ML20064A816

Forwards Info Re Performance of NDE Exam of Feedwater Nozzles & Safe Ends During 1989/1990 Maint/Refueling Outage, Per NUREG-0619,Section 4.4.3.1(2)

ML20064A816
Person / Time
Site:	Brunswick
Issue date:	09/14/1990
From:	Loflin L CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20064A817	List: ML20064A816 ML20064A818
References
RTR-NUREG-0619, RTR-NUREG-619 NLS-90-183, NUDOCS 9009280128
Download: ML20064A816 (8)

Text

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T Carolina Power & L6ght Company SERIAL; NLS 90 183 5

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United States Nuclear Regulatory Commission ATTENTION: Document Control Desk i- , Washington, DC 20$$$

BRUNSWICK STEAM ELECTRIC PIANT, UNIT 2 DOCKET No.-50 324/ LICENSE NO. DPR 62 PERFORMANCE OF NONDESTRUCTIVE EXAMINATION OF FEEDWATER N0ZZLES AND SAFE ENDS DURING THE 1989/1990 MAINTENANCE / REFUELING OUTAGE centlemen:

Pursuant to'NRC NUREG 0619, subsection 4.4.3.1(2),. Carolina Power & Light Company (CP&L) hereby submits the enclosed information concerning the non- -

destructive examination of the feedwater nozzles and safe ends performed during the 1989/1990 maiitenance/ refueling outage at Brunswick Steam Electric

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Plant Unit 2.

Should you have any questions on this matter, please contact Mr. M. R. Oates at (919) 546 6063.

Yours very truly, D].R.Onn & L.r. ws L. I . Loflin Manager Nuclear Licensing Section DBB/ecc (808BNP)

. Enclosure

. cc: Mr. S. D. Ebneter Mr. N. B. Le N Mr. R. L. Prevatte

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BRUNSWICK STEAM ELECTRIC PLANT + UNIT 2 NRC DOCKET 50 324 l OPERATING LICENSE NO. DPR 62 PERFORMANCE OF NONDESTRUCTIVE EKAMINATION i OF FEEDWATER NO22LES AND SAFE ENDS DURING ,

THE 1989/1990 MAINTENANCE /REPUELING 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  ;

ends performed at Brunswick Steam Electric Plant (BSEP) Unit 2 during the  ;

1989/1990 maintenance / refueling outage. ~

1. STARTUP/ SHUTDOWN CYCLES EXPERIENCED i

When BSEP Unit 2 was shut down in September 1989 for maintenance and refueling, 175 startup/ shutdown cycles had been experienced.

This quantity included five startup/ shutdown cycles since the '

previous inspection. ,

i II. NONDESTRUCTIVE EXAMINATION RESULTS a The attached table provides a summary of the examination results  !

for the feedwater nozzles and safe end examinations conducted at BSEP during the 1989/1990 maintenance / refueling outage. No recordable indications or evidence of cracking were noted for the '

feedwater nozzles and safe ends. Cracking has been observed i around the feedwater sparger flow holes. These, however, have been evaluated as acceptable for another operating cycle.  !

III. NONDESTRUCTIVE EXAMINATION METHODS ,

The NDE methods employed for the examination of the subject ,

components during the Unit 2 1989/1990 maintenance / refueling outage was manual ultrasonics. Ultrasonic examinations were performed from the nozzle outside diamoter using special contoured

• transducer wedges designed specifically for zones 1, 2, and 3 at BSEP (see attached excerpt from General Electric procedure GE UT-303). The ultrasonic examinations employed angle beam shear wave techniques as recommended by General Electric Company. The routine liquid penetrant testing of the FW nozzle blend radii is scheduled for the next refueling outage in accordance with Table II of NUREG 0619. A liquid penetrant test was, however, performed on the feedwater sparger flow holes to confirm visually identified 1 indications. The results were compared to previous refueling outage examination results. No significant growth was noted.

IV. SYSTEM MODIFICATIONS AFFECTING FEEDWATER FLOW AND/OR TEMPERATURE The feedwater Startup Level Control Valve (SULCV) and the 4A high

pressure feedwater heater were replaced during the Brunswick 2 l Cycle 8 Refueling Outage. Since the unit initially came on line, l various feedwater heater tubes have been plugged as routine maintenance. Replacement of the SULCV will result in improved 1

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feedwater flow control, i.e. , fewer flow fluctuations during low

. ;, power operation. Plugging of the feedwater heater tubes reduces the efficiency of the feedwater heaters and therefore reduces final feedwater temperatures. The 4A feedwater heater was replaced due to the high number of plugged tubes. This replace.

ment will increase final feedwater t6mperature. Additionally, a new feedwater temperature monitoring system has been installed in Unit 2. The system employs RTDs installed in the feedwater piping downstream of the RWCU and HPCI injection points. The system provides a permanent record of final feedwater temperature via a strip chart recorder.

l- V. ON LINE LEAKAGE MONITORING e No on line leakage monitoring system for the detection of feed.

water leakage past the feedwater thermal sleeves has been installed at Brunswick, i

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BRUNSWICK UNIT 2 FEEDWATER N0ZZLE AND SAFE END l

NONDESTRUCTIVE EXAMINATION RESULTS

SUMMARY

1989/1990 MAINTENANCE / REFUELING OUTAGE j COMPONENT EXAMINATION PROCEDURE USED EXAMINATION- l l IDENTIFICATION TECHNIQUE RESULTS j N4A, B, C, D Visual and P7 90.1, Rev. 8 Cracking exists around' I Feedwater LP around CE PT 100. Rev. O sparger flow holes. The Spargers flow holes cracking was evaluated  ;

as acceptable for l another operating cycle (ref. GE Report No. RDE 42 1289 - Rev. 1)

N4A, B, C, D UT GE UT 303, Rev. O No recordable l Inner Blend indications. i Radii l 2B21 N4A SE UT GE UT 101, Rev. 0 One indication recorded.

(Feedwater Indication was evaluated 1 Safe End @ 45 0 to be geometric in l nature due to the sound beam entering the thermal sleeve through a water interface. This i indication exhibits no j apparent change from  ;

previous outages. '

2B21 N4B SE, UT CE UT 101, Rev 0 One indication  !

2B21 N4C SE, aswociated with thermal ,

2B21 N4D SE sleeve geometry seen -l (Feedwater below recordable levels Safe Ends @ during the previous .

1350 , 2250, outage was also seen and 3150 this outage below  ;

respectively) recordable levels. '

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MO: 08.U7 303 REV. O PAGE 18 0F 36 TITLE: PROCEDURE FOR MMeuAL UL11RAscelle EXAMINATI0li 0F $101 ELE IBOIER RADIUS 05 NUOb**f 50*f9Y ^ .0RthTER fnMt 10* btMsttR

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