ML20113H493

Forwards Feedwater Nozzle Bypass Leakage Monitoring Data,Per Guidance Provided in NUREG-0619,Section 4.3.2.4,consisting of Rev 0 to TVA-17-001, Licensing Topical Rept,Nutech Feedwater Nozzle Bypass Monitoring Sys App:Results For..

ML20113H493
Person / Time
Site:	Browns Ferry
Issue date:	07/29/1992
From:	Zeringue O TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20113H494	List: ML20113H493 ML20113H496 ML20113H499 ML20113H505
References
RTR-NUREG-0619, RTR-NUREG-619 NUDOCS 9208040105
Download: ML20113H493 (5)

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O. J '!ke' Zenngue -

V(e Presdent. Brewns Fe'ry Operakna JUl. 2 91992 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the-Matter of ) Docket Nos. 50-259 Tennessee Valley Authority ) 50-260 50-296

-BROWNS FERRY NUCLEAR PLANT (BFN) - NUREG-0619, BOILING WATER R" ACTOR (BWR) FEEDWATER (FW)-AND~ CONTROL ROD DRIVE (CRD)

NOZZLE CRACKING - FW NOZZLE THERMAL SLEEVE LEAKAGE VALUES.

References:

1. TVA letter dated August 17, 1983, Browns Ferry' Nuclear Plant, FW Low-Flow Controller Analysis and NUREG-0619 Inspection Alternative

2. NRC-letter dated-June 6, 1984, Browns Ferry Nuclear' Plant Units 1, 2 and 3, Implementation of NUREG-0619, BWR Feedwater.

and CRD NozLle-Cracking

-This letter submits feedwater nozzle bypass leakage monitoring data for BFN Units 1, 2 and 3 in accordance with the guidance provided in NUREG-0619, section 4.3.2.4.

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9208040105 DR ADOCK 05000259 920729 '

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2 U.S. Nuclear Regulatory Commission JUL 291992 In reference 1 TVA outlined its plan for resolution of BFN feedwater nozzle cracking pursuant to NUREG-0619. The plan included removal of the stainless steel nozzle cladding and installation of General Electric (GE) triple-sleeve spargers for all BFN Units. TVA committed to install a leak detection system to monitor feedwater thermal-sleeve bypass leakage for each BFN Unit and to inform the staff as to its performance and provide an assessment of leakage measurements. TVA also performed a fracture mechanics analysis of the BFN feedwater nozzles and determined installation of a low-flow controller as described in NUREG-0619, section 4.2 to be unwarranted.

TVA proposed an alternative to the routine dye penetrant (PT) surface examination frequency for the nozzles as required by NUREG-0619, Table 2, from nine refueling cycles (or 135 startup/ shutdown cycles) to once every 20 years of operation for each unit.

The staff concluded in reference 2 that the BFN plan for feedwater nozzle cracking mitigation is in accordance with applicable guidance provided in NUREG-0619 and GE report NEDE-21821A. However, the staff concluded that TVAs proposed alternative PT surface examination frequency could not be l granted until leak rate data and ultrasonic testing (UT) results could support-such an extension.

The enclosure-to this letter provides a report of feedwater therma) sleeve bypass leakage data for each of the BFN Units.

The reports show that five of six feedwater nozzles on Unit 1 had no leakage and one nozzle had leakage of 0.052 gallons per minute (GPM). For Unit 2, five of six feedwater nozzles-had no leakage and one nozzle had leakage of 0.04 GPM. No leakage was recorded for any of the six feedwater nozzles on

-Unit 3. Since there is no significant leakage around any of the triple thermal sleeves spargers, TVA concludes that there is minimal contribution to the fatigue usage factor due to

rapid thermal cycling. TVA plans to monitor the performance of the feedwater triple thermal sleeve spargers closely to assure'that with time, any leakage that may occur is detected and evaluated. TVA also plans to pursue a reduction in the l routine PT surface examination frequency for the feedwater l nozzles as-required by NUREG-0619, Table 2 when sustained leak rate data and UT. technology can support such a request.

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3 U.S.~ Nuclear! Regulatory Commission Jtit 291997

-There are no new commitments conta3ned in this letter. If

.you have any questionc, contact R. R. Baron, Manager of Site Licensing, at (205) 729-7566.

Sincerely,

/

i L > .

O. J. Zeringue Enclosure cc: -See page 4 l

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4 U.S. Nuclear Regulatory Commission JUL 291912 -

Enclosure cc (Enclosure):

NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35611 Mr. Thierry M. Ross, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323

. s T

ENCLOSURE FEEDWATER NOZZLE LEAKAGE MONITORING SYSTEM BROWNS FERRY NUCLEAR PLANT This enclosure-contains feedwater nozzle bypass leakage

- monitoring reports for BFN; Units 1, 2 and 3.

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