ML19256E442

Summary of 791019 Meeting W/Util in Bethesda,Md Re Feedwater Line Indicators

ML19256E442
Person / Time
Site:	Millstone
Issue date:	10/25/1979
From:	Conner E Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
TAC-11793, NUDOCS 7911050527
Download: ML19256E442 (37)

Text

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'o UNITED STATES 8

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NUCLEAR REGULATORY COMMISSION

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WASHINGTON, D. C. 20655 o

.0ctober 25, 1979 Docket No. 50-336 LICENSEE: Northeast Nuclear Energy Company (NNECO)

FACILITY: Millstone Unit No. 2 (M-2)

SUMMARY

OF MEETING HELD OCTOBER 19, 1979, ON FEEDWATER LINE CRACK INDICATIONS The meeting was held it the Comission's office in Bethesda, Maryland. A list of attendees is given in Enclosure 1.

Introduction By letter dated September 28,1979, NNEC0 submitted their proposed repair replacement program for the steam generator feedwater line crack indications at Millstone-2. This was in response to Comitment No. 4 of our August 25, 19791etter, authorizing operation until' Uctober 31r 1979.

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The staff had requested the meeting to discuss the Enclosure 2, additional information required to ascertain actions necessary regarding the feed-water system piping at Millstone-2.

Sumary After opening remarks by the NRC (Conner), the licensee (DeBarba) presented an outline, discussed the history and reviewed the previous NNECO comitments.

The viewgraphs used are presented in Enclosure 3.

• In responding to the additional information we had requested, Bechtel (McManon) de!cribed the procedure for concrete removal from the shield wall and CE (Crane) and NNECO (Kupinski) discussed repair from inside the pipe (Option B). Pictures of the Option B repair mockup,,nowing a man working inside the 18 inch Schedule 60 pipe, the air driven grinding devise and the welding machine were passed around. NNECO (DeBarba) stated that the Option B repair method was preferred.

However, the Option A concrete removal will be perfonned in parallel with Option 8 to gain access to the safe end-to-pipe weld should the Option A repair be required.

Westinghouse (Ayoob) presented the temperature / strain data taken at Millstone-2 during the startup in August, Enclosure 4.

The temperature cycles occur when auxiliary feedwater is added to the steam generators.

In this startup, about nine cycles occurred. This is more than normal since auxiliary feedwater was added for the purpose of data collection. Westinghouse (Bamford) then presented 7@oA 1255 2_76

an assessment of growth of feedwater line flaws, Enclosure 5.

This presentation is not based on the Millstone-2 data. The input parameters used were conserva-tive compared to Millstone-2.

In the concluding remarks, NNECO (DeBarba) stated that if no crack growth is found when the October feedwater line inspection is performed NNEC0 would plan

.to operate until the 1980 refueling outage in May or June.

It was also stated that the inspection would be repeated if M111 stone-2 was placed in the cold shutdown mode after January 1, 1980. We (Conner) pointed out that our Auaust 25, 1979 letter, forwarding the-safety evaluation of this pr)blea, conclude'd that Millstone-2 could be operated only until October 31,197) without'further staff review.

Conclusion During a staff caucus, questions about compliance with Section XI of the ASME B&PV code surfaced. The licensee was requested to address these concerns before any further staff review takes place.

E. L.

onner, Project Manager Operating Reactors Branch #4 Division of Operating Reactors

Enclosures:

1.

List of Attendees 2.

Additional Information Required to Ascertain Actions Necessary Regardir.g Fee + ater System Piping 3.

Viewgraphs 4.

Temperature / strain data 5.

Assessment of Growth of Feedwater Line Flaws i255 277

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L MEETING StM1ARY DISTRIBUTION ORBf4

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r Docket File R. Reid NRC PDR V. Noonan L PDR P. Check ORB #4 Rdg G. Lainas NRR Rdg G. Knighton H. Denton Project Manager E. G. Case OELD Ol&E(3)

D. Eisenhut R. Ingram R. Vollmer R. Fraley, ACRS (16)

W. Russell Progr.am Support Branch B. Grimes (TERA-)

Ti J. Carter

'JN. Buchanan A. Schwencer Meeting Summary File D. Ziemann NRC Participants T. Ippolito E. L. Conner W. Gamill Bob Hermann L. Shao Ed Jordan

