ML13311A455
| ML13311A455 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 10/23/1978 |
| From: | Southern California Edison Co |
| To: | |
| Shared Package | |
| ML13311A456 | List: |
| References | |
| TAC-47835, NUDOCS 7810270216 | |
| Download: ML13311A455 (89) | |
Text
RESULTS OF STEAM GENERATOR INSPECTION PROGRAM FOR CYCLE VII REFUELING OUTAGE SAN ONOFRE NUCLEAR GENERATING STATION UNIT.1 SOUTHERN CALIFORNIA EDISON COMPANY October 23, 1978 7.7
C 0 NTENT S SECTIONS
- 1.
INTRODUCTION -
SUMMARY
AND CONCLUSIONS
- 2. RESULTS OF GENERAL SURVEILLANCE INSPECTION
- 3. RESULTS OF AVB-AREA INSPECTION
- 4.
RESULTS OF DENTING INSPECTION APPENDICES A.
FIGURES AND TABLES GENERAL SURVEILLANCE INSPECTION B.
FIGURES AND TABLES AVB-AREA INSPECTION C.
FIGURES AND TABLES DENTING INSPECTION D.
PHOTOGRAPHS DENTING INSPECTION E. REFERENCES
SECTION 1
- 1. INTRODUCTION During the San Onofre Unit 1 Cycle VII refueling outage, inspections were performed in steam generators A, B and C for the following purposes:
Establish general surveillance of steam generator tubes as a minimum in accordance with proposed Technical Specification 4.16 (Reference 1) submitted in Docket No. 50-206.by letter dated July 31, 1978 as Proposed Change No. 75 to the Technical Specifications; Obtain data for reassessing the conditions of steam generator tubes in contact with anti-vibration bars (AVB's) in accordance with paragraph 3.F(l) of the San Onofre Unit 1 Provisional Operating License (POL), and Confirm that previously identified dented tubes have not significantly changed in fulfillment of paragraph 3.E of the POL.
These inspections were performed in accordance with the Steam Generator Inspection Program (Reference 2) which was submitted to the NRC for approval by SCE letter dated August 17, 1978. By letter to SCE dated September 14, 1978 (Reference 3 the NRC approved the scope of the inspection program but withheld consideration of the program of supplemental inspections and corrective actions proposed therein-subject to NRC staff review of initial inspection results.
Preliminary results of initial inspections in steam generators A and C were presented to the NRC in SCE report entitled "Preliminary Results of Steam Generator Inspection Program for Cycle VII Refueling Outage" dated October 1, 1978. That report was submitted pursuant to the NRC's request in Reference 3 as a basis for completing the overall inspection program, including supplemental inspections and corrective actions, in accordance with Reference 2.
This report presents the results of the completed overall inspections program, corrective actions taken, and conclusions based on these results regarding continued plant operation and future steam generator inspections. It is intended that this report provide a basis for obtaining NRC approval to resume power operations following the completed inspections pursuant to paragraph 3.E of the San Onofre Unit 1 POL. In addition, this report is intended to fulfill SCE's commitments on reporting of overall inspection program results to the NRC as set forth in Sections 2, 3 and 4 of Reference 2.
1-1
Introduction (Cont'd)
Discussion of results including corrective actions taken and conclusions therefrom, of the general surveillance, AVB area, and denting inspections are presented herein in Sections 2, 3 and 4 respectively and are summarized below:
Regarding the general surveillance inspection, significant or excessive degradation of tube integrity due to wastage type imperfections does not appear to be occurring in San Onofre Unit 1 steam generators. It is concluded that San Onofre Unit 1 steam generator tube integrity can be ensured in the future without compromise to plant safety by performing limited general surveillance at refueling outage inspection intervals.
Regarding the AVB-Area inspection, it is concluded that the AVB modifications performed during the 1976 (Cycle VI) refueling outage sufficiently arrested AVB induced tube wear in steam generators A, B and C such that continued use of a 50% plugging limit in combination with limited AVB area tube inspections performed on a refueling outage frequency will assure continued safe operation of San Onofre Unit 1 steam generators.
Regarding the denting inspections, it is concluded that significant progression of denting is not occurring in steam generators A, B and C and that continued surveillance of denting can be provided without compromise to plant safety by performing a program of limited tube ID gauging and dent detection in steam generators A or C on a refueling outage frequency.
Corrective actions taken as a result of the overall inspection program consisted of 1) plugging one tube in steam generator A having a wastage type imperfections of 50%, 2) plugging one tube in steam generator with both a wastage type imperfection and an AVB-area imperfection, each in excess of 50%, 3) plugging two additional tubes in steam generator C having AVB-area imperfections in excess of 50%, 4) plugging one tube in steam generator C which restricted passage of a.460" probe, and 5) plugging one tube in steam generator B which restricted passage of a.460" probe.
1-2
SECTION 2
- 2. RESULTS OF GENERAL SURVEILLANCE INSPECTION Tubes Selected and Inspected General surveillance of tubes in steam generators A, B and C using eddy current techniques was performed in accordance with the inspection plan described in Section 2 of Reference 2 with the following additions:
In addition to the tubes selected for inspection in accordance with Section 2.2 of Reference 2, tubes selected for inspection in accordance with the AVB area inspection plan in Section 3.2 of Reference 2 were also included in the general surveillance plan. Consistent with 2.3.1.5 of Reference 2, however, areas of these tubes at AVB intersections were not considered to be included within the general surveillance inspection.
Additional tubes were inspected as deemed necessary in order to verify proper selection and inspection of certain tubes in the inspection plans.
Completed general surveillance inspection plans for the inlet and outlet sides of steam generators A, B and C are presented in Figures A.1 through A.6 in Appendix A. Consistent with Reference 2 and the above additions, tubes are identified on these figures as having been inspected under the general surveillance plan if they are included among the following inspection categories:
U-bend inspection from either the inlet or outlet side due to presence of one or more previously noted AVB indications.
U-bend inspection from inlet side as a result of tube being in the basic pattern of tubes located at the intersections of every fourth row, beginning with row 6 and higher, and column.
Inspection through the first support plate from outlet side of tubes falling in the above described basic pattern.
Inspection through first support plate from inlet and/or outlet side of tubes with previous history of tube sheet indications on inlet and/or outlet.
The results for each steam generator are discussed below:
2-1
- 2. Results of General Surveillance Inspection (Cont'd)
Steam Generator A Tables A.1 and A.2 in Appendix A tabulate the inlet and outlet results, respectively, in terms of the criteria for supplemental inspections and tube plugging presented in Section 2.3 of Reference 2. Based on 630 tubes inspected from the inlet, representing 17% of the operable tubes in the steam generator, and 458 tubes from the outlet, representing 12% of the operable tubes, the following conditions were found:
Less than 10% of the tubes inspected (0% inlet, 1% outlet) had new indications of wall penetration >20%. It is noted that the tubes inspected from the outlet with new indications >20%
were inspected from the outlet for the first time during this inspection.
Less than 10% of the tubes inspected (.5% inlet,.7% outlet) had previously detected indications of wall penetration that increased more than 10% in successive inspections.
No tubes had indications equal to or greater than 50% that increased more than 10% in successive inspections.
One tube (R37 C49, inlet) was pluggable with an indication of 50% at the tubesheet from among the 1088 tube ends inspected.
Based on these results, no supplemental inspections were deemed warranted in steam generator A and none were performed. Tube R37 C49 was plugged in that it registered a tubesheet indication of 50% which is at the plugging limit for San Onofre Unit 1.
Steam Generator B Tables A.3 and A.4 in Appendix A tabulate the inlet and outlet results of the general surveillance inspection of steam generator B, again in relation to the proposed corrective actions in Section 2.3 of Reference 2.
Based on 685 tubes inspected from the inlet, representing 18% of the operable tubes in the steam generator, and 226 tubes inspected from the outlet, representing 6% of the operable tubes, the following conditions were found:
Less than 10% of the tubes inspected (.5% inlet, 2% outlet) had new indications of wall penetration >20%. In all cases these indications were at or near the tubesheet. The 5 tubes, or 2%, of tubes inspected from the outlet having such indications were inspected from the outlet for the first time during this inspection.
2-2
- 2. Results of General Surveillance Inspection (Cont'd)
Steam Generator B (Cont'd)
No tubes had previously detected indications which have increased more than 10% in successive inspections.
No tubes were pluggable with indications of wall penetration equal to or greater than 50% from among the 911 tube ends inspected.
Based on these results no supplemental inspections were deemed warranted and none were performed. No tubes were plugged as a result of general surveillance results.
Steam Generator C Tables A.5 and A.6 in Appendix A tabulates the inlet and outlet results of the general surveillance inspection of steam generator C in relation to the proposed corrective actions in Section 2.3 of Reference 2. Based on 523 tubes inspected from the inlet, representing 14% of the operable tubes in the steam generator, and 226 tube inspected from the outlet, representing 6% of the operable tubes, the following conditions were found:
Less than 10% of the tubes inspected (4.6% inlet,.04% outlet) had new indications of wall penetration >20%. In all cases these indications were at or near the top of tubesheet. The one tube (.04%)
inspected from the outlet having such an indication was inspected from the outlet for the first time during this inspection.
Less than 10% of the tubes inspected (.8% inlet, 0% outlet) had previously detected indications'that increased more than 10% in successive inspections.
No tubes had indications equal to or greater than 50% that increased more than 10% in successive inspections.
One tube (R35 C47 - inlet) was pluggable with an indication of 56%
at the tubesheet from among the 749 tube ends inspected.
Based on these results, no supplemental inspections were deemed warranted in steam generator C and none were performed. Tube R35 C47 was.plugged based on exceeding the 50% plugging limit for San Onofre Unit 1.
Conclusions The results of the general surveillance of steam generators A, B and C indicate that significant degradation of tube integrity due to wastage type imperfections is not occurring. It is concluded that San Onofre Unit 1 steam generators tube integrity can be ensured in the future by performing limited general surveillance at refueling outage inspection intervals.
2-3
SECTION 3
- 3. RESULTS OF AVB AREA INSPECTION Tubes Selected and Inspected Tubes were selected and inspected in steam generators A, B and C in accordance with the plan set forth in Section 3.2 of Reference 2.
Any additional U-bend inspections of tube areas intersecting AVB's were also included in the overall AVB area inspection program. Such additional inspections were added as deemed necessary for the purpose of verifying proper identification and inspection of certain tubes. The completed AVB area inspections for each steam generator are presented in Figures A.1 through A.6 in Appendix A. In these figures, AVB area inspections include all tubes which are among the following categories:
U-bend inspection from inlet side of all tubes having AVB indication(s) in previous inspections.
