ML20198Q512
| ML20198Q512 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/31/1997 |
| From: | Salas P TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9711120230 | |
| Download: ML20198Q512 (4) | |
Text
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4 Tenneesee Vaney Authority, Post Omce Box 2000 Soddy-Daisy, Tennessee 37379-2000 October 31, 1997 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk
' Washington, D.C. 20555
' Gentlemen:
In the Matter
)
Docket No. 50-328 Tennessee Valley Authority
)
SEQUOYAH NUCLEAR PLANT (SQN) - UNIT 2 STEAM GENERATOR (SG)
TUBE PLUGGING AND NOTIFICATION OF UNIT 2 SG TUBE INSPECTIONS THAT FALL INTO CATEGORY C-3 As-required by SON Technical Specification (TS) 4.4.5.5.a, thic submittal provides a report of SG tube plugging during the Un?! 2 Cycle 8 refueling outage.
The in-service inspectivy 'TSI) of the Unit 2 SG tubes was completed on October 26, 1297.
In accordance with SON TS 4.4.5.5.b, TVA will submit a special report of the rcsults of this inspection on or before Jctober 25, 1998.
Pursuant to the reporting requirements of TS 4.4.5.5.c, NRC was notified of the SG tube inspections that fall into Category C-3 as a result of SON's ISI of SG Nos.
1, 2,
3, and 4.
Notification of these results were made during a telephone conference call on October 22, 1997, and an Occober 24, 1997, telephone call to Ron Hernan.
In
-accordance with SON TS 3/4.4.5, all SGs were classified as Category C-3.
The initial Row I and 2 U-Bend plus point
-examination samples in SG Nos.
1, 2,
3, and 4, were 98, 86,
-93, and 74 tubes, respectively.
There were two tubes in each of~the.four SGs that-were determined to have primary water-stress corrosion cracking. The remaining nonplugged tubes in Row 2 in all four SGs were subsequently examined as required by TSs, and no further U-bend indications were p
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Identified.
9711120230 971031 PDR ADOCK 05000328 e
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- .U.S'.1Nuclearf Regulatory, Commission 4
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October, 31.1--1997-TS 4.4.5.5.c,also.rcylires a~-. written-follow-up report. -This' report will be.sent in conjunction with the'90-day alternate-plugging ~ report.
Enclosed is a summary of-the tubes'plugge, during the Unit 2
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Cycle--8:refuelingLoutage.
Please' direct questions concerning this issue to me atL(423) 843-7170 or:J. D. Smith at (423)- 843-6672.
Sincerel
!/-
C 1
p
= Pedro Salas
-Site-Licensing:and Industry Affairs Manager cc; (Enclosure) :
-Mr.- R. W. Hernan, Project Man,tger
-Nuclear' Regulatory Commission
'One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379-3624 4
Regional Administrator
- U.S.. Nuclear Regulatory Commission Region II
' Atlanta-Federal Center L61":Forsyth St.,-SW,: Suite 23T85-Atlanta, Georgia.30303-3415
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ENCLOSURE SEQUOYAH-NUCLEAR PLANT UNIT 2 CYCLE 8 REFUELING OUTAGE STEAM GENERATOR TUBE PLUGGING SUt44ARY-
STEAM GENERATOR 15-DAY PLUGGING REPORT Sequoyah Unit 2. Cycle 8 SG ROW COL INDICATION
- LOCATION RESOLUTION sample:0 1
1 46 SAI H07+9.83 PLUG 1
1 68 SAI H07+4.13 PLUG l'
23 69 SCI HTS-1.69 PLUG Total Number of Tubes Plugged This Generator 3
sasple 0 2
1 55 SAI H07+4.20 PLuc 2
1 61 SAI H07+10.56 IN-SITU / PLUG 2
2 53 3AI HTS.55 PLUG
'2 10 54 SAI HTS-3.88 PLUG 2
12 57 SCI HTS.08 PLUG 2
12 92 42 C01.06 PLUG 2
27 49 SAI IITS-1. 34 PLUG 2
29 42 43 AV3.03 PLUG Total Number of Tubes Plugged This Generator 8
sample:0 1
18 SgI H O *7 + 10. 2 9 PLUG 3
1 23 MCI C07+3.54 PLUG 3
11 2
40 C01.09 PLUG 3
22 12 SAI HTS.12 PLUG 3
23 7
SAI HTS.43 PLUG 3
24 67 SAI HTS-2.38 PLUG 3
35 76 57 C01+.00 PLUG Total Number of Tubes Plugged This Generator 7
sample : 0 79 SCI H07+10.16 IN-SITU / PLUG 4
1 90 SCI H07+9.83 PLUG 4
7 17 SAI HTS.15 IN-SITU / PLUG 4
8 63 SCI HTS-1.84 PLUG 4
43 61 44 CO2.17 PLUG Total Number of Tubes Plugged This Generator 5
Total Number of Tubes Plugged 23
- sAI = single Axial Indication SCI = Single Circumferential Indication WCI. Multiple Circumferential Indication c
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