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J. Miller R. W. Klecker i

B. D. Liaw T. H. Liu W. S. Hazelton Tom Shedlosky W. F. Sanders W. J. Collins 1255 278 411M506ML

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MILLSTONE-2 FEEDWATER LINE CRACK MEETING OCTOBER 10, 1979 NAME POISTION Monte Conner NRR/0RBf4/PM Eric DeBarba NUSCO Matthew Kupinski NUSCO Richard Kacich Northeast Utilities Michael Cass Northeast Utilities Bob Hermann NRC/ DOR /EB Ed Jordan NRC/IEHQ R, W. Klecker NRC/ DOR /EB P. M. McManon Bechtel J. C. Crane C.E. Chattanooga Tom Hemphill C.E. Chattanooga K. B. Frisbee Combustion Engineering W. J. Heilker C.E. Chattanooga W. H. Bamford Westinghouse A. J. Ayoob Westinghouse E. T. Hughes Westinghouse B. D. Liaw NRC/ DOR /EB T. H. Liu NRC/ DOR /EB W. S. Hazelton NRC/ DOR /EB C. W. Hirst WNTD NUC-Safety Tom Shediosky NRC/ Region I W. F. Sanders NRC/Rsgion I W. J. Collins NRC/IEHQ 1255 279

MILLSTONE NUCLEAR' POWER STATION UNIT 2 ADDITIONAL INFORMATION REQUIRED TO ASCERTAIN ACTIONS NECESSARY REGARDING THE FEEDWATER SYSTEM PIPING 1.

In your letter of September 28, 1979 you stated that thermal variations (stratification) was observed during low flow conditions. Address the potential for crack propagation during these low flow conditions (low cycle f ai;igue). Provide a quanitative analysis regarding crack growth rates during the thermal transient cycle.

2.

Assuming the analysis requested above predicts crack growth at a sufficiently low rate to ensure adequate _ safety margins can be maintained until a perm-anent repair. can be made at the June 19M refueling outage, provide the

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details of an augmented inspection program which verifies that crack growth has not occurred at a rate faster than predicted by the analysis.

3.

In the proposed repair / replacement progrim you submitted, you stated that

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the removal of the shield wall section can be made within design bases

1. imitations, a.

Provide the technical information supporting your conclusion.

b.

Provide assurance that the method of removing part of the concrete wall by drilling and chipping will not damage the concrete left in place and the existing reinforcing bars. Describe the quality assurance procedures which will be used during the concrete removal operation.

c.

Describe the procedure which will be used 5# the reinforcing bars must be removed.

d.

If replacement on the removed shield wall segment is required, address the following:

(1) Define the concrete mix which will be used to fill the recess in the shield wall.

(2) Describe the procedure for reinforcing bar.reple:ement.

(3) Define the method to be used to ensure compatibility of the new and old concrete, especially the measures planned to limit shrinkage of the new concrete. Discuss the degree of working together that can be expected from the new concrete and existing wall,

l..

Provide the details fer material removal as discussed in repair Option B.

Also, provide the detailed procedures for the weld repair on the ID of the pipe shoulc the wall thickness be reduced below Code limits. Address the cock-u:: usG to qualify the welding procedures,fer training and to qualify the v. eiders / welding machine operators.

E.

Describe the simulation for welder training and qualification to account for the li.-ited access oetween the shield wall and steam generatcr in Option A.

Provide any details regarding the consideratior cf automated welding to make the. nozzle to pipe repair.

6.

State if a UT baseline examination will be performed for the nozzle to piping weld if Option A is used.

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OF TEMPERATURE PROFILE OCCURRENCES I2 RANGE (3) NUMBEROFOCCURRENCES(I)0FPROFILE NUMBER PLANT EVENT 0F EVENTS PROFILE i PROFILE 2 1 2 3 4 5 MILLSTONE !!0T STAND 8Y 6 6 6 5 9 ._115 276-1242 276-1242 (LINE2). [ (1) NUMBER OF OCCURRENCES (WITil ATT0P/ BOTTOM"-300*F)ISBASEDONAV g (2) NUMBER OF EVENTS IS BASED ON PRESENTLY AVAILABLE PLANT OPERATING llISTORY INFORMATION. (3) RANGE FOR TOTAL NUMBER OF OCCURRENCES OF THE PROFILE AND IS CALCUL u$ X (# EVENT 5) X S. WHERE S = EVENT SIMILARITY FACTOR AND.5 S 1.5. 55

ASSESSMENT OF GROWTH OF FEEDWATER LINE FLAWS MILLSTONE II W.H. Bamford The purpose of this work is to estimate the future growth of a flaw located in the counterbore region near the feedwater nozzle safe-end-to-pipe weld. The flaw of interest has been confirmed by UT to be approximately 0.10 inches deep, and oriented circumferential1y. As a result of the location of this flaw, instrumentation was in-stalled to monitor the temperature fluctuations in one loop. Results showed that in a certain flow rate range the water stratifies, produ-cing significant stresses which are potentia 11 important for crack ~ growth. The types of stratification produced were typical of those observed .in other plants, but not as severe. The observed stratifications were classified under five different types, as shown in Figure 1. The tem-perature difference from top to bottom of the pipe for profile 1 was measured at about 350*F, whereas for other plants it has beer, found to be as high 'as 450*F. ~ ~ ~ ~ ~ ~ ~ ~ ~ T ~~"~~' A three dimensional finite element stress analysis has been completed for each of the five temperature profiles in Figure 1, and transient studies have shown that the five profiles represent limiting conditions compared with the stress results obtained for any transient step in be-tween the profiles. To accomplish a fatigue crack growth analysis, the system design tran-sients for normal, upset and test conditions were combined with the cycles of stress from stratification, which occurs during hot standby operation. As shown in Figure 2, there are approximately nine cycles of variour, degrees which for tne purpose of this analysis, we will assume, o': cur each time hot standby occurs. 1255 301

