ML18038B951
| 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 FACIi:50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee AUTH.NAME AUTHOR AFFILIATION ABNEY,T.E.
Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
DOCKET 05000296
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 ID CODE/NAME PD2-3 WILLIAMS,J.
INTERNAL:
ENTER T
RES/DET/EIB EXTERNAL: LITCO ANDERSON NRC PDR COPIES LTTR ENCL 1
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1 RECIPIENT ID CODE/NAME PD2-3-PD AEOD/SPD/RAB NRR/DE/EMEB OGC/HDS3 RES/DET/EMMEB NOAC COPIES LTTR ENCL 1
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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
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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:
Docket No. 50-296 In the Matter 'of
')
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:
- 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
0 4l
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
Ik el C
4 a
p C'NCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 3 AMERICAN SOC IETY OF MECHANICAL 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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~ I
~ V Browns Ferry Unit 3 RPV Examination Coverage Weld ID Estimated Total Weld Volume (cu in) *
" vz P p>g.pSkp?gkgag+&)?pc> mp~~?$ ?'.c S?j?
Estimated Weld Volume Examined (cu in)
- ASME Volume Examined (cu in)
- Flaws Reported In Flaws Reported Outside Weld Weld Volume C-4-5 C-3-4 C-2-3 C-1-2 C-BH-1 C-5-FLG V-1-A V-1-B V-1-C V-2-A V-2-B V-2-C V-3-A V-3-B V-3-C V-4-A V-4-B V-4-C V-5-A V-5-B V-5-C 6,529 6,529 6,529 6,529 6,529 6,529 1,197 1,197 1,197 1,197 1,197 1,197 1,197 1,197 1,197 437 437 437 1,197 1,197 1,197 6,072 6,333 5,223 5,876 1,828 5,354 982 994 1,053 1,017 1,077 1,089 1,185 1,185 838 437 362 437 1,197 1,185 1,197 32,472 33,869 27,933 31,425 9,777 28,632 4,908 4,968 5,267 5,087 5,387 5,446 5,925 5,925 4,190 2,183 1,811 2,183 5,985 5,925 5,985 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 Totals 54,848
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44,922 kc? >? V~"'i%i>'~"'YF>>>>YF
'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'reaxial Weld identifications that begin with the letter "C" are circumferential
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