ML20082J177

Forwards Info Re Nondestructive Exam of Feedwater Nozzles & Safe Ends Performed During 1990/1991 Reload 7 Outage,Per NUREG-0619,Subsection 4.4.3.1(2)

ML20082J177
Person / Time
Site:	Brunswick
Issue date:	08/22/1991
From:	Floyd S CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20082J180	List: ML20082J177 ML20082J181
References
RTR-NUREG-0619, RTR-NUREG-619 NLS-91-208, NUDOCS 9108270220
Download: ML20082J177 (14)

Text

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' AUG 221991 SERIAL: NLS 91208 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWK K STEAM ELECTRIC PLANT, UNIT NO,1 DOCKET NO,50 325/UCENSE NO. DPH 71 UNIT 1 RELOAD 7 NONDESTRUCTIVE EXAMINAll0N RESULTS FEEDWATER NOZZLES AND SAIE ENDS Gentlemen:

Putsnant to NRC NUREG 0019, subsection 4.4.3.1(2), Carolina Power & Light Company (CP&L) hereby submits the enclosed information concerning the nondestructive examination of the feedwater nonles and safe ends performed during the 1990/1991 Reload 7 outage at the Drunswick Stearn Electric Plant, Unit 1.

Please refer any questions regarding this submittal to Mr W. R. Murray at (019) 540-4001.

Yours very truly, I h f '

S. D. Floyd Manager l Nuclear Licensing Section WRM/wrm (sparltr,wpf)  !

Enclosure I i

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Mr. R. L. Prevatte  !

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, ^e . i ENCLOSUME 1 r

DRUNSWICK STEAM EuECTRIC PLANT, UNIT 1 NRC DOCKET 60 325 ,

OPERATING LICENSE DPR 71 UNIT 1 RECOAD 7 NONDESTRUCilVE EXAMINATION REEULTS FEEDWATER NOZZLES AND SAFE ENDS 1

The following information is provided in accordance with NRC NUREG 0019, *0WR reedwater ,

Norrie and Control Rod Drive Return Line Norrlo Cracking.' and portains to the nondestructive  !

examination (NDE) of feedwater norries and safe ends performed at the Brunswick Steam Electric Plant, Unit 1 during the 1990/1991 maintenance / refueling outage.  ;

l. START-UP/ SHUTDOWN CYCLES EXPERIENCED When Brunswick Plant, Unit 1 was shut down in September 1990 for maintenance and refueling,129 start up/ shutdown cycles had been experienced. This quantity included ten (10) startup/ shutdown cycles since the previous inspection. ,

11. NONDESTRUCTIVE EXAMINATION RESULTS The attached table provides a summary of the examination results for the feedwater nozzles and safe end examinations conducted at the Drunswick Plant, Unit i during the 1990/1991 maintenance / refueling outage.

No recordable indications or evidence of cracking were noted for the feedwater norries. Cracking has been observed around the feedwater sparger flow holes.

However, these have been evaluated as acceptable for another operating cycle. An indication was recorded in the N4D safe end and the examination results discussed in CP&L letter NLS 91-001 dated January 7,1991. Two non geometric indications were detected in the bi-metallic weld of the safe end extension N4C.

lli. NONDESTRUCTIVE EXAMINATION METHODS The NDE methods employed for the examination of the subject components during the Unit 1.1990/1991 maintenance / refueling outage were manual /autornated ultrasonics and liquid penetrant testing. The automated ultrasonic examination -

methods of shear wave and refracted longitudinal techniques were used on the bimetallic and inconel weldments of th9 safe end and safe end extension. The manual ultrasonic examinations were performed from the nozzle outside diameter using special contoured trer'sducer wedges designed specifically for zones 1,2, and 3 at th9 Brunswick Plant. The ultrasonic examinations employ angle beam .

shear wave techniques as recommended by General Electric Company. The routine penetrant testing of the feedwater norile blend radii was performed during the outage with no recordable indications. Additionally, a liquid penetrant t' at was j performed on the feedwater sparger flow holes to confirm visually identh'ed indicatioris. Indications were also noted in the circumferential and longitudinal weld seams of the spargers. The indications were evaluated as acceptable for an El 1

~ _ , - - _ . . _ . . _ _ _ . _ . _ _ . . _ _ . _ _ . . _ _ _ _ . _ _ _ _ _ ._ _ . . _ _ . _ _ ~ . .

additional fuel cycle by Gant rol Elsctric Company (sco C>neral Electric Report No, RDE 461290).

IV, EFFEC 1S ON PREDICTION OF FUTURE CRACKING TENDENCIES The feedwater startup level control valve (SULCV) Internals were replaced in Unit I during the Unit 1 Reload 7 outage. Since the unit was initially put into service, various feodwater heater tubes have been plugged as routine maintenance.

Replacement of the SULCV in'ernals should rewit in improved feedwater flow control, i.e. fewer flow fluctuations during low power operation.

