ML20052D043

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Forwards Eddy Current Rept in Response to 820325 Request. Test Results of 1D Hot Leg Tube Sheet & 1A,1B & 1C Cold Leg Periphery Regions Will Be Provided by 820515
ML20052D043
Person / Time
Site: Zion File:ZionSolutions icon.png
Issue date: 05/03/1982
From: Lentine F
COMMONWEALTH EDISON CO.
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
4031N, NUDOCS 8205060222
Download: ML20052D043 (65)


Text

{{#Wiki_filter:g_ / 'N Commonwealth Edison [ ) one First Nation:t Ptua, Chiergo. Ilknois i ? 7 Addrrss R ply to: P:st Offica bot 767 ~~ \\ Chicago, Illinois 60690 May 3, 1982 N o Mr. Darrell G. Eisenhut, Director Division o f Licensing U.S. Nuclear Regulatory Commission C.7C C'r;9 9 Washington, DC 20555 d-T- ,,N O 1962n- ?

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Subject:

Zion Station Unit 1 s Steam Generator ( y'/ Inspection and Repair

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NRC Docket No. 50-295 References (a): March 10, 1982, letter from D. G. Eisenhut to L. De lGeo rge. (b): March 17, 1982, letter from F. Lentine to D. G. Eisenhut. (c): April 1, 1982, letter from F. Lentine to D. G. Eisenhut. (d): April 14, 1982, letter from T. Novak to L. DelGeorge.

Dear Mr. Eisenhut:

This is to provide Commonwealth Edison's report on the eddy current examinations of the Zion Unit 1 steam generators. This report was requested by the NRC in our meeting of March 25, 1982, and in reference (d). The report is complete with the exception of the 10 hot leg tubesheet and the 1A, 1B and 1C cold leg periphery regions. Examinations in these areas are still in progress. Results of these examinations will be provided in a supplemental report about May 15, 1982. The results of the extensive examination program have been carefully analyzed and evaluated by Commonwealth Edison and Westinghouse personnel. While the number of defective tubes has increased compared to the number observed in previous examinations at Zion, the overall incidence of tube defects continues to be low in relation to the general industry experience. In our judgment, none of the types of degradation observed present a hazard to safe plant operation. By removal from service of defective and degraded tubes according to conservative criteria, we have provided reasonable A I assurance that tube leakage in excess o f Technical Specification limits will not develop over the course of the next operating g C)CII cycle. We will continue to pursue an aggressive program for the long-term investigation of tube degradation phenomena, with the intent of identifying possible corrective actions and preventive / ( measures. 8205060222 820503 PDR ADOCK 05000295 G F:3R

g- _ b D. G. Eisenhut May 3, 1982 Reference (d) a ffirmed the NRC's intention to review the results of the eddy current examinations and approve any proposed actions before Unit I returns to power. The unit's return to power is now scheduled for June 4, 1962. Should you desire additional clarification of any of the information presented in the eddy current report, Commonwealth Edison will be available for further discussions at your convenience. Please address questions regarding these matters to this Very truly yours, k =$ F. G. Lentin e Nuclear Licensing Administrator 1m Enclosure 4031N e

EDDY CURRENT REPORT INTRODUCTION In December, 1980 small primary to secondary leakage was identified in Ziorr Ul,1B and 1C steam generators (45 gpd and 5 gpd respectively). During the January to March 1981 refueling outage, extensive inspections of the steam generator tubes were conducted to identify and remedy the source of the leakage. A secondary side hydrostatic test of the 1B steam generator failed to show any evidence of leakage. ne following BSdy Current Testing Program was then performed from the hot leg side: 1B steam generator - approximately 3350 tube through first support, hot leg side - approximately 2700 tubes through seventh support, cold leg side - approximately 100 tubes full length IC steam generator - approximately 2700 tubes through seventh support, cold leg side - approximately 100 tubes full length 1A steam generator - row 1 and 2 through seventh support, cold leg side 1D steam generator - row 1 and 2 through seventh support, cold leg side %e results of this testing showed scme indications in row 2 of the 1B steam generator and row 1 of the 1C steam generator that were believed to be the source of the leakage. These tubes were removed from service using mechanically expanded plugs. A few other tubes were also iemoved from service due to indications exceeding the 40% plugging criteria in the plant 'Ibchnical Specifications. In the months following return of the unit to service a small amount of primary to secondary leakage (approximately 20 gpd) was observed in the 1B steam generator. E rough the months of July, August, and September 1981 the leakage could no longer be detected. In October 1981, leakage was again observed in the 1B steam generator and subsequently in the other three steam generators. E is leakage continued to be monitored and increased until the unit was shut down for refueling in February 1982. During the current refueling outage, eddy current testing of 100% of the tubes is being conducted. To date these examinations are essentially complete in the 1A, 1B, 1C, and 1D steam generators. In addition, a newly developed helium leak detection technique was employed to assist in pinpointing the source of leakage. Tabulations of the inspections and a stenary of the results are found in Enclosure 1. Also indicated are those tubes which have been or will be plugged. %ese criteria and tube sheet maps depicting the tubes removed from service by plugging are included in Enclosure 2..