U-bend inspection from inlet side of all tubes in the basic pattern in rows 14 and above (tubes below row 14 do not intersect AVB's).
U-bend inspection from inlet side of all tubes in the "flow triangles", i.e., tubes in rows 30-36, columns 12-17 and 84-89.
U-bend inspection from outlet side of any tube in the above categories which is restricted on the inlet side.
Description of Eddy Current Data Interpretation Techniques The data base for analysis of AVB area eddy current indications was obtained from comprehensive review of signals recorded on magnetic tapes. The data was obtained using equipment and procedures substantially the same as that employed during the September 1977 AVB area inspection and data re evaluation. Determinations from the data of the depth of wear indications at AVB locations employed the two separate techniques used for the September 1977 data re-evaluation, i.e., phase angle measurement and amplitude measurement. In the first of these, the phase angle of the indication is measured and converted to a percent of wall thickness indication by use of appropriate calibration curves. As reported to the NRC in a meeting among SCE, Westinghouse and NRC, personnel on October 3, 1977 (Reference 4) and in submittal to the NRC entitled "Re-Evaluation of Steam Generator Eddy Current Inspection Results" dated November 18, 1977 (Reference 5), phase angle measurements alone do not necessarily produce sufficiently accurate results for quantifying small volume AVB type inspections. Therefore, a second technique is employed which uses signal amplitude measurement to better characterize the size of the AVB inspection. The technique and its development are further discussed below.
3-1
- 3. Results of AVB Area Inspection (Cont'd)
Description of Eddy Current Data Interpretation Techniques (Cont'd)
Simulationsof steam generator tubes containing minimum volume 30% and 50% AVB-induced through wall penetrations were prepared and tested in the laboratory. The objective of these simulations was to most closely approximate the minimum amplitude eddy current signal which could be generated due to AVB wear by assuming that AVB wear occurs on only one side of the tube and no wear occurs on the AVB. Laboratory testing determined that the amplitude of the minimum volume 30% indication corresponds to 34% of the amplitude of the 20% through wall penetration in the usual calibration standard. Likewise, the minimum volume 50%
indication produces a signal amplitude corresponding to 85% of the 20%
calibration standard signal amplitude. Application of these results to the evaluation of imperfection depths is illustrated by the following examples: If the'phase angle of an AVB wear indications is in the range corresponding to a 30% to 50% standard indication but the signal amplitude is less than 34% of the amplitude of the 20% through wall calibration standard, then a value of <30% is assigned to the wear indication; if the signal amplitude is >34% of that of the 20% calibration standard, then a discrete value of indication size corresponding to the phase angle measurement is assigned. The same principle is used when an indication is evaluated as being " <50%".
Use of the above techniques has resulted in the reduction of uncertainties in indicated depth to the uncertainty in instrument calibration.
Distribution of AVB Wear Indications Distributions of discretely quantifiable AVB area indications in steam generators A, B and C are presented in Figures B-1, B-2 and B-3, respectively, of Appendix B. The number of discrete indications, their mean sizes and standard deviations are tabulated in each figure. Also shown are the number of indications-which could not be discretely quantified and are characterized as being " <20%", " <30%" or " <50%".
Figures B.1, B.2 and B.3 illustrate that while the number of indications reported in each steam generator differ, the average indication sizes and standard deviations of distributions are consistent among all three steam generators. Table B.1 compares for each steam generator the distribution of absolute AVB wear statistics with corresponding values from the September 1977 inspection.
Table B.1 shows that the mean sizes of AVB wear indications in the steam generator have individually and collectively remained substantially unchanged between the 9/77 and 9/78 inspections. The operating interval between these two inspections was 9.7 effective full-power months (EFPM).
3-2
- 3. Results of AVB Area Inspection (Cont'd)
Distribution of AVB Wear Indications (Cont'd)
The changes in indication sizes from the 9/77 to 9/78 inspections were calculated on an indication-by-indication basis for those discretely quantifiable indications reported as >20% in both inspections, those reported as >30% in both inspections, and those reported as >40% in both inspections. The distributions of these changes are presented in Figures B.4, B.5, and B.6 for steam generator A, Figures B.7, B.8 and 8.9 in steam generator B, and Figures B.10, B.11 and B.12 for steam generator C. These figures also include the mean indication change and standard deviation statistics calculated from the distribution of differential AVB wear. Table B.2 summarizes these statistics for each steam generator, presents calculated mean growth rates per month for each distribution and presents calculated overall differential wear statistics and mean growth per month for all three steam generators.
Table 8.2 shows, as expected, the decreasing variability of indication changes with increasing sizes of indications compared. Referring to the most reliable data base, i.e., comparison of indications reported as
>40% in both 9/77 and 9/78, the overall calculated wear rate is -.09%
per EFPM or effectively zero. It is noted that no significance in terms of AVB wear mechanisms is attached to the negative wear rates shown in Table B.2. The calculated mean indication changes in all cases in Table B.2 suggest a higher level of precision than can in fact be achieved by the eddy current techniques employed in this application.
Evaluation of Flow Triangle Indications As noted in Appendix D of Reference 2, confirmation of wear rates consistent with the 50% plugging limit would be sought among tubes in the flow triangles during this inspection in order to sustain continued application of this limit to such tubes. The data from this inspection and the re-evaluated '76 and '77 data are such that reliable statistical inference of wear rates cannot be made. However, it is noted that in no case among the flow triangles of all steam generators does a discrete AVB area indication exist in excess of 36%.
Thus, in a total of 14.4 EFPM of operation since installation of the AVB modification during the 10/76 refueling outage, no tube among the total in steam generators A, B and C flow triangles has experienced tube wear in excess of the plugging limit of 50%. In Reference 6, the plugging criteria of "any measurable indication" for tubes in the flow triangles was established on the expectation that, if these tubes were postulated to be unsupported above the fourth support plate they could be fluidelastically unstable and subject to wear rates up to 40% per year. Since such excessive wear has not occurred for even one tube in the flow triangles since installation of the AVB modifications, it is reasonable to conclude that the postulated unsupported conditions have not occurred. It is therefore concluded that tubes in the flow triangles are not experiencing unstable fluidelastic vibration and that excessive wear inconsistent with the plugging limit is not expected to occur.
3-3
- 3. Results of AVB Area Inspection (Cont'd)
Corrective Actions The total number of tubes inspected in the AVB area plan was as follows:
Steam Generator No. of Tubes A
671 B
683 C
548 TOTAL 1902 Each tube has four possible locations of AVB wear, thus, a total of 7608 potential wear locations were inspected. The composite wear rate among these locations is calculated to be -.09% per EFPM as shown in Table B.2.,
From among 1902 tubes inspected, three tubes in steam generator C had AVB-area indications in excess of 50% as follows:
Row Column Indication 35 47 51%
37 49 52%
42 27 53%
- Also, this tube had tubesheet indication of 56%
These three tubes were removed from service by plugging.
No other corrective actions were taken or supplemental inspections performed.
Conclusions The results of the AVB area inspections performed during the Cycle VII refueling outage following 9.7 EFPM of operation confirm that overall growth of tube wear indications at AVB locations in San Onofre Unit 1 steam generators is insignificant. Based on these results in comparison with results obtained during the September 1977 AVB inspection, it is concluded as follows:
AVB modifications performed during the 1976 (Cycle VI) refueling outage appear to have arrested overall, actual AVB induced tube wear rates to values so small as to be indeterminate using eddy current techniques.
Statistically calculated wear rates at AVB intersections in all steam generators are consistent with the 50% tube plugging limit previously established for San Onofre Unit 1 steam generator tubes.
3-4
- 3. Results of AVB Area Inspection (Cont;d)
Conclusions (Cont'd)
AVB induced tube wear is occurring at a uniformly insignificant rate throughout each steam generator and is not occurring at preferentially high rates in any particular region of the steam generator such as the flow triangles.
The continued use of a 50% plugging limit for tube indications at AVB intersections in combination with limited steam generator tube inspections performed on a refueling outage frequency will conservatively assure continued safe operation of San Onofre Unit 1 steam generators.
3-5
SECTION 4
- 4. RESULTS OF DENTING INSPECTION The denting inspection, consisting of tube ID gauging/dent detection and flow slot photographs and videotape inspections and measurements, was performed in accordance with the inspection plans detailed in Sections 4.2 and 4.3 of Reference 2. These inspections were performed during the Cycle VII refueling outage with the intention of fulfilling the requirement of paragraph 3.E of the San Onofre Unit 1 POL to "perform an inspection of the steam generators within twelve months of operation from April 20, 1978.... for reassessment of the magnitude of inplane expansion or hourglassing... and the potential for continued steam generator tube denting." It is further required by paragraph 3.E that "NRC approval shall be obtained before resuming power operation following this (denting) inspection". The results presented herein are intended to provide a basis for obtaining NRC approval to resume power operation vis-a-vis steam generator denting.
A. Results of ID Gauging/Dent Detection The completed ID gauging and dent detection inspections, conducted in accordance with Section 4.2 of Reference 2, are shown for steam generators A, B and C in Figures C.1 through C.5 of Appendix C.
As shown in these figures, ID gauging was performed on both the inlet and outlet of steam generators A and C and on the inlet only of steam generator B. The results for each steam generator are discussed below. In each steam generator, all restricted tubes were bounded by tubes determined in the inspection to be unrestricted.
- 1. Steam Generator A Table C.1 presents the results of the current (9/78) inlet gauging program and compares these with previously established gauging information. Table C.1 shows good correlation between 9/78 and previous results with respect to identification.of restricted tubes and the probe sizes which these tubes pass.
These results show that from the total of 314 tubes gauged from the inlet side, 77 restrictions in a total of 75 tubes were found at the first and/or second tube support plate locations.
75 of these restrictions were unchanged from previous gauging inspections. The locations of restricted tubes in the tube array are shown in Figures C.1 and C.2. Table C.2 presents the distribution of sizes of these restrictions. It is noted that no tubes in steam generator A restricted passage of a.460" probe.
4-1
- 4. Results of Denting Inspection (Cont'd)
- 1. Steam Generator A (Cont'd)
The data in Table C.1 shows that one tube (Rl C33) exhibited a "possible" ID decrease and one tube (R1 C50) exhibited a restriction not previously noted. Rl C33 had restricted passage of a.500" probe at the second support plate in 10/76 and again in the current inspection but passed a.500" probe in the 4/78 inspection.
