ML17284A819

Forwards WNP-2 Feedwater Nozzle Insp Rept for R-13 Maint & Refueling Outage.Rept Submitted Pursuant to Commitments Made in Response to NUREG-0619, BWR Feedwater Nozzle & Control Rod Drive Return Line Nozzle Cracking.

ML17284A819
Person / Time
Site:	Columbia
Issue date:	12/03/1998
From:	Coleman D WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-0619, RTR-NUREG-619 GO2-98-203, NUDOCS 9812090193
Download: ML17284A819 (5)

Text

CATEGORY 1 REGULATORY XNFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9812090193 DOC.DATE: 98/12/03 NOTARIZED: NO DOCKET ¹ FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAi'.E, 'UTHOR AFFILIATION COLEMAN,D.W. Washington Public Power Supply Sys'em RECXP.NAME RECIPIENT AFFILIAT1ON Records Management Branch (Document Control Desk)

SUBJECT:

Forwards .WNP-2 feedwater nozzle insp rept for R-13 maint Sc refueling outage. Rept submitted pursuant to commitments made in response to NUREG-0619, "BWR Feedwater Nozzle & Control Rod Drive Return Line Nozzle Cracking."

DISTRXBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal: General Distribution E NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL 0 PD4-2 LA 1 '

1 . PD4-2 PD 1 1 POSLUSNY,C 1 INTERNAL: ACRS 1 1 ILE CENTER 0 1 1 NRR/DE/ECGB/A 1 1 1 1 NRR/DRCH/HICB 1 1 NRR/DSSA/SPLB 1 1-NRR/DSSA/SRXB 1 1 NRR/SPSB JUNG,I 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D

E NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415"2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 15 ENCL 14

WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ Richland, Washington 99352-0968 December 3, 1998 G02-98-203 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Gentlemen:

Subject:

WNP-2) OPERATING LICENSE NPF-21 FEEDWATER NOZZLE INSPECTION REPORT R-13 MAINTENANCEAND REFUELING OUTAGE

Reference:

Letter GO2-95-268, dated December 8, 1995, JV Parrish (SS) to NRC, "WNP-2 Feedwater Nozzle Inspection Report" The WNP-2 Feedwater Nozzle Inspection Report for the R-13 Maintenance and Refueling Outage is attached. This report is submitted pursuant to commitments made in response to NUREG-0619, "BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking."

Should you have any questions or desire additional information pertaining to this report, please call me or PJ Inserra at (509) 377-4147.

Respectfully, S.u.

DW Coleman Manager, Regulatory Affairs Mail Drop PE20 Attachment cc: EW Merschoff - NRC RIVc GA Pick - NRC RIV C Poslusny, Jr. - NRR 98i2090i93 98i203

'L

" q t,o Q 8 NRC Sr. Resident Inspector - 927N Williams - BPA/1399 PD Robinson - Winston &, Strawn PDR ADOCK 05000397 8 PDR

WNP-2 FEEDWATER ZZLE INSPECTION REPORT R- INTENANCE AND REFUELING OUTAGE Attachment Page.l of 3 I. Introduction This report is submitted pursuant to the Supply System response to NUREG-0619, where we committed to perform ultrasonic examinations of at least one of the six feedwater nozzle inner radii, bore and safe-end regions Rom the reactor outside diameter each refueling outage.

The report covers the period &om June 30, 1997 to June 12, 1998 and includes reactor vessel feedwater nozzle inspections performed during the WNP-2 R-13 Maintenance and Refueling Outage (Spring 1998).

As with all'previous examinations, no unacceptable indications were found during this inspection period.

Re ort Details These report details are formatted in accordance with the reporting guidance of Section 4.4.3.1(2) of NUREG-0619.

(a) Number of startup/shutdown cycles since the previous inspection and total number of cycles.

There were two startup/shutdown cycles &om the date of the previous feedwater nozzle inner radius examination (Spring 1997) to when the plant was shutdown in April 1998 for the R-13 Maintenance and Refueling Outage.

The total number of reactor feedwater thermal cycles, due to startups and shutdowns since initial heatup in April 1984, is 63.

(b) Summary of methods used and results of previous inspections.

The Supply System has developed an angle beam shear wave technique for the WNP-2 feedwater nozzle design. The technique was qualified on the WNP-2 feedwater mock-up, which is a feedwater nozzle &om the terminated Douglas Point Unit 1 reactor vessel. The inner radius, Zone 1, of the nozzle is scanned using a 70-degree angle transducer. The inner radius, Zone 2, and bore region, Zone 3, are scanned using a 25-degree angle transducer.

%NP-2 FEEDWATER ZZLE INSPECTION REPORT R MAINTENANCEAND

.REFUELING OUTAGE Attachment Page,2 of 3 The ultrasonic testing (UT) procedure used for the examinations is Supply System NDE&I Instruction QCI 6-4 "Ultrasonic Examination of Feedwater Nozzle Inner Radii." A copy of QCI 6-4 was included in the R10 feedwater nozzle inspection report (see Reference). Any changes to this procedure that affect UT scanning techniques are verified on the feedwater nozzle mock-up. No changes to this procedure have been made since the R10 submittal.

Calibration data for reactor feedwater nozzle inner radius examinations have also been predetermined using the WNP-2 feedwater nozzle mock-up. This allows the examiner to use the reactor vessel calibration block representing the shell course containing the feedwater nozzle for calibration.

Indications that exceed 25 percent full-screen-height are recorded. Indications that exceed 50 percent full-screen-height are evaluated.

No unacceptable indications were detected fiom these feedwater nozzle inner radius examinations.

(c) Changes in feedwater system or operating procedures that will affect feedwater flow or temperature.

There were no changes to the system or method of operation that could potentially increase the tendency for nozzle cracking.

(d) Inspection results.

During the R-13 Maintenance and Refueling Outage, ultrasonic examination of one reactor feedwater nozzle inner radius, bore and nozzle-to-safe-end weld at azimuth 90 fi'om the vessel outside diameter was performed.

The examinations were performed by Supply System and General Electric examiners.

These examiners were certified to either Level II or Level IIIUT.

No indications were detected that met the threshold for recording or evaluation.

(e) Leakage monitoring.

We do not have on-line leakage monitoring for the reactor feedwater sparger.

WNP-2 FEEDWATER ZZLE INSPECTION REPORT R- MAINTENANCEAND

,REFUELING OUTAGE Attachment

~

Page3 of 3 (f) Information regarding all UT crack-like indications and any subsequent liquid penetrant information.

No crack-like indications were observed.

III. Next Scheduled Examination The next examination is scheduled for the R-14 Maintenance and Refueling Outage (Fall, 1999).