ML20045C349
| ML20045C349 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/17/1993 |
| From: | James Fisicaro ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2CANO69302, NUDOCS 9306220394 | |
| Download: ML20045C349 (5) | |
Text
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June 17,1993 2CAN069302
.i U. S. Nuclear Regulatory Commission Document Control Desk Mail Station PI-137 Washington, DC 20555
Subject:
Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 Voluntary Steam Generator Tubes Plugged or Sleeved Report Gentlemen:
i Arkansas Nuclear One - Unit 2 (ANO-2) performed a limited inspection of the A &' B steam i
generator tubes during a recent planned outage (2P93-1). ANO-2 Technical Specification 4.4.5.5.a requires the number of tubes plugged or sleeved in each steam generator to be reported to the Commission following each inservice inspection. Except for the inspection of two tubes which were not examined during the last refueling outage (2R9), these tube inspections were not performed as part of a Technical Specification required inservice inspection. However, Entergy Operations is reporting the number of tubes that were plugged or sleeved during this outage.
'L An examination of 5614 tubes in 2E-24A (steam generator "A") and 5832 tubes in 2E-24B l
(steam generator "B") was conducted between May 6,'1993, and May 12, 1993. A Rotating l
Pancake Coil (RPC) probe was used to perform the examination of the hot' leg expansion transition region in the interior of the tube bundle, referred to as the " sludge pile" region, for -
each steam generator. The RPC examination was limited to this region because all previously identified circumferential cracks are bounded by this area. In steam generator "A", 47 tubes were plugged (45 circumferential cracks and two volumetric indications). In steam generator
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"B",3 tubes were plugged (all classified as circumferential cracks). In both steam generators, all tubes plugged for circumferential cracks were also stabilized at the hot leg tubesheet through -
the first support plate to preclude adjacent tube damage if tube severance occurred. 'No tubes in either steam generator were sleeved as a result of this examination. The location of the tubes which were plugged are identified in Table 1.
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e U.S.NRC June 17,1992 2CANM9302 Page 2
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ANO-2 Technical Specification Amendment 143, dated February 23,1993 (2CNA029302),
added a note to Table 4.4-2 of the Technical Specifications granting a one time exemption to the C-3 inspection requirements for the 2R9 inspection of "B" steam generator tubes 38-66 and 37-67 for the period of November 27,1992, through May 30,1993. Inspection of these two tubes was not completed as part of the 100% C-3 sample inspection performed during 2R9 (see Entergy Operations letter dated November 27,1992 (2CAN119205)). The inservice inspection of these tubes was completed in conjunction with the RPC examination described above. No indications were identified in these tubes as a result of this inspection.
Entergy Operations intends to further discuss the engineering analyses of the examination results during an upcoming meeting with the NRC. Should you have any questions regarding this submittal, please contact me.
Very truly yours,
/7
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' mes J. f sicaro a
Director, Licensing JJF/JJD Attachment 9
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U.S.NRC June 17,1992 2CAN069302 Page 3 cc:
Mr. James L. Milhoan U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive,' Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One - ANO-l&2 Number 1, Nuclear Plant Road Russellville, AR 72801 Mr. Roby Bevan NRR Project Manager, Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint Nonh 11555 Rockville Pike Rockville, MD 20852 Mr. Thomas W. Alexion NRR Project Manager, Region IV/ANO-2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint Nonh 11555 Rockville Pike Rockville, MD 20852 l
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Attachment to:
2CAN069302 Page 1 of 2 TAEi t
SicAni GENERATOR TL..-
PLUGGED DURING 2P93-1 CIRCUMFERENTIAL CRACKS LENGTH MAX AVG SG ROE LINE VOLTS DJi(L fe'DV_
M A
16 30 3.72 114 75 23.7 A
15 33 2.42 49 87 11.9 A
20 34 1.21 100 74 20.5 A
24 38 1.55 53 35 5.1 A
35 45 4.80 163 93 42.1 A
45 45 0.91 33 66 6.1 A
42 46 1.72 193 76 40.7 A
54 50 1.79 33 85 7.9 A
62 50 1.93 40 92 10.3 A
53 51 1.69 42 75 8.8 A
30 52 2.96 79 84 18.4 A
54 52 1.83 58 67 10.8 A
4 56 1.74 144 57 22.7 A
100 56 1.47 194 75 40.5 A
109 73 1.19 159 67 29.7 A
103 75 2.59 60 82 13.6 A
77 77 2.22 96 72 19.3 A
101 77 2.79 39 70 7.5 A
53 79 1.25 65 36 6.5 i
A 77 79 2.64 252 50 35.0 A
111 79 3.09 105 89 26.0 A
101 81 4.54 58 86 13.8 A
101 85 2.94 137 77 29.2 t
A 98 86 3.87 21 97 5.7 A
104 88 2.40 56 90 14.0 i
A 105 89 1.67 121 83 27.9 A-104 90 5.76 84 88 20.6 A
106 90 0.87 117 45 14.7 A
114 90 1.20 35 74 7.2 i
A 105 91 0.91 107 78 23.2 A
111 91 0.89 35 46 4.5 A
114 96 1.19 51 66 9.3 A
106 102 2.I1 137 80 30.4 A
64 108 2.11 102 48 13.6 A
49 115 2.26' 63 58 10.2 A
52 118 0.95 96 27 7.2
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Attachment to:
2CAN069302 Page 2 of 2 TABLE 1 (cont)
STEAM GENERATOR TUBES PLUGGED DURING 2P93-1 i
CIRCUMFERENTIAL CRACKS LENGTH MAX' AVG EG RO_W LINE VOLTS DJKL
%TW
%TW A
30 126 2.09 63 70 12.3 A
82 126 5.92 203 91 51.4 A
27 127 3.14 44 90 11.0 A
31 129 1.96 102 60 16.9 A
33 129 1.46 84 56 13.1 A
10 130 2.56 53 85 12.4 A
34 130 2.55 81 80 17.9 A
72 130 4.27 75 87 18.2 A
27 131 2.80 95 60 15.8 B
66 128 3.04 30 -
95 7.9 B
82 44 0.97 112 30 9.3 B
90 48 0.83 60 32 5.3 l
VOLUMETRIC INDICATIONS LENGTH MAX AVG-EQ EQW LINE VOLTS DIKL
%TW
%TW I
A 6
56 1.31 ODI 33 N/A A
42 102 2.00 ODI 73 ODI SG = Steam Generator LENGTH DEG. = Degree of arc containing indication MAX % TW = Maximum throughwall percentage ofindication AVG % TW = ((MAX % TW) X (LENGTH DEG.))/360 ODI = Outside Diameter Indication
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