DISCUSSION We results of the helitra leak detection and eddy current testing clearly show the source of primary to secondary leakage to be at the U-bend tangent point in a significant number of row 1 tubes. Some substantially smaller contribution may have come from the same location on a few row 2 tubes. Removal of these tubes from service is expected to remedy this leakage. Additionally, tubing defects at other locations were identified that i have not progressed to the point of causing tube failure. %e examination results for each of these defect locations are discussed individually. It must be kept in mind that examination of 100% of the tubes in each of the steam generators is the basis underlying all the data. For example, indications at the #7 tube support plate were found in 0.1% of the tubes, i indications in the tube sheet crevice were found in 0.08% of the tubes and the highest incidence were indications in the AVB locations found in 1% of the tubes. 'Ibbe Support Plate Iocations Sumary of Indications: Tabulation and analysis of the data at tube support plate ('ISP) e locations is included in Enclosure 3. It is clear that the tubes are experiencing some CD degradation at the top (#7) and bottom (#1) tube support plate locations only. %e #7 TSP indications are scattered among the four steam generators and 4 are as likely to be on the cold leg as the hot leg side. W ey all have occurred in a limited area of the bundle, between rows 9 to 16 and coltans 43 to 69. l %e #1 TSP indications are more segregated. %ey occur on the hot leg l side primarily in 1B and 1D steam generator and on the cold leg side exclusively in the 1D steam generator. %e latter might be explained due to i the fact that only 1D was tested 100% on the cold leg side. However, 3% (approximately 100 tubes) of the tubes were tested full length in each of the l other three generators with no resulting cold leg side, lower support plate indications. All tubes affected at the #1 TSP are found to lie on the tube bundle outer periphery. Based on these results, an additional 400 periphery tubes in each of 1A, 1B, and 1C steam generators will be examined on the cold leg side. An update to this report will be made by May 15, 1982 when the data evaluation is completed. In addition to those identified as having a certain percentage wall penetration, approximately 55 tubes were identified as having indication of dents at support plates. %ese dents appear to be very small in magnitude and probably do not exceed approximately.001 inches. Similar indications have occurred on each inspection since 1975 and no progression or worsening of the dents appears to be ongoing. _

Comparisons to Previous Inspection: Of the tubes with indications at the #7 TSP, six were tested in 1981. %e increase in wall penetration ranged from no growth to 43%, averaging approximately 29%. W is growth applies to a full operating fuel cycle of approximately ten effective full power months. %e remainder were not tested previously. Of these, the current wall penetration ranges from 21% to 73%, averaging approximately 51%. Since these were not tested in 1981, the growth is not known over a controlled time span as those above. It is likely that this degradation has been progressing for more than the previous year and therefore is better represented by the 29% in ten full power months described above. Only the tubes with hot leg side #1 TSP indications in 1B were examined in 1981. We increase in wall penetration (over ten full power months) ranged from 28% to 38% averaging approximately 33 1/2%. Here, as for the #7 'ISP indications, the conservative assumption is made that no indication represents 0% wall penetration. None of the tubes in 1D with hot leg or cold leg side #1 TSP indications were examined in 1981. % e hot leg side indications ranged from 21% to 58%, averaging 39%. %e cold leg side indications ranged from 21% to 49%, averaging 33 1/3%. Again it is likely. hat this degradation has been progressing for more than the previous operating cycle. Plugging Criteria: he Plant Technical Specification criteria of 40% will be used for removing tubes from service due to #1 and #7 TSP indications. Safety Significance To date tubing defects associated with TSP locations have not resulted in any leakage. %ey will not progress rapidly enough to result in tube leakage or failure providing those 40% and greater wall penetration tubes are removed frcan service by plugging. All periphery tubes will be examined from tube end to tube end and those degraded tubes remaining in service will be re-examined at the next scheduled refueling outage which will not exceed approximately ten full power months of operation. Continued operation with the few degraded tubes poses no undue risk on the safe operation of the unit. 'Ibbe Sheet Crevice Region Summary of Indications: Tabulation of the data in the tube sheet crevice region is included in. 'IWlve tubes are experiencing OD degradation between 6 and 18 inches above the tube ends. To date, indications have been found exclusively in the hot leg side with the highest occurrence in IB steam generator. - - -