Rl C50 passed a.560" probe in 4/78 but restricted a.560" probe at the second support plate in the current inspection. At the same time, however, 3 tubes passed probes in the.current inspection while restricting these same probe sizes in the 4/78 inspections. Since only one tube of 314 inspected showed new evidence of ID decrease while 3 showed evidence of ID increase, it is considered likely that a combination of differences between the 9/78 and 4/78 inspections in overall equipment rigidity, probe wear, equipment alignment and/or restrictions that closely approximate the passing or restricting probe size resulted in above noted differences in 4/78 and 9/78 inspection results rather than the denting process itself.
Table C.2 also shows that 18 tubes were gauged from the outlet side and that 3 of these were restricted to a.560" probe. There is no previous data on these tubes. - Furthermore, the tubes in question are located at hard spots on the tube bundle periphery (see figure C.2) and are restricted at the fourth support plate.
It is believed that these tubes were restricted mechanically during pre-service shipment and handling and not-as'a result of the denting process.
Table C.3 presents the results of dent detection at the third and fourth support plates from the inlet side. The data shows that from among the 314 'tubes inspected, 18 tubes had dent indications at the fourth support plate, all of which had been previously detected. The majority of these dents are also believed to be associated with pre-service shipment and handling.
Based on the above results, it is concluded that in steam generator A 1) denting is not progressing at the first and second support plates, and 2) there is no significant denting at the third or fourth support plates.
- 2. Steam Generator B Table C.4 summarizes the gauging results in steam generator B in terms of the distribution of restriction sizes. The locations of restricted tubes are shown on Figure C.3. All fifteen tubes found restricted during this inspection were restricted to the same probe size in the 4/78 inspection. All 15 tubes are located on the periphery of the tube bundle at the-hard spots.
14 of the 15 restrictions are at the fourth support plate while one is at the second support plate. All of these tubes are tubes which were known to be restricted during pre-service as a result of shipment and handling.
4-2
- 4. Results of Denting Inspection (Cont'd)
- 2. Steam Generator B (Cont'd)
Table C.5 presents the listing of tubes from among those inspected which have dent indications.
Each of the dent indications were confirmed to be present during the 4/78 inspection.
Based on the above results, it is concluded that there is no significant chemical denting in steam generator B. One tube (R38 C20), which was restricted to a.460 probe, was plugged.
- 3. Steam Generator C Table C.6 presents the results of the 9/78 inlet inspection and compares these with previously established gauging information.
Table C.6 shows that from the total of 432 tubes gauged from the inlet side, 85 restrictions in a total of 83 tubes were found as the first and/or second support locations. The locations of these restricted tubes in the tube array, are shown in Figure C.4 and C.5.
80 of these restrictions were unchanged from previous gauging inspections. Table C.7 presents the distribution of these restriction sizes. It is noted that no tube in steam generator C restricted passage of a.460" probe from the inlet side. On the outlet side, one tube (R3.7 C19) restricted passage of a.460" probe and seven others restricted passage of a.560" probe. These tubes had not been previously gauged from the outlet side and are thus not regarded as evidence of a new restrictions. Furthermore, the restrictions were located at the fourth support plate at hard spots and are believed to have resulted from pre-service shipment and handling.
Table C.6 shows that 5 tubes not previously reported as being restricted in 4/78 were noted to be restricted to a.560 probe during this inspection; however, 43 tubes that were noted to be restricted during 4/78, passed a.560 probe during this inspection.
Factors mentioned under "Steam Generator A" above are again believed to have contributed to differences in the 4/78 and 9/78 gauging results. Specifically, a new and more rigid fixture for positioning the probe within the steam generator tubes was utilized in steam generator C. With this fixture, a probe is less likely to hang-up in a tube due to being misaligned or being marginally restricted by the tube.
Table C.8 lists all inlet side dent indications found at the third and fourth support plates among the 432 tubes inspected in steam generator C gauging program. The 48 tubes listed with dent indications were previously identified as having these dent indications.
Furthermore, the tubes in question are all located at the tube bundle periphery at the hard spots and the dent indications are attributed to mechanical interaction of the tubes with tube support plates during pre-service shipment and handling.
4-3
- 4. Results of Denting Inspection (Cont'd)
- 3. Steam Generator C (Cont'd)
Based on the above results, it is concluded that in steam generator C 1) denting is not progressing at the first and second support plates, and 2) there is no significant denting at the third and fourth support plates. Corrective action taken in steam generator C as a result of the denting inspections consisted of plugging one tube (R37 C19) noted to be restricted on the outlet side to passage of a.460 probe.
B. Photographic and Videotape Inspections and Measurements In accordance with Section 4.3 of Reference 2, photographic and videotape inspections were made through the manway and nozzle inspection ports above the tube sheets in steam generators A, B and C and a video-fiberscopic examination was conducted through the three inch drilled inspection port in steam generator C. These inspections were made in order to reassess the extent of flow slot hourglassing and support plate cracking in each steam generator.
Copies of photographs taken are included in Appendix D as photographs 1 through 21.
Tables C.9 and C.10 tabulate observations of support plate cracks at flow slots and the method of observation in steam generators A and C.
Figures C.6 through C.9 graphically illustrate the locations of cracks observed at the first and second support plates in steam generators A and C. The locations were determined from various photographs and/or videotapes taken through the manway and nozzle side inspection ports during the 1976, 1977, 4/78 and current (10/78) inspections.
Review of photographs and videotapes taken during the current inspection disclosed the presence of a crack in steam generator A not previously noted. This crack is located in the first support plate on the inlet side of the third flow slot from the manway side near the center stay rod. (Refer to photograph number 3 in Appendix 0, Figure C.6 and Table C.9). It is concluded that the crack is not new, but had been either out of view or obscured by sludge in previous inspections. During the current inspection, photographs and videotapes were taken in steam generator A following sludge lancing such that the crack was not obscured by sludge on the support plate.
Re-review of previous photographs and videotapes disclosed that a crack-like indication exists at the above described location in an October 1977 photograph provided to the NRC. This indication had been considered to be a shadow due to camera lighting angle on the 4-4
- 4. Results of Denting Inspection (Cont'd)
B. Photographic and Videotape Inspections and Measurements (Cont'd) sludge formation. In comparing that indication with photographs taken during this inspection, it is concluded that the indication was due to the presence of a crack beneath the sludge and not solely the result of shadow effects. The lack of flow slot displacement at this crack location contributed to the inability to identify the indication as a crack in the October 1977 photograph.
With respect to steam generator B, photographs and videotapes continue to show the absence of hourglassing and support plate cracking. The effects of sludge on photographic observations are demonstrated in the photographs taken in steam generator B before (Nos. 7, 8, 9) and after (Nos. 13, 14, 15) sludge lancing.
Table C.11 summarizes measurements of the minimum flow slot widths in the first support plates of steam generators A and C as determined from photographs taken in 1976, 1977, April 1978 and the current inspection. Within the limits of precision of the measurement technique, these measurements indicate no apparent changes in flow slot widths.
To confirm that no hourglassing has occurred at the top support plate of steam generator C, photographs were taken and a videotape fiberscopic gauging examination performed through the three inch drilled inspection port. The results of this examination are summarized in Table C.12. Photograph No.21 in Appendix D shows the condition of the top support plate and flow slots as viewed through the inspection port.
Based on the photographic and videotape examinations of San Onofre steam generators, the following conclusions are presented:
- 1. Steam Generator A There has been no perceptible change in the overall condition of the secondary side of the steam generator since September 1976.
First support plate flow slot minimum widths as determined from photometric measurements have remained substantially unchanged.
No new cracks have been observed at flow slots and the condition of the observed cracks appear to be unchanged. To the extent that visual observation can be made from photographs and videotapes, there does not appear to be distortion or "hourglassing" at the third or fourth support plate flow slots.
- 2. Steam Generator B Support plate photographs and videotapes taken through the manway and nozzle hand holes continue to show no evidence of hourglassing or support plate cracking in this steam generator.
4-5
- 4. Results of Denting Inspection (Cont'd)
- 3. Steam Generator C There has been no perceptible change in the overall condition of the secondary side of the steam generator sinceobservations were first made during the 1976 outage. Minimum widths of flow slots in the first support plate have remained substantially unchanged as determined by photometric measurements.
Visual observations, photographs and videotape fiberscopic gauging of the three flow slots in the manway side of the top support plate found that these flow slots do not appear to be distorted. Observations during this inspection of the nozzle side flow slots as seen from the three inch inspection port found these to be apparently undistorted.
C. Corrective Action As a result of the ID gauging/dent detection inspections and the photographic and videotape examinations of steam generators A, B and C, corrective action was taken as follows:
Tube R38 C20 in steam generator B and R37 C19 in steam generator C were restricted to a.460" probe and were plugged as preventative measures. No other corrective actions were taken or supplemental inspections performed.
D. Conclusions Based on the results of the denting inspection discussed above, the following conclusions are presented:
- 1. Sufficient data have been compiled as a result of the current and previous inspections to enable reassessment of the magnitude of inplane expansion or "hourglassing" in the top and bottom tube support plates and the potential for continued steam generator tube denting.
- 2. Hourglassing is confined to the first and second support plate in steam generators A and C and does not appear to be progressing based on measurements and observations of flow slots and support plate cracks.
- 3. Based on ID gauging and dent detection inspections, significant progression of denting is not occurring in steam generators A, B or C.
- 4. Continued surveillance of denting can be provided without compromising safe operation of the plant by performing a program of limited tube ID gauging and dent detection in steam generators A or C on a refueling outage frequency.
