ML20237C886
| ML20237C886 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/01/1983 |
| From: | Felder A PRECISION SURVEILLANCE CORP. (FORMERLY INRYCO, INC.) |
| To: | |
| Shared Package | |
| ML20237C867 | List: |
| References | |
| NUDOCS 8712220240 | |
| Download: ML20237C886 (295) | |
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ENGINEER 1rlG FILE NUMBER: h
- h. J Inryco an Inland Steel company Main 10 YEAR PHYSICAL SURVEILLANCE OF THL ARKANSAS NUCLEAR Title ONE - UNIT 1 PRIMARY REACTOR CONTAINMENT BUILDING m
T e ' SURVEILLANCE REPORT BY ANTHONY L. FELDER, P.E., SUPERVISOR, NUCLEAR ENGINEERING ENGINEERING DEPARTMENT ' c CONCRETE SYSTEMS DIVISION - ABSTRACT l This report presents the findings of the ten year physical tendon
. surveillance of Arkansas Nuclear One - Unit 1. Based on the results of this surveillance, no abnormal degradation of the containment post tensioning ,
is evident. REVIs!ON. CONTROL LOG Rev. By e Pages Affected 6/29/83 I,$ 1 thru iv,1 thru 27, A-1 thru A-3, B-1 thru B-40, C-1 thru C-ll, D-1 thru D-27, E-1 thru E-28, F-1 thru F-23, G-1 thru G-24, H-1 thru H-34, I-1 thru I-28, J-l thru J-5,' K-1 thru K-13, L-1 thru L-15, M-1 thru M-7, N-1, N-2 8/1/83 dN ii, iii, 2, 4, 7 thru 29, i a .
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l INRYCO, Inc. - 10 YEAR PHYSICAL TENDON SURVEILLANCE OF THE ARKANSAS NUCLEAR ONE - UNIT 1 PRIMARY REACTOR CONTAINiiENT BUILDING D
SUMMARY
. The purpose'of this report was to investigate the present condition of the post: tensioning system of the Arkansas Nuclear One - Unit 1 Primary Reactor Containment Building. The results of this investigation were as follows:
- 1. - The sheathing filler had acceptable levels of ions (chlorides, nitrates, sulfides) and water.
- 2. All anchorage' components except the shop greasing cap of tendon V25 had adequate filler coverage. The lack of coverage for the grease cap was b not deemed serious (See Section III).
- 3. The corrosion level of all the anchorage components was found to be mostly Level 1 (bright metal, no rust), with a small amount of Level 2 (reddish brown, no pitting) present.
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- 4. It was determined that hydraulis. stressing jack 17240-0 was in a properly .
calibrated state throughout the surveillance. Jack 17240-l's ram area apparently decreased by 2.34% during the course of the surveillance. However, this jack had acted erratically in the past so its behavior was not considered unusual. As a conservative measure, its smaller calibrated
~ ram area.was used to determine its jack force. After awhile, Jack 17240-2 a was unable to sustain internal pressure and so was sent to Inryco for
" . repair and recalibration. It was determined that an internal seal for g , the jack was installed backwards, although this condition had no adverse effect on the surveillance. Its recalibration was found acceptable.
- 5. The normalized liftoff force for all the tendons exceeded the minimum limits. This included tendon 32H43 which was inadvertently lifted off ^
-b and tendon.32H14 which initially was believed low.
g 6. Only four wires were found to have anomalies. These anomalies, which were judged to be inconsequential to the post tensioning system, included: a i wire which wasn't present at the field end but was present at the shop end (32H14), one wire not buttonheaded at the field end (32H15), and two wires which were sheared off during detensioning (3D102).
- 7. All wires tested exceeded 'the minimum of 192 KSI yield, 240 KSI ultimate, and 4% elongation.
- 8. Comparison with past surveillance presented no evidence'of system !
-degradation. i Based on the results of this ten-year tendon surveillance test report herein,
. the conclusion is reached that no abnormal degradation of the containment structure is indicated for Arkansas Nuclear,One - Unit 1.
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ms . - wa w.y. m - ,~.m. - - - . INRYCO, Inc. 10 YEAR PHYSICAL TENDON SURVEILLANCE OF THE ARKANSAS NUCLEAR ONE - UNIT 1 PRIMARY REACTOR CONTAINMENT BUILDING h TABLE OF CONTENTS List of Illustrations ................................................... iii Introduction ............................................................ iv l l I. Surveillance Procedures .......................................... 1 l II. Sheathing Filler ................................................. 1 l III. Anchorage Components ............................................. 4
/fs IV. Hydraulic Jacks, Tendon Lif tof f Force & Normalizing Factor . . . . . . . 8 V. Discontinuous or Missing Wires .................................... 16 VI. Wire Inspection and Testing ...................................... 16 j{g VII. Tendon Retensioning and Resealing ................................ 18 VIII. Comparison with Previous Surveillance ........................... 21 Conclusions .....................................................,c....... 28 Notes on Table II ....................................................... 7 Notes on Table III ...................................................... 15 Ii
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) Notes on Table V ........................................................ 20 hh/ List'of References ...................................................... 29 APPENDICES A. 10 Year Surveillance Tendon Locations ............................... A-1 B. Arkansas Power & Light - Arkansas Nuclear One - Unit 1
, Surveillance Procedure (1304.91, Rev. 3) ............................ B-1 C. Inryco Jack Calibration Procedure ................................... C-1 D. Sheathing Filler Removal & Installation Data Sheets ................. D-1 E. Tendon End Anchor Data Sheets ....................................... E-1 F. Tendon Detension & Retension Force & Elongation Data Sheets ......... F-1 G. Neutralization Factor & Force Calculation Worksheets ................ G-1 H. Hydraulic Jack Calibrations ......................................... H-1 1
I. Gauge Calibrations .................................................. I-l J. Wire Inspection Data Sheets ......................................... J-l K. Tendon Wire Test Data Sheets .......................t................ K-1
. L. Laboratory Analysis of Sheathing Filler ............................. L-1 I \
% n.s/ M. Material Certifications ............................................. M-1 i) N. Proposed Revision to the ASME Section III Division Code ............. N-1 ) l 1 ii )
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a-c _ - -_ _.. . . ,__ , INRYCO, Inc. --- 10 YEAR PHYSICAL TENDON SURVEILLANCE OF THE ARKANSAS NUCLEAR ONE - UNIT 1 PRIMARY REACTOR CONTAINMENT BUILDING e9, c l LIST OF ILLUSTRATIONS 1 TABLES 1., Laboratory Analysis of Sheathing Filler ........................... 3 II. Stnm=ary of Tendon End Anchorage Inspection ........................ 5 III. Summary of Force and Elongation Data During Detensioning - 1983 ............................................... 14 IV. Wire Test Results ............................'..................... " 17 V. Summary of Force and Elongation Data During Retensioning - 1983 ............................................... 19 Ihi VI. Summary of Force and Elongation Data During Detensioning - 1975 ............................................... 22 VII. Sum =ary of Force and Elongation Data During Detensioning - 1977 ............................................... 23 VIII. Summnry of Force and Elongation Data During . r ~g Detensioning - 1979 ............................................... 24 6 .]
