ML19347F451
| ML19347F451 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 05/11/1981 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML19347F447 | List: |
| References | |
| LER-81-002-01T, LER-81-2-1T, NUDOCS 8105190291 | |
| Download: ML19347F451 (16) | |
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REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h f5Tf1 ion 4-20-81 an 800 psid secondary-to-primary leak check was performed in i 9 3 geach steam generator during the Ifnit 2 Refueling 7 outage. One leaking l
, g l plug was detected in the "A" steam generator. On 4-26-81 final results I i o s iof the steam generator eddy current examination indicated the existence l l O s lof some degraded and defective tubes in each steam generator. 'This I o y l event is similar to others and reportable per Technical Specification l 0 8 I l5.6.9.2.A.3. 80 I
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44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS i O lEssentially all of the tubes in the " A" steam generator and about 75% inI y lthe "B" steam generator were inspected through the first support plate , I
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, , gi n addition to inspections required by Technical Specifications. 25 l l,3 lpluggable tubes were found in "A" and 16 were found in "B". One of thesd g l tubes was pulled for analysis. All tubes were plugged as of 4-30-81. I 7 s , e0
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T % POWER OTHER STATUS ISCO RY Ol5COVERY DESCRIPTION 5
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i ATTACHMENT TO LICENSEE EVENT REPORT NO. 81-002/OlL-0 Wisconsin Electric Power Company .
Point Beach Nuclear Plant Unit 2 Docket No. 50-301 On April 20, 1981, an 800 psig secondary-to-primary.
leak check was performed in each steam generator. Detailed l inspections of the 'tubesheets with remote television equipment showed leakage from the explosive plug in the tube R32C15 in the "A". steam generator. The leakage rate'was about two drops per minute. Another plug in the "A" steam generator (R31C52) was hertily coated with boric acid but no water was present.
Af ter considering the location of the . leaking plug, which is in the tubesheet periphery, and the effect that repair of.the. plug would have on exposure, critical path, and problems associated with repairs in the area, the decision was made not to repair the plug during this outage. An additional consideration-was the fact that the primary-to-secondary leakage rate in the steam
- generator was only one gallon per day before the outage.
The initial addy current inspection programs for the "A" and "B" steam generators consisted of_ inspection through the U-bend of 0% of the tubes in each steam generator plus all l previously degraded tubes, in accordance with Technical Speci-fication requirements. ' Additionally, the "A" steam generator i
program included a full le7gth inspection for a previous- indication in the cold leg and inspe. tions through the U-bend of about 190
- tubes in connection with xube degradation at' contact with anti-i vibration bars (AVB) reported by other plants. The program for the "B" steam generator inlet included inspecting 33 previously degraded tubes through the U-bend and 172 randomly located tubes .
to meet Technical Specification requirements and for AVB tube j.
degradation. The program for the "B" steam generator outlet i
consisted of inspection through the first support plate of all previously degraded tubes, inspection through the first support
! plate of about 200 tubes in problem areas determined by previous l inspections, and inspection through the third support plate j of about 170 tubes around the periphery, in connection with tube degradation in these areas reported at Prairie Island. The l programs in the inlets of both steam generators were later
- expanded in accordance with Technical Specifications resulting
! in inspection of essentially all tubes in the "A" steam generator j through the first support plate and approximately 75% of the tubes i in the "B" steam generator through'the first support. A summary of the extent of the inspection and the results are given in Table 1. A summary of eddy current indications by size and location is given in Table 2 and illustrated in Figures 1, 2, and 3.
Results of the eddy current inspections showed 25 pluggable tubes in the "A" steam generator and 16 pluggable tubes in the "B" steam generator. One of the tubes in the "A"
steam generator, R15C73, was pulled for detailed analysis and the hole was weld plugged on April 30, 1981. A degraded tube in the "B" steam generator, R24C25, had interference preventing insertion of a mechanical plug. The tube entrance area was re-rolled and then successfully plugged. Plugging of all tubes was completed on April 30, 1981. Photographs of the tubesheets taken _later the same day verified plugging of the proper tubes, A list of eddy current indications of all pluggable tubes found in the steam generators is provided in Table 3. For a map showing all tubes plugged to date, see Figures 4 and 5. No evidence of AVB tube degradation or degradation of the type experienced at Prairie Island was observed in any of the tubes inspected.