4-6
APPENDIX A FIGURES AND TABLES GENERAL SURVEILLANCE INSPECTION
97 ao 24 9
87 as 85 BS 84 83 81 11 A*
SO 7
1~
117 78 75 I.l 74 73 72 37 IOS (f1 It 83g 82 N**
9 5 7 C
Ss H (A 54 TZ 63 5
49 47 4
47 C34 3
C42 31
-4~~~3 29Tilit14
-421 U1.~2 Z-Z 32 317 200 O
F 12 I1I I
I tI I
N~
08 it I
asa 97 07 go as 24 93 22 0
as 91 so 97 84 83 79 77 70 7S 74 73 72 79 Ni7t as e
OOxw P-N7 i
U W4 6 3 S[183 H
50 0
0 so 5
54 0 oI 3us to 45s 0
4 41 Z
C430 I t [,
T
~
30 T
1 Mt P 35
-~
33 3929 O
27 2825 23 2
o to 1
N ItI
'A15 N
0 r
7 A(
Sool r~~r.~
Pl c
-4 I
3 m
4 rq 1
is z
p 4
3 Tmc3 70 l I
3
RE~at:SER858
- -COLUMNS a:
s S
S SE CD ol, C
)L O
)U n
NNSl l
SCE -
B INLET 01 6 0 a m
m
~' ~ ' ~ ~
~
"~
"~
"~
"~ ~
OL-N 7
46 44 44 23 32 21 20 13 36 tS 5
3 4 1312 29' 2
-8 a PREVIOUSLY PLUGGED TUBES X -
80BE WITH OME ce Meoes A"/B ENovenTIoI4 OA SMSras ro 7
c~ 1~C1t*
N P cron 111L FR5 5' ePORT 12 TUBES
-TieES
- p5L~
2v7 SRTES STEAM GENERAT NOZZLE
- -.-MANWY NOZLE-FIG A-
90 92 at C
87 85 79, 77 75 74 73 7 71 7
as 64 8 3 89 Xa 60 is a m4 a3 m h0 12 Se e7 0 MH so e
s H
S7 7.0 SH5
(/)
4 531 LA U 0 S2 59 47 0 or 40 44 45 43 m
29 50? O 40 39 Z
-4.3s 9
C 38 434
>~
32p 33
-4 32 31 O N s
30 W-4 28 27 0
-2 2S 24 23 22 2 t tB17 14 i5 12 N
te 04 8
2t me of (1)4 A" 9
Si S
COLUMNS 48 48 44 42 49 47 28 35 24 32 39 29 36
'4 212
-18 1
16 45 34 32 11 9
7
-mm-I T5?
S W A
/--
2 27 SERIES
- J*P R V O U L t.GE U
no- -- - - - - --re A U25IE T o = 5 2 U E W P C E
<---MAN----
AY----------
27 SE I
S S
E M
GE E
A2 O
ZL
-FG
90 07
. o as 93 St 8
7 85 77 8
7 7 3 7 2 71 70 a
sV H
so S7 75 r LnC 54 ri 72 in Br 434 41 P1 30 79 z
3a 3S 37 0
I1F 1i3 29 4
Y L
as Lt 2t4 3
21 so 17 to 55 r
e 54 53 i
'54 42 Ia ao as 3
2 71 22It 9 0 17 rr Joll t14 ttC~
onn a.,n
-c 0m't
SCE - SONGS 1 TABLE A.1 GENERAL SURVEILLANCE PLAN INSPECTION
SUMMARY
"A" STEAM GENERATOR -
INLET SIDE Tube Inspections planned 1:
552 Tube Inspections completed 2:
630 Tubesheet Indications:
Number of Tubes
% of Completed Inspections New Indications
>20%:
0 0 %
Previous Indications of >20%
with >10% Increase from previous Inspection:
3 0.5 %
Indications of >50% with
>10% Increase from previous Inspection:
0 0
Pluggable Tubes Row - Col
% Defect 37 49 50% @ Tubesheet Total includes general surveillance and AVB inspection plans per SCE Cycle VII Steam Generator Inspection Program.
2 Total includes tubes in excess of original plan as deemed necessary.
SCE -
SONGS 1 TABLE A.2 GENERAL SURVEILLANCE PLAN INSPECTION
SUMMARY
"A" STEAM GENERATOR -
OUTLET SIDE 1
Tube Inspections planned 397 Tube Inspections completed 2:
458 Tubesheet Indications:
Number of Tubes
% of Completed Inspections New Indications
>20%:
24 5.2 %
Previous Indications of >20%
with >10% Increase from previous Inspection:
3 0.7 %
Indications of >50% with
>10% Increase from previous Inspection:
0 0
Pluggable Tubes None 1
Total includes general surveillance and AVB inspection plans per SCE Cycle VII Steam Generator Inspection Program.
2 Total includes tubes in excess of original plan as deemed necessary.
SCE -
SONGS I TABLE A.3 GENERAL SURVEILLANCE PLAN INSPECTION
SUMMARY
"B" STEAM GENERATOR -
INLET SIDE Tube Inspections planned 1:
685 Tube Inspections completed 2:
685 Tubesheet Indications:
Number of Tubes
% of Completed Inspections New Indications >20%:
4
.5%
Previous Indications of >20%
with >10% Increase from previous Inspection:
0 0
Indications of >50% with
>10% Increase from previous Inspection:
0 0
Pluggable Tubes None Total includes general surveillance and AVB inspection plans per SCE Cycle VII Steam Generator Inspection Program.
2 Total includes tubes in excess of original plan as deemed necessary.
SCE - SONGS 1 TABLE A.4 GENERAL SURVEILLANCE PLAN INSPECTION
SUMMARY
"B" STEAM GENERATOR - OUTLET SIDE Tube Inspections planned :
209 Tube Inspections completed 2:
226 Tubesheet Indications:
Number of Tubes
% of Completed Inspections New Indications >20%:
5 2%
Previous Indications of >20'Z with >10% Increase from previous Inspection:
0 0
Indications of >50% with
>10% Increase from previous Inspection:
0 0
Pluggable Tubes None 1
Total includes general surveillance and AVB inspection plans per SCE Cycle VII Steam Generator Inspection Program.
2 Total includes tubes in excess of original plan as deemed necessary.
SCE - SONGS 1 TABLE A.5 GENERAL SURVEILLANCE PLAN INSPECTION
SUMMARY
"C" STEAM GENERATOR - INLET SIDE Tube Inspections planned 1:
480 Tube Inspections completed 2:
523 Tubesheet Indications:
Number of Tubes
% of Completed Inspections New Indications
>20%:
24 4.6 %
Previous Indications of >20%
with >10% Increase from 4
0.8 %
previous Inspection:
Indications of >50% with
>10% Increase from previous Indications:
0 0
Pluggable Tubes Row
- Col
% Defect 35 47 56% @ Tubesheet 1
Total includes general surveillance and AVB inspection plans per SCE Cycle VII Steam Generator Inspection Program.
2 Total includes tubes in excess of original plan as deemed necessary.
SCE - SONGS I TABLE A.6 GENERAL SURVEILLANCE PLAN, INSPECTION
SUMMARY
"C" STEAM GENERATOR - OUTLET SIDE Tube Inspections planned 1:
226 Tube Inspections completed 2:
226 Tubesheet Indications:
Number of Tubes
% of Completed Inspections New Indications >20%:
1
.04 Previous Indications of >20%
with >10% Increase from previous Inspection:
0 0
Indications of >50% with
>10% Increase from previous Inspection:
0 0
Pluggable Tubes None 1
Total includes general surveillance and AVB inspection plans per SCE Cycle VII Steam Generator Inspection Program.
2 Total includes tubes in excess of original plan as deemed necessary.
APPENDIX B FIGURES AND TABLES AVB-AREA INSPECTION
SCE SONGS 1 TABLE B.1 QUANTIFIED AVB WEAR INDICATIONS RECORDED IN THE 9/77 AND 9/78 INSPECTIONS S/G "A" S/G "B" S/G "C" 77 78 77 78 77 78 Number of Indications 147 78 209 135 321 369 Mean Indication Size 30.14 30 32.7 33.4 33.4 32.2 Standard Deviations 7.52 6.6 8.45 6.3 7.67 6.8
DISTRIBUTION OF ALL AVB WEAR INDICATIONS RECORDED AT THE 9/78 INSPECTION SAN ONOFRE UNIT 1 STEAM GENERATOR B NUMBER OF INDICATIONS REPORTED = 135 MEAN INDICATION SIZE
=
33.4 STANDARD DEVIATION 6.3 IN ADDITION:
8 INDICATIONS <20%
256 INDICATIONS <30%
5 INDICATIONS <50%
40 38 40 30 30 24 319
= 20 C>-
13 w
10 7
0 20 25 30 35 40 45 50 55 INDICATION SIZE (% WALL PENETRATION)
FIGURE B.2
DISTRIBUTION OF ALL AVB WEAR INDICATIONS RECORDED AT THE 9/78 INSPECTION SAN ONOFRE UNIT 1 STEAM GENERATOR C NUMBER OF INDICATIONS REPORTED = 369 MEAN INDICATION SIZE
=
32.2 STANDARD DEVIATION 6.8 IN ADDITION:
40 INDICATIONS <20%
96 INDICATIONS <30%
120 56 INDICATIONS <50%
100 99 89 80 61 o
60 54 46 o
- 40.
