ML18038B899

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Summary of 970529 Telcon W/Tva Re NRC Which Asked TVA to Provide Info Re Evaluation of CS Weld Flaws Identified During Recent Refueling Outage
ML18038B899
Person / Time
Site: Browns Ferry 
Issue date: 06/18/1997
From: Williams J
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
NUDOCS 9706200263
Download: ML18038B899 (6)


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LICENSEE :

Tennessee ey Authority FACILITY:

Browns Ferry Nuclear Plant, Unit 3 3

18, 1997 QO 2q

SUBJECT:

SUMMARY

HAY 29, 1997 TELEPHONE CONFERENCE A telephone conference call took place on.Hay 29, 1997 between representatives of the U.S. Nuclear Regulatory Commission (NRC) and the Tennessee Valley Authority (TVA).

Call participants are listed in the enclosure.

This call was held to discuss an NRC letter to TVA dated Hay 28, 1997 which asked TVA to provide the information regarding evaluation of core spray weld flaws identified during the recent Browns Ferry Nuclear Plant (BFN) Unit 3 refueling outage.

TVA was asked to provide the following information:

l.

A plant-specific system assessment assuming complete failure of weld P9 considering that the structural integrity of weld P8 is not assured.

2.

Discuss the implications from a risk perspective, including effect on core damage frequency, if weld P9 is assumed to fail considering that the structural integrity of weld P8 is not assured..

TVA indicated that it had initiated engineering work to address the NRC questions.

TVA stated that a prel'iminary loss.of coolant accident analysis indicates that peak cladding temperature will be about 1600 1650 F if the affected core spray line is unavailable.

This result is well within the 10 CFR 50.46 acceptance criterion of 2200 F.

TVA also stated that preliminary risk assessment calculations indicate loss of this core spray capability does not result in. a significant increase in core damage frequency.

TVA requested that the staff accept a delay in submitting its response to the Hay 28, '1997 letter.

TVA believes a delay would improve their ability to coordinate its response with the Boiling Water Reactor Vessel Internals Program participants, and. improve consistency of information provided.

The NRC staff stated it still desires a response by June 11, suggesting that TVA provide whatever information is available at that time, with a description of additional activities.planned and' schedule for submitting that additional work to the NRC.

TVA indicated that it,understood the staff's suggestion.

TVA subsequently responded. to the NRC letter of.May 28 on. June 10, 1997.

Original signed by Joseph, F.'i'll:-liams,i Project Manager Project Dir.ector,ate II-3 Division"of Reactor Projects I/II Office of 'Nuclear Reactor.Regulation

Enclosure:

Attendance:List cc w/

Enclosure:

See next page DOCUMENT NAME:

G:(BFNiMeaoss.TEL To receIve e copy of this document, indicete in the born C

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Varg=

(SAV)

F.

Hebdon (FJH)

'J. Williams (JWFI)

B. Clayton (BAC2)

M. Lesser (MSL)

J. Johnson, RII (JRJ)

M. Lesser (MSL)

J. Johnson, RII (JRJ)

J. Strosnider (JRS)

R. Hermann (RAH)

K. Kavanaugh (KAK)

R.

Koo (WHK)

J.

Rajan (JRR)

L. Wert (LXWl)

J. Coley (JLC2)

~ard Co

,Docket Fi.le No. 50-,296 PUBLIC BFN Rdg.

OGC ACRS

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PARTICIPANTS NRC TVA TELEPHONE CONFERENCE BROWNS FERRY UCLEAR PLANT UNIT 3 CORE SPRAY WELD FLAW EVALUATION NRC Joe Williams Bob Hermann Kerri Kavanagh Bill Koo Jai Rajan Len Wert Mark Lesser Jim Coley TVA Lee Williams Tim Abney Steve Kane

,Dave Burrell ENCLOSURE

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