ML20012B729

Forwards Owners Data Rept for Inservice Insp Ei Hatch Nuclear Plant,Unit 2 Sept-Dec 1989 & Metallurgical Evaluation of Four Inch Pipe to Elbow Weld from Plant Hatch, Unit 2

ML20012B729
Person / Time
Site:	Hatch
Issue date:	03/07/1990
From:	Hairston W GEORGIA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20012B730	List: ML20012B729 ML20012B733 ML20012B735
References
RTR-NUREG-0313, RTR-NUREG-0619, RTR-NUREG-313, RTR-NUREG-619, RTR-NUREG-CR-3052 GL-88-01, GL-88-1, HL-978, IEB-80-13, NUDOCS 9003160182
Download: ML20012B729 (3)

Text

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Guarpia f%vr Comtuny 3YJ Pedrmw Avenue i

/wanta. Georgia 30308 s

letephone 4D4 LM 319$

Ma4.ng /dtrest -

40 inverne,s Ce~ter Pwkway Post Oltce box 1295 lDmingham, Adabama 35201 leieptone 205 (M) %81 t',e sw% m en n 1,wm W. G. Hairstog HI berwor Vce Pfeudent l

New Operanons g[.gyg l

000281 March 7, 1990 U.S. Nuclear Regulatory Commission i

ATTN: Document Control Desk Washington, D.C.

20555

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PLANT HATCH - UNIT 2 i

NRC DOCKET 50-366 OPERATING LICENSE NPF-5 INSERVICE INSPECTION ASSOCIATED WITH THE FALL 1989 MAINTENANCE / REFUELING OUTAGE i

Gentlemen:

Pursuant to the requirements of Article IWA-6000 of the ASME Code,-

Section.XI, enclosed for your review is the Owner's Data ' Report for j

Inservice Inspection (form NIS-1) for the inservice inspection activities conducted at Plant Hatch Unit 2 during the Fall 1989 maintenance / refueling outage.

The'0wner's Data Report is included as Enclosure 1.

The outage marked the end of the first 10-year ISI inspection interval for Unit 2.

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Also, pursuant to NRC NUREG-0619, subsection.4.4.3.l(2), Georgia Power Company (GPC),hereby submits information concerning the nondestructive examination - (NDE) of the feedwater nozzle, safe end, and control rod drive l-welds performed during the outage.

No new reportable indications were detected. provides a summary of the examination results under j

" Class 1 Components" and " Class 2 Components." Details on startup/ shutdown

cycles, NDE methods, and effects' on prediction of future cracking

~

tendencies are presented in Enclosure 2.

-j Georgia Power Company has also performed ultrasonic examination of austenitic steel piping welds in the primary coolant pressure boundary per l:

. Generic Letter 88-01 and NUREG 0313 Revision 2.

Results are presented in under " Class 1 Components." No new reportable indications were

'l detected in these welds.

i Based on commitments to the NRC related to Generic Letter 88-01, seven (7) welds in the Class 3 portion of the reactor water cleanup (RWCU) system i

were ultrasonically examined. Georgia Power Company and the NRC met and i

corresponded several times during 1989 on this issue. A July 24, 1989 l

1etter from the NRC documented our agreement to examine the seven welds in this non-safety related piping.

The exams were performed early in the 00 h $$838366 b I

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Georgia Power A U.S. Nuclear Regulatory Commission March 7, 1990 Page Two i

1 outage and discussed during a conference call with the NRC on October 2, l

1989, and documented in a letter from GPC to the NRC (HL-744) dated l

October 16, 1989.

No rejectable indications were detected; however, a combination surface / interior indication in RWCU weld number 11 was deemed significant enough to warrant investigation. A portion of the pipe was cut j

from the system and sent for metallurgical examination.

contains a copy of the evaluation, which concluded the weld defect was I

caused by lack of fusion, not intergranular stress corrosion cracking 1

(IGSCC).

In our October 16, 1989 letter to the NRC, GPC had committed to re-examine weld No. 11 during the next Unit 2 outage. However, since the weld was cut out of the system, this commitment no longer applies.

Georgia Power Company performs many augmented inspections which are not l

specifically required by the ASME Section XI Code.

The results of these i

inspections are described in the NIS-1 report.

In addition to the IGSCC inspections (primary pressure boundary and non-safety RWCU piping), and the NUREG-0619 inspections discussed above, GPC performed the following:

i o The core spray sparger and associated piping was visually examined per Bulletin 80-13. No reportable indications were detected, l

o All thirty-six (36) shroud head bolts were ultrasonically examined per GE SIL-433.

Two of the bolts had been previously noted as l-having minor indications, which had been deemed acce ) table. No l

additional indications were detected during the exam t11s outage.

The minor indications noted previously could not be reproduced.

1 L

o During the previous Unit 2 outage, a visual exam of the jetpump mixing nozzles revealed evidence of erosion in the throat area. The erosion had been evaluated and deemed acceptable by GE.

Visual exams this outage revealed no significant changes in the throat area

erosion, j

o All twenty (20) jet pump hold down beams were replaced with beams made of improved material.

This new material is considered a permanent resolution of IGSCC in hold down beams by NUREG/CR-3052, 1

and will eliminate the need to perform ultrasonic testing each outage.

I o Ultrasonic thickness measure:aents were performed on selected components in the extraction steam and condensate /feedwater system i

piping per GPC's ongoing erosion / corrosion program, o Eddy current testing was performed on several feedwater heaters, the main generator stator water coolers, and the hydrogen coolers.

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Georgialbwer d U.S. Nuclear Regulatory Commission March 7, 1990 Page Three o Non-code required surface exams were conducted on selected welds in the reactor core isolation cooling (RCIC), emergency-core cooling s

(ECC), control rod drive (CRD) and RWCU systems.

Surface and/or visual exams were also performed on sixty-six small bore (less than or equal to 2 inches) pipe line in the reactor coulant pressure boundary.

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

Sincerely, u)d. /LW W. G. Hairston, III GKM/eb

Enclosures:

r 1.

Owner's Data Report for Inservice Inspection -

Edwin I. Hatch Nuclear Plant Unit 2 September 1989 - December 1989.

l-2.

Non Destructive Examinations of Feedwater L

Nozzle, Safe End, and Control Rod Return l

Line Welds During the 1989 Maintenance /

Refueling Outage.

3.

GE Report No. 89-178-021, " Metallurgical Evaluation of a four-Inch Pipe-to-Elbow L

Weld from Plant Hatch Unit 2",

l November 1989.

c:

Georaia Power Company Mr. H. C. Nix, General Manager - Nuclear Plant l

Mr. J. D. Heidt, Manager Engineering and Licensing - Hatch GO-NORMS i

U.S. Nuclear Reaulatory Commission. Washinaton. D.C.

Mr. L. P. Crocker, Licensing Project Manager - Hatch U.S.- Nuclear Reaulatory Commission. Reaion 11 Mr. S. D. Ebneter, Regional Administrator Mr. J. E. Menning, Senior Resident Inspector - Hatch 000281 w.

.-.