r WesGnghouse Series 51 steam generator design includes a 21 inch thick tube sheet in which the tubing is rolled into contact for approximately the bottom 2 1/4 inches. W is design leaves an annular crevice between the tube and tube sheet from approximately 2 inches above the tube end to the top of the tube sheet. Half of the indications found had measurable defects similar in nature to OD initiated intergrannular stress corrosion cracking (IGSCC) found at a n eber of other domestic plants. Some of these tubes have eddy current signals superimposed that may be indicative of OD initiated intergrannular attack (IGA). We remaining indications were severly distorted eddy current signals that preclude wall penetration measurement. n e nature of any defects that may cause these distortions is currently uncertain. Comparison to Previous Inspections: All of the tubes with tube sheet crevice indications in the 1B and 1C steam generators were inspected in 1981. No indications were found in any tubes in the crevice region during that inspection. Se six tubes with measurable indiction grew from 25% to 94%, averaging approximately 74%. Plugging Criteria: % e Plant Technical Specification criteria of 40% is normally used for removing tubes from service. However, due to the rate of growth experienced during the past operating cycle, the tube with a 25% wall penetration signal will also be removed from service. Additionally, those tubes with immeasurable distorted signals will be removed from services. Mitigating Actions: Metallurgical and chemical analyses of tube samples from other operating plants indicate that IGSOC or IGA are the failure modes in the tube sheet crevice region. Phosphates, caustics or other corrodant species apparently " hide out" in the sludge that builds up in the annular crevices. Zion Station intends to perform a crevice flushing operation similar in technique to that used at Point Beach prior to unit start up. By flushing, the soluble contaminents should be removed or the concentrations sufficiently modified to minimize the rate of attack. Additionally, by sampling the flushing effluent, the corrodant species may be identified. Safety Significance: ib date, no tube has failed or leaked due to a defect in the tube sheet crevice region at Zion Station. Should through wall penetration occur it is expected that leakage rates would remain very low and catastrophic tube separation would not occur due to restraint provided by the tube sheet. We experience of other operating plants with tube sheet crevice region degradation incidents are cited as supportive. Examination of every tube in the hot leg tube sheet crevice region, the use of conservative plugging criteria, and cleaning of the crevices by a flushing technique should ensure safe unit operation will not be adversely affected by this mode of tube degradation. Anti-Vibration Bar Incations Sumary of Indications: Tabulation and analysis of the data at anti-vibration bar (AVB) locations is included in Enclosure 5. We tubing is experiencing some CD degradation due to loss of wall at the #2 and #3 AVB in particular. In total, there are 158 tubes with sme eddy current indication. Were are 57 indications that were significant enough to have measurable wall penetration between 20% and 86%. These indications did not extend beyond the edges of the anti-vibration bars and were therefore less than 1/4 inch in length. Another 48 were interpreted to be 20%, 34 were so small or distorted to be imeasurable and 10 show some very minor dent signals. No particular pattern has emerged to contribute to the analysis. Comparison to Previous Inspection: Of the 57 tubes with measureable indications, 25 were tested in 1981. One tube showed no growth by remaining at 38%. Fifteen tubes showed no indications detected in 1981. %ese increased to a range of 21% to 86%, averaging approximately 39% (over ten effective full power months). Nine showed very small distorted signals in 1981. Wese increased to a range of 20% to 82%, averaging approximately 36%. 2e remaining 32 indications were in tubes not tested in 1981. Without i a known starting point, calculation of a growth rate is not practical. 'Ib be conservative, however, the wall penetration could be applied over the same ten effective full power months as above. %e average would be slightly higher at 45% but the range 22% to 70% shows that none were as severe as those above. Plugging Criteria: In order to ensure degraded tubes at AVB locations will not result in primary to secondary leakage through the next operating cycle (ten full power months) all tubes with irdications 20% and greater will be removed from service by mechanical plugging. Mitigating Actions Zion Station has requested Westinghouse Electric Corporation to develop a long-term plan for investigation of tube degradation at the AVB. Wis effort will include consideration of removal of a tube at an AVB location along with a section of AVB. i O Safety Significance: To date, after nine years of power operation, no tube has failed or leaked due to a defect at the AVB locations at Zion Station. We only place this has occurred was at another domestic plant were leakage occurred after approximately two months of power operation following the failure to plug an 86% defect. %e leakage in that case reached 500 gpd 14 days after it was first detected. By examining every tube through the U-bend and conservatively plugging all tubes with measureable defects, power operation should not be adversely affected by tube degradation at the AVBs. At an average progression of 39% over one operating cycle, less then 59% wall penetration is expected at the end of the next operating cycle. Since the area of degradation is thought to be confined to the small area of contact between the tube and the AVB, tube integrity is expected to be maintained at an acceptable level under all normal and accident conditions. In the unlikely event that degradation proceeds through-wall, the flaw would be expected to develop gradually and grow to a maximum size of about 1/4" by 1/4". This would correspond to leakage greater than the Technical Specification limit of 500 gpd but within the capacity of the normal charging system, such that orderly plant shutdown could be achieved by the use of normal operating procedures. U-Bend Tangent Point Incations Sumary of Indications: Tabulation of the data at Row 1 and 2 U-bend tangent point locations is included in Enclosure 6. We tubes are experiencing ID originated degradation that appears similar to those identified at other damestic plants as stress corrosion cracking. The indications are limited to the tangent point of the U-bend to straight length transition and do not exceed approximately 1/2 inch axial length. We results of helium leak detection testing performed showed ninteen potentially leaking Row 1 tubes in lA, 1B and 1C steam generators. Of these, eight tubes were confirmed to have 100% through wall eddy current indi-cations. he remaining eleven had the eddy current signals distorted at one of the tangent points that are apparently masking any defect signals. It is believed this distortion is created by probe motion entering the U-bend or geometric discontinuities manufactured into the tubing at these locationc. We helium leak testing additionally resulted in three Row 2 tubes that were possibly leaking. None of these tubes resulted in eddy current defect signals. One Row 1 and one Row 2 tube were found with 80% wall penetration indications at a U-bend tangent point in non-leaking tubes. Eleven additional Row 1 tubes resulted in eddy current signals distorted similarly to the eleven described above. It is possible that there are defects present that are masked. If so, it is assumed they do not penetrate 100% through wall since no helium leakage was detected. he results of helium and eddy current testing showed no Row 1 or 2 indications in 1D steam generator. Comparison to Previous Inspections: All of the Row 1 and 2 tubes in lA, 1B, 1C and 1D were inspected through the U-bends in 1981. At that time sixteen Row 2 tubes in 1B and two Row 1 tubes in lc were found to have distorted U-bend tangent point indications. Since hydrostatic leak testing was not successful in identifying any failed tubes, all of the above tubes were removed from service in an attempt to remedy the known leakage. None of the tubes left in service, including those that have been identified as leakers or potential leakers in 1982 were identified as having eddy current indications in 1981. Review of the data from 1981 and direct comparison to the 1982 data has been performed. We previous evaluation was confirmed. Additionally no correlation of signal characteristics between tubes that became leakers and those that didn't could be made. Data evaluation to predict next cycle leakers does not appear to be practicable at this time. Plugging Criteria: Any tube showing evidence of leakage will be removed from service by mechanical plugging. Any Row 1 or 2 tube with any defect indication or distorted signal at the U-bend tangent point will also be plugged in order to decrease the probability of leakage during the next operating cycle. Mitigating Actions: Due to the evidence of Row 1 tube leakage, Zion Station has decided to remove all Row 1 tubes from service by mechanical plugging. W is decision has been made because of pressing needs to assure high unit availability. Additionally, all Row 2 tubes will be re-examined through the U-bends at the next scheduled refueling outage. Safety Significance: In addition to Zion Station, seven units have experienced U-bend cracking. Experience and the nature of intergranular stress corrosion cracking results in any leakage from these locations beginning very small (on the order of 10 gpd). As the cracking progresses slowly or as a number of additional tubes are penetrated, the leakage rate climbs at a slow, managable rate. %e largest leakage observed to date did not exceed approximately 0.7 gpn (" 1000 gpd). t 'Ihe experience at Zion strongly supports this behavior. As discussed previously, leakage was observed at low rates at the beginning of the last operating cycle and took nine full operating months (or nearly one full fuel cycle) to reach the Technical Specification limit of 500 gpd. Power operation of the steam generators with Row 1 or 2 tubes in service, providing no leakage or defects are currently detectable, poses no undue risk to safe operation of the unit. Zion Station has taken the additional step of plugging all Row 1 tubes. It is expected that the probability of primary to secondary leakage will be significantly reduced as a result. ) t I e 1 T 4 1 l l f