To determine if tube degradation-is progressing, a two-part comparison waa tone. The first part consisted of comparing the indicati_i size reported in 1981 for all unplugged indications reported in 1980. The results of this comparison are shown in Table 4. Af ter considering the inherent inaccuracies in evaluating and categorizing small volume eddy current indica- ,
tions which occur at or near the top of the tubesheet, the results indicate that the majority of the indications did not change. There is some indication of growth- based just on the ;
reported size of the indication. The second part of the comparison was performed by having a level IIA' evaluator directly compare the 1980 and 1981 eddy current signals for the tubes with 40%
or greater tube wall degradations in the "A" steam generator.
This comparison was biased in that it concentrated on tubes which had a large change in the reported eddy current signal in 1981 as compared to 1980. Table 5 provides the result of this comparison.
It too shows that there may be some growth in tube degradation but less than that implied by Table 4. A similar comparison for the "B" steam generator was not conducted since only four of the tubes with 40% or greater tube wall degradation in this outage had been inspected in 1980.
The results of earlier inspections of the "A" steam generator as previousl repcrted to the NRC were also examined for those tubes having greater than 40% indications in 1981.
This comparison is reported in Table 6. A similar comparison for the "B" steam generator indicated that only five of the tubes in the 40% or greater category had been inspected prior The to 1980 single '
and no degradation was reported in those inspections.
frequency eddy current inspections in 1977, 1976 and 1974 l indicated that many of these same tubes' had either distorted tubesheet entry signals or indications of <20% wall degradation.
Accordingly, we believe that the majority of the tubes plugged in this inspection had tube wall degradation for a significant period of time. The tube which was removed will provide alditional information on the method of degradation. However, tre indications being detected are believed to be the result of phosphate wastage and/or stress corrosion cracking. The results of previous steam generator inspections, as summarized in Table 7, have shown the existence of numerous eddy current indication
! and distorted tubesheet signal in the past. The continued use >
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and development of multi-frequency eddy current has given the
- evaluator the capability to identify and quantify small volume indications which were previously masked by the tubesheet entrance signal. A report on the results of the tube analysis will be provided at a later date.
This event is reportable in accordance with Technical Specification 15.6.9.2.A.3. ,
TABLE 1
SUMMARY
OF EDDY CURRENT EXAMINATION "A" "B" , "B" Type Extent Inlet Inlet Outlet Multi-frequency U-Bend 491 208 Multi-frequency First Support 2,693 2,061 30 7 Multi-frequency Third Support 163 Multi-frequency Full Length 1 Total 3,185 2,269 470 Results 90-100% 2 0 0 80-89% 0 0 0 70-79% .
0 0 0 60-69% 0 2 0 50-59% 5 3 0 40-49% 20 11 0 30-39% 123 60 1 20-29% 150 62 30 .
S ubtot.al 300 138 31
<20% 309 81 253 Distorted 110 195 0 No Defect Detected 2,466 1,855 186 Total 3,185 2,269 470 i
_ . . _ . - _ _ _ _ . _ - . . . _ - _ _ . . . . - . . _ . . . _ . . . - _ _ . . - . _ . _ _ . . . _ , . . _ _ . , , _ - . . _ . . . . ._ _ __ _ _ . ....- ,.._... ~... . - , _ . . . - - - -
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TABLE 2 -
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POINT BEACH NUCLEAR PLANT UNIT 2, APRIL, 1981, INSPECTION EDDY CUnRENT INDICATIONS BY SIZE AND LOCATION
<20% 21-29% 30-39% 40-49% 50-59% 60-69% 70-79% 80-89% 90-100%
- 1. "A" Ilot Leg Top of Tubesheet 300 146 119 20 4 0 0 0 0 Deep Crevice 0 0 0 0 0 0 0 0 2
" Above Tubesheet 9 2 0 0 1 0 0 0 0
- 17" Above Tubesheet 0 1 0 0 0 0 0 0 0 First Support Plate 0 1 3 0 0 0 0 0 0 i
Second Support Plate 0 0 1 0 0 0 0 0 0 i
Total 309 150 123 20 5 0 0 0 2 1 2. "B" Ilot Leg 1
Top of Tubesheet 70 55 58 11 3 2 0 0 0 h" Above Tubesheet 9 7 1 0 0 0 0 0 0 1" Above Tubesheet 1 0 1 0 0 0 0 0 0
- 2" Above Tubesheet 1 0 0 0 0 0 0 0 0
. Total 81 62 60 11 3 2 0 0 0 i
- 3. "B" Cold Leg <20% 20-29% 30-39% >40%
Top of Tubesheet' O O O O Above Tubesheet 174 19 0 0 1" Above Tubesheet 64 7 0 0
. 1 " Above Tubesheet 15 4 1 0 >
, Totals 253 30 1 0
(" Top of tubesheet" equals. indication at top of .tubesheet 'or within 1/2" above or below top of tubesheet."