- W FIGURES
- 1. Normalized Liftoff Forces - Vertical Tendo'ns .,.................... 11
- 2. Normalized Lif toff Forces - Horizontal Tendons .................... 12
- 3. Normalized Lif to f f Forces - Dome Tendons . . . . . . . .. . . . . . . . . . . . . . . . . . 13 j{$
- 4. Cummulative Normalized Liftoff Forces - Vertical Tendons .......... 25
- 5. Cummulative Normalized Liftoff Forces - Horizontal Tendons ........ 26
- 6. Cummulative Normalized Lif tof f Forces - Dome Tendons . . . . . . . . . . . . . . 27 e-)
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IN RYC O, Inc. 10 YEAR PHYSICAL TENDON SURVEILLANCE OF THE ARKANSAS NUCLEAR ONE - UNIT 1 PRIMARY REACTOR CONTAINMENT BUILDING
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9 INTRODUCTION This report covers the ten-year reactor building tendon surveillance for the Arkansas Nuclear One - Unit 1. The reactor building tendon program is a systematic means of assessing the continuing quality and structural performance of the post tensioning system. The ten-year tendon surveillance is the fourth in a series with the previous tests having been performed one, three, and five years after the structural integrity test (SIT). Additional tests are scheduled at every five years after this fourth surveillance. The tendon surveillance consists of a periodic inspection for physical condition of a randomly selected group of surveillance tendons. This provides confidence in the condition and functional capability of the system and an opportunity for timely corrective measures if adverse conditions are detected. Tendon surveillance testing consists of sheathing filler and anchorage inspection, tendon liftoff force measurement, tendon wire continuity testing, tendon wire' inspection and tensile testing, and tendon retensioning and rescaling. c This ten-year tendon surveillance of the Arkansas Nuclear One
- Unit 1 reactor building post tensioning system began in February , 1983, (approximately 111 months af ter completion of the structural integrity test performed in November, 1973) and was completed in March, 1983. The surveillance was co -
- t ducted in accordance with " Reactor Building Tendon Surveillance Procedure", i Operating Procedure No. 1304.91, Revision No. 3.
A copy of that test procedure is included in this repo,rt as Appendix B. The I group of three vertical, three dome, and four hoop. tendons was selected for inspection in compliance with NRC Regulatory Guide 1.35 (Rev. 2, January 1976) . The location and identification of the surveillance tendons are shown in Appendix A. Inryco services were provided under the AFL/Inryco Operating Services Contract, Number I-053A, and included manual labor and materials ! required for the tendon surveillance. Arkansas Power and Light Company I furnished the equipment required for the surveillance. It should be noted that of the four hoop tendons selected, one was a special case. This tendon, 32H14, was not to be a full surveillance tendon. Rather, only a lif tof f was to be performed on it. This action was recommended in light of the past dif ficulties in surveying 32H14. Initially, the lif tof f for this tendon was believed low so its adjacent tendons, 32H13 and 32H15, were z$h designated to be full surveillance tendons. It should be noted that this decision was also made in light of 32H14's past history.
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INRYCO, Inc. 1 10 YEAR PHYSICAL TENDON SURVEILLANCE OF THE ARKANSAS NUCLEAR ONE - UNIT 1 PRIMARY REACTOR CONTAINMENT BUILDING hLs] I. SURVEILLANCE PROCEDURES Appendix B contains the detailed procedure for conducting the tendo'n surveillance. Basically, the surveillance will consist of the following:
- 1. Visual and laboratory examination of sheathing filler samples f from each of the surveillance tendons.
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- 2. Inspection of the anchor assembly of each of the surveillance tendons for deleterious conditions such as corrosion, cracks !
missing and broken wires or of f size buttonheads.
- 3. Measurement of the liftoff force for each of the surveillance tendons.
- 4. Detensioning of each of the surveillance tendons and checking wire continuity by pulling wires and observing their movement at the opposite end. The wire continuity check will only be performed if a visual inspection of the tendon anchor determines that a continuity check is required.
5.. Removal of a minimum of one wire from one surveillance tendon. O of each group. i.e., hoop, vertical and dome, for examinati6n
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% and testing.
- 6. Retensioning of each of the surveillance tendons to the liftoff -
force measured in Section 3 above less the effect of any wires removed, and measuring the corresponding tendon elongation.
- 7. Visual inspection for corrosion, pitting or any significant !
physical change of wires removed from tendons.
- 8. Testing of wires removed from tendons for yield strength, ultimate strength, and percent elongation.
- 9. Evaluation of test and inspection results to assess the general condition of the post tensioning system and evaluate time dependent factors such as prestress losses and corrosion.
II. SHEATHING FILLER A sample of sheathing filler was removed from each end of each surveillance tendon. Chemical tests were performed on one sample for each tendon. The sample analyzed was selected arbitrarily from the tendon shop or field end with an effort made to use approximately , the same number of shop and field end samples.* Chemical tests on the ; second sample from a tendon were required only if the results of the ! tests on the first sample failed to meet the acceptance criteria o,f b Paragraph 11.0 of Operating Procedure 1304.91.
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II. SHEKt'i!MG htLER,.,Nont / ; mxi=u,m 1b t .ugtance limits of 10 percent by weight for' v& ater and 10 parts, per mi.hlion for water-soluble chloride't/,,ltetrades, rand sulfides ; vere established in Section 9.3 of Operatingctrocedure 1304.91.