00tCLUSIOtB 1. Extensive steam generator tubing inspections have been performed. 1 ' a. Helium leak testing was performed on all four steam generators. b. All previously unplugged tubes were eddy current examined from the hot leg tube sheet through the top support on the cold leg side. c. 3% of the tubes in lA, IB, and 1C were eddy current examined tube end to tube end. d. 100% of the tubes in 1D will be eddy current examined tube end to tube end. 2. An increase of defective tubes have been observed and some new defect locations have been identified. 3. Primary to secondary leakage has occurred only due to defects at the row 1 (and possibly row 2) U-bend tangent points. 4. Plugging criteria more conservative than the Technical Specifications have been adopted. 5. Continued safe operation is justified due to removal from service of defective tubes and removal from service of tubes that may degrade through the next power operating cycle. 6. Should further tube degradation occur, it is expected that it will be observed as leakage within Technical Specification limits. Resulting safe and orderly shutdown will then occur before the limits are exceeded. 7. Ebrther investigations are being undertaken to determine the failure causes and develop mitigating actions. a. Engineering studies have been initiated to remove a tube at an AVB location along with a section of AVB. b. Methods for identification of corrodant species in the tube sheet crevice region are being investigated, including chemical analysis of the crevice flushing effluent. t c. All degraded tubes remaining in service will be re-examined at the next scheduled refueling. I d. All periphery tubes will be examined tube end to tube end at the l next refueling outage. e. All Row 2 tubes remaining in service will be re-examined at the next scheduled refueling outage. 1 f. An additional 3% sample of tubes, showing no previous indications will be examined at the next scheduled refueling outage. l _ _.

l l ENCIDSURE 1 Tabulation of 1982 Outage Eddy Current Data Ebr Zion Unit 1 Steam Generators t l ) j

Steam Generator 'Ibbes Examined "A" Steam Generator 'Ib 7th TSP Cold Ieg 3263 2 tubes plugged originally Full Iength 123 'Ibtal 3386 "B" Steam Generator 'Ib 7th TSP Cold Ieg 3244 20 tubes plugged 1981 Full length 124 'Ibtal 3368 "C" Steam Generator ' 'Ib 7th TSP Cold Ieg 3255 10 tubes plugged 1981 Full Iength 123 'Ibtal 3378 "D" Steam Generator From Cold Iag to Ibt leg Tube sheet Midplane 2992 (Hot Iag Tube Sheet yet to do) Ebll Iength from Hot Iet 396 Total 3388

s "A" STEP. GENERATOR

  1. 7 ibbe Support Plate Indications E/C RESULTS S/G ROW CDLINN TSP #

SIDE 1982 PLUG A 8 61 7 C/L 63% Yes A 8 56 7 H/L 53% Yes A 11 61 7 H/L 53% Yes A 11 63 7 H/L 48% Yes A 8 69 7 C/L 47% Yes A 9 44 7 C/L 42% Yes A 9 43 7 C/L 21% tb Above Tube End (ATE) Indications INCHES E/C RESULTS S/G ROW 00LINN ATE SIDE 1982 PLUG A 2 38 6 to 10 U/L 77% Yes A 17 10 16 to 18 H/L SO (imeasurable) Yes 46 48 12 H/L SQ (imeasurable) Yes Anti-Vibration Bar (AVB) Indications E/C RESULTS S/G RON COLINN AVB# 1982 PLUG A 39 70 4 54% Yes A 39 66 2 52% Yes A 32 55 2 51% Yes A 41 32 4 51% Yes A 39 72 2 44% Yes A 20 39 2 33% Yes A 20 36 1 29% Yes

"A" STEAM GENERA'IOR Row 1 & 2 Indications E/C RESULTS He INDICATION S/G RON ODIINN 1982 1982 PLUC A 1 58 100% C/L Tangent Yes Yes A 1 26 100% C/L Tangent Yes Yes A 1 7 Unknown-Defect masked Tang Dent Yes Yes A 1 48 Possible-Distort C/L Tangent No Yes A 1 73 Possible-Distort C/L Tangent No Yes A 1 80 Possible-Distort C/L Tangent No Yes A 1 85 Possible-Distort C/L Tangent No Yes A 1 74 Possible-Distort H/L Tangent No Yes A 1 77 Possible-Distort H/L Tangent No Yes A 1 86 Possible-Distort H/L Tangent No Yes A 1 93 Possible-Distort H/L Tangent No Yes A+ 1 94 Possible-Distort H/L Tangent No Yes A 1 3 Possible-Distort H/L Tangent No Yes A 2 3 NI Yes Yes A 2 48 NI Yes Yes Miscellaneous Indications E/C RESULTS SjG ROW ( D LI M 3 TSPf_ SIDE 1982 PLUG A 27 78 12" above 5 H/L 27% No 1 A 37 48 40" above 3 H/L 24% No A 27 10 20" above 6 C/L 22% No e