20 17 0
20 3
0 S
21 A
5 40 45 50 5
60 INDICATION SIZE (%) WALL PENETRATION)
FIGURE B.3
DISTRIBUTION OF ALL AVB WEAR INDICATIONS RECORDED AT THE 9/78 INSPECTION SAN ONOFRE UNIT 1 STEAM GENERATOR A NUMBER OF INDICATIONS REPORTED = 78 MEAN INDICATION SIZE
=
30.0 STANDARD DEVIATION
=
6.6 IN ADDITION:
24 INDICATIONS <20%
98 INDICATIONS <30%
2 INDICATIONS <50%
30 25 23 21 20 15 11 10 9
5 1
0 20 25 30 35 40 45 50 55 INDICATION SIZE (% WALL PENETRATION)
FIGURE 8.1
DISTRIBUTION OF THE CHANGE IN AVB NEAR INDICATIONS RECORDED AS >20%
AT BOTH THE 9/77 AND 9/78 INSPECTIONS SAN ONOFRE UNIT 1 -
STEAM GENERATOR A NUMBER OF INDICATIONS COMPARED = 58 MEAN INDICATION CHANGE
= -4.4 STANDARD DEVIATION
=
4.7 25 28 20 18 15 C) 0 c1 1
0
-20
-15
-10
-5 0
5 10 5
CHANGE IN INDICATION SIZE (% WALL PENETRATION)
FIGURE B.4
DISTRIBUTION OF THE CHANGE IN AVB NEAR INDICATIONS RECORDED AS >30%
AT BOTH THE 9/77 AND 9/78 INSPECTIONS SAN ONOFRE UNIT 1 -
STEAM GENERATOR A NUMBER OF INDICATIONS COMPARED = 23 MEAN INDICATION CHANGE
= -4.0 STANDARD DEVIATION
=
3.7 15 10 9
9 5
5 C)
=
0 10
-5 0
5 10 CHANGE IN INDICATION SIZE (%WALL PENETRATION)
FIGURE B.5
DISTRIBUTION OF THE CHANGE IN AVB NEAR INDICATIONS RECORDED AS >40%
AT BOTH THE 9/77 AND 9/78 INSPECTIONS SAN ONOFRE UNIT 1-- STEAM GENERATOR A NUMBER OF INDICATIONS COMPARED = 7 MAIN INDICATION CHANGE
= -2.6 TANDARD DEVIATION
=
2.8 15 CA 10 C>
5 w~
5 0F
-10
-5 0
5 10 CHANGE IN INDICATION SIZE (% WALL PENETRATION)
FIGURE B.6
DISTRIBUTION OF THE CHANGE IN AVB NEAR INDICATIONS RECORDED AS >20%'
AT BOTH THE 9/77 AND 9/78 INSPECTIONS SAN ONOFRE UNIT 1 -
STEAM GENERATOR B NUMBER OF INDICATIONS COMPARED
= 75 MEAN INDICATION CHANGE 5.12 STANDARD DEVIATION
=
4.25 35 30 30 26
,z 25 20
-4 u-15 12 co 10 5
0
-30
.-25
-20
-15
-10
-5 0
5 10 CHANGE IN INDICATION SIZE (% WALL PENETRATION)
FIGURE B.7
DISTRIBUTION OF THE CHANGE IN AVB NEAR INDICATIONS RECORDED AS >30%
AT BOTH THE 9/77 AND 9/78 INSPECTIONS SAN ONOFRE UNIT 1 -
STEAM GENERATOR B NUMBER OF INDICATIONS COMPARED
=
52 MEAN INDICATION CHANGE 5.27 STANDARD DEVIATION
=
3.60 25 22 21 20 Ci) c15 10 C)6 00
-20
-15
-10
-5 0
5 10 CHANGE IN INDICATION SIZE (% WALL PENETRATION)
FIGURE B.8
DISTRIBUTION OF THE CHANGE IN AVB NEAR INDICATIONS RECORDED AS >40%
AT BOTH THE 9/77 AND 9/78 INSPECTIONS SAN ONOFRE UNIT 1 -
STEAM GENERATOR B NUMBER OF INDICATIONS COMPARED = 16 MEAN INDICATION CHANGE
=
3.56 STANDARD DEVIATION
=
2.92 CD 2
10-9 0-4 U
as 5-4 3
0
-15
-10
-5 0
5 CHANGE IN INDICATION SIZE (% WALL PENETRATION)
FIGURE B.9
DISTRIBUTION OF THE CHANGE IN AVB NEAR INDICATIONS RECORDED AS> 20%
AT BOTH THE 9/77 AND 9/78 INSPECTIONS SAN ONOFRE UNIT 1 - STEAM GENERATOR C 1110 NUMBER OF INDICATIONS COMPARED = 239 MEAN INDICATION CHANGE
= 0.67 TANDARD DEVIATION
= 4.41 100 90 80 70 69
> 60 30 50 u
-3 40 38 2-30 20 12 10 5
4 0 25 15
-0
-5 5
10 15 20 25 30 CHANGE IN INDICATION SIZE (% WALL PENETRATION)
FIGURE 9.10
DISTRIBUTION OF THE CHANGE IN AV8 NEAR INDICATIONS RECORDED AS _30%
AT BOTH THE 9/77 AND 9/78 INSPECTIONS SAN ONOFRE UNIT 1 -
STEAM GENERATOR C NUMBER OF INDICATIONS COMPARED = 138 MEAN INDICATION CHANGE 0.42 STANDARD DEVIATION
=
3.35 90 80 70 70 60 50 47 40 30 20 16 10 4
1 0
-20
-15
-10
-5 5
1 15 2
CHANGE IN INDICATION SIZE (% WALL PENETRATION)
FIGURE 8.11
DISTRIBUTION OF THE CHANGE IN AVB NEAR INDICATIONS RECORDED AS >40%
AT BOTH THE 9/77 AND 9/78 INSPECTIONS SAN ONOFRE UNIT 1 - STEAM GENERATOR C NUMBER OF INDICATIONS COMPARED = 42 MEAN INDICATION CHANGE
=
0.52 STANDARD DEVIATION
=
3.18 50 40 30 E-30 C) 21 20 LA-15 co 10 0
1 T
-15
-10
-5 0
5 10 15 20 CHANGE IN INDICATION SIZE (% WALL PENETRATION)
FIGURE 8.12
SCE-SONGS 1 TABLE B.2 ANALYSIS OF SAN ONOFRE AVB INSPECTION RESULTS GROWTH IN INDICATION SIZE BETWEEN THE 9/77 AND 9/78 INSPECTIONS (9.7 EFFECTIVE FULL POWER MONTHS)
Indications Reported as:
>40% in Both
>20% in Both
>30% in Both Tsetol Inspections Tnspections STEAM GENERATOR A 58
-2.6 Number of Indications Compared
-4.4 7
- 2.
Mean Indication Change (%) 9.7 EFPM
-4.7 3.0
-2.6 Standard Deviation
-0.45/EFPM 2
Calculated Mean Growth (%) per Month STEAM GENERATOR B 75 52 16 Number of Indications Compared
-5.12 35.60 23.92 Mean Indication Change (%) 9.7 EFPM 4.25
-5.27
-3.58 Standard Deviation
-0.53/EFPM Calculated Mean Growth (%) per Month STEAM GENERATOR C
.239 13804 02 Number of Indications Compared 239 3
42 Mean Indication Change (%) 9.7 EFPM 1.67 0.42 0.52 Standard Deviation 4.41 3.35 3.18 Calculated Mean Growth (%) per Month 0.07IEFPM 0.04IEFPM 0.05IEFPM OVERALL (A+8+C) 3214 08 Number of Indications 372 213 65 Mean Indication Change (%) 9.7 EFPM
-1.29
-1.45
-0.83 Standard Deviation 5.14 4.28 3.55 Calculated Mean Growth %)per Month
-O.13/EFPM
-0.15/EFPM
-0.09/EFPM
APPENDIX C FIGURES AND TABLES DENTING INSPECTION
S.
98 07 z4 03 02 a t 8
94 s3 as as 87 84 5
73 72 79 77 70 0
74 71 78 a
till4 e4 45 st at 64 at U)4 0
IIILS e
=
SO 53 32 s
2A 47 3
42 T
3
-4 IL.3 32 r7 I
I 9
72 217 15 O
t2 N
19 17 4 3 4,
2 rfl c
I I
Z 0
1C G')
zC I.z >
.atsW38tsat
d999 3-07 IS 04 a 83 9 2 7
91 78 77 70 7S 73 92 79 7
-474 70 a
687 af aa Is I-2 Se S
5 45 rs s7 so ss 5
4 3
M2 41 Mr 5a 3
m 3
9 M
C 36 3
37 Pt 34 33
-432 31 30 29 28 27 28,25 24 23 22 21 20 to9 17 10 1 5
N I
a LL a
4 3
2
'I mz Go
94 as 0
G2 93 92 87 as 84 83 85 82 2
St 79 78 70 75 74 73 77 7t
[Frill I
liu l j-1170 a
f~1 67 e4 as 2
83 H
5o o C 54 0
5
-~
49
[
48 47 vp CIII 4 5 r
4 42 39 39 3
3a 35 A M 3S
-4 34 33 32 31 29 29 27 25 24 2
22 2 2t 1
Is 17 14 13 12 it rf I i L la 7
N g
N7 r6 5
3 2 Z m
C:
1
tn m
ane (n co 1 a nr
- CD tnto COLUMNS 00 IS, g
as 10, SI'-
- 4)
V)
I-C N N "0
U SC C.
46 47 4 40 44 4S 42 4g
'4 99 37 32 29 3
96 22 5
14 s2 2
19 T
2 R O-S S.. PREVIOUSLY PLUGGED TUBES t.ES--t-------------9-Trs t IosM5,c7 0
-ts
/
r
-Vc NL OG 1"7 PRVIo L
YTEAM O NERAT T
40 1c 5Th E
c
- C 5
o?
1.r pRV~
5 D. GAUGING PLAN
+--MANWAY 27 SERIES STEAM
'F-NERAT(-
FIG ti@7L
le g o 04 93 as Be 99 88 87 85 83 0t 79 78 77 75 73 74 89 Ox I I 67 II II I83IL7 P1 SS 1-1 62 e 83 eal H
58 57 Oj S e 55
-f L5 1111 111S
(/)
s 2 5 5051 JM I
I 49 T
F 47 3
G 4
45 44 41
-ULA 40
,3 37 33 31 O
+t 3029 28 27 25 L24 23 2221 20 17 4-o O
1 2
NT-I I I
L2 N
to 9
It I5 4
3 2
9, pt CO' 0n GCO cnmc Z
RESTRICTID TORE DATAa SAN ONOFRE UNIT 1 TABLE C-1 SIA' CE.%
T?00 A I.t(t 4/;_'
- Evidence of PRE -1978 GAJGI::G DATA 6.55640 0.500 460.40 10 Decrease Coments 5.. - -- /1/36 4/74 4155
.500-.560(4/78)
,m o.. 1/21/73 6132 0__
2 0
N S 7. 072 1
0 900
.500-.560 4/78 1 33 500(2) 2 0
POSSIBLE
.460-.500(10/76) 1 3--
0)0
.500-.560 4 78 1 49 1
0 P D
-1 0
NO0 500-.560(4/78)
- 1 1
0 0M_0-1 66..-
1 1
01 I
0 1 68
.0--
1 0 1
0 500-.560(4/78) 1 8
.500()
1 0
1 0
500-.560(4/78) 1 84 2
0 2 02 0
No0 Smj-.560(4/78) 2....---
2 0
1 0
No0.500-.540(10/76) 2 2
2o2.5O0(1)0
.460-.500 2 17
.500(2) 2 0
0
.500-.560(4/78) 2 1
0.6 2 2-2 0
0 0500-.560(4/78) 2 18 1 0 2
34
.500(1) 0 0
No
.50-54 7
1~n 0 Noo-0.560(4/78) 540(2) 0 1
0.540(1016) 00 2
3..S00-.540(2) 0 0
0 0
10 2-2 0
.00-560 4/78) 1 0
38
(
>.540(1) 2 46 5
0 2 0 47.50o(l) 5.40(l) 0o 0
no0 S650(4 2 o0 0-N SOO.560 4/78) 1 0N.500-.560(4/78) 2 511 2
54 5-- - 560(4/78) 2 54 5005(540(10/76) 2 65
-500-.540()
0 N
540(6/73) 2 69
.0540 1 ----- -
540(1076
---2 *69O Eon-ufficie(t revious1 data
- a.
that tube 1to is greater than the probe siTe shown.
ir.i.Ctes that tube 10 is less than the probe Size hoz h
- c.
