ML20101E354

Submits Addl Info on IGSCC Evaluations of Repairs to Welds in Recirculation Sys Piping,Per 841217 Telcon Request. Summary of Total Stresses Encl

ML20101E354
Person / Time
Site:	Hatch
Issue date:	12/19/1984
From:	Gucwa L GEORGIA POWER CO.
To:	Stolz J Office of Nuclear Reactor Regulation
References
NED-84-626, TAC-55236, NUDOCS 8412260220
Download: ML20101E354 (4)

Text

Georg;a Power Cornpany

(. -'- 333 P,edmont Avenue Atlanta Georgia 30308

- Telephcne 404 526 6526 Ma;t ng Address:

Post Ott,ce Eox 4545 At!anta, Georg a 30302 Georgia Power L. T. Gucwa tne soutpem e:ec:rc system Manager Nuctear Engineenng and chief Nuc! ear Eng.neer N 84-626 December 19, 1984 Director of Maclear Reactor Recplation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensirg U. S. N2 clear Re<platory Oxtimission Washirgton, D. C. 20555 NRC DOCKET 50-321 OPERATING LIGNSE DPR-57 EWIN I. HA'ICH NUCLEAR PLANP UNIT 1 SUPPLD4 ENTAL INFORMATION W T"CC EVALUATIOtB ATTENTION: W. Hazelton -

Gentlemen:

In a Decanber 17, 1984 telephone conference between Mr. W. Hazelton ?nd Mr. R. Hermann of the NRC staff and representatives of Georgia Power Gnmpr.ny (GPC) regardirg repairs to welds in recirculation system piping at Plant Hatch, a recuest was made by Mr. Hazelton for additional information on the Intergramlar Stress Cbtrosion Cracking (IGSCC) evaluations which hate been y performed. 'Ibe information recuested concerned those flawed welds which l have been shown by analysis to be acceptable without repair, with emphasis i on the 12"-to-22" sweepolet-to-header welds. GPC hereby aihnits the following infonnation in response to that recuest.

WEID 22-BM-1BC-1 FIAWS IDDffIFIED:

o 7.5 inches (in leryth) by 11% (maximam depth through the wall thickness) circumferential indication located at approximately "l:30" seen as if a clock face ("12:00" is toward reactor vessel and "3:00" is toward end cap);

o 4.2 inches by 17% circumferential indication located between "3:30" and "4:30";

o 1 inch by 29% circumferential indication located at "5:00"; and o 15% spot indication located at "8:00".

8412260220 841219 PDR ADOCK 05000321 P PDR 'i _.

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• 1 Georgia Pbwer A

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' Director of-Maclear Reactor'IWplation

- Attention:;. Mr. John F. Stolz, Chief

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- ..Operatirg Reactors Branch No. 4 :

. . Deceraber'19, 1984 ~

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1 FIMS ASSLBED' POR AIRLYSIS 1

.o 13 inches by -30% ::ircumferential' located at "3:00". I

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l- STRESSES DUE '10 APPLIED LQADS/SSE IORDS:

. The lstresses rea11 ting from applied ' loads are provided in Attachment A.

The : stresses :provided .- are : derived from conservative assunptions 'and

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. bound the ? stresses associated ~with SSE for .this weld as well as 7 22-AM-1BC-1. .

a= I IESIIXRL S'IRESS ASSLMPTIONS:

6 - Uko residial stress cases' were asalmed -

o Typical stresses due to a' 22. inch hatt weld; R '. o Zero residial ? stresses (sweepolet-to-heoder welds were solution

_ _ annealed).

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E LD 22-AM-1BC '

FIMS IDENTIFIED: (the clock definition is the same as for 22-BM-1BC-1)~

.o 6.6 inches by 11% circumferential indication located at "2:00";

-o. 8% spot indication located'at "5:00",

o' 18% spot indication located at "6:00",

o 10% spot ' indication located at "8:00";

o 2.2 inches-by 8% circumferential. indication located at "9:00"; and

, o. 8% spot indication located at "11:00" The analysis for 22-AM-1BC-l'is bounded by the analysis for 22-BM-1BC-1.

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(GeorgiaPower A

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Director : of Maclear i Reactor? Regulation

' Attention:J Mr.' John F. Stolz, Chief 4- Operatirg Reactors Branch No. '4 .

., 3- D h r 19, 1984

- Page Three' k

. MIDS 28-A-6 Ale 28-B-16

. These welds each had 'a single axial flaw identified as follows:

28-A-6 10.5 ' inch by 16% axial . indication, 'and

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28-B 1 inch by 17% axial indication.

These ' indications'were analyzed using a -resi&al . stress pattern d2e to the original weld which was analytically derived for the hoop direction.

All; of the ~above flaws were evaluated . by analytically _ projecting the

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-growth 'of - the flaw for an 18-month - fuel' cycle and conparing . the rea11 ting

-end of cycle. flaw with '2/3 ~of the allowable "a/t" from IE-3641,Section XI of the ASE code.i Crack growth was calculated using a conservative crack growth law which was derived from data contained in NUREG-1061.

If you' have 42estions regarding the' infonnation, please contact Mr.

James Edwards.at ~(404) 526-7011 Ycars tery truly,

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Attachment xc: H.;C. Nix, Jr.-

--J.? P. O'Reilly (NRC- Region II) .

. Senior Resident Inspector

- . J. A. Edwards W.:D. Drinkard 4-b I

I 700775

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NED-84-626 Attachment A

. , . 4 PLANT HATCH Summary of Total Stresses a e *M Total Stress (PSI) ileld Maximum Stresses (PSI) "DW +

Identification 'DW "TH #seis " press #

DW # TH+ press "seis " press 12AR-K-3 489 1855' 2892 7436 9780 10817 28-A-10 . 408- 492 1647 6755 7655 8810 ,s 28-B-ll 494 492 1618 6755 7741 8867 cc* 22-BM-1BC-1(1) .61 1588 903 7288 8937 8252

• • • 22-AM-1BC-1(1) 145 1588 906 7288 9021 8339 -

12-AR-H3 731 .2915 2358 7436 11082 10525 24-A-13 1036 5111 4350 7749 13896 13135 12-BR-C3 419 2915 2146 7436 10770 10001 12-BR-D3 453 1497 2527- 7436 9386 10416 12-BR-E2' 442 1200 2225 7436 9078 10103 12-BR-E3 679 1855 3190 7436 9970 .11305

~12-AR-K2 ~ 419 1200 2064 7436 9055 9919 28-B-3 828 1093 1559 5819 7740 8206 28-B-4 568 917 1652 5819 7304 8039 12-AR-F2 415 3260 1936 7436 11111 9787 12- AR-H2 .. 646- 1481 1720 7436 9563 9802 ,c 12-AR-J3 232 1497- 2220 7436 9165 9888

.12-BR-C2 ' 534 1481 2032 7436 9451

• 10002

.12-AR-F3 756- 4215 2997 7436 12407 11189 28'-B-16 ( 2 ) __ __ __ __ __

28-A-6(2) __ __ __ __ __

' Notes:-

(1) ~Sweepolet Welds (2)' The flaws on these were axic.1 only and the only applied stress is the hoop component of pressure stress.

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