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i Those limits /Ot9ater-soluble " ions are the same ns given bv. ASME Section III, Di>ision 2, Code for Cor.prete Reactor Vessel.t [j nd ; Containments _, for new sheathinE fill er while no litrp.t for wey ,s
' contrnt is given by the ASME cof tt. ll samples ten W.tr.pt'th=.i '
( act;epcance critetia for water and wr@t,r -soluble
'In;ioqs;results
'/. ' E 4 laboratory analysis of the sheatiing fille.r are ilpv4pfed in
, Table I, and the sheathing filler removaY rad insdGDtYp data y
shnets are in Apt /iadix D of this report; aSheathing anb rdis reppias ,
, j; , l i h p.jareaso in'Aqq/ndix L.
,s "ihe nautralizatim test is guerally cun by grease manufacturers
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d %s nef ba'tchei.s of prodact. IE is a'rethod of determining the , y, J eve bre additives in the gream. 'n b adation of the,tnaathing - V 4 y fi'ller will yield a change in h eidity of the material and would I
- be do ected as an increase in ion content (chlorides, nfrcates, L .
and su? fides). Up;until this survehld;e,t, the neutralization - numb O suas tested tor as per ASTM Dfi'e4'. Currentis, there is q
+ revisits bein d mesidered to the ASME Section TM Division 2' -
y '] Code (Apphdix M wquiring the neutralization uceer t( be - 9 > s tested' fort $ per.tSTM D974 - Modified. This ru{ talon also would 4 ,/ 'J
" plan a 1.'Ut on tSte.' neutralization nwaber as thil as water content. J" .
LWen M ou'tn 'tois requirement wat J Aot in fo de'ar this tism it was I' decided td test Mor the neutralization uusber per three o n Mds (ASTM D64? , . A'mi 1974, A345 fgU , < ndified) so as to devglot a I historical base fhe the futst:t. <
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' . The greans samples tahn from tendda V73 were very tan in colu. <
J Iso ound4 2 of water vere found >in rne f$i.1d (Gallery) end. Three ' samples Une shop, two field) were tak O anl' tested. All thre9 , ,'
-samples analyzed were 16und acceptabJf ulthca& the two samples i a frb ftfue field end had high watar content (') .7%, 9.9% comparedL to /
O u d yimum allowable of 10.3%f.- A wire sample was removed for tersile' rests and found acceptable. 'C a f .' f 4
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INRYCO. Inc. 10 YEAR PHYSICAL TENDON SURVEILLANCE OF THE ARKANSAS NUCLEAR ONE - UNIT 1 PRIMARY REACTOR CONTAINMENT BUILDING hI w III. ANCHORAGE COMPONENTS . The anchorage components were inspected after end cap removal to i determine whether sheathing filler coverage was adequate. In ! $ every case but one (shop cap of V25 had no coverage), the anchorage icomponents were covered by the sheathing filler. After the sheathing filler was cleaned off, the anchorage components were inspected for l corrosion, cracks, and buttonhead size and condition. Corrosion of anchorage components was found to be either corrosion level No. 1 -
" Bright metal, no visible oxidation" or corrosion level No. 2 -
" Reddish brown, no pitting" in every case. No cracking of anchor heads, shims, or bearing plates was apparent, only four split buttonheads were found. ,
A tabulated summary of the tendon end anchorage inspection results is given in Table II with the complete set of data sheets included as Appendix E.
't It should be noted that the lack of coverage for the can of tendon V25 is not considered serious as that the corrosion level was no worse than #2 (reddish brown no pitting). Proper rescaling of V25 b , assured adequate filler coverage. .
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.5 10' YEAR PHYSICAL TENDON SURVEILLANCE OF THE ARKANSAS NUCLEAR ONE - UNIT 1 PRIMARY REACTOR CONTAINMENT BUILDING i _
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. TABLE II:
SUMMARY
OF TENDON END ANCHORAGE INSPECTION I . y - 88 _88_ _88_ _88__88_S_ _E _88_ g,g 8_ 8_8_8_ _8 8_ . _8 8 _88_ 8__8__ '.l 2 < < g < o= o*u :
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INRYCO, Inc. l 6 1 10 YEAR PHYSICAL TENDON SURVEILLANCE OF THE APJANSAS NUCLEAR ONE - UNIT 1 PRIMARY REACTOR CONTAINMENT BUILDING [ \, t e bg.-) TABLE II:
SUMMARY
OF TENDON END ANCHORAGE INSPECTION (CONT.) 45. U
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INRYCO, Inc. 4 e i 10 YEAR PHYSICAL TENDON SURVEILLANCE OF THE ARKANSAS d NUCLEAR ONE - UNIT 1 PRIMARY REACTOR CONTAINMENT BUILDING e NOTES ON TABLE II l a l.
- 1. Corrosion levels are synbolized as follows:
I 1 = Bright metal, no visible oxidation 2 = Reddish brown, no pitting-.
- 'i 3 = '0"< Pitting.( .003" -
4 = .003"< Pitting ( .006" ,_ 5 = .006"< Pitting ( .010" l '
- 2. Tendon end defined as follows: , ,
S = Shop End (top for verticals) l F = Field End (bottom for verticals) ,
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- 3. ,N/A = Not applicable (there are no shims on the field end of the *
,g vertical tendons).
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- 4. For 32H14: One wire missing at field end but present (with wire
-l wrapped around it) at shop end.
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- 5. N/A = Not applicable (tendon 32H14 was not retensioned).
I l- 6. For 32H15: One wire not buttotiheaded at field end.
- 7. N/A = Not applicable (tendon 32H43 was needlessly selected to be surveillance. Consequently, it was only partially investigated).
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INRYCO, Inc. -- 8 10 YEAR PHYSICAL TENDON SURVEILLANCE'0F THE ARKANSAS NUCLEAR ONE - UNIT 1 PRIMARY REACTOR CONTAINMENT BUILDING a b IV.
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HYDRAULIC JACKS, TENDON LIFT 0FF FORCE & NORMALIZING FACTOR Inryco has developed a program for calibrating hydraulic jacks utilizing regression analysis (see Appendix C). This is a process whereby a straight line is mathematically best-fitted to a set of data points (in this. case, force vs gauge pressure). Complete
- , calibrations of all the hydraulic jacks used are contained in Appendix H with the gauge calibrations in Appendix I.