P,!nne of values irdicates that tube I
- 2.
1978 G~u,;bnq Cata a.l r-ictc rrobe easq Is&
I spljl a.' C' '
,, Catio j
%))(
probe naasaqoq Isu' ~ 1P a in. tEItd
- b.
1..
,or i ndicateii ctOr rb
Page 2 of4 RESTPTCTE0 Tilr PATA SAN ONOFRE UNIT 1 STEA C.Z':Io A I.tT 4/;..,.:ir.
,;?
- :. sa Evidence of PE-197
.0 1 Decrease nts
.S.
0/71/73 6/3D4/-197 1-----------
a
.560
.500 N.460j 47n. IDAntin 0
1072 470-.5002 )
2 2
J nn.
n ir 70 1-0-
500-.560(4/781 74-2-Z--
ann.0ini 74
.500-.540 2 2
0 n2
.500
.500-.540 1
1 0
500(1)
.500(1)
.15 0
2 0
2 02 0
3 100
,.480(1)<
4f11-
-2 0.50 606/
L 0---
-- -0 0
0 0
l) 06 4 1000 50- 6001l 0
0 9R.5 40 1 1 050507 00
.500-.540 1 1n-0 1nt0n 0-0 40(10/76)
.500-.540(
0.500 1?
.500.460-.540 2
0
- 1. 500-.540 (10 /76 )
.500-.540 1 1
0 0
2 96.500-.600
- 1)
.500-.540 1
.460-.541 1
0 1
0*50.
067 2 0 2
0.500-.54 73 14 9
.500-.540(1)
.500-.560(1) 1 0
--. 54-14 4
.500-.560(1) 1 0
.5---
14 0.5--.---6 12 96 5----
.500-540 1
.460-.560 1
L N 05 13
>5 5.4004(
11-si 0-m l_4-
.540 1
.500-.560 1
.10-00 6 14 4 1
0n 1
0__
_50~
.500-.560 1 0
.4on.500-.560 1
0 26 92 03 27 91 Ei:,re-q tha-t tube 10 is greater than the probe sie z hoe n.
ntv cat%
- .at tube 10 Is less than the probe size sot shjwn o c R. ane of values indicates that tube 10 Is betw on p.<be size s ShOuf.
- 2. 1978 Grauqonq Data
- a.
- V o, 4'iicates"I probe passq hofs ~ l~t1?~bpoep5a0e IS restricted.
PAqe 3 of A Pr-,1'1(.Tr Ti IF PIATA SAN ONOTRE UNIT 1 TEA' CE.
0r A 1. I t CI Evidence of F-197F GAJCOI:.
DATA 10 Decrease
-- -- 4/74 4/75 1')76 NO 1 0 1/73i No
.500-.560(9/7 9-
-77
__00__oo.500-. 540110 L6 17 QL0 0
NO0
.460-
.4(6L7)11
.540(1) 00..--
A6.ftLq 7
0 89
.500-.560( 4L 7?
1 1 t50 0 -.5 4 0i n
0 I
M
- 5) 0O 0
1 0
0IL 11 1_
Ll.-.5401 0
No
.2 R 13 82.50)500-.6001
>.5001 Il 113
_L___
I50.50 n 0 57 82 0
0.0O1
.500-.600(1)
.500(1) 0 21500540)
.500-560 (l 0I
.560-560 9
.500-0600(1
.500 38 80 50 0
.50-60O67 500-.6000)
>.500(1) 38 8 1 10-56i
- -_L N_
1 01 a.:
'e"r' ~at tube 10 is reater than the probe Sire o
i4. " int c t es at tube ID is less than the probr si/e
- n.
nr' of value; indcates that tube 10 is betwe probe siteS shown.
- 2. 1r78 o
a.t1jhno Data a.i r-iCatCs rrobe pa8isqcl throij ill TS~ 1olation, nrn. P passaqe is restrtoT.d.
~ ~.
o
,n,1ratn oatton.
RSTRICTED TUtt DATA PAge 4
of 4
SAN ON0FRE UNIT I 5T(A" C.ERATOR A
I'.dtT P/i978 GAGIiG DATA 4/
'i?
J Ir. a Evidence of I
1-1.
G T.
Decrease Coments a 0
- 7872/
<540 1 )
500-.540 1 )
.500-.520(1)
.500-.540(1) I. 500O.560(1) 1 0
1_
0 -. 40 /73)
.540(2) 4 60 0
1 500-.560()
0n..54040/174) 1 so.0) 500 -.540(1)
.500-.520( )
.500-.5 40(1)
- 560( )
0
.500- 540(6/73)
- 0.
5 1
.500-.540(1) 0 NO 1
Qj..
.540(1)
.560(1) 0
.540(1)
.500-520(1) 0
.5o-.54 (2)
.o o(<.()540(2) 05 eo917?
.5
- 2) 1.500 (l) 1 0
No.
.540(6/73).....
.5 40<.540(lS__5401(l
.500_.520().500-.540.540 <.540(1) 1 0 150-.540(6/73 EL..~ L...
540 1)-
0--
.5 0-.560 4
+ 500.540)_
O.500-560(2) 0
-MOLD__
.540(1)
.560(---
0 2 0nt 46 AT -
~.500-.560(2) 2 0
a50.2(15
.500-.520(1)
<.560(1) 1 01-m
-. 50()
_______540(2) 500-540(2)
.500-.540(2) 0
.50.4-07 5 4 0 (l)
. 5 0 0 -.5 2 0 ( 1 )
5 No
.540(2.500-.540(2)
.500-.540(2) 1 0
0 5
<.540(2)
>.540(U)
.500-560(l-1)01 ng i
7 47 37
<__5605_1)9/
____1___
.500-560 IL 47 1R 0
5
(
2 ro 1 f
son-1t rvoat
- ar DrSo that tube 10 is gr(ater than the probe seC shown.
ir1ct" s :1at tube ID is less than the prb" siZ e how.
ho n
- c.
n of valurs indicates that tube 10 is betwwfl probe sires hon 2.
978 ']rM1a nl o at i d '
pro e passage is restricted.
prob 6aS I
1
.:70.54 (2
.5 0.5 0 2 A.
ir5C00-S r
41I0lo ati n.
_..40(2 c.
540(24 0dca
SCE -SONGS 1
TABLE C.2 STEAM GENERATOR "A" GAUGING
SUMMARY
OF INSPECTION RESULTS INLET OUTLET Tube Inspections Planned 314 0
Tube Inspections Completed 314 18 Tube Restrictions
.400" 0
0
.400" -
.460" 0
0
.460" -
.500" 4
0
.500" -
.560" 73 3
Total Restrictions 77 3
Total Restricted Tubes 75 3
TABLE C.3 DENTED TUBE INDICATIONS STEAM GENERATOR 'A' THIRD AND FOURTH SUPPORT PLATES October 1978 SUPPORT PLATE
- PREVIOUSLY ROW COLUMN
- 3
- 4 IDENTIFIED 10 3
NI 9/77, 4/78 11 3
X 9/77, 4/78 11 4
x 4/78 12 4
X 7/73, 4/78 12 6
X 4/78 37 19 NI 9/77, 4/78 38 20 X
9/77, 4/78 39 21 X
9/77, 4/78 39 80 NR 9/77, 4/78 3
64 X
4/78 11 97 X
X 4/78 14 4
X 4/78 29 11 x
4/78 29 90 X
4/78 30 12 x
9/77 31 12 x
4/78 40 23 x
4/78 46 34 x
4/78
. *Data search limited to verification of dent in at least one previous inspection NI - Not inspected NR - None reported
TABLE C.4 STEAM GENERATOR B GAUGING
SUMMARY
OF INSPECTION RESULTS INLET OUTLET Tube inspections planned 44 0
Tube inspections completed 44 0
Tube Restrictions
<.400" 0
.400" -
.460" 1
.460" -
.500" 3
.500" -
.560" 11 Total Restrictions 15 Total Restricted Tubes 15 Tubes Plugged Row
- Col Basis 38 20 Restricted to a.460" probe
TABLE C.5 DENTED TUBE INDICATIONS STEAM GENERATOR 'B' THIRD AND FOURTH SUPPORT PLATES October 1978 SUPPORT PLATE
- PREVIOUSLY ROW COLUMN
- 3
- 4 IDENTIFIED 11 2
X 4/78 12 3
X 4/78 12 4
X 4/78 13 3
X 4/78 13 4
X 4/78 14 3
x 4/78 28 88 X
4/78 28 89 x
4/78 28 90 X
9/77 28 91 X
9/77 29 88 X
4/78 29 89 X
4/78 29 90 X
4/78 30 88 X
4/78 31 89 x
4/78 35 19 X
4/78 35 20 X
4/78 35 21 x
4/78 35 22 x
4/78 35 23 x
4/78 36 17 X
4/78 36 18 x
4/78
Dented Tube Indications Steam Generator 'B' Page 2 TABLE C.5 SUPPORT PLATE
- PREVIOUSLY ROW COLUMN
- 3
- 4 IDENTIFIED 36 19 X
4/78 36 20 X
4/78 36 21 X
4/78 36 22 X
4/78 36 23 X
4/78 37 18 X
4/78 37 22 X
4/78 37 23 X
4/78 38 22 X
4/78 38 23 X
4/78 39 21 X
4/78 39 22 X
4/78 39 23 X
4/78 40 22 X
4/78
- Data search limited to verification of dent in at least one previous inspection NI -
Not in'spected NR -.None reported
f 6
we4i otr: RE 1T I TABLE C6 STEAM C[tR.IAIOT C INLET S 4.
PRL-1973 GAJGING DATA 19 34/74
-?51/
01 18u 1
0 0
. O...- --.---- hl(JZ1 21
~-------
1 28---_1_
1 1
-500-.56 (4/
)
1 451 0
.500 2
1~~~N 45---.--5 060 478 1-50 1
61o 1
60 1
61 2
0 0
1 64 n.anA11 0
R 1-0 0O
.500-.560(4/78) 3 0
No 1
0 1.71 0
.500-.560478 1
71 0
N0 0
N 5---
0 1
76 1
75 0
1 76
-500-.560/78) 2 11 2
1 Soo-0 No 2
14 2
17
_--------_-L 0
-no 2
20 h sofir ict p eviouS f ata J ES:
re-atP'S tat tube 10 is areater than the probe ize shownl.
b,iit'5 that tube ID is less than the probe 5I~ e h how.
c Pen'ie of values indscates that tub'e 10 is betwwfn prbCses ho.