L i t "B" STEAM GENERA'IOR

  1. 1 'Ibbe Support Plate Indications E/C RESULTS S/G ROW COLLNN TSP #

SIDE 1982-PLUG B 11 2 1 H/L 38% tb B 43 35 1 H/L 37% No B 14 3 1 H/L 35% te B 20 6 1 H/L 35% No i B 26 11 1 H/L 32% No 1 B 9 3 1 H/L 30% tb l B 16 4 1 H/L 28% No [ Above 'Ibbe End (ATE) - Within 'Ihe Tube Sheet - Indications INCHES E/C RESULTS S/G ROW CDLLMN ATE SIDE 1982 PLUG l B 3 39 6 to 10 H/L 94% Yes B 2 58 8 H/L 89% Yes B 22 18 12 to 14 H/L 89% Yes B 25 18 14 H/L 72% Yes B 30 23 10 to 13 H/L SQ (imneasurdble) Yes l B 29 23 9 to 12 H/L SQ (imneasurable) Yes B 25 21 9 to 14 H/L SQ (iarneasurable) Yes B 23 19 8 H/L 25% Yes i l

"B" STEAM GENERATOR Anti-Vibration Bar (AVB) Indications E/C RESULTS S/G ROW COLLEN AVB4 1982 PLUG B 37 56 3 86% Yes B 36 52 2 82% Yes B 36 52 3 27% Yes B-36 52 4 24% Yes B 27 11 1 55% Yes B 39 43 1 49% Yes B 39 43 2 38% Yes B 39 40 2 46% Yes B 39 45 2 41% Yes B 31 48 2 38% Yes B 38 58 1 37% Yes B 38 58 2 25% Yes B 34 51 3 36% Yes B 37 55 3 29% Yes B 34 58 2 28% Yes B 29 63 3 25% Yes B 33 55 2 20% Yes B 33 55 3 23% Yes B .78 40 3 22% Yes B 34 53' 4 22% Yes B 35 54 3 20% Yes Row 1 & 2 Indications E/C REULTS He INDICATION S/G ROW CDLINN 1982 1982 PLUG B 1 20 100% H/L Tangent Yes Yes B 1 42 100% H/L Tangent Yes Yes B 1-79 80% C/L Tangent No Yes B 1 11 Defect masked by Tang Dent Yes Yes B 1 10 Defect masked by Tang Dent Yes Yes B 1 9 Defect masked by Tang Dent Yes Yes B 1 8 Defect masked by Tang Dent Yes Yes B 2 47 80% H/L Tangent No Yes

k a "B" STEAM GENERA'IOR Miscellaneous Indications t E/C RESUL'IS S/G R0ki ODIINN 1982 PLUG B 3 31 Restricted U-Bend Area Yes I - d j E/C RESULTS l S/G ROf QLINN TSP # SIDE 1981 1982 PLUG B 9 46 7 C/L 30% Distorted Ib B 9 53 7 C/L Distorted 37% .No 9 W 4 1

"C" STEAM GENERA'IOR

  1. 7 'Ibbe Support Plate Indications E/C RESUL'IS S/G ROW COLLNN

'ISP # SIDE 1982 PLUG C 8 52 7 C/L 54% Yes C 9 53 7 C/L 43% Yes C 8 56 7 C/L 42% Yes C 9 52 7 H/L 38% No

          • =*************************************************************************

Above 'Ibbe End (ATE) - Within 'Ihe '1bbe Sheet - Indications INCHES E/C RESULTS S/G ROW (DLLNN ATE SIDE 1982 PLUG C 22 9 12 to 16 H/L SQ (imeasurable) Yes Anti-Vibration Bar (AVB) Indications E/C RESULTS S/G ROW 00LINN AVB# 1982 PLUG C 35 56 3 70% Yes C 35 56 4 49% C 35 57 4 52% Yes C 35 57 3 21% C 39 59 3 45% Yes C 15 31 4 34% Yes

i "C" STEAM GENEPAIOR Row 1 & 2 Indications E/C RESULTS He INDICATION S/G ROW COLINN 1982 1982 PLUG C 1 7 100% Tangent H/L Yes Yes C 1 23 100% Tangent C/L Yes Yes C 1 65 100% H/L Tangent Yes Yes C 1 74 100% C/L Tangent Yes Yes C 1 24 C/L Tangent Distorted by Dent No Yes C 1 33 Distorted by Tangent Dent Yes Yes C 1 55 Defect Masked by Tangent Dent Yes Yes C 1 80 Defect Masked by Tangent Dent Yes Yes C 1 93 Defect Masked by Tangent Dent Yes Yes C 1 48 NI ? Yes C 2 23 NI ? Yes-Miscellaneous Indication E/C RESUL'IS S/G ROW COLINN TSP # SIDE 1982 PLUG C 45 44 1 H/L 34% tb C 30 13 4 H/L 28% No