V. ON LINE LEAKAGE MONITORING No on line leakage monitoring system for the detection of feedwater leakage past the feedwater thermal sleeves has boon Installed at the Brunswick Plant, Unit 1.

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TABLE I BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 FEEDWATER NOZZl.E, SAFE END, AND SPARGER NONDESTRUCTIVE EXAMINATION RESULTS

SUMMARY

1990/1991 MAINTENANCE / REFUELING OUTAGE COMPONENT EXAMINATICN PROCEDUAE USED EXAMINATION IDENTIFICATION TECHNIOUE REGULTS N4A,B,C,D Visual and LP PT 90.1, Rev. 8 Cracking exists bround spaiger 410w holtst c Feedwater around flow GE PT 100. Rev. O Linear indications were also identifieo et the Spargers holes weld toes nf tFe spargets' circumferential and longitudint,1 welds. The cracking was evaluated as acceptable for another operating cycle without implementinD repairs (ref. GE Report No RDE 401290L N4A,B,C,D. UT GE UT 303, Rev. O No recordable indications, inner Blend Radil

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1821 N4A SE UT GE UT 101, Rev. 2 Dase mutal of the safe ends showed no 1821 N48 SE FRR 2 reportable indications. Used 45' shear and 45'

-1021 N4C SE and 60' refracted longitudinal examination 1821 N4D SE techniques.

1821 N4D 5- PT GE PT 100, Rev. O Recorded geometric, non relevant and one SW12 UT GE UT 200, Rev. 2 non cecme'.ric planar indication. Automated ex6minations with 45' shear and 45' and 60*

(Bimetallic N4D refracted longitudinal examination techniques.

Safe End Weld) Although the indication was not ASME Section XI reportable or characterized as an IGSCC indication, the indication was evaluated as IGSCC due to the weld and base metal (inconell susceptibility and indication orientation. An IWB 3640 evaluation was

, performed by StructuralIntegrity Associates for continued operation without repair for an additional cycle.

1821 N4C 6- PT GE PT 100, Rev. U Two non geometric circ. planar indicat'ons SW23 UT GE UT 200, Rev. 2 were detected with a 45 degree refracted longitudinal search unit. The indications are (Dimetallic N4D not IC connected and do not exhibit

! Safe End Weld) characteristics typical of IGSCC. The it.dications are acceptable per ASME Section XI.

-. . . r-Nine (9) of twelve (12) weldments with inconel were exaneed this outage with techniques to detect IGSCC (shear wave and refracted longitudinal) for NUREG 0313. The sensitivity of these exams usually exceed the shear wave technique alone.

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SERIAL: NLS 91208 United States Nuclear Regulatory Commiss:on ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO.1 DOCKET NO. 50 325/ LICENSE NO DPR 71 UNIT 1 RELOAD 7 NONDESTRUCTIVE EXAMINATION RESULTS FEEDWATER NOZZLES AND SAFE ENDS Gentkmen:

- Pursuant to NRC NUREG 0019, subsection 4.4.3112), Carolina Power & Light Company (CP&L) hereby submits the enclosed information concerning the nondestructive examination of the feedwater nozzles and safe ends performed during the 1990/1991 Reload 7 outage at the Brunswick Steam Electric Plant, Unit 1.

Please refer any questions regarding this submittal to Mr. W. R. Murray at (919) ti46 4661.

Yours very truly,

[YIglO I b

j E[ l S. D. Floyd Manager Nuclear Lir:ensing Section WRM/wrm (sparltr.wpf)

Enclosure cc: Mr. S. D. Ebneter Mr. N. B, Le p,,e s/u/cu 4. , I n e n w/s . c2 a1 3 '

Mr. R. L Prevatte i e 64,< r e w 1. .

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1. k ENCLOSURE 1 DRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 NRC DOCKET 50 325 OPERATING LICENSE DPR 71 UNIT 1 RELOAD 7 NONDESTRUCTIVE EXAMINATION RE3ULTS ,

FEEDWATER N0ZZLES AND SAFE ENDS L The following information is p:ovided in accordance with NRC NUREG 0019, '0WR feedwater Nenle and Control had Drive Return Line Norrie Cracking," and pertains to the nondestructive examination (NDE) of feeds ater roules and safe ends performed at the Brunswick Steam Electric Plant, Unit 1 during the 1990/1991 maintenance / refueling outage.

l. START UP/SHU1DOWN CYCLES EXPERIENCED When Brunswick Plant, Unit 1 Wes shut down in September 1990 for maintenance and refueling,129 start up/ shutdown cycles had been experienced. This quantity included ten (10) startup/ shutdown cycles since the previous inspection.

11. NONDESTRUCTIVE EXAMINA flON RESULTS The attached table provides a summary of the examination results for the feedwater nonles and safe end examinations conducted at the Brunswick Plant, Unit 1 during the 1990/1991 maintenance / refueling outage. I No recordable indications or evidence of cracking were noted for the feedwater norries. Cracking has been observed around the feedwater Aparger flow holes.

