ML19316A111
| ML19316A111 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/23/1974 |
| From: | DUKE POWER CO. |
| To: | |
| References | |
| NUDOCS 7911280633 | |
| Download: ML19316A111 (9) | |
Text
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DUKE P C.W E R
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REACTOR SUILDING I.
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END ANCHORAGE SURVEILLANCE 3
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M IR THE ATTACHED FILES ARE OFFICIAL RECORDS gung I
OF THE OFFICE OF REGULATION. THEY HAVE APR 2 6 1974 i
BEEN CHARGED TO YOU FOR A LIMITED TIME
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PERIOD AND MUST BE RETURNED TO THE 0IInc osY CENTRAL RECORDS STATION 008. ANY PAGE(S)
REMOVED FOR REPRODUCTION MUST BE RETURNED g
TO ITS/THEIR ORIGINAL ORDER.
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OCONEE NUCLEAR STATION UNIT 1 REACTOR 3UILDING POST-TENSIONING SYSTEM END ANCHORAGE SURVEILLANCE a
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APRIL 23, 1974 REGULATORY DOCKETFILE COPY 3
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1
1.0 INTRODUCTION
1 The end anchorage concrete surveillance program for the Oconee Nuclear Station, Unit'l reactor building post-tensioning system was defined and is executed in order to assure the continued structural integrity of the Reactor Building.
The program consists of periodic inspec,tions of selected end anchorages and adjacent concrete surfaces.
The requirements for the program are detailed in the Oconee Nuclear Staticn, j
Units 1 and 2,~ Technical Specification 4.4.2.3.
The inspection interval, as specified therein, will be one-half year and one year after the operation j
of the unit and will occur during the warmest and coldest part of the year.
Consequently, the specified surveillance was performed on July 26 and 31, 1973 and January 23, 1974. Results were compared with similar surveillance per-formed during the Reactor Building Structural Integrity Test of July 29 through August 4,1971.
Surveillance was conducted in accordance with approved test procedure TP/1/B/
0150/13 Prestressing Tendon Anchor Zone Surveillance Program, and the results of th s program are reported herein.
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SUMMARY
AND CONCLUSIONS The inspections at the one-half year and one year intervals after operation were performed as specified during the warmest and coldest part of the year.
Due to a very mild winter, there was little difference in outside air tem-peratures during the inspections.
Visual inspection of the end anchorage exterior surfaces revealed no symptoms of abnormal cracking or deterioration.
Measurements of tendon anchor movement showed no abnormal motion during che surveillance program.
Based on the tests and inspections described herein, it is concluded that greater than nor=al cracking or movements have not occurred and that the functional capability of this portion of the post-tensioning system has not diminished. Therefore, the requirements of Technical Specification 4.4.2.3 have been completed, i
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3.0 RESULTS 3.1 END ANCHORAGE CONCRETE SURVEILLANCE Six locations along the 90* buttress and one location on top of the ring girder in line with the 90* buttress were selected and examined during the Each of these areas were Reactog Building Structural Integrity Test.
selected after an overall visual inspection of the accessible buttress areas.
Results of inspections made during the Reactor Building Structural Inte ri:-;
m Test and at the one-half year and one year intervals following initial operation, are presented in Table 1.
3.2 TENDON ANCHOR MOVEMENTS Position measurements for three of the tendon anchors were made during the Reactor Building Structural Integrity Test and at the one-half year and one year intervals following initial operation. Results of these measurementt, are given in Table 2.
Details of the denountable reference frames and the location of measurements are shown on Figure 1.
1
TABLE 1 CONCRETE CRACK DATA AT PRESTRESSING TINDON ANCHORS RB RB Tenperature (*F)
Pressure Observed Frame Elevation Date Inside
- Outside (Psig)
Condition 1
810 7-28-71 78 0
No Surface Crac'cs 7-30-71 78 72 29.5 No change 8-1-71 78 73 48 No change 8-1-71 83 84 68 No change 8-2-71 83 73 59 No change 8-3-71 82 73 30 No change 8-3-71 82 90 0
No change 7-26-73 98 74 0
No change 1-23-74 75 73 0
No change 2
835 7-28-71 78 0
Small crack (0.002")
and some spalling 7-30-71 78 72 29.5 No change 8-1-71 78 73 48 No change 8-1-71 83 84 68 No change 8-2-71 83 73 59 No change 8-3-71 82 73 30 No change 8-3-71 82 90 0
No change 7-26-73 98 74 0
No change 1-23-74 75 73 0
No change 3
860 7-28-71 78 0
Several small cracks (0.002" x 4" max.)