                                                                                                                                                • 4 r*****

'Ibbe Plug Corrections S/G ROW OOLLMN SIDE S/G ROW CDIDW SIDE C 1 63 . C/L only C 1 64 H/L Only C 1 69 C/L only C 1 70 H/L Only C 9 43 C/L only C 9 45 H/L Only C 15 66 C/L only C 15 67 H/L Only C 17 66 C/L only C 17 67 H/L Only

t f a "D" STEAM GENEPA'IOR

  1. 1 'Ibbe Support Plate Indications E/C RESUL'IS S/G RON COLLNN TSP #

SIDE 1982 PLUG D 46 53 1 H/L 58% Yes D 21 7 1 C/L 49% Yes D 39 23 1 C/L 46% Yes D 8 93 1 H/L 46% Yes D 23 85 1 C/L 45% Yes D 21 8 1 C/L 44% Yes D 26 85 1 C/L 43% Yes D 9 92 1 C/L 43% Yes D 23 87 1 C/L 38% tb D 40 69 1 C/L 37% No D 21 87 1 H/L 36% No D 46 54 1 H/L 34% No D 21 86 1 C/L 31% No D 45 51 1 C/L 28% No D 20 7 1 C/L 27% te D 40 25 1 C/L 25% No D 8 92 1 C/L 23% No D 18 29 1 C/L 23% No D 20-89 1 C/L 22% No D 18 90 1 C/L 21% No D 10 93 1 C/L 21% lb D 45 54 1 H/L 21% No

e r 4 i i r I a i "D" STEAM GENERA'IOR

  1. 7 'Ibbe Support Plate Indications l

E/C RESULTS f S/G ROW CDLINN TSP # SIDE 1982 PLUG t-i' D 16 61 7 C/L 73% Yes l D 15 48 7 H/L 67% Yes j D 15 66 7 C/L 64% Yes D 9 47 7 C/L 49% Yes ( D 9 59 7 C/L 30% No [ i f e I k f 4 v b i I A. t t ,v.. w a, y

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g. t L "D" STEN 4 GE2ERATOR i Anti-Vibration Bar (AVB) Indications E/C RESULTS S/G RON 00LINN AVB# 1982 PLUG D 19 67 2 65% Yes D 29 47 2 65% Yes D 40 52 2 60% Yes D 29 52 2 56% Yes i D 18 48 2 55% Yes i D 40 55 3 54% Yes i D 41 30 2 53% Yes D 14 81 3 53% Yes D 32 52 2 50% Yes D 40 58 1 49% Yes l D 18 65 3 43% Yes D 29 49 2 43% Yes D 40 50 2 42% Yes l D 17 72 3 42% Yes D 40 45 4 41% Yes t D 17 30 3 40% Yes D 41 57 2 34% Yes D 40 57 3 30% Yes D 32 48 2 29% Yes D 40 54 3 29% Yes D 38 64 1 22% Yes i 4 }

"D" STFJN GENERATOR Above ibbe End (ATE) Indications t Ibne Row 1 & 2 Indications None 7

i l l t ENCLOSURE 2 Tube Maps Showing Tubes Plugged in Zion Unit 1 Steam Generators F e l F

ZION STATION L 'IUBE PLUGGING CRITERIA MARCH 1982 ALL TUBES WITH DEFECT INDICATIONS 40% OR GREATER THROUGH WALL PENETRATION PER TBCilNICAL SPECIFICTIONS, WITH THE FOLIIMING ADDED CONSERVATIONS: A. Row 1 and 2 U-bend tangent points - any eddy current indication B. Anti-Vibration Bar (AVB) locations - any tube with 20% or greater wall penetration C. Ubbe sheet locations - any tube with 40% or greater wall penetration or any severely distorted ("squirrely") indication D. All locations - any tube showing evidence of leakage 7 i I

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ENCIOSURE 3 Analysis of Data for Indications at Tube Support Plate locations 4 e

4 Eddy Current results from 1981 examination compared to 1982 examination of the indications at the W be Support Plate locations.

  1. 7 hbe Support Plate (TSP) Indications Nr = No Test NI = No Indi
                                                                                                                                • cation E/C RESULTS S/G ROW COLIFW TSP #

SIDE 1981 1982 A 8 61 7 C/L NT 63% A 8 56 7 H/L Nr 53% A 11 61 7 H/L NT 53% A 11 63 7 H/L NT 48% A 8 69 7 C/L NT 47% A 9 44 7 C/L NT 42% A 9 43 7 C/L NT 21% B 9 46 7 C/L 30% Distorted B 9 53 7 C/L Distorted 37% C 8 52 7 C/L 30% 54% C 9 52 7 H/L 38% 38% C 8 56 7 C/L NI 42% C 9 53 7 C/L NI 43% D 9 47 7 C/L NT 49% D 16 61 7 C/L Nr 73% D 15 48 7 H/L NT 67% D 15 66 7 C/L NT 64% D 9 59 7 C/L NT 30%

  1. 1 Tube Support Plate ('ISP) Indications E/C RESULTS S/G POW COLLEN TSP #

SIDE 1981 1982 B 11 2 1 H/L NI 38% B 43 35 1 H/L NI 37% B 14 3 1 H/L NI 35% j B 20 6 1 H/L NI 35% 1 B 26 11 1 H/L NI 32% l B 9 3 1 H/L NI 30% B 16 4 1 H/L NI 28% C 45 44 1 H/L NI 34%