Results of the jack cala'brations were as follows:
- 1. INITIAL FINAL 1
Jack Date Area Const Date Area Const 17240-0 2-16-83 210.812 +4.345 3-8-83 209.837 -5.402
- 17240-1 2-16-83 216.898 -6.261 3-10-83 211.820 -6.528 17240-2 2-16-83 219.454 -10.719 5-19-83 212.738 -3.777 l
l Note that the force exerted by a, jack can be calculated as follows: b Force = Area x Pressure + Const (K) (IN2) (KSI) (K) s l Notes on each jac c: 17240-0 A before vs af ter comparison shows this jack's ram area to apparently decrease by .46%, which is cionsidered normal and acceptable. l. 1 1 ' 17240-1 Af ter tensioning was completed on Unit 1, the jacks were - recalibrates. The ram area of Jack 17240-1 had apparently decreased by 2.34%. Repeated calibrations confirmed that I the ram area was indeed roughly 211 square inches. At first, it was felt that the 2-16-83 calibration might have l been in error but investigation of the past surveillance lJ revealed the.following: 17240-0's ram area apparently decreased by 2.6% during the first year surveillance, held
- fairly constant during the third, and increased by 3.3%
during the fifth. In light of its past behavior, its current behavior should not have been unexpected. As a conservative measure, it was decided to use the jack's
- final calibration to determine the forces exerted by this jack. This calibration indicates a smaller ram area and therefore will calculate a smaller force.
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} 10 YEAR PHYSICAL TENDON SURVEILLANCE OF THE ARKANSAS ) . NUCLEAR ONE - UNIT 1 PRIMARY REACTOR CONTAINMENT BUILDING
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b IV. HYDRAULIC JACKS, TENDON LIFTOFF FORCE & NORMALIZING FACTOR, Cont. 17240-2 While taking the initial liftoff of Tendon V73 at the shop end, it was noticed that Jack 17240-2 had difficulty f maintaining its gauge pressure. A new initial liftoff was I taken with Jack 17240-1 and 17240-2 was sent to Inryco for repair and recalibration. Jack 17240-0 was calibrated on site and served as a replacement for 17240-2. It was determined that a seal for 17240-2 was installed backwards which eventually led to its inability to ' maintain gauge pressure. It should be noted that up until
/{h this point, jack 17240-2's performance was not affected.by this condition. Under the circumstances, its new calibration is considered acceptable.
The liftoff test was used to measure tendon prestress force applied to the structure. To aid interpretation of lif toff force data, the measured lif tof f force was converted to a normalized lif toff force per wire by multiplying the measured lif toff force by acnormalizing factor and dividing it by the number of effective tendon wires. The normalizing factor accounts for the original tensioning force being slightly different from the specified nominal value and for the elastic losses resulting from the tendon tensioning sequence. (See qf ) Appendix B for normalizing factor computation procedure). The normal-2/ ized liftoff forces per wire are plotted on Figures 1, 2 and 3. The value plotted for each hoop and dome tendon is the arithmetic average of the forces at the two ends. All tendon liftoff forces were acceptable'. In addition to liftoff force measurements, data were recorded for' tendon elongation during detensioning. The force and elongation data are summarized in Table III, and the field data sheets are included in Appendix F. Initially, it was believed that the initial liftoff of Tendon 32H44 was low, so work began to take a lif toff of Tendon 32H43 (to be followed by 32H45). By the time 32H43 had a lif tof f performed, - it was discovered that 32H44 actually was not low. Consequently, work was terminated on Tendon 32H43. Using normalizing f actors from' the fif th year surveillance, it was determined that the initial liftoff of Tendon 32H14 was low. This led to the decision of taking lif tof fs on the adjacent tendons: 32H13 and 32H15. It was then realized that the normalizing f actors of the first and third year were calculated with formulas which have since been l altered. Remember, however, that a normalizing factor calculated during any one surveillance will be directly used to calculate the fj) 7( factor for that same tendon when it is surveyed next. Therefore- I it is important that all the normalizing f actors from all the surveillance be calculated f rom the same formulas.
_,.7 _ _ _ _ _ . - - - , - - - _ . _ - - - - - - - . , ,m .- , , y, .
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INRYCO, Inc. - 10 f' 10 YEAR PHYSICAL TENDON SURVEILLANCE OF THE ARKANSAS NUCLEAR ONE - UNIT 1 PRIMARY REACTOR CONTAINMENT BUILDING
/$1. IV. HYDRAULIC JACKS, TENDON LIFTOFF FORCE & NORMALIZING FACTOR, Cont.
This led to the Inryco Engineering Report #314 (Ref. 4). This report presents a recalculation of the normalizing factors and normalized forces for all surveyed tendons during the first, third and fifth year surveillance for Unit 1. Utilizing the normalizing factors from this report -it was determined that the initial lif toff force of 32H14 was indeed acceptable. At this point, it was decided to make 32H13 and_32R15 full surveillance tendons. It should be noted that the decision to 2dh make 32H13 and 32H15 full surveillance tendons was also due to the past history of 32K14. , In order to provide a common base for comparison, tendon liftoff forces'must be normalized to account for the following:
- 1. Elastic stress loss during initial installation (a function of the post tensioning sequence).
The liftoff force deviation from the average lifioff force 2. in the' tendon group (dome, ho'op and vertical tendons).
- 3. The number of effective tendon wires at initial installation.
kh- - As was mentioned earlier, the formulas for calculating the normalizing
' factors / forces are contained in Appendix B. Calculation worksheets were developed to facilitate computation (See Appendix G). Data for
- the computations were obtained from several sources:
-1. Letter from' APL's Mike Coombs to Inryco's Harry Hendrickson (2/15/83). .
For clastic shortening losses and poissons ratio.
- 2. Inryco Engineering Report #314 (Ref. 4).
For number of tendons stressed before any particular one, original stressing jack calibrations, plus blank calculation worksheets.
- 3. Original stressing cards.
For original stressing data.
- 4. First, third, and fifth year surveillance reports (Ref. 1, 2 & 3).
