) STEAM GENERATOR NO. 2: 143 TUBES (2ETEC PROBE) i STEAM GENERATOR NO. 1: BOTH PROBES, 18 IUBES l l e lo

w TUBE DENTING AT EGG CRATE COMPRESSION 1 EXPANSION y 3 r f TOP 0F EGG CRATE 7(MINIMUMDIAMETER 0.610 IN,) / I ~ 8 RADII DENT SIZE OVALITY CALCULATED PROFILES TENSILE STRAIN, I.D. j BOTT0ft 0F EGG CRATE TENSILE STRAIN, 0.D. MAXIMUM VALUES MAXIMUM LOCATI0ils \\

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CT a xD b! 1 a w =W dg a mg / LLJ e l o 9 0 l

RELATIONSHIP BETWEEN MAXIMUM DIAMETER REDUCTION AND E MILLSTONE UNIT NO. 2 -- STEAM GENERATOR NO 1 AUGUST 1980 OUTAGE -- B&W PROFIL0 METER DIAMETER REDUCTION (MILS) STANDARD ELEVATION NO. OF TESTS AVG. MAX. DEVIATION 1 157 24 71 17 2 157 35 72 16 3 157 38 76 15 4 157 30 70 15 5 157 29 87 16 6 157 18 59 12 7 110 15 52 12 8 30 6 32 6 9 13 3 6 2 1-9 1095 27 87 14 e e 14

P RELATIONSillP BETWEEN FRACTION OF MAXIMUM DENTS >20 MILS (DIATIETRAL) AND ELEVATION tilLLSTONE UNIT N0. 2; STEAM GENERATOR NO. 1 AUGUST 1980 OUTAGE -- B8W PROFIL0 METER MAX. DENTS ELEVATION NO. OF TESTS >20 fMLS, % 1 157 46 2 157 82 3 157 84 4 157 73 5 157 66 6 157 38 7 110 31 8 30 3 9 13 0 1-9 1095 59 15

RELATIONSHIP 0F MAXIMUM DIAMETER REDUCTION TO ELEVATION MILLSTONE UNIT NO. 2; STEAM GENERATOR NO. 2 AUGUST 1980 OUTAGE -- ZETEC PROFILOMETER l l DIAMETER REDUCTION (MILS) STANDARD ELEVATION NO. OF TEST AVG. MAX. DEVIATION 1 143 27 56 13 2 143 18 57 12 3 142 22 55 12 4 141 15 42 10 5 142 16 60 12 6 137 7 37 6 7 124 9 47 8 8 21 5 24 6 9 0 1-9 994 16 60 13 l l f4

( 4 REL TIONSHIP BETWEEN FRACTION OF (1AXI(1UM DENTS >20 MILS (DIAi1ETRAL) AND ELEVATION T1ILLSTONE UNIT NO. 2; STEAM GENERATOR N0. 2 AUGUST 1980 OUTAGE -- ZETEC PROFIL0 METER MAX. DENTS ELEVATION NO, OF TESTS >20 tills, % 1 143 70 2 143 35 3 142 50 4 141 30 5 142 27 6 6 137 7 124 10 8 21 5 9 0 0' ~ 1-9 994 33 t i7'

1 .s c Cl) EFFECT OF ELEVATION ON "ID" TENSILE STRAIN MILLSTONE UNIT N0. 2 -- STEAM GENERATOR NO. 2 AUGUST 1980 OUTAGE -- ZETEC PROFILOMETER TENSILE STRAIN,'% INSIDE DIAMETER STANDARD ELEVATION NO. OF TESTS MAX. AVG (2) DEVIATION 1 143 1.6 0.77 0.35 2 143 1.5 0.56 0.30 3 142 1.9 0.71 0.34 4 141 2.0 0.55 0.36 5 142 1.5 0.50 0.30 6 137 1.1 0.26 0.22 7 124 1.7 0.37 0.32 8 21 0.9 0.21 0.23 9 0 1-9 994 2.0 0.54 0.36 1. IN DENTED INTERSECTIONS 2. OF MAXIMUM VALUES ' i8

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4 COMPARIS0N CONVENT 10flAL EDDY CURRENT VERSUS PROFIL0 METER MEASUREMENT OF DENT EFFECTS filLLSTONE UNIT NO. 2 AUGUST 1980 OUTAGE PROFIL0t1ETER, MILS ECT, Mits SUPPORT AVG. aR MAX. AR f1AX. AD ~ 0 EC 0.5 6 7 0.5 EC 0.5 9 10 2 EC 4.5 44 68 10 TSPL 12 46 55 4 e 20

