ML18038B951

Provides Voluntary Response to NRC Staff Request for Info Dtd 970619 Re Unit 3 Reactor Pressure Vessel Shell Weld Insp Completed During Cycle 5 Refueling Outage.W/Listing of RPV Exam Coverage

ML18038B951
Person / Time
Site:	Browns Ferry
Issue date:	09/15/1997
From:	Abney T TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9709230207
Download: ML18038B951 (10)

Text

CATEGORY 1 REGULATOR ZNFORMRTZON DZSTRZBUTZONOSTEM (RZDS)

ACCESSION /BR:9709230207 DOC.DATE: 97/09/15 NOTARIZED: NO DOCKET FACIi:50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee 05000296 AUTH. NAME AUTHOR AFFILIATION ABNEY,T.E. Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Provides voluntary response to NRC staff request for info dtd 970619 re Unit 3 reactor pressure vesel shell weld insps completed during Cycle 5 refueling outing.W/listing of RPV exam coverage.

DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code GL-8 -04 NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-3 1 1 PD2-3-PD 1 1 WILLIAMS,J. 1 1 INTERNAL: 1 1 AEOD/SPD/RAB 1 1 ENTER 1 1 NRR/DE/EMEB 1 1 T 1 1 OGC/HDS3 1 0 RES/DET/EIB 1 1 RES/DET/EMMEB 1 1 EXTERNAL: LITCO ANDERSON 1 1 NOAC 1 1 NRC PDR 1 1 D

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N 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)'N EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL 13

t 0 Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 September 15, 1997 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter 'of ') Docket No. 50-296 Tennessee Valley Authority )

BROWNS FERRY NUCLEAR PLANT (BFN) UNIT 3 RESPONSE TO REQUEST FOR INFORMATION REGARDING REACTOR PRESSURE VESSEL SHELL WELD INSPECTIONS This letter provides TVA's voluntary response to the NRC staff's request for information dated June 19, 1997, regarding Unit 3 reactor pressure vessel (RPV) shell weld inspections completed during the Cycle 5 refueling outage. The staff requested TVA provide the volume of axial and circumferential welds inspected and the number of recordable indications identified. The enclosure to this letter contains a tabular listing of the following: weld examined, estimated weld volume, estimated weld volume examined, ASME Code volume examined, and location of each reportable indication relative to the weld metal volume.

Four of the RPV welds have a total of ten indications that exceed the acceptance standards of the American Society of Mechanical Engineers (ASME)Section XI, XWB-3500. The

.indications are associated with welds C-2-3, C-3-.4, C-4-5, and V-4-B. One indication is identified in both welds V-4-B and C-3-4 due to the intersecting weld joint. In addition to the four welds listed above, one weld (C-5-FLG) contains five g gqOQ e.

9709230207 970915 PDR ADQCK 05000296 PDR IIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIII

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U.S. Nuclear Regulatory Commission Page,2 September 15, 1997 reportable indications which exceed IWB-3500 acceptance standards. This weld is included in. the table but was not part of the augmented examination.

The results of these inspections were initially provided to NRC by TVA letter dated March 6, 1995. TVA determined that the weld indications that exceed ASME Section XI, IWB-3500 acceptance standards are within the IWB-3600 evaluation acceptance criteria. NRC concurred with TVA's evaluation by letter dated November 8, 1995.

There are no commitments contained in this letter. If you have any questions, please contact me at (205) 729-2636.

Si cere T. E. Abney Manage z.ce sing Industry ffairs losure cc ( re):

Mr. Mark S. Lesser, Branch Chief U.S. Nuclear Regulatory Commission Region II 61 Forsyth Street, S.W.

Suite 23T85 Atlanta, Georgia 30303 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611 Mr. J. F. Williams, Project Manager U.S. Nuclear Regulatory Commission

'One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852

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TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

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AMERICAN SOC IE TY OF MECHAN CAL ENGINEERS (ASME ) SECTION XI REACTOR PRESSURE VESSEL (RPV) AUGUMENTED SHELL WELD INSPECTIONS FOR THE CYCLE 5 REFUELING OUTAGE NRC REQUEST FOR INFORMATION (SEE ATTACHED)

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Browns Ferry Unit 3 RPV Examination Coverage Weld ID Estimated Total Weld Estimated Weld Volume ASME Volume Flaws Reported In Flaws Reported Outside Volume (cu in)

• Examined (cu in)

• Examined (cu in)

• Weld Weld Volume

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C-4-5 6,529 6,072 32,472 0 C-3-4 6,529 6,333 33,869 C-2-3 6,529 5,223 27,933 0 C-1-2 6,529 5,876 31,425 0 0 C-BH-1 6,529 1,828 9,777 0 0 C-5-FLG 6,529 5,354 28,632 0 V-1-A 1,197 982 4,908 0 0 V-1-B 1,197 994 4,968 0 0 V-1-C 1,197 1,053 5,267 0 0 V-2-A 1,197 1,017 5,087 0 0 V-2-B 1,197 1,077 5,387 0 0 V-2-C 1,197 1,089 5,446 0 0 V-3-A 1,197 1,185 5,925 0 0 V-3-B 1,197 1,185 5,925 0 0 V-3-C 1,197 838 4,190 0 0 V-4-A 437 437 2,183 0 0 V-4-B 437 362 1,811 0 V-4-C 437 437 2,183 0 0 V-5-A 1,197 1,197 5,985 0 0 V-5-B 1,197 1,185 5,925 0 0 V-5-C 1,197 1,197 5,985 0 0 QP:.>> ??>??>??>>>~/>>>>P>j>>i?'j???>> '>,,??g)~

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?'Nglg>>NN>)>>m4>>ha.'>>: >A/3,>>vugg>i>>,i>>>Nt>gobi', kc? >? V~"'i%i> '~" 'YF>>>>YF Totals 54,848 44,922 '35,281 Notes:

• Volumes shown are estimated based on the average weld width.

The flaw associated with V-4-B is also listed as a flaw associated with C-3-4.

Weld identifications that begin with the letter "V're axial Weld identifications that begin with the letter "C" are circumferential

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