For number of effective wires and liftotf forces during these surveillance. 1
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10 YEAR PHYSICAL TENDON SURVEILLANCE OF THE ARIOdSAS 12
- NUCLEAR ONE - UNIT 1 PRIMARY REACTOR CONTAINMENT BUILDING i FIGURE 2: NORMALIZED LIFTOFF FO'RCES - HORIZONTAL TENDONS h"
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- 10 YEAR PHYSICAL TENDON SURVEILLANCE OF THE ARKANSAS
- NUCLEAR ONE - UNIT 1 PRIMARY REACTOR 'CONTAIDIENT BUILDING
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15 10 YEAR FHYSICAL TENDON SUR'/EILLANCE OF THE ARKANSAS
. NUCLEAR ONE - UNIT 1 PRIMARY REACTOR CONTAINMENT BUILDING w ,
NOTES ON TABLE III'
- l. Elongation is defined as the distance from the outside face of the bearing plate to the inside face of the anchorhead.
- 2. Total elongation is the sum of the elongations at each end.
- 3. Tendon end defined as follows:
S = Shop End (top for verticals) F = Field End (bottom for verticals)
,c
- 4. For 32H14': Only' initial liftoff performed.
- 5. For 32H43: Needlessly selected to be surveillance. Consequently. -
g . it was only partially investigated.
- 6. For 3D102: Two wires broke at field end shdrtly after initial liftoff. Wires vere sheared due to' cocked shims.
Both wires were selected for tensile tests. m e e w l i ,r.,y G M
, INRYCO, Inc.
16 10 YEAR PHYSICAL TENDON SURVEILLANCE OF THE ARKANSAS NUCLEAR ONE - UNIT 1 PRIMARY REACTOR CONTAINMENT BUILDING g., ,
. T,
) ~
V. DISCONTINUOUS OR MISSING WIRES Four wires from a total of' thirteen tendons surveyed showed anomalies.
/$i These anomalies' were judged to be inconsequential to the overall tendon j system:
32H14 One wire is missing from the field end but is present (with a wire wrapped around its buttonhead) at the shop end. 32H15 One wire was not buttonheaded at the field end. 3D102 Af ter initial lif toff, just before the shima were to be removed, two wires broke. It had been observed that the shims had been initially cocked and it was this condition that led to the wires being sheared. Both wires were subjected to tensile tests and found acceptable. VI. WIRE INSPECTION AND TESTING One inspection wire was removed from tendons 32H44 and V73 while the two wires that broke in tendon 3D102 were also tested. All wires removed were inspected and had no visible corrosion at the time of removal from the tendons. The wire inspection data
, sheets are included in Appendix J. Wire samples were field tested 1&q / according to ASTM A421-74 which specified a minimum yield strength
-UGA
/Ds of 192,000 psi at 1% extension, a minimum ultimate strength of 240,000 pai, and elongation at failure greater than 4.0%. The only deviation from A421-74 was that a gage length of 100 inches, not 10, was used. Details of the field wire test results are given in Table IV. The wire test data sheets are included in Appendix K.
~
All wire samples exceeded the minimum values and were therefore found acceptable. Jack 7702 was used for conducting tensile tests on individual wires. Results of its calibrations were as follows: INITIAL FINAL 22b Date Area Const. Date Area Const. 1-25-83 1.554 +.298 5-23-83 1.562 +.214 A before vs after comparison shows the jack's ram area to apparently _ increase by .51%, which is considered normal and acceptable. d t4cTC (:oftrihT C.HANCnE L_ __ - - _ . _ ra a+rve am-
_. . . . - . . . ~ . -, ~ IN RYCO. Inc. 17 10 YEAR PHYSICAL TENDON SURVEILLANCE OF THE ARKANSAS NUCLEAR ONE - UNIT 1 PRIMARY REACTOR CONTAINMENT BUILDING
~
TABLE IV: WIRE TEST RESULTS SAMPLE 1% YIELD TENSILE SAMPLE LENGTH STHENGTH STRENCTH 2 1 ELONCATION FAILUME TENDON NO. (lN) (KSt) (KSI) (IN/IN) LOCATION 3D102 IB 100.125 226 268 4.02 M 28 100.0 227 266 4.59 M 3B 99.75 229 270 ' . 54 4 M IC 99.75 225 261 4.66 M 2C 99.625 227 265 4.67 M i 3C 99.75 226 262 4.54 M l l 32H44 ' ID- 99.75 223 260 4.54 H 2D 99.5 222 261 4.92 M La 3D 99.0 222 258 5.20 M ($' V73 1A 99.875 223 268 4.66 M 2A 99.5 226 267 *5.43 H 3A '99.75 223 268 5.66 M MINIMUM 192 KSI 240 KSI (ASTM A421) NOTES: 1. I ELONCATION CALCULATED AS FOLLOWS,: . g (READINC @ FAILURE) - (READINC 0 YIELD) + .9% CACE LENCTH CACE LENGTH
- 2. FAILURE LOCATION:
BH = WLTH1N 1 INCH OF BUTTONHEAD M = MORE THAN 1 INCH FROM BttrTUNHEAD bh h A 'l L-i 't . i Q w , PA4t C.HA % c
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INR YCO, Inc. T 18 e 10 YEAR PHYSICAL TENDON SURVEILLANCE OF THE ARKANSAS ' NUCLEAR ONE - UNIT 1 PRIMARY REACTOR CONTAINMENT BUILDING e VII. TENDON'RETENSIONING AND RESEALING The surveillance tendons were retensioned to a force per wire equal
, to 80% of its ultimate tensile strength. In all cases, additional shins were required to obtain the needed force. Elongation measure-ments were taken during retensioning. A summary of the force and elongation date during retensioning is given in Table V with the
[ field data records included in Appendix F. After each tendon was retensioned, the grease cap was reinstalled and new sheathing filler was pumped or, poured into the tendor sheath to replace that which was removed during t,he surveillance test. .The data sheets for sheathing filler removal and installation are included in Appendix D. i l l' e to e w
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19 10 YEAR-PHYSICAL TENDON SURVEILLANCE OF THE ARKANSAS
. NUCLEAR ONE - UNIT 1 PRIMARY-REACTOR CONTAINMENT BUILDING .
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' 10 YEAR PHYSICAL TENDON SURVEILLANCE .0F THE ARKANSAS .
, NUCLEAR ONE - UNIT 1 PRIMARY REACTOR CONTAIN>ENT BUILDING NOTES ON TABLE V .,
- 1. Elongation is defined as the distance from the outside face of the bearing plate to the inside face of the anchorhead.
- 2. Total elongation is the sum of_the elongations at each end..
- 3. Change of elongation between distressing and res'tressing for this surveillance.
- 4. Tendon end defined as follows: ,
'S = Shop End (top for verticals) .
