ML20244E422

Submits Info Re NDE of Feedwater Nozzles & safe-end Welds During 1988 Maint/Refueling Outage.No Significant Indications or Evidence of Cracking Noted

ML20244E422
Person / Time
Site:	Hatch
Issue date:	06/16/1989
From:	Hairston W GEORGIA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HL-543, NUDOCS 8906200333
Download: ML20244E422 (11)

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HL-543-0145V X7GJ17-H220 June 16, 1989 U.S. Nuclear Regulatory Commission-ATTN: Document Control Desk Hashington, D.C. 20555 PLANT HATCH - UNIT 1

~NRC DOCKET 50-321 OPERATING LICENSE DPR-57 PERFORMANCE OF NONDESTRUCTIVE EXAMINATION OF-FEEDHATER N0ZZLES AND SAFE-END HELDS DURING THE 1988 MAINTENANCE / REFUELING OUTAGE Gentlemen:

Pursuant to NRC NUREG-0619, Company (GPC) . hereby submits the~ subsection enclosed 4.4.3.1(2),

information . Georgia concerning the Power nondestructive examination of the. feedwater nozzles and: safe end welds performed ' during the.1988 maintenance / refueling outage- at Plant Hatch-

Unit 1. . The results of previous Plant' Hatch Unit 1 ~ feedwater component examinations, which were performed in accordance with NUREG-0619, were provided' to the NRC in GPC letter NED-83-434, dated August 22, 1983 and letter SL-1484 dated October 31 1986.. . Consequently, the earlier examination results are only referencedLand' are not included in this

, submittal.

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

Sincerely, alJ MW

~

W. G. Hairston, III GKM/eb

Enclosure:

1 c: (See next page.) 8 I

8906200333 890616 PDR '- ADOCK 050CCs21 P eDC

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'U.S. Nuclear Regulatory Commission

. June 16,1989 Page Two.

c: Georaia Power Comoany-Mr.. H. C.: Nix, General Manager - Nuclear Plant

' Mr. L. T. Gucwa, Manager Engineering and Licensing - Hatch GO-NORMS.

EtS. Nuclear Regulatory Commission. Washinaton. D.C.

L; .; Mr. L. P. Crocker, Licensing Project Manager - Hatch

U.S. Nuclear Regulatory Commission. Reaion II-Mr. S. D. Ebneter, Regional Administrator Mr. J. E. Menning Senior Resident Inspector - Hatch

(

)

0145V

l ENCLOSURE I- NRC DOCKET 50-321 I l EDWIN I. HATCH NUCLEAR PLANT UNIT 1 l

PERFORMANCE OF NONDESTRUCTIVE EXAMINATION OF FEEDHATER N0ZZLES AND SAFE END HELDS DURING THE 1988 MAINTENANCE / REFUELING OUTAGE The following information is provided in accordance with NRC NUREG-0619, "BHR 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 i during the 1988 maintenance / refueling octage.

I. STARTUP/ SHUTDOWN CYCLES EXPERIENCED When Plant Hatch Unit I was shutdown on September 28, 1988, for maintenance and refueling, 269 startup/ shutdown cycles (including 55 training and test criticals) had been experienced. One hundred seven (107) startup/ shutdown cycles had elapsed since the cladding ,

had been removed from the feedwater nozzle areas of the Plant Hatch Unit I reactor pressure vessel in 1979. Twenty (20) startup/

shutdown cycles have elapsed since the feedwater nozzles and safe end welds were last examined during the 1985-86 maintenance /

refueling outage.

II. NONDESTRUCTIVE EXAMINATION RESULTS Table 1 (pages E-3 and E-4) provides a summary of the examination results for the feedwater nozzles and safe end weld examinations conducted at Plant Hatch Unit 1 during the 1988 maintenance /

refueling outage.

No significant indications or evidence of cracking were noted during the performance of any of the examinations, The scheduled external ultrasonic (UT) examinations of the N4A, N4B, 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 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 cmfiguration welds. The enclosed Figures A-1, A-10, A-11, A-12, and A-13 (pages E-5 through E-9) 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 SL-1484, dated October 31, 1986, and consequently, are not inc;'ded herein.

i 0145V HL-543 E-1

ENCLOSURE (CONTINUED)

' PERFORMANCE OF NONDESTRUCTIVE EXAMINATION OF FEEDHATER N0ZZLES AND SAFE END HELDS DURING THE 1988 MAINTENANCE / REFUELING OUTAGE III. NONDESTRUCTIVE EXAMINATION METHODS-The. NDE methods employed for the examination of the sLbject feedwater components during the Plant Hatch Unit 1 1988 maintenance / refueling outage were: (1) manual ultrasonic, and (2) 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 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 No design or procedural changes relative to predicting future cracking tendencies based upon past history have been implemented at Plant Hatch Unit 1.

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

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0145V HL-543 E-2 l 3

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a . .

ENCLOSURE (CONTINUED)i PERFORMANCE OF NONDESTRUCTIVE EXAMINATION OF FEEDHATER N0ZZLES AND SAFE END HELDS DURING THE 1988 MAINTENANCE / REFUELING OUTAGE TABLE 1 (SHEET 1 0F 2)

PLANT HATCH UNIT 1 FEEDHATER N0ZZLE AND SAFE END NONDESTRUCTIVE EXAMINATION RESULTS

SUMMARY

1988 MAINTENANCE / REFUELING OUTAGE Component Examination Procedure Examination Identification Technioue Used Results N4A, B, C, D, Remote visual N/A Feedwater-spargers Only required every 4th refueling cycle N4A, B, C, D, UT SCS No significant Nozzle center bore UT-H-481, Rev. 1 indications sections N4A, B, C, D, UT SCS No significant Nozzle inner blend UT-H-480, Rev. 3 indications radii 1821-1FH-12AA-15 SCS Pipe-to-transition UT UT-H-400, Rev. 7 No significant piece MT MT-H-500, Rev. 3 indications 1821-lFH-12AA-16 .SCS Transition piece- UT. UT-H-400, Rev. 7 No'significant to-nozzle MT MT-H-500, Rev. 3 indications 1821-?FH-12AB-9 SCS Pipe-to-transition UT UT-H-400, Rev. 7 No significant piece MT MT-H-500, Rev. 3 indications IB21-lFH-12AB-10 SCS Transition piece- UT UT-H-400, Rev. 7 No significant to-nozzle MT MT-H-500, Rev. 3 indications IB21-1FH-12BC-9 SCS Pipe-to-transition UT UT-H-400, Rev. 7 No significant piece MT MT-H-500, Rev. 3 indications 0145V HL-543 E-3

ENCLOSURE ~(CONTINUED)

PERFORMANCE OF NONDESTRUCTIVE EXAMINATION OF FEEDHATER N0ZZLES AND SAFE END HELDS DURING THE 1988 MAINTENANCE / REFUELING OUTAGE TABLE 1 (SHEET 2 0F 2)

Component Examination Procedure Examination Identification- Techniaue Used Results IB21-1FN-12BC-10 SCS Transition piece- UT UT-H-400, Rev. 7 No significant to-nozzle MT MT-H-500, Rev. 3 indications IB21-1FH-12BD-15 SCS Pipe-to-transition UT UT-H-400, Rev. 7 No significant piece MT' MT-H-500, Rev. 3 indications 1821-1FH-12BD-16 SCS Transition piece- UT UT-H-400, Rev. 7 No significant to-nozzle 60f MT-H-500, Rev. 3 indications LEGEND:

SCS - Southern-Company Services, Inc.

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0145V HL-543 E-4

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