ML20213G248

Forwards Info Re NDE of Feedwater Nozzles & Safe End Welds Performed During 1985-86 Maint/Refueling Outage,Per NUREG-0619.No Significant Indications or Evidence of Cracking Noted

ML20213G248
Person / Time
Site:	Hatch
Issue date:	10/31/1986
From:	Gucwa L GEORGIA POWER CO.
To:	Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
RTR-NUREG-0619, RTR-NUREG-619 0852C, 852C, SL-1484, NUDOCS 8611170402
Download: ML20213G248 (10)

Text

.

Georgia Power Company 333 Piedmont Avenue Atlanta %gia 30308 Telephorie 404 526-6526 Maihng Address.

Pbst Othee Box 4545 Atlanta, Georgia 30302 1 gay 10 All : I5 GeorgiaPower U

L T. Gucwa ine sourtwyn electnc s, stem Manager Nuclear Safety and Licensing SL-1484 0852C October 31, 1986 U. S. Nuclear Regulatory Commission

REFERENCE:

Office of Inspection and Enforcement RII: JNG Region II - Suite 2900 50-321 101 Marietta Street, N.W.

NUREG-0619 Atlanta, Georgia 30323 ATTENTION: Dr. J. Nelson Grace Gentlemen:

Pursuant to NRC NUREG-0619, subsection 4.4.3.1(2), Georgia Power Company (GPC) hereby submits the enclosed information concerning the nondestructive examination of the feedwater nozzles and safe end welds performed during the 1985-86 maintenance / refueling outage at Plant Hatch Unit 1.

The results of previous Plant Hatch Unit 1 feedwater component examinations, which );ere performed in accordance with NUREG-0619, were provided to the NRC in GPC letter NED-83-434, dated August 22, 1983.

Consequently, the earlier examination results are only referenced and are not included in this submittal.

Should you have any questions in this regard, please contact this office at any time.

Sincerely, f4=

L. T. Gucwa JAE/lc Enclosure c: Georsia Power Company U.S. Nuclear Regulatory Commission Mr. s. P. O'Reilly Director, Office of Inspection and Mr. J. T. Beckham, Jr.

Enforcement (Washington, D.C.)

Mr. H. C. Nix, Jr.

Director, Office of Nuclear Reactor GO-NORMS Regulation (Washington, D.C.)

Mr. P. Holmes-Ray, Senior Resident Inspector-Hatch N.

-um,,,,,,,,_,.

N.'dS$6M'd7,ii@k i

0611170402 861031 d d Fr W /i('Clp W 6 4

PDR ADOCK 05000321 P

PDR m'

if _1Eol

I j'

ENCLOSURE NRC DOCKET 50-321 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 PERFORMANCE OF NONDESTRUCTIVE EXAMINATION OF tLEDWATER N0ZZLES AND SAFE END WELDS DURING THE 1985-86 MAINTENANCE / REFUELING OUTAGE The following information is provided in accordance with NRC NUREG-0619, "BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking,"

and pertains to the nondestructive examination (NDE) of feedwater nozzles and safe end welds performed at Georgia Power Company's (GPC) Plant Hatch Unit 1 during the 1985-86 maintenance / refueling outage.

I.

STARTUP/ SHUTDOWN CYCLES EXPERIENCED When Plant Hatch Unit 1 was shut down on November 27, 1985, for maintenance and refueling, 249 startup/ shutdown cycles (including 55 training and test criticals) had been experienced.

Eighty-seven startup/ shutdown cycles had elapsed since the cladding had been removed from the feedwater nozzle areas of the Plant Hatch Unit 1 reactor pressure vessel in 1979.

Thirty-three startup/ shutdown cycles have elapsed since the feedwater nozzles and safe end welds were last examined during the 1982 maintenance / refueling outage.

II. NONDESTRUCTIVE EXAMINATION RESULTS Table 1 (pages E-3 and E-4) provides a sumary of the examination results for the feedwater nozzles and safe end weld examinations conducted at Plant Hatch Unit 1 during the 1985-86 maintenance / refueling outage.

No significant indications or evidence of cracking were noted during the performance of any of the examinations.

The scheduled visual examinations of feedwater spargers N4A, N48, N4C, and N40 were performed in accordance with Table 2 of NUREG-0619, and included the sparger flow holes and accessible welds.

The visual examinations were performed using remote camera equipment and were documented per Hatch Procedure 42SV-B11 -001 -1 S.

The scheduled external ultrasonic (UT) examinations of the N4A, N48, N4C, and N4D feedwater nozzle safe end configuration welds (pipe-to-transition piece weld and transition piece-to-nozzle weld), nozzle center bore sections, and nozzle inner blend radii were also performed in accordance with Table 2 of NUREG-0619.

In addition to the UT examinations, a required ASME Code,Section XI surface examination was performed on the safe end configuration welds.