F = Field End (bottom for verticals)
- 5. .For 32H14': Only initial liftoff-performed. '
. 6. For_32H43: Needlessly selected to be surveillance. Consequently, it was only partially investigated.
- 7. For 3D102: Two wires broke at field end shortly after initial liftoff.
Wires were sheared due to cocked shims. Both wires were selected for tensile tests. o e M em> g . .. g h
2., 25 10 YEAR PHYSICAL TENDON SURVEILLANCE OF THE ARKANSAS NUCLEAR ONE - UNIT 1 PRDIARY REACTOR CONTAINMENT BUILDING r t;, ,
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VIII. COMPARISON WITH PREVIOUS SURVEILLANCE Summaries of forces and elongation data during detensioning for the three previous surveillance of the Arkansas Nuclear One - Unit 1 reactor building are shown in Tables VI, VII and VIII. Comparison b of these data with the 1983 surveillance indicated no evidence of system degradation. i For additional comparison purpose, Figures 4, 5 and 6 present normalized forces per wire for the three surveillance. S e
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mrt r w. me. p~ !- 10 YF.AR PHYSICAL TENDON SURVEILLANCE OF THE ARKANSAS l NUCLEAR ONE - UNIT 1 PRIMARY REACTOR CONTAINMENT BUILDING . 7-l TABLE VI:
SUMMARY
OF FORCE AND ELONGATION DATA DURING
, DETENSIONING - 1975 l Ey ,.
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V19 S 1509 11.30 11.30 1 85 0.84 0.01 186 0.9978 8.10 8.10 2 10-73 4375 V40 S 1466 9.32 9.32 185 2.13 2.13 . 186 . 1.0044 7.92 7.92 1973 4 2-75 l V60 $ 1433 9.50 9.50 185 1.94 1.94 186 1.0139 7.81 7.81 1573 33175 l V80 S 1469 8.02 8.02 183 3.70 -3.70 186 1.0021 7.91 7.91 11073 3 26-75 V100 S 1450 10.67 10.67 185 -0.95 -0.95 186 0.9987 7.78 7.78 1573 32475 l 10320111 S 1397 4.37 8.50 185 1.50 1.59 186 1 0218 7.67 7.80 12 22 72 41575 F 1421 4.13 183 0.09 1.0377 7.93 10328111 S 1416 4.62 8.80 185 2.12 3.04 185 1.0271 7.86 2 8.01 12 26 72 +23 75 , F 1470 4.'18 187 0.92 1.0271 8.16 l 20207212 S 1470 4.41 8.80 185 1.47 2.12 186 1.0379 8.20 8.09 11573 5175 F 1429 4.39 186 0.65 1.0379 7.97 2021042 S 1443 4.36 8.44 187 0.50 1.42 185 1.0511 8.23 8.15 12 15 72 43075 F 1409 4.08 185 0.92 1.0595 8.07 'e. 3D110322 S 1350 4.79 9.54 185 0.95 2.80 185 1.0511 7.66 7.79 121572 62575 F 1372 4.75 185 1.85 1.0674 7.92 30120322 S 1407 4.80 9.30 187 0.83 2.25 186 1'.0266 7.77 7.78 124172 42875 f/ 1401 4.50 185 1.42 1.0346 7.79 21H24 S 1322 3.75 7.31 185 2.75 -7.08 186 1.0546 7.50 7.59 2273 63075 F 1355 3.56 185 4.33 1.0548 7.68 21H30 S 1375 4.68 9.32 185 2.48 -5.38 186 1.0e97 7.78 7.82 24 73 62975 F 1405 4.64 185 2.90 1.0422 7.87 21H36 S 1326 3.30 6.56 185 3.68 6.99 186 1.0358 7.38 7.53 71072 52975 F 1369 3.26 185 3.31 1.0432 7.68 31H27 S 1397 4.40 8.75 185 2.40 -4.98 186 1.0035 7.54 7.48 21973, 6-6 75 F 1342 4.35 185 2.58 1.0267 7.41 31H28 S 1401 4.36 8.50 185 Data Data- 186 1.0388 7.82 7.69 2273 51475' F 1352 4.14 183 Missing Missing 1.0388 7.55 31H29 S 1395 4.81 8.71 185 2.80 4.25 186 1.0267 7.70 7.60 21973 6-4 75 F 1348 3.90 185 2.45 1.0340 7.49 31H40 S 1354 3.26 6.57 185 3.98 7.16 186 1.0534 7.75 7.77 11 22 72 59 F 1380 3.31 185 3.18 1.0368 7.78 31H52 S 1339 3.01 6.08 185 3.62 7.87 184 1.0666 7.76 7.95 2772 5 7-75 F 1380 3.07 185 -4.25 1.0842 8.13 32H10 S 1405 4.12 8.21 185 3.35 4.46 183 1.0220 7.85 7.97 12673 52375 F 1426 4.09 182 3.11 1.0382 8.09 32H2O S 1364 4.50 8.95 187 2.85 -4.78 186 1.0518 7.71 7.89 13173 52275 F 1427 4.45 185 1.93 1.0518 8.07 k/ g 32H32 S F 1329 1326 3.43 3.32 6.75 186 185 2.51
-4.25 6.76 188 1.0453 1.0453 7.41 7.45 7.43 2972 61975 32H44 S 1364 3.10 6.15 185 3.80 4.16 185 1.0489 7.73 7.87 11 30 72 5 15-75 F 1411 3.06 186 4.36 1.0489 y 8.00
- Elongation is defined here as distance from bearing plate to stressing wesher.
** Total elongation is aurn of elongetton at the two enda. gg pyg g g-
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IN'RYCO, Inc.