- 2. 197
..ugn Ct prb~a tr oa1 nS boot probr p..sag is restricted.
a 7r1ae 1rb Qosq th b
12
- 2Y.
- 3 or 4
5(00ate octloi de 781
RESTRICTED TU9E DATA Pane 2 of 6 SA*I OttoCRE 11I1T I STEAM GENERATOR C
IN1LET 9;7-!
inf ta Cvo e'q PRE-1978 GAJGI:G DATA 1Ir"____Co_.
rat R0tt COL. 1 2/72 11(73 4/7Z 0/5N 2
23 0
N1 0 o
.500-.560(4/78) 0 2
03 W-2 4
2 0
No-.
6-2 43 1
01 NO
.60-5801/78)
NO
.5T:~.56041/)
-J 1
0 No
.500-.540(0/76) 2 49
.500-.540(1)
No.500-.540(9/77) 2UR W 0
o 40 M
a ir~"Jte tha tu<e10QL'Ljr--er1ha1 he0p.b460-e.500(i
<o t.500(1)
NhLo tu----D-i---oo rh0.500-.580(2/72) 2n 51MO
.60-.580(2/72)
.340-.580(1)0-2.
1978.
0 n
N O
.56 0 -
2 60 01-
--- L1 -
5-"-"
-- o
.560-.580(6/15) 2-61 50 50
.0-50I00
.500-.580(1 2N0
.500-.540(10/76)
>.500(2) 2~~N 65----w_50.540(10/76
.500(2) 1 0_
2 6600>..500(1) 0 0
.500-.54ja7 2
68
.50
)
0L_
n 0
-No(_78
- a.
~
~
assao h roe as 2
69
-5.
1
.- L..
I 0
I 2
71 n
0
-n 2
72 n11...D-S04j8 3--
-2 1
3 13 3l P
. Insuifficient previous datA 1.25 L rel^
1 Da tat tube 10 is greater than the probe Size Shown.
- b.
'ctsta ueID is less than th
)robe sit Shown C.
Panqe of values irdwcates that tube ID 15 betwr p
a.
G 8 iia s probe pasg thro TS ahn a
f probe passage i s tit
RESTRICTFCr a
min Page 3 of 6 sr-; on10 P
ti'lIT 1 STEAM GENERATOR C ItiEf 4/;8 r (1irq i'.;!
ri '
Ir 0
ROW
!CL012--!L7 5
3 27 3
44 3
262o 3150 4 01 0
2_ 1 0
N 500-.560478 3
24 2
0 2
0 3
S43
~2 0 20 O
- V-507 4 51
.50.8 1o
.50-58 10 3
6 1
0 0
3 62 1
3 750 2
0 r3 60 0.00 0
N
.500-.580(2)
.500-58022 0
0 6-1 0
2 0
-s-1 0
0-i
_o
.5 0.5 0 1.5 0.5 0 1
_ 1 0 0
00
.560o -. 580(6/751 61 ___ I_
50 0.50(1)
.500-.580(1) 0061 4
11 1
0 0n
_12 2
0 No 2.~~~ 198
/781q at 4 24 2
0 604/78) 4 25
--- 2 02 01 50 4
430.60.
4 59
.50l 1
0N i
4 60SO-00 O-1 01 0NOO-.6 4L8 4
61 0
5 262 5 2 5
60 N
6 60
.5 00 0) 1
.500-.580(1)
.500-.580(1) 1106-.T 7
10
.580-.600(1) 6,~~
-6
- -- 6 1
01
.500-580(1 500 50(1) 05 6
600
.00)--
U j-
-I--
1-0 0
'94 rd I 9 atp aht tube i0 is greater than teprobe % i e hown.
ind.icatps thit tube 10 is less than the prb 17 son b.~~
"Y0
.560-.580(6ate
RESTRICTED TtIMt DATA Page 4 of 6 Sil olo-,RE IiT 1 STEAM GENERATOR C INLET TUE W.PRE-1978 GAGIGDT R031 COL. 2/72 11/73 4/74 6/75 1017 4 0 0
No 11 2
1 4
0 0
11 3
4 0
4 0
mn 114 0
4 12 3
0___E 12 4
0 13 4
.500-5600) 0 mn 14 3
1 0
1 0
14 4
2 0
no 1L J
27 9 11 1
0111 2 9 1 2
T _0_
S-.5 0(4/78 1 30NO 89-.5401076
~ o_____________________________
.50(1 )
.460-.50001) 1 1
0 1
1 0
no
- 460'500aaaI7l1 3 2 9 1 2
,_ _.5 4 0 ( l)_ _I 1 0
1 0
N O n o5 0
0 - 5 6 ( 4 1 7 )
- 512502 0
100
.500-.540(9177) 30.500(1)
.460.500() 1 1
0 1 1 04 31139 2
0 0
No 31 13 1
0 0
No 31 00 31 89
__NO____r,0_4 37 0
4 0
4 0
37 120 0I 38 21
_.0()2
/5007 M 7
0 4
0 No
.500-.540(1076) 4~
00 M
2 0
2 0n
.500-.540(1) 1 0
0 0O
.50.501 1
1 "D
.500(2)
.460-.50(2) 00 2
2 0
1 0
1 0
NO
-1L-JUL 0.O-.50 1
0NO 40_1_23___0 NO
.500-.540 0{76) 40(10 500-5402)5
<tt
.500(
- 3..6 (
1 1P" 0n,1 1ficrnt p p 46io-s dAtA
.re-l3;A '.-eqiriq Data
- a.
irditates that tube 10 is Iess thAi' the probe size shown.
- b.
p',iqr. of values irdicates that tuhe ID is be'tw-en probe sizes shownl.
- 2. 1978 G..!uqinq rata
- a.
ir'licates probe rassaqe, throj9h III TS i1onl aeI etltd
- b.
"3.. 3. or -4' indicates
_,P ocation.'~
t' rb
~
RESTPICTFD Itf PATA Pae of 6 Sr,; O?:07R ti vIT I STEAM GEtRATOJ R C V..ET JGN AA4/78i fuqing Data 9178 Gauqim-Data
- ECre1, Co-.ents O
0500-.540017 0Q 2
0-It 910500- 5400176) 12 0
No
.0-.6(/8 14n 7f 72 D0
.50 0 -.56 0 (4 / 78 )
1 40 79
- ~~00-.540(2)2
-It 2 4 2
0 0
41 33 0
R 1
010 4-02n2 43 311 31540
)
1o 41 0500-
.60 4 78 43 32 1
I 11 1
1 No J4f4 n2 2
1 0
N o.
5 0 0.
5 4 0{ 6 { 7 9 )
45<
.s4 i <
soo -. 0o0i o4 U 1
o No 500-. 540 f 6/79).
35
<.540( )
540 1
. -500-.540 11-_J 0
06.4.0-
.500-.540(9/77
.0 - 4 ( ) 1 0
2 0
IPD 46 31 O-S-o-0w 64 2
0 46 642
.540(2)0-0 65 NO 460-.500(4/78)
L --
" r)"
Inujf f icient previous data 5:,
r-1 g atp tat tube 10is greater than the probe size Shown.
ndticatp% thit tube 1D is less than the probp site shown
- c.
Pn se of values indicates that tube In is betwern probe sizes shown.
G. 1
- 19. ate5 probe passae thror II TP 1 alji,hpoeaage is restricted.
RESTrnIFn Tlirf PATA Page 6 of SA'I 0N0PE iirdT I STEAM GENERATOR C I-LET 4//ri G -uqirq Dta 91?.; j-jqin1 rjat."
,.;c:rc TUSE~D.PRE-198 GAIGING ATA 6-q1L.)I~~..~
~
TUBE
.5 0
CO.
2172 1
1/73 4/74 1076
.500-.560(4/79) 37
.500.540()
1 0
47 62
.450-.540(2) 0 NO
.90-.540(9o7)
.560(2) 2 0
2 0_
47 63NO 48 52
_________2 0
IPU 27 IPO 11 25 0P 5
28 P
O IRI 20 2
~~~
N 1;O NO
- a.
i~,rae~, hat ube 0 1~qrater han the probe sze shown.
IP' pvihSdt in'iicatp s, th a't tube ID is le ss than the prob e i te hown.
40-.5402) 0
.h~
NOe1 Sttbe1 sbt-np~h-i~
h Rpno-of value-irdicates thao
- 2.
1918 G0uq'nq Data
- a. C" ir'!icd?."s probe paSsaqc l thoISP lolat, isionrci
- 8. "~.V r4' pho~ ocat'ofl 4 h p e WpareI etit
- b.
or indicate'
SCE -SONGS I
TABLE C.7 STEAM GENERATOR "C" GAUGING
SUMMARY
OF INSPECTION RESULTS INLET OUTLET Tube Inspections Planned 429 0
Tube Inspections Completed 432 31 Tube Restrictions
<.400" 0
0
.400" -
.460" 0
1
.460" -
.500" 6
0
.500" -
.560" 79 7
Total Restrictions 85 8
Total Restricted Tubes 83 8
Tubes Plugged Row
- Col Basis 37 19 Restricted to a.460" probe
TABLE C.8 DENTED TUBE INDICATIONS STEAM GENERATOR 'C' THIRD AND FOURTH SUPPORT PLATES October 1978 SUPPORT PLATE
- PREVIOUSLY ROW COLUMN
- 3
- 4 IDENTIFIED 9
3 X
4/78 9
4 NI 4/78 10 2
x 4/78 10, 3
X 4/78 10 4
X 4/78 11 2
X 4/78 #3 & #4 11 3
X X
4/78 #3 & #4 12 3
X X
4/78 #3 & #4 12 4
X 9/77, 4/78 13 4
X 9/77, 4/78 14 3
NR 9/77 27 9
X X
9/77, 4/78 27 10 X
9/77, 4/78 27 88 X
9/77, 4/78 27 89 9/77, 4/78 27 90 NR 9/77, 4/78 27 91 X
9/77 27 92 x
9/77, 4/78 28 10 x
9/77, 10/76 28 88 NI 9/77 28 89 X
9/77,-4/78 28 90 X
9/77, 4/78
Dented Tube Indications Steam Generator 'C' Page 2 TABLE C.8 SUPPORT PLATE
- PREVIOUSLY ROW COLUMN
- 3
- 4 IDENTIFIED 28 91 x
9/77, 4/78 29 11 X
9/77, 4/78 29 88 X
9/77, 4/78 29 89 X
9/77, 4/78 29 90 NR 4/78 30 12 X
9/77, 4/78 30 88 X
9/77, 4/78 31 12 NR 9/77, 4/78 36 19 X
9/77, 7/73, 4/78 36 20 X
9/77, 7/73, 4/78 36 21 X
9/77, 7/73, 4/78 36 22 X
9/77, 7/73, 4/78 37 18 x
X 9/77, 7/73, 4/78 37 19 x
9/77, 10/76, 4/78 37 20 X
9/77, 7/73, 4/78 37 21 X
9/77, 7/73, 4/78 37 22 X
9/77, 7/73, 4/78 38 21 X
9/77, 4/78 38 22 X
9/77, 7/73, 4/78 39 21 NR 9/77, 4/78 39X21 NR 9/77, 4/78 39 22 X
4/78 45 67 NR 9/77, 4/78 45 68 NI 9/77, 4/78 46 65 X
9/77, 4/78 46 66 NR 4/78
Dented Tube Indications Steam Generator 'C' Page 3 TABLE C.8 SUPPORT PLATE
- PREVIOUSLY ROW COLUMN
- 3
- 4 IDENTIFIED 47 64 X
9/77, 7/73, 4/78 12 1
X 4/78 7
3 X
4/78 10 5
X 4/78 11 4
x 4/78 12
- 5.