7-30-71 78 72 29.5 No change 8-1-71 78 73 48 No change 8-1-71 84 84 68 No change 8-2-71 84 73 59 No change 8-3-71 83 73 30 No change 8-3-71 83 90 0
No change 7-26-73 98 74 0
No change 1-23-74 75 73 0
No change 4
890 7-28-71 79 0
Some spalling on bearing plate 7-30-71 79 72 29.5 No change 8-1-71 79 73 48 No change 8-1-71 84 84 68 No change 8-2-71 84 73 59 No change 8-3-71 83 73 30 No change 8-3-71 83 90 0
No change 7-26-73 98 74 0
No change 1-23-74 75 73 0
No change
RB RB Tenperature (*F)
Pressure Observed Frace Elevation Date Inside*
Cptside (Psig)
Condition 5
920 7-28-71 79 0
No initial cracks 7-30-71 79 22 29.5 No change 8-1-71 79 73 48 No change 8-1-71 84 84 68 No change 8-2-71 84 73 59 No change 8-3-71 83 73 30 No change 8-3-71 83 90 0
No change 7-26-73 98 74 0
Hairlina crack :n buttress face 1-23-74 75 73 0
No change O
2 stall cracks 6
940 7-28-71 83 (0.002" x 6")
7-30-71 83 72 29.5 No change 8-1-71 83 73 49 No change 8-1-71 85 84 68 No change 8-2-71 85 73 59 No change 8-3-71 84
' 73 30 No change 8-3-71 84 90 0
No change 7-26-73 98 74 0
Chip found on exterior face of RB shsll 1-23-74 75 73 0
No change 7
970'8" 7-28-71 85 0
No initial cracks; (Vertical) surface conced 7-30-71 85 72 29.5 No change 8-1-71 84 73 48 No change 8-1-71 86 84 68 No change 8-2-71 86 73 59
.No change 8-3-71 85 73 30 No change 8-3-71 85 90 0
No change 7-26-73 98 74 0
No change 1-23-74 75 73 0
No change
- RB temperatures (inside) were derived from data given in the Oconee Nuclear Station, Unit 1 Integrated Leak Rate Test Report, October 29, 1971.
- Data not taken.
TABLE 2 PRESTRESSING TENDON ANCHOR MOVEMENTS RB Exterior RB Eleiation Temperature Pressure Micrometer Readines (In.)
(Feet)
Date~
(*F)
(Psig) 1 2
3 4
810 7-28-71' 0
4.441 2.735 4.077 4.012 7-30-71 72 29.5 4.441 2.735 4.050 4.009 8-1-71 73 48 4.441 2.735 4.082 4.012 8-1-71 84 68 4.441 2.735 4.080 4.009 8-2-71 73 59 4.441 2.740 4.078 4.G09 i
8-3-71 73 30 4.441 2.735 4.07S 4.009 8-3-71 90 0
4.441 2.738 4.080 4.012 7-31-73 73 0
4.426 2.748 4.074 3.998 l-23-74 73 0
4.411 2.738 4.075 4.000 940 7-28-71 O
4.670 4.548 4.029 3.693 7-30-71 72 29.5 4.670 4.547 4.034 3.690 8-1-71 73 49 4.670 4.545 4.032 3.690 68 4.670 4.548 4.032 3.690 l
8-1-71 84 8-2-71 73 59 4.670 4.552 4.036 3.693-8-3-71 73 30 4.670 4.552 4.034 3.693 8-3-71 93 0
4.665 4.552 4.036 3.693 7-31-73 73 0
4.672 4.547 4.035 3.700 j.
1-23-74 73 0
4.654 4.567 4.025 3.679 Dome 7-28-71 0
5.392 4.899 4.991 7-30-71 72 29.5 5.392 4.899 4.991 8-1-71 73 48 5.392 4.899 4.991 i
8-1-71 84 68 5.392 4.899 4.991 4
8-2-71 73 59 5.392 4.899 4.991
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8-3-71 73 30 i
8-3-71 90 0
5.392 4.899 4.991 7-31-73 73 0
5.394 4.902 4.992 1-23-74 73 0
5.404 4.966 4.952
- Data not taken.
- Data not recorded due to rain and insecessibility of crane.
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Figure 1 GREASE CAP
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