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. . . . _ . ~ .- . .
TABLE 3 TUBES PLUGGED DURING THIS OUTAGE "A" Steam Generator
. Tube Indication
, Identification Size, % Indication Location-R12C22 52 Top of tubesheet R10C24 44 Top of tubesheet
, R20C24 41 Top of tubesheet R19C29 55 Top of tubesheet
%" above tubesheet R26C31 59 R17C33 92/26 6" above tube end/ Top of tubesheet R19C39 92 9-13" above tube end R12C41 46 Top of tubesheet R20C41 41 Top of tubesheet R23C41 45 Top of tubesheet R12C43 42 Top of tubesheet R13C44 45 Top of tubesheet R19C44 51 Top of tubesheet R21C44 51 Top of tubesheet R22C44 49 Top of tubesheet R10C45 43 Top of tubesheet R11C45 41 Top of tubesheet R2 3C45 47 Top of tubesheet R33C49 43 Top of tubesheet ,
R25C55 42 Top of tubesheet R21C62 . 4.7 Top of tubesheet R19C66 46 Top of tubesheet R12C71 41 Top of tubesheet R17C71 41 Top of tubesheet R15 C73
- 41 Top of tubesheet "B" Steam generator R06C17 60 Top of tubesheet R07C17 66 Top of tubesheet R06C18 41 Top of tubesheet R06C19 '
41 Top of tubesheet R06C20 46 Top of tubesheet R06C22 46 Top of tubesheet 1 R14C22 46 Top of tubesheet !
R22C25 46 Top of tubesheet
' )
. R24 C25 46 Top of tubesheet
- R26C25 41 Top of tubesheet R26C26 41 Top of tubesheet R22C29 44 Top of tubesheet R15C32 54 Top of tubesheet R09C64 53 Top of tubesheet R06C74 46 Top of tubesheet R08C76 50 Top of tubesheet
- Pulled and weld plugged. .
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TABLE 4 i .
COMPARISON OF 19 80 EDDY CURRENT RESULTS WITH 1981 1980 1981 Still No De fe ct Increased Increased Increased Signal
<20% <20% De tected <10% 10-20% >20% Distorted
$ "A" SG Inlet 253 130 28 69 16 2 8
'"A" SG Outlet 9 3
1 0 0 0 0 0 "B" SG Inlet 48 13 18 6 4 1 6 406 2 "B" SG Outlet 208 5 9 0 0 0 Same No Defect Decreased Increased Increased Increased Signal
{ 20-29% 13% Detecte d >3% 4-10% 11-20% >20% Distorted l "A" SG Inlet 118 42 3 8 36 22 3 4 1
"A" SG Outlet 0 "B" SG Inlet 24 9 1 5 5 1 1 2
- "B" SG Outlet 28 15 0 9 4 0 0 0 Same No Defect Decreased Increased Increased Increased Signal 30-39% 3%_ Detected >3% 4-10% 11-20% >20% Distorted i- " A" S G Inle t 80 8 26 0 12 21 7 0 4 "A" SG Outlet 0 "B" SG Inlet 8 2 0 3 3 0 0 0
- l. "B" SG Outlet 4 0 0 4 0 0 0 0 l -
f Eight tubes not inspected in .1981.
184 tubes not inspected in 1981.
8 10 tubes were plugged in 1980.