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10 YEAR PHYSICAL TENDON SURVEILLANCE OF THE ARKANSAS 23 NUCLEAR ONE - UNIT 1 PRIMARY REACTOR CONTAINMENT BUILDING TABLE VII:
SUMMARY
OF FORCE AND ELONGATION DATA DURING . DETENSIONING - 1977 Uttoff L 1000 lb/ Wire , y r 3 . 5 I I j { b .i _ j 3 h E h
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.962 7.44 V56 S 1422 11.31 11.31 - 106 0.3 43 18e .961 7.36 7.35 2/B03 4/13 M V75 $ 1460 10.31 10.31 139 1.38 1.38 186 .946 7.47 7.47 2/10/73 4/13 M V95. S 1330 10.54 10.54 186 1.50 1.60 148 .960 7.06 7.06 2/993 4/12/77 1020 5 1346 4.58 198 1.57 F
9.00 1g 2.18 18e 7.31 12/2292 2/28&7 1411 4 42 Q.58 .983 7.53 1D28 3 1369 A50 ,146 2.70 g,gg 3.25 tes F 1436 A54 lee 0,53 1.009 7.58 12/18&2 3.W 7.79 2D04 3 1339 ( 36 183 0.78 .990 7.13-F 1371 1 81 g,37 191 0.3s 1.86 m 1.006 7.42 gj g 2D11 3 1422 4 32 191 0.34 M M 8.62 3,44 1,, 7.38 1/2/73 F 1341 4,30 183 1.10 .9e4 5/18/77 7.17
' DOS S 1296 5.21 183 0.77 .900
,y3 1 90 F 1337 A52 191 0.48 988 7.04 12/21/72 5/10/77 7.17 I b 3D21 3 136e A50 186 1.32 g ,,
- F 1420 4.3s 189 0.70 2.02- 11Hf 7.27 1/17 # 3 3/10/77
.900 7.48 21H42 8 1350 1 33 106 1 75 7'13 F 1390 1 75 189 2.25 4 00 W '.941 983 7.36 m MM WM 21H46 3 1390 5.50 185 2.12 .966 7.18 1423 4.39 9,,, 1 99 186 848 y
F 189 1.87 729 21H63 3 1364 4.32 186 117 .982 7.20 g ,, 7,34 . F 1415 4.30 129 1 52 .S82 7.47 31H38 8 1342 1 30 139 120 .888 4.20 188 7.21 7.19 12/13n2 5/3#7 P 1343 los 181 4 00 .992 y,1g 31H38 5 1366 4.10 191 1 26 .0e 7,,, 8.06 7.00 F 1324 1 73 183 2.80 1se J72 2/21/73 54/77 8.92 31H40 3 1188 4.25 186 4 70 1.006 S.53 g 4,, g F 1258 4.31 178 41g .900 E74 31H41 3 1371 A40 E.56 W # 0.30 1ae 7.16 8.80 F 1247 (16 180 2.10 .979 6.54 2/2103 5/6/77 31H60 S 1363 4.34 8I 4 81 .964 7.00 8.57 -4 88 1M E83 2/2 V73 M F 1273 ( 33 183 1.C 3 .960 8.57 32H14 3 1344 4.56 186 1.54 7.23 g g ,7 g3 , .966 g 73,777 F 1360 4 40 164 1.23 .978 7.21 32H24 3 1306 1 90 7.23 6.06 13e
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- E00 7.64 133 7.08 12/502 V2967 F 1322 1 00 189 4.00 .983 7.10 32H48 3 1326 1 08 186 170 .987 7.07 6.19 , 7.16 12/1/72 3/24/77
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f INRYCO. Inc. f 10 YEAR PHYSICAL TENDON SURVEILLANCE OF THE ARKANSAS 24 l NUCLEAR ONE - UNIT 1 PRDIARY REACTOR CONTAINMENT BUILDING l m TABLE VIII: SU> DIARY OF FORCE AND ELONGATION DATA DURING i w) 4
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.963 7.172 tr 2D22 s 1315 3.78 185 0 58 7.62 1 5 F 1360 3.84 0.70 6.992 185 0 12 .978 47.188 !
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g,93 95 - 12,19/73 M i 7.071 F 1389I4.41 185 1.39 - 61 .965 7.246 i 3D24 S 13 5 8 l 4. 81 186 1.75 9.23 ' ' 6.975 213/13/M
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21H50 S 13 30 l 4. 39 I ~ 2_ M 186 361 1 6.870 8.53 - 5.22 6.991 2h 4/5/M ) F 1377 4.14l 186 - 2.72 .961 7.112 31H11 S 1338 4.14 i 186 - 2. 6 9' 186 .977
-4.81 7.030 7.074 12/13/73 4/12/79 F 1355 4.88I 9*02 186 '- 2.12 .977 7.118 31H35 S 13001 5.19l 186 .98 186 .979 6.84 0 6.743 '2/20/7313/26/79 i
l F 1272l5.38i 186 .91
.972 6.646 l 31H47 S 1321 I 4.09 l 186 -3.81 186 .975 6.924 16.947 2/15/73 3/15/79 F 1339i 4.301 186 *** .968 6.970 1 3'2H 26 S 13211 3,131 186 :-3.13 186 .988 7.018 6.980 2'293 2N
- 6.91 F ' 1007 i 3.34 i 6*47 186 -3. 7 B i .988 l 6.9421 i 32H14 S I1296I5.09h)*;7 182 -2.00 182
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- 135613.73 l 7* j 3 184 i-3.52 - 7.15 1 EA l .965 17.113 7.110 f1/31/73 2/28/79 F 1355 ) 3.381 184 6-3.63 ' 965 7.107 l
21H42 S 1321 ! 5.03 jN F 133714.63 9*66 186 l-231 .976 17.016 i
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~ ELONGATION 85 OEPINED MERE AS OsSTANCE P ROM BEARING PL., ATE TO STRES$4NG WASMER ,
** TOTAL ELONG ATION f 5 SUM OF ELONGAYlON AT THE TWO ENDS.
*** OATA M8SslNQ .
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. 28 10 YEAR THYSICAL TENDON SURVEILLANCE OF THE ARKANSAS ,
NUCLEAR ONE - UNIT 1 PRIMARY REACTOR CONTAINMENT BUILDING. i n . CONCLUSIONS Based on the results of the ten-year tendon surveillance test reported herein, the conclusion is reached that no ab;.ormal degradation of the containment structure post tensioning system is indicated for Arkansas Nuclear One - Unit 1. h I 9
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__ _ _ _ _ _ _ _ __- _ _ _ _ _ _ _ _ _ _ Am9TE P@fd CMA%e
-- - -~ T 29 10 YEAR PHYSICAL TENDON SURVEILLANCE OF THE ARKANSAS ,
NUCLEAR ONE - UNIT 1 PRIMARY REACTOR CONTAI!3ENT EUILDING s.1 ,
- LIST OF REFERENCES
- 1. . Reactor Building Tendon Surveillance - One Year Surveillance - Arkansas l Nuclear One - Unit No. 1, Bechtel Corporation Scientific Development, l
San Francisco, CA, August, 1975.