\\ S/G ROW COLINN TSP # SIDE 1981 1982 D 46 53 1 H/L NT 58% D 21 7 1 C/L NT 49% D 39 23 1 C/L NT 46% D - 8 93 1 H/L NT 46% D 23 85 1 C/L NT 45% D 21 8 1 C/L NT 44% D 26 85 1 C/L Nr 43% D 9 92 1 C/L NT 43% D 23 87 1 C/L Nr 38% l D 40 69 1 C/L Nr 37% i D 21 87 1 H/L Nr 36% D 46 54 1 H/L NT 34% r D 21 86 1 C/L Nr 31% D 45 51 1 C/L Nr 28% D 20 7 1 C/L Nr 27% D 40 25 1 C/L Nr 25% D 8 92 1 C/L Nr 23% D 18 89 1 C/L NT 23% D 20 89 1 C/L Nr 22% D 18 90 1 C/L Nr 21% D 10 93 1 C/L Nr 21% D 45 54 1 H/L Nr 21% j l e I l

ZION UNIT 1 'IUBE SUPPORT PLATE EDDY CURRENT INDICATIOtE* IN ALL EDUR STEAM GENERNIORS (MAR 31-APRIL 1982) Stm Gen l Dent i Distorted l 420 l 20-29 l 30-39 l 40-49 I 50-59 l 60-69 1 70-79 1 80-89 l 90-99 l 100 l 'Ibtal 1A 14 0 0 1 0 3 2 1 0 0 0 0 21 1B 18 1 -3 1 7 0 0 0 0 0 0 0 30 1C 5 0 2 0 2 2 1 0 0 0 0 0 12 1D 18 0 4 9 5 8 1 2 1 0 0 0 47 Tbtal 55 1 9 11 14 13 4 3 1 0 0 0 110 'Ihis tabulation includes all indications, in some cases more than one indication occurs in a tube.

~. -. ZION UNIT 1 'ItJBE SUPPORT PLATE EDDY CURRENP INDICATIONS

  • IN ALL EDUR S'IEAM GENERA'IORS (MARCH-APRIL l')82) 56 54 52 50

/ / - 40 38

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ENCIDSURE 4 Analysis of Data for Indications in the 'Ibbe Sheet Crevice Region ~

Eddy Current results from 1981 examination compared to 1982 examination of the indications at the Tube Sheet Crevice Region. Nr = No Test NI = No Indication INCHES ABOVE E/C RESULTS S/G RN COLLMN 'IUBE END 1981 1982 A 2 38 6 to 10 H/L Nr 77% A 17 10 16 to 18 H/L NT SQ (Im measureable) A 46 48 12 H/L NT SQ (Im l measureable) B 3 39 6 to 10 H/L NI 94% B 2 58 8 H/L NI 89% B 22 18 12 to 14 H/L NI 89% B 25 18 14 H/L NI 72% B 30 23 10 to 13 H/L NI SQ (Im measureable) B 29 23 9 to 12 H/L NI SQ (Im measureable) B 25 21 9 to 14 H/L NI SQ (Im measureable) B 23 19 8 H/L NI 25% C 22 9 12 to 16 H/L NI SQ (Im measureable) m

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DCIOSURE 5 Analysis of Data for Indications at Anti-Vibration Bar (AVB) Iocations

Eddy Current results from 1981 examination compared to 1982 examination of the indications at the Anti-Vibration Bar (AVB) locations. NP = No Test NI = No Indication UD = Undeterminable (Distorted) E/C RESULTS S/G BOW COLUMN AVB# 1981 1982 A 39 70 4 !TP 54% A 39 66 2 NT 52% A 32 55 2 Nr 51% A 41 32 4 NT 51% A 39 72 2 Nr 44% A 20 39 2 Nr 33% A 20 36 1 NT 29% B 35 64 3 56% Plugged B 33 57 3 52% Plugged B 29 32 2 In'easurable Plugged B 29 32 3 Imi.?asurable Plugged B 29 32 4 Inneasurable Plugged B 37 56 3 NI 86% B 36 52 2 UD 82% B 36 52 3 UD 27% B 36 52 4 UD 24% B 27 11 1 NI L5% B 39 43 1 UD 40 B 39 43 2 38% 38% B 39 40 2 Nr 46% B 39 45 2 UD 41% B 31 48 2 NI 38% B 38 58 1 UD 37% B 38 58 2 UD 25% B 34 51 3 NI 36% B 37 55 3 NI 29% B 34 58 2 NI 28% B 29 63 3 NI 25% B 33 55 2 UD 20% i B 33 55 3 NI 23% L B 28 40 3 NI 22% B 34 53 4 NI 22% B 35 54 3 UD 20% C 17 66 2 Inneasurable Plugged C 17 66 3 Immeasurable Plugged C 35 56 3 NI 70% C 35 56 4 NI 49% C 35 57 4 NI 52% C 35 57 3 NI 21% C 15 31 4 NI 34% C 39 59 3 NT~ 45%

i i E/C RESUL'IS S/G MM 00LINN AVB# 1981 1982 D 19 67 2 Nr 65% D 29 47 2 Nr 65% D 40 52 2 Nr 60% D 29 52 2 Nr 56% i D 18 48 2 Nr 55% 1 D 40 55 3 Nr 54% D 41 30 2 NP 53% D 14 81 3 Nr 53% l D 32 52 2 NT 50% D 40 58 1 Nr 49% D 18 65 3 Nr 43% D 29 49 2 NT 43% D 40 50 2 Nr 42% D 17 72 3 NT 42% i D 40 45 4 Nr 41% D 17 30 3 NT 40% i D 41 57 2 Nr 34% D 40 57 3 NT 30% D 32 48 2 Nr 29% I J 40 54 3 Nr 29% D 38 64 1 NT 22%