TABLE 5 COMPARISON OF 1981 AND 1989 EDDY CURRENT SIGNALS "A" STEAM GENERATOR INLET - POINT BEACH UNIT 2 1981 1980 Tube _ Reported Reported Signal Comparison R12C22 52 35 VC and DC R10C24 44 37 Prob. NC
R19C39 92 ND New-(9" to 13" above tube end)
R12C41 46 35 NC R20C41 41 25 NC R23C41 45 31 NC R12C43 42 35 NC R13C44 45 32 NC R19C44 51 34 NC R21C44 51 33 NC-R22C44 49 <20 NC R10C45 43 34 NC RllC45 41 ND DC and VC R23C45 47 26 NC R33C49 43 36 NC R25C55 42 26 DC and VC
Codos:
DC = Depth change VC = Volume change NC = No change ND = No degradation reported Undefinable indication VI =
Comparison of the Above Tubes:
The depth and/or volume changes in the eddy current test results from 1980 to 1981 range from small to moderate. Those tubes with asterisks (*) exhibit the most change from 1980 to 1981 in depth and/or volume. The test results are all analyzed off the mixing of 400 KHz and 100 KHZ to suppress the tubesheet signal and deposits on the OD of the tubing. The reevhluation of the 1980 test was done using the same mix as was used in 1981.
- - - . -_ _. . _ . , . _ . . _ . . ___ ~ _ _ _ _ _ _ , .
TABLE 6 STEAM GENERATOR A INLET COMPARISON OF 1981 EDDY CURRENT RESULTS WITH PREVIOUS EDDY CURRENT INSPECTION RESULTS Inspection Results Reported Tube J98J 1980 1979 1978 1977 1976 1974*
R12Cl2 52/TTS 35/TTS -- -- -- -- --
R10C24 44/TTS 37/TTS -- -- -- -- --
R20C24 41/TTS <20/TTS -- -- -- -- --
l R19C29 55/TTS 25/TTS --
ND DTS --
ND 1 R26C31 59/h ND --
ND ND ND ND R17C33 92/Crev. <20/ --
ND <20/ <20/h <20/h Rl9C39 92/Crev. ND --
ND <20/ <20/1 <20/1 R12C41 46/TTS 35/TTS --
ND DTS <20/TTS ND ,
R20C41 41/TTS 25/TTS --
ND <20/TTS <20/TTS <20/TTS R23C41 45/TTS 31/TTS --
ND <20/TTS <20/TTS <20/TTS R12C43 42/TTS 35/TTS --
ND ND ND ND R13C44 45/TTS 32/TTS --
N0 DTS DTS ND R19C44 51/TTS 34/TTS Cu ND ND <20/TTS 21/TTS R21C44 Sl/TTS 33/TTS --
ND DTS DTS ND R22C44 49/TTS <20/TTS --
ND DTS DTS ND R10C45 43/TTS 34/TTS --
ND DTS DTS NS RllC45 41/TTS ND --
ND DTS DTS ND R23C45 47/TTS 26/TTS --
ND DTS ND ND R33C49 43/TTS 36/TTS -- -- --
ND --
R2EC55 42/TTS 26/TTS --
ND DTS DTS ND ,
R21C62 47/TTS 35/TTS --
ND DTS DTS ND R19C66 46/TTS 21/TTS --
ND DTS -- --
R12C71 41/TTS 31/TTS -- -- -- -- --
Rl7C71 41/TTS 32/TTS -- -- -- -- --
R15C73 41/TTS 36/TTS -- -- -- -- --
A/B = Percent Degradation / Location Above Tubesheet In Inches.
TTS = Top of Tube Sheet Cu = Copper ND = No Degradation Reported DTS = Distorted Tubesheet Signal
-- = Not Inspected
- In 1975 the Unit 2 "A" Steam Generator was not eddy current inspected.
TABLE 7
SUMMARY
OF PREVIOUS STEAM GENERATOR EDDY CURRENT INSPECTION RESULTS POINT BEACH NWCLEAR PLANT UNIT 2 Number Of Number Of Tubes Recorded Tubes Inspected With Following Degradations Year Of > 40% 39-30% 29-20% < 20% DTS
- Inspection A Inlet B Inlet A/B. A/B A/B A/B A/B 1974 1090 442 12/8 8/5 14/2 169/110 NR 1975 0 722 -/3 -/0 -/4 -/1 NR 1976 1223 1120 14/3 14/6 29/5 174/73 186/25 1977 1056 1457 0/4 12/7 28/5 153/51 493/997 1978 133S 796 1/0 6/7 18/5 19/7 NR 1979 570 455 0/1 6/3 5/3 20/10 NR 1980 3138 717 26/0 80/8 118/23 253/9 NR DTS = Distorted Tube Sheet Signal NR = None Reported ,
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