- 2. Reac' tor Building Tendon Surveillance - Three Year Surveillance -
Arkansas Nuclear One - Unit No. 1, Bechtel Corporation Research and Engineering, San Francisco, CA, October, 1577.
- 3. Reacter Building Tendon Surveillance - Five Year Surveillance - Arkansas Nuclear One - Unit No. 1, Bechtel National Inc. Research and Engineering, San Francisco, CA, July, 1979. .
- 4. Recalculation o5 Normalized Forces for the 1st, 3rd, & Sth Year Surveillance of Arkansas Nucle.ar one - Unit 1 (Report #314), Inryco, Inc., Concrete Systems Division, Bedford Park, IL, June 1983.
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>{ 10 TEAR PHYSICAL,TURVEILI.e:CE OF THE ARKANSAS NUCLEAR
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7 A '2. 10 YEAR P!(YSICAL TENDON SURVE1LLAMCE 0F THE '
~ ARKANSAS NUCLEAR ONE - UNIT 1 PRIMARY REACTOR * .
PAGE
,- b O CONTAINMENT BUILDING .
i an Inland Steel codpiny
- APPENDIX A: 10 YEAR SURVE'7.LLANCE TENDON LOCATIOFS DATE l ,
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, 10 YEAR PHYSICAL SURVEILLANCE OF THE ARKANSAS NUCLEAR ONE - UNIT 1 PRIMARY REACTOR CONTAINMENT BUILDING '
1 r.. 0
, --x - '! APPENDIX B: ARKANSAS POWER & LIGHT ARKANSAS NUCLEAR ONE -
b - , UNIT 1 SURVEILLANCE PROCEDURE (1304.91, Rev. 3) i r ( 1 i' e e ur O 8 s e g.' s'* gg
s -2. I ~ E m.:. ARKANSAS POWER & LIGHT COMPANY CD C l. . Arkansas Nuclear One
@h'*. YAM ##
y, RECORD OF CHANGES AND REVISIONS I&C"/EERIODIC C ;; lFOWNo.1000.06A I ).i I$h REV. # 12 PC 9 A NI p Vh} E E -
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15 3 33 3 1 1 16 3 34 3 3 17 3' 35 3 3 18 3 1 36 3 l APPROVED BY: APPROVA1. DATE ll9l73 c7 __ . u se / (General Manager) lvemb - REQUIRED EFFECTIVE DATE: 1 __ W--,-,,-_w----_-_---- _ _ - - - . - - - O O _ & W_ b.
, 1 . . ,. .
- 1. g-s PLANT MANUAL SECTION: PROCEDURDWORK PLAN TITLE: NO:
t i I&C REACTOR BUILDING, TENDON J' . 1, ~. , ,. - . - , . - - - , . . . . . , M W) ARKANSAS NUCLEAR ONE mEwsion oAh
, e,,-.,e, CHANGE DATE I
TABLE OF CONTENTS l' SECTION PAGE l 1.0 PURPOSE 2 2.0 SCOPE * - 2 3.0 GENERAL REQUIREMENTS 2 4.0 SURVEILLANCE TENDONS 3 5.0 ANCHORAGE AND SIEATHING FILTER INSPECTION 4 6.0 TENDON DETENSIONING 5 7.0 TENDON WIRE INSPECTION .7 8.'0 TENDON RETENSIONING AND RESEALING 10 9.0 EVALUATION OF DATA AND CORRECTIVE ACTION 12 9 10.0 DATA REPORT'ING AND RECORDING 14 11.0 ACCEPTANCE CRITERIA 14
12.0 REFERENCES
14 - APPENDIX A - PROCEDURE FOR LABORATORY TESTING OF SHEATHING FILTER 15-16 (VISCONORUST 2090P OR VISCONORUST 2090P-4) APPENDIX B *- RAM CALIBRATION REQUIREMENTS 17-19 APPENDIX C,- FORMULAE FOR NORMALIZING FACTORS 22-25 APPENDIX D - INDEX TO POST TENSIONING SYSTEM DESIGN DRAWINGS 26 APPENDIX E - SURVEILLANCE DATA SHEETS 27-33 . FIGURE l'- TENDON SURVEILLANCE GO, NO G0 GAGE ~ 34 . FIGURE 2 - TENDON SURVEILLANCE WIRE PULLER 35 FIGURE 3 - TENDON SURVEILLANCE WIRE PULLER DETAILS 36 - FIGURE 4 - NORMALIZED AVERAGE TENDON WIRE FORCE VS TIME PLOT 37 FIGURE 5 - VERTICAL TENDON UPPER CAP - TEMP. VS FREE VOLDE 38 0 0 u/ . o
(_______,_.-.-.-_-_-._-- -. . - _ _ __ s +. d' - t PLANT M ANUAL SECTION: PROCEDUREMORK PLAM title: NO: [' Iy,, 7j j I&C REACTOR BUILDING, TENDON . t .
- r::::: :::T: sur E:::rm:
EE* h ARKANSAS NUCLEAR ONE aevisioN
- "- o, ATE e,,,,-
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CHANGE DATE 1.0 PURPOSE This procedure specifies the work to be performed and the equipment to obtain the data necessary to assess the continuing quality and structural performance of the containment post-tensioning system. 2.0 SCOPE P Each surveillance shall consist of the following: 2.1 Visual and laboratory examination of sheathing filler samples from each of the surveillance tendons. 2.2 Inspection of the anchor assembly of each of the surveillance tendons for deleterious conditions such as corrosion, cracks missing and broken wires or offsize buttonheads. 1 . 2.3 Measurement of the liftoff force for each of the surf'eillance tendons. 2.4 Detensioning of each of the surveillance tendons and checking L wire continuity by pulling wires and observing their movement V~ at the opposite end. The wire continuity check will only be performed if a visual inspection of the tendon anchor determines ; that a continuity check is required. l 1
~ 2.5 Removal of a minimum of one wire from one surveillance tendon 1
of each group, i.e., hoop, vertical and dome, for examination and testing. 2.6
- Retensioning of each of.the surveillance tendons to the liftoff force measured in Section 2.3 above less the effect of any wires removed, and measuring the corresponding tendon elongation.
2.7 Visual inspection for corrosion, pitting