2- ~ ~ ~ ~ ._ A tabulation of. t'he cycle.. types used'in the crack growth. analysis, Talong with appl.icable stresses...is..provided in Table 1. Tables 2 threugh 5 ~ show the stresses at various locations around the pipe as a result of 'th'e stratif' cati,on. The actual stresses from the three dimensional analysis were used for the fatigue crack growth analysis, except in two cases, where compres-sive stresses far exceeded the yield stress in compression. The locat-ion is at the top of the pipe, and the condition occurs only when the pipe is nearly filled with cold water (profile 1) at low flow. For this case, tensile residual stress values were assumed to exist, equal to the yield strength. This is seen at locations 1 and 2 in Tables 2 and 4. This assumption is considered to be extremely conservative. ~ . Crack growth was calculated at each of thirteen locations around the pipe for periods of 1, 2, 3 and 4 years, assuming an initial flaw of 0.100 inches deep', extending entirely around the inside of the pipe. A fatigue crack growth law which accounts for mean stress or R ratio (omin./ e max.) as well as the presence of the water environment was used. The law is shown in Figure 3. Results of the crack growth analysis are shown in Table 6, for each of the locations considered. These results show that the observe flaws will not grow significantly during the next years service. The final flaw size for the worst location is a factor of 5 smaller than the critical flaw size for the pipe, as shown in Figure ;. f f 1255 302

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OF TEMPERATURE PROFILE OCCURRENCES I2) RANGE (3) PLANT EVENT NUMBER OF OCCURRENCESU) 0F PROFILE NUMBER OF EVENTS PROFILE 1 PRCFILE 2 1 2 3 4 5 MILLSTONE H0T STANDBY 6 6 6 5 g _115 276-1242 276-1242 (LINE2). i l i N tn TOP / BOTTOM 300*F) IS BASED ON AVAILABLE TEST DATA AND MAY VARY BY b )' NUMBER OF GCCURRENCES (WITH AT 3 W (2)NUMBEROFEVENTSISBASEDONPRESENTLYAVAILABLEPLANTOPERATINGHISTORY INFORMATION. (3) RANGE FOR TOTAL NUMBER OF OCCURRENCES OF THE PROFILE AND IS C X (# EVENTS) X S WilERE S = EVENT SIMILARITY FACTOR AND.5<S<1.5.

APPENDIX A-NONMANDATORY Hg. A 4300 1 coe .w eco ' 700 , t.w dg -- - I.0lx10 $ Goo A Soo (bk%10 4oo 300 d -7 i.9 s-g 1 - 2.52.5 to Ak. an [hY.MN 200 goo. - 9a 80 70 60 SUB4URFACE FLAWS g 50 (Air Environment) f4o = (.0267X10-8 )aK 3#2' i U /N O 30 5 gw 2 R E A* SURFACE FLAWS (Water Reactor Environinent) J 10 - Applicable for R ratio g 9 ~ (kmin/Kmex) bet m en C 8 0 and 0.5 onty. Z 7 ~ ,E h.</g_ s,0.5 8' g sv 3 dg4 M.is s o a Sas - 3.W x10 3 .u A.

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TABLE 2 STRESS RESULTS - AXIAL DIRECTION CONDITION 5 HOT STANDBY f1 Outside Surface Inside Surface Location Max. Min. Max. Min. (Ksi) (Ksi) ~ 1 40.0 0.0 -40.0 0.0 2 40.0 0.0 -40.0 0.0 3 9.46 -23.0 8.56 8.29 4 35.12 4.63 11.23 7.02 5 68.97 - 1.43 13:20 4.66 6 66.05 - 7.28 12.61 1.71 7 46.17 - 8.06 10.83 -0.33 8 24.37 7.27 7.34 3.68 9 24.61 7.27 8.98 2.01 10 23.67 - 2.47 6.47 -3.44 ggg l 11 14.93 - 5.67 - 0.44 -7.05 I UUli U l ei 12 9.30 - 5.44 - 6.03 -8.45 13 7.62 - 4.95 - 8.11 -8.69 2-

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