4 1 PROFIL0 METER MEASUREMENTS OF DENT PROGRESSION IN EGG CRATES filLLSTONE IlNIT NO. 2, STEAM GENERATOR NO. 2 MAX A DIA., MILS MAX. I.D. STRAIN, % EGG CRATE NO. 1979 1980 1979 1980 L 107 R 41 1 23 17 0.4 1.1 2 42 35 1.2 0.6 3 10 39 3.5 1.1 4 39 35 1.9 1.4 5 16 17 0.8 0.6 6 40 37 1.0 0.5 L 107 R 43 1 48 43 1.0 1.4 2 18 15 1.0 0.4 3 14 9 0.5 0.6 4 10 7 0.6 0.4 5 23 22 0.7 0.8 6 18 15 0.9 0.6 AVERAGE-BOTH TUBES 1-6 25 24 1.1 0.8 r + 2 2L\\

SUMMARY

1. MOST Eco CRATE INTERSECTIONS DENTED, AS MANIFESTED BY ONE OR MORE AD OF 10 MILS OR MORE, WITH AN ASSOCIATED OVALIZATION. 2. FREQUENCY AND MAGNITUDE OF DENTS LOWER AT UPPER - ELEVATIONS. 3. AXISYMMETRIC EFFECTS ASSOCI ATED WITH Eso CRATE DENTS SMALLER THAN WITH TSPL DENTS. 4. Ecs CRATE IUBE STRAINS LOW COMPARED TO STRAINS ASSOCIATED WITH IUBE EAILURE IN-SERVICE. 5, DENTING ESSENTIALLY STABILIZED BASED ON NO SIGNIFICANT PROGRESSION BETWEEN MARCH 1979 AND AucuST 1980. 22

STEAM GENERATOR STRUCTURAL ANALYSIS FOR "EGGCRATE" OVALIZATION ACCIDENT ANALYSIS OF TUBES PER REGULATORY GUIDE 1.121 1. RELEVANT TUBE SUPPORT GE'OMETRY 2. TUBE SUPPORT ASSUMPTIONS BASED ON. INSPECTION DATA 3. LOCA + SSE EVALUATION OF BEND REGION k.MSLB+SSEEVALUATIONOFBENDREGION 5. SSE EVALUATION OF VERTICAL RISER REGION 6. CONCLUSIONS 4 \\ ~

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TUSE REIPONSE TO RAREFACTIO!! LOAD CAUSED BY LOCA 1 Fr Fp = 37 etute To ir ( Fv >4 >f e

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e F.AREFACTICH LOAD AND STRESS VS TIP.E i

LOCA + SSE ANALYSIS RESULTS FOR BEND REGION 1. MAXIMUM RAREFACTION LOAD ACROSS THE TUBE BENDS OCCURRED IN TUBE R0w 140: F = 53.5 LBS. a 0,02 SECONDS max 2. MAXIMUM STRESS OCCURRED AT SUPPORT ELEVATION NUMBER 9 (TOP PARTIAL "EGGCRATE"): (I + T = 44.3 KS1( 7 g B MAX 4ttow WHERE EI = 1. 56 ( 7 S ) = 75.9 KS1 ALLOW u ABOVE STRESS CONSIDERS LOADS DUE TO: 1) LOCA-RAREFACTION 2) LOCA IMPULSE RESPONSE 3) SSE RESPONSE (HORIZONTAL) 4) INTERNAL PRESSURE l i e e 30

D*"D TT(L .A.Q sa oo CoNr*Arpp: .2.s- / @~ E is ~ s 3 w OOOO NE (_O308 3 ,4@ ? l_ i t t 2 Q[d p b;E s--@I .l S 0 22 I 23 1* \\ (ih r i w- ..r - .z. i r @p;-- gwA--e (V.)-1-.+ L/ !&L[ L _e n l e L L: C io W - _ - - - m -- - = ii /e, W = O/7 5 s .,.,a = _ _ _ - m, q g,; m A --~_ g r-I IL /3 k__a n 17a.ll /4 13 26 nii.,.s/i,, ._... - x iS n,-<> W [s vm L 27 i is 1 ~ S. G. SECONDARN SINE FLASH MODFLING 31

M M t ), Pcs n , rFf"F7_^ " t l l I I AP/I!!CII I I I I I l ~ co e m I I I I i g I g I. 'I M "d YF fry ~ ~ r t SECONDA1W FLO'<l AND TUBE IllTERACTION FORCES 3,XAGGERATED 1)EFLECTIOli ACTIllG Oil TUBE Till1E DEFf.KCTIO!! DUM TO MSJ.h ACCJ1 Et1T l'lew e - e