                          • s2*****************************************************************

4 4 I t L I r

~ ZION UNIT 1 ANTI-VIBRATION BAR EDDY CURRENT INDICATIOtE* IN ALL EDUR S'IY1N GENERA'IORS (MARCH-APRIL 1982) Stm Gen l Dent i Distorted l 420 l 20-29 l 30-39 I 40-49 l 50-59 l 60-69 l 70-79 I 80-89 l 90-99 l 100 l 'Ibtal 1A .3 3 7 1 1 1 4 0 0 0 0 0 20 'lB 2 4 17 11 4 3 1 0 0 2 0 0 44 1C 13 17 11 1 1 1 1 3 1 0 0 0 49 1D 1 10 13 3 2 7 6 3 0 0 0 0 45 'Ibtal 19 34 48 16 8 12 12 6 1 2 0 0 158 (

  • 'Ihis tabulation includes all indications, in some cases more than one indication occurs in a tube.

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ENCIDSURE 6 Analysis of Data for Indications (Including Helium Ieakage) At Row 1 and 2 U-Bend Tangent Point Iocations

Eddy Current results from 1981 examination compared to 1982 examination of the indications at U-bend tangent points, location in row 1 & row 2 tubes. Row 1 & 2 Indications E/C RESULTS He INDICATION S/G RGi 00LINN 1981 1982 1982 A 1 58 NI 100% C/L Tangent Yes A 1 26 NI 100% C/L Tangent Yes A 1 7 NI Unknown Defect masked Tang Dent Yes A 1 48 NI Possible Distort C/L Tangent No A 1 73 NI Possible Distort C/L Tangent No A 1 80 NI Possible Distort C/L Tangent No A 1 85 NI Possible Distort C/L Tangent No A 1 74 NI Possible Distort H/L Tangent Ib A 1 77 NI Possible Distort H/L Tangent No A 1 86 NI Possible Distort H/L Tangent rb A 1 93 NI Possible Distort H/L Tangent No A 1 94 NI Possible Distort H/L Tangent No A 1 3 NI Possible Distort H/L Tangent No A 2 3 NI NI Yes A 2 48 NI NI Yes

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1 1 Restricted Plugged B 2 8 Imeasurable Tang C/L Plugged B 2 9 Imeasurable Tang C/L Plugged B 2 10 Imeasurable Tang C/L Plugged B 2 11 Imeasurable Tang C/L Plugged B 2 12 Imeasurable Tang C/L Plugged B 2 13 Immeasurable Tang H/L & C/L Plugged B 2 14 Imeasurable Tang C/L Plugged B 2 15 Imeasurable Tang C/L Plugged B 2 17 Immeasurable Tang C/L Plugged B 2 24 Imeasurable Tang C/L Plugged B 2 46 Imeasurable Tang C/L Plugged B 2 69 Imeasurable Tang H/L Plugged B 2 70 Imeasurable Tang H/L Plugged B 2 77 Imeasurable Tang H/L Plugged B 2 79 Imeasurable Tang H/L Plugged B 2 80 Imeasurable Tang H/L Plugged

E/C RESULTS He INDICATION S/G FOW COIINN 1981 1982 1982 Row 1 & 2 Indications Continued B -1 20 NI 100% H/L Tangent Yes B 1 42 NI 100% H/L Tangent Yes B 1 79 NI 80% C/L Tangent tb B 1 11 NI Defect Masked by Tang Dent Yes B 1 10 NI Defect Masked by Tang Dent Yes B 1 9 NI Defect Masked by Tang Dent Yes B 1 8 NI Defect Masked by Tang Dent Yes B 2 47 NI 80% H/L Tangent No C 1 7 NI 100% Tangent H/L Yes C 1 23 NI 100t Tangent C/L Yes C 1 65 NI 100% H/L Tangent Yes C 1 74 NI 100% C/L Tangent Yes C 1 24 NI C/L Tangent Distorted by Dent Ib C 1 33 NI Distorted by Tangent Dent Yes C 1 55 NI Defect Masked by Tangent Dent Yes C 1 80 NI Defect Maksed by Tangent Dent Yes C 1 93 NI Defect Masked by Tangent Dent Yes C 1 63 Inneasurable Tang Point Plugged C 1 69 Inneasurable Tang Point Plugged C 1 48 NI NI ? C 2 23 NI NI ? t i i .V

2 OCMPARISON OF S/G "B" 1NDICATIONS Row Column 1982 Indication 1981 Indication 1 8 Defect masked by tangent dent No apparent indication 1 9 Defect masked by tangent dent No apparent indication 1 10 Defect masked by tangent dent No apparent indication 1 11 Defect masked by tangent dent No apparent indication 1 20 100% H/L Tangent Slight distortion 100 KHZ differential only 1 42 100% H/L Tangent No apparent indication 1 79 80% C/L Tangent Slight variation in 100 KHZ absolute only 1 47 80% H/L Tangent Slight variation in 100 KHZ absolute only

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f.' DEIDSURE 7 Analysis of Miscellaneous Indications l l

.. v ' o e Miscellaneous Indications Nr = No Test NI = No Indication IN/ABOVE E/C RESUL'IS S/G FOh7 CDLLMN TSP # SIDE 1981 1982 A 27 78 12" above 5 H/L Nr 27% A 37 48 40" above 3 H/L Nr 24% A 27 10 20" above 6 C/L Nr 22% C 9 43 .5" above 7 C/L 79% Plugged C 15 66 .5" above 7 H/L 63% Plugged C 30 13 4 H/L NI 28% Restricted Tube E/C RESUL'IS S/G ROh7 00L}!N 1981 1982 B 3 31 NI Restricted U-Bend u ~ i}}