The enclosed Figures A-1, A-10, A-11, A-12, and A-13 (pages E-5 through E-9) 0852C E-1 10/31/86

ENCLOSURE NRC DOCKET 50-321 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 PERFORMANCE OF N0NDESTRUCTIVE EXAMINATION OF PEEDWATER N0ZZLES AND SAFE END WELDS DURING THE 1985-86 MAINTENANCE / REFUELING OUTAGE from the Plant Hatch Unit 1 Long-Term Inservice Examination Plan depict the nozzle and safe end areas examined.

The results of previous Plant Hatch Unit 1 feedwater component examinations were provided to the NRC in GPC letter NED-83-434, dated August 22, 1983, and consequently, are not included herein.

III. NONDESTRUCTIVE EXAMINATION METHODS The NDE methods employed for the examination of the subject feedwater components during the Plant Hatch Unit 1 1985-86 maintenance / refueling outage were:

(1) manual ul trasonic, (2) visual, and (3) magnetic particle (MT).

Ultrasonic scans of 30-degree shear and 45-degree shear were performed on each nozzle center bore section.

A 70-degree shear UT scan was performed on the inner blend radius of each nozzle.

Safe end welds were ultrasonically examined using a 45-degree shear scan.

In addition, a magnetic particle surface examination was performed on the safe end welds.

Table 1 references the vendor examination procedures employed.

The subject NDE procedures are available at the Hatch plant site for review by NRC personnel upon request.

IV. EFFECTS ON PREDICTION OF FUTURE CRACKING TENDENCIES Ho design or procedural changes relative to predicting future cracking tendencies based upon past history have been implemented at Plant Hatch Unit 1.

At times, the unit may operate at reduced power levels due to various circumstances (e.g.,

out-of-service feedwater heaters, turbine bucket removals, etc.)

which, as expected, affect plant operating parameters.

V.

ON-LINE LEAKAGE MONITORING An on-line leakage monitoring system for the detection of feedwater leakage, which could resul t in nozzle cracks, as described in NUREG-0619, is not installed on Plant Hatch Unit 1 and, therefore, is not applicable to this report.

0852C E-2 10/31/86

i ENCLOSURE NRC DOCKET 50-321 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 PERFORMANCE 0F NONDESTRUCTIVE EXAMINATION OF tttDWAILK N0ZZLES AND SAFE END WELDS DURING THE 1985-86 MAINTENANCE / REFUELING OUTAGE l

TABLE 1 (SHEET 1 0F 2) 1 PLANT HATCH UNIT 1 FEEDWATER N0ZZLE'AND SAFE END NONDESTRUCTIVE EXAMINATION RESULTS SUPNARY -

i 1985-86 MAINTENANCE / REFUELING OUTAGE Component Examination Procedure Examination Identification Technique Used Results N4A, B, C, D, Remote visual Hatch No significant Feedwater spargers 42SV-Bil-001-l S,

indications Rev. 0 4

N4A, B, C, D, UT - 30' & 45' LMT No significant Nozzle center bore shear UT-12, Rev. 4 indications sections N4A, B, C, D, UT - 70* shear LMT No significant i

Nozzle inner blend UT-3, Rev. 9 indications radii I

1821-lFW-12AA-15 SCS l

Pipe-to-transition UT - 45' shear; UT-H-400, Rev. 5 No significant piece MT MT-H-500, Rev. 1 indications I

1821-lFW-12AA-16 SCS l

Transition piece-UT - 45* shear; UT-H-400, Rev. 5 No significant to-nozzle MT MT-H-500, Rev. 1 indications 1821 -l FW-12AB-9 SCS Pipe-to-transition UT - 45' shear; UT-H-400, Rev. 5 No significant piece MT MT-H-500, Rev. 1 indications i

1 B21 -l FW-12AB-10 SCS I

Transition piece-UT - 45* shear; UT-H-400, Rev. 5 No significant to-nozzle MT MT-H-500, Rev. 1 indications 1821-l FW-12BC-9 SCS Pipe-to-transition UT - 45* shear; UT-H-400, Rev. 5 No significant piece MT MT-H-500, Rev. 1 indications l

0852C E-3 10/31/86 l

ENCLOSURE NRC DOCKET 50-321 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 PERFORMANCE OF NONDESTRUCTIVE EXAMINATION OF PEEDWATER N0ZZLES AND SAFE END WELDS DURING THE 1985-86 MAINTENANCE / REFUELING OUTAGE TABLE 1 (SHEET 2 0F 2)

Component Examination Procedure Examination Identification Technique Used Results 1821 -1FW-12BC-10 SCS Transition piece-UT - 45' shear; UT-H-400, Rev. 5 No significant to-nozzle MT MT-H-500, Rev.1 indications 1821-1 FW-12BD-15 SCS Pipe-to-transition UT - 45* shear; UT-H-400, Rev. 5 No significant piece MT MT-H-500, Rev. 1 indications 1821 -1 FW-12BD-16 SCS Transition piece-UT - 45' shear; UT-H-400, Rev. 5 No significant to-nozzle MT MT-H-500, Rev. 1 indications LEGEND:

LMT - Lambert, MacGill, Thomas, Inc.