However, these have been evaluated as acceptable for another operating cycle. An indication was recorded in the N4D safe end and the examination results discussed in CP&L letter NLS-91001 dated January 7,1991. Two non geometric indications were detected in the bi metallic wold of the safe end extension N4C.

1 l'i. NONDESTRUCTIVE EXAMINATION METHODS The NDE methods employed for the examination of the subject components during the Unit 1 1900/1991 maintenance / refueling outage were manual / automated ultrasonics and liquid penetrant testing. The automated ultrasonic examination methods of shear wave and refracted longitudinal techniques were used on the bimetallic and inconel weldments of the safe end and safe end extension. The manual uttrasonic examinations were performed from the norrie outside diameter using special contoured transducer wedges designed specifically for zones 1,2, and 3 at the Brunswick Plant. The ultrasonic examinations employ angle beam shear vwave techniques as recommended by General Electric Company. The routine penetrant testing of the feedwater norrie blend radil was performed during the nutage with no recordable indications. Additionally, a liquid penetrant test was performed on the feedwater sparger flow holes to confirm visually identified indications. Indications were also noted in the circumferential and longitudinal weld seams of the spargers. The indications were evaluated as acceptable for an El 1

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.g yg additional fuel cyclei by General Electric Company (see General Electric Report No. RDE 461290).

IV. EFFECTS ON PREDICTION OF FUTURE CRACKING TENDENCIES

• O'/ htttn=ls wart The feedw6ttf startup level control valve (SULCVLwee raplaced in Unit I during the Unit 1 Reload / outage. Since the unit was i'litially put into service, various feedwater t eat tubes have been plugged as routine maintenance. Replacement of the SULCV'}m4 etylt.lnimproved feedwater flow control, i.e. fewer flow fluctuatiorn duri glow power operation, intertuds Shw1d V. ON LINE LEAKAGE MONITORING No on line leakage monitoring system for the detection of feedwater leakage past the feedwater thermal sleeves has been installed at the Brunswick Plant, Unit 1.

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TABLE 1 l BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1  !

FEEDWATER NOZZLE, SAFE END, AND SPARGER NONDESTRUCTIVE EXAMINATION RESULTS

SUMMARY

1990/1991 MAINTENANCE / REFUELING OUTAGE

• COMPONENT EXAMINATION PROCEDURE USED EXAMINATION IDENTIFICATION TECHNIQUE RESULTS ,

i N4A,B.C,D Visual and LP PT 90.1, Anv. 8 Cracking exists around sparger flow holes.

Feedwater around flow GE PT 100, Rev. O Linear Indications were also identified at the  !

Spargers holes weld toes of the spargers' circumferential and ,

longitudinal welds. The cracking was  !

evaluated as acceptable for another operating L cycle without implementing repairs (ref. Gr  ;

Repet1 No. RDE 461290).  !

r N4A,B,C,D UT GE-UT 303, Rev. O No recordable indications. l Inner Blend Radil  ;

1821 N4A SE UT GE UT 101, Rev. 2 Date metal of the safe ends showed tw 1821 N48 SE FRR 2 reportable indications. Used 45* shear and 45' f 1821 N4C SE and 60' refracted long.tudinal examination l 1821 N40 SE techniques. l 1821 N40 5- PT GE PT 100, Rev. O Recorded geometric, non relevant and one l SW12 UT GE UT-200, Rev. 2 non geometric planar indication. Automated l examinations with 45'shePr and 45' and 60'  :

I (Bimetallie N4D refracted longitudinal examination techniques.

Safe End Weld) Although the indication was not ASME Section  :

XI reportable or characterized as an IGSCC i indication, the indication was evaluated as ,

IGSCC due tu the weld and base metal (inconell susceptibility and indication l orientation. An IWB 3640 evaluation war. i f performed by Structural Integrity Associa.e ,

r for continued operation without repair for an f__ acditional cycle.

I iU N4C6- PT GE PT 100, Rev. O Two non geometric cire planar Indications l SW2-3 UT GE UT 200, Rev. 2 were detected with a 45 degree refracted longitudinal search unit. The indications are (Bimetallic N4D not ID connected and do not exhibit Safe End Weld) characteristics typical of IGSCC. The indications are acceptable per ASME Section XI.

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- Nt ne (9) of twelve (12) weldments with inconel were examined this outage with techniques to detect IGSCC (shear wave and refracted longitudinal) for NUREG-0313. The sensitivity of these exams usually exceed the shear wave technique alone.

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ENCLOSURE 2 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 NRC DOCKET 50 325 OPERATING LICENSE DPR 71 UNIT 1 RELOAD 7 NUNDESTRUCTIVE EXAMINATION RESULTS FEEDWATER N0ZZLES AND SAFE ENDS QLNERAL ELECTRIC REORT NO RDE4Qd22Q FEEDWATER SPARGER CRACK GRQ1VTH ASSESSMENT, DECEMBER 199Q l.

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