-~ MSLB + SSE ANALYSIS RESULTS FOR BEND REGION 1. MAXIMUM PRESSURE DROP ACROSS THE TUBE BEND DUE TO SECONDARY SIDE BLOWDOWN WAS 32 PSI. DISTRIBUTED LOAD ON TUBE IN R0W 140 WAS: F/L = 0.232 LBS./IN. OR F = 33.4 LBS. 2. MAXIMUM STRESS OCCURRED IN THE TUBE BEND AND WAS: = 22.4 KS1 'C '0' M+ B MAX 3ttow ~ WHERE = 1.356 (.7 S ) ""75.9 KS1 ALLOW u ABOVE STRESS CONSIDERS LOADS DUE TO: 1) MSLB BLOWDOWN 2) SSE RESPONSE (VERYlCAL-) 3) INTERNAL PRESSURE

o s Support N0DAi. Elevations POINTS 234.625 EC7 cm 29 dr O 27 197.625 EC6 a 25

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O 23 162.875 EC5=== = c= O O 19 O l O ,130.875 EC4 :==

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l l TYPICAL 0 15 E 93.875 EC3 c== i 11 59.125 EC2 c.m t== TUBE R0W 36 07 27.125 EC1 c=, es !G3 ~ j-f); i i o, i i, i io i i - - ia 1 SSE EVALUATION OF VERTICAL RISER REGION s e a we-- p r m r* e 'w w Y

w /7 Dawde-SSE TUs I i.Ii,e 6 i o i!Isi 3 e iii i 1 !A i (* e i I;a6i i e i i 6 : : eie i IIilli I i i

  • I I

I I I Ill I !f a i [I i id l 1 l I ll l l 1 l ill i I ll ill i I i i 111 \\l - i i il ~ ll l I/ _ \\ II __i l_. I l n.s*,( / / / .1a f ei4 i 4 i l' i et eii /r i i e i e ie i I\\ i e i ei I I t ili / e i e i eIi il I l\\ l I list i I l i l i l/ l l l ll l l U l 0.45-f lllll l l l I l lll I I i I I ,i I NOR/2 )M7~.?L D/Rf U/CN Il'l11 i i i -el i .e >eii 4 I u e iei i i i e ieis i i i ei I I e a 11 I I I I I I I l'l i I I I i IIl l l llll l l l ll ll. l l l' l l l l! !I lill l I l li I l l lll l llll ll o01 d o = = o o -e .a t i

  • FREQUENCY (CPS)
  1. - N 'd/8 i9ds. u>

s>. / t i 3f i

SSE ANALYSIS RESULTS FOR VERTICAL RISER REGION 1. LOADING RECORDING TO RESPONSE SPECTRUM FOR VARIOUS ASSUMPTIONS: 2. SUPPORT EFFECTIVE CI MAXIMUM (KSI) B (FOR ALL I'iODES) IN-PLANE OUT-OF-PLANE NO. 7 & TBSHT. 16.1 *- 15,8 NO. 6 & TBSHT. 11.0 12.9 NOS 6, 7 & TBSHT. 12.6 12.0 . NOS 5 - 7 & TBSHT. 13.0 9.8 NOS. 4 - 7 & TBSHT. 13.6 13.1 NOS. 3 - 7 & TBSH.T. 16.1 *- 15.8 NOS. 2 - 7 & TBSHT. 12.9 7.2 THE ABOVE STRESSES ARE COMBINED WITH INTERNAL PRESSURE STRESS. (7 = 21.5 KSI 6 M B MAX 4ttow WHER'E U' ALLOW = 1. 356 (.'7 S ) = 75.9 xS I u O e e 1,

s e 4 CONCLUS10tlS 1. BASED ON PROFILOMETRY DATA, SOME VERY CONSERVA-TIVE ASSUMPTIONS WERE MADE RELATIVE TO EFFECTIVE TUBE SUPPORTS. 2. HIGHEST ACCIDENT STRESS OCCURS FOR LOCA + SSE: 4.3 KSI <( U~3ttaw = 75.9 KSI = max 3. EXPECTED WORST CASE VIBRATORY STRESSES DURING NORMAL OPERATION: CT = 0. 5 KS I 4. ANALYTICAL AND EXPERIMENTAL ON-GOING WORK TO BETTER QUANTIFY MARGINS. MARGINS ARE ANTICIPATED TO INCREASE. e e t 4 37}}