SCS - Southern Company Services, Inc.

0852C E-4 10/31/86

l WAciot W,rS$f L WLD peletAffael affGWA,. CIERT Oco$

iso-se*

o*

ero-ese*

weta,.

,,,,c,,

I wi c,ecitess weto s'. sr-s-o l

1,.C* n W-E" A

wt a

=

\\

',- c.. e c.,

n...

- c...

@:l@

l

• '.0'.7':

i-@ @.

t......

A.

.s.

..,.r..-

-- +w-G....- -,,,,,

! - -G,<,.,..- - -^_;;,q, et.c

-c' r-.. w.

..,. r..

uc 1,

a.

w,.

E'"" #'8888 88'O 3~ 8 # ~3" 4

Q

1. 1. 'C e-ceo. 3 m-e4.

Ih 44

's e'

l otE T sap e,sto s' **s**

• L t" cast m. wets

f. e* s t'- S

• as4 44 wie j

g esec /ges 1--_.-+- C-3 was e

.g1

_ _ WIQ_ p _ _ _

C 3-8 O

8 attatz st es4s Sag M faus I

e gh, asst g

80*

W estm ateaus enstafT 1

1 I

I B

e sp aks S

sa" accapret&tage asetst e' C'4 EE"*"*""'#'

'~~~~~

W85 wS pe.n veu.w.mio.

sesam e.erstr 4

te*

l w

c 4-a r=-c a r+-c-4 c

)) g e 4 e. o e e p,.,g 2(<

m f,,

-c -

a(:,

Al r

c.-

.a

~.

,,s

&jpi.c'pi-m'}ns

-n1 w}p%1 %f-,'

c.,

nanta. ge,6 t

t~

senergen.gatrarnent 4

d

,_c note. nets t

t'

.MS V& gen.6dTA Toe.f su,0 /

n". Justs E

sassreswaf4 TA vseW l

%(c.c.

SUPPO,t7 SK21rT WELD) i l

i RPV LONGI TUDINAL,CIRCUMFERE NTI AL, &

l NOZZLE-TO-SHELL WELDS I

I FIGURE A-l R E V. I l

l

1 I,

8 l

N j

m ren n

,y r h n~44 peo wtel 708-29 _

r i

pse mIELES N r 3

u e

i rut-s dont s e3 1 [

u s er 7

i 4' L_

J 5

)*

m j

f

I w'e n-,rw-r-a res A s see. ore r -A-8 1s6. A E l

l 1

j 192 l-IFW-12 A 'A' i

FE E DWATER'A-(

HATCH 1. CLASS 1 CA L BLOCK'.15-H l

LOCA T3 ON:DRYWELL l

FIGURE A-IO NOTE: ALL DEVICE NUMBERS REV.O PRECEDED BV 1921 l

i j

i l

rn.) -

e:

1r

~

~(%

.i p;

ses l

J N poss easa ffA

w. wet.>

, +- es*st 3

i 1

9880-96 _

tfELC) neee wd st'-A-A poss-e9 -

pse A 4 l

f(no une.N 4

2

,w.

\\answea:,r rio. +a a

l i

4 sw-m g i

l

""** 0p5:0 l

ree-s y i

I B21-IFW A-9

\\

FEE DUA TE R *A-8' l

HATCH I, CLASS I i

CAL 9 LOCK: IS H LOCATION:DRYWELL F3GURE A-11 NOTE: ALL DEVICE NUMBERS REV.O PRECEDED BY 1921 i

t i

l RPW 1

N ogc---* &

9

)

13 3 (

l 1 pop.gsedett (we ustL8) 4 6

sets-fFW-if"8'O rse. A*lS s

,,-nw.m -a FAR-4 T

\\ peg.ge __

g rap

• re was.a) m FON-6 FM-f i

FDN-Il gy,g ce utte) i l

I IB21-IFW-12-B-C l

FEE D WAT ER'B-C' i

HATC H I, CLA 55 i CAL BLOCK:IS-H LOC ATION: DRYWELL FIGURE A-12 NOTE: ALL DEVICE NUMBERS 3

RE V. O PRECEDED BY 1921 i

'I

j 1

i 8

non e*

,n wa'=>

p l

,o,.es -

m ata jr,,

1 1

l 1

n': reargt., rase )

\\

s' l

i, os i

l

- >(

g b

l I[~

rri A

I, e...n,.',.n, Nese.

,r s.e F 8 6. A-,E i

ris. A 9 l

1

)

IB21-IFW-12-9-D I

FEEDWAT ER ~B-D' l

HATCH 1. CLASS I l

CAL BLOCK: IS-H LOCATION: DRYWELL FIGURE A l'3 NOTE: ALL DEVICE NUMBERS i

REV. O PRECEDED By 1921 l

i l

- -