X 4/78 14 4
X 4/78 15 4
X 4/78 36 18 x
4/78 39 23 x
4/78 48 51 X
4/78
- Data search limited to verification of dent in at least one previous inspection NI - Not inspected NR - None reported
SCE -SONGS1 TABLE C.9 STEAM GENERATOR SUPPORT PLATE CRACK OBSERVATIONS STEAM GENERATOR A Crack Location Support How Observed Photo/and/or Tube Side Plate 10/76 Photo 10/77 Photo 10/77 _Tape 4/78 Tape 10/78
- Remarks RlC2/Inlet Nozzle 1
X X
XXXTiF~ue
.l2llt Nzl x
Tube is plugged.
RlC2/Inlet Nozzle 2
X Out of view x
x x
Tube is plugged.
RlC3/Outlet Nozzle 1
x x
x x
x Appears to be supported.
RICiB/Inlet Nozzle 1
x X
x X
x Tube is plugged.
RIC83/Inlet Manway 1
x x
x X
X Tube is plugged.
RlC83/Inlet Manway 2
Out of view x
x X
X Tube is plugged.
Xe X I Appears to be RIC85/0utlet Manway 1
.Xsupported supported.
RIC85/Outlet Manway 2
Out of view X
x X X
RIC99/Inlet Manway 1
X X
X X
x Tube is plugged.
R1C52/Inlet Manway I
Out of view X
Obscured Out re/
Appears to be Obscured Xpprt supported.
SCE -
SONGS 1 TABLE C-10 STEAM GENERATOR SUPPORT PLATE CRACK OBSERVATIONS STEAM GENERATOR C Crack Location Support How Observed Photo/and/or Tube SPt 10/76 Photo 10/77 Photo 10/77 Tape 4/78 Tape 10/78.
Remarks RlC2flnlet Nozzle 2
X No Photo x
X Obscured Tube is plugged.
Available R1C/Outlet Nozzle 1
X No Photo x
x X
Tube is plugged.
Available R1C52/Inlet Manway 1
Out of view X
X X
Tube is plugged.
R1C83/!nlet Manway 1
x x
X X
x Tube is plugged.
R1C83/Inlet Manway 2
Out of view x
X X
X Tube is plugged.
RIC84/Outlet Manway 2
x x
x X
x Tube is plugged.
RIC98/Outlet Manway 1
x x
x x
x Tube is plugged.
RIC99/Inlet Manway 1
X Out of view x
X X
Tube is plugged.
I SEPIES 27 A-WAR GUNIEATOR
.1ST SUPPORT PLATECRAKS A
\\
S 1
1 1 1a1 1
1,v t
1' I
II 1
il 1
oss r!*'l~
il:
I
~
r,***
a a e ra e~ c
-67 711 t.i
~
~
S9 5
SIJ
-- MANW'%Y 7/77 78 P(7(8
I 4*t Areas in which a crack is shown for one year only are out o view of the camera in the other year.
P C.
C-7 SERIES 27 A-.
AM CGRA1DR 2tD SUPoRT PLAIE C'.R$W S 9 9 W e a e t e 9 o 9 9 3 1 7 '.9.9.3 0 9 S s 4 9 *4 1 4 ',. 1 4% s. 1 '
. t o s.It 't
- ' f. : ? ' 1 1 1 3 9 5 1 4 3 I II Li llw IS IJJJJ1j 11111!
I I
l Il 1 1 11 1M COLUMNS
, -4f.
4 at I
I W6
-o..
t~~
t
.a
'f
.~~~
LI'..
il. 't~
I 11.it~*
- 1 1
- 1 I
.66 j
- 11....
S..,....
- 6.
a
.9 ft g
I ZL.
E 4
/M. *Y 78 79 161-79 713' 10174
/6(75
?~
'o(7
Areas in which a crack is shown for one year only are out of view of the camera In the other year.
v-..e CRi4tol 1T SUPP'OT kATE CtCKS qOqMqs308160 M1-M1*1111 q 107 LShIAf.7.S 4SA1, 4i 41 V1%11154 No$3 t" V!m to 11 ~1 t3 1 S 3 1 I
I i.1 g!4 1..
J 5,
. 1.
I
.~~.
5 MAI,
Y 7
I/h?7
/0/77
Areas in which a crack is shown for one year only are out of view of the camera in t other year.
V1 que.- C-7J SERIES 7
W-tito SUPPORT P~.nc case.Ks~
..O, Ii no. -- I1 L' I 4
'COLUMNS tfi
- 1 1
I1 j
I I It
- lo It Il IiIII' '1, II '1..
- ~ t l
l I
- -, 11, 1 -*
- -~ -.
I T
- 11.
m I
7617776
SCE -
SONGS 1 TABLE C.11 COMPARISON OF FLOW SLOT MINIMUM WIDTH IN SCE STEAM GENERATORS FROM 1976 TO OCTOBER, 1978 STEAM FLOW SUPPORT A
A A
GEN.
SIDE SLOT PLATE 1976 1977 4/78 10/78 76-77 77-78 76-78 76-10/78 A
Manway 1
1 0.43 0.32 0.36 0.36
-0.11
-0.04
-0.07
-0.07 A
Manway 21 0.73 0.73 0.89 0.86
+0.00
+0.16
+0.16
+0.13 A
Manway 3
1 0.95 0.98 1.09
+0.03 A
Nozzle 1
1 1.52 1.44 1.44 1.57
-0.08 0.00
-0.08
+0.05 A
Nozzle 2
1 1.09 0.91 0.98 1.02
-0.18
+0.07
-0.11
-0.07 A
Nozzle 3
1 1.05 1.28 1.04 1.12 0.23
-0.24
-0.01
+0.07 C
Manway 1
1 1.58 1.71 1.58 1.81 0.13
-0.13 0.00
+0.23 C
Manway 2
1 1.02 1.19 1.26 1.16 0.17 0.07
+0.24
+0.14 C
Manway 3
1 1.28 1.26 1.21
-0.02 C
Nozzle 1
1 1.90 1.83 1.88
-0.07
-0.02 C
Nozzle 2
1 1.25 1.24 1.38
-0.01
+0.13 Average Change
+0.02
-0.01
-0.01
+0.07 Not included is Steam Generator B data, which shows no perceptible change in flowslot width in any support plate.
SCE -SONGS 1
TABLE C.12 FLOW SLOT GAUGING OF STEAM GENERATOR C TOP SUPPORT PLATE BASED ON VIDEOTAPE FIBERSCOPE GAUGE METHOD SIDE FLOW SLOT GAUGED WIDTH INCHES Manway 1
2-3/8 Manway 2
2-3/8 Manway 3
2-7/16 Notes:
- 1. All flow Slot Sides appeared to be straight visually.
- 2. Nominal width of Flow Slot is 2-3/8 in.
- 3. Flow slots 4,5 & 6 past the center stay rod also appeared to be straight.
- 4. Flow slots 1, 2 and 3 in the third support plate also appeared to be straight.
APPENDIX D PHOTOGRAPHS
PHOTOGRAPHS STEAM GENERATOR INSPECTION NUMBER STEAM GENERATOR FLOW SLOT HAND HOLE LOCATION 1
A 1
Manway 2
A 2
Manway 3
A 3
Manway 4
A 1
Nozzle 5
A 2
Nozzle 6
A 3
Nozzle 7
B 1
Manway Before S/L*
8 B
2 Manway Before S/L*
9 B
3 Manway Before S/L*
10 B
1 Nozzle 11 B
2 Nozzle 12 B
3 Nozzle 13 B
1 Manway 14 B
2 Manway 15 B
3 Manway 16 C
1 Manway 17 C
2 Manway 18 C
3 Manway 19 C
1 Nozzle 20 C
2 Nozzle 21 C
3" Hole
- These photographs were taken before sludge lancing.
All others were taken after sludge lancing.
N 4A
.!/4
5C 4
C4
7 I-w
/0/pp A k~GIt4~
a 1..
.5 CL' S/c~ ($2 9
"-Cr J/4~
/!J23
10
..../
iior__
11 Iva Sf412 SC tof ?
Iv.J.
1117R "44
19 c
5? (
vi~
&W(
j,- ? ii
APPENDIX E REFERENCES
REFERENCES
- 1. Proposed Technical Specification 4.1.6, "Inservice Inspection of Steam Generator Tubing", submitted in Docket No. 50-206 by letter dated July 31, 1978 as Proposed Change No. 75 to San Onofre Unit 1 Technical Specifications.
- 2. "Steam Generator Inspection Program for Cycle VII Refueling Outage" Submitted to NRC by SCE letter dated August 17, 1978.
- 3. NRC (D. L. Ziemann) letter to SCE (J.H. Drake) dated September 14, 1978, Docket No. 50-206.
- 4. Report entitled "Interim Steam Generator Inspections of all Tubes in Area of Anti-Vibration Bars", San Onofre Unit 1, dated October 1977.
- 5. Report entitled "Re-Evaluation of Steam Generator Eddy Current Tube Inspection Results", submitted to NRC (A. Schwencer) by SCE (J.T. Head,Jr.)
letter dated November 18, 1977.
- 6. Report entitled "Steam Generator Inspection", San Onofre Unit 1, January 30, 1977, submitted to NRC (A. Schwencer) by SCE (J.G. Haynes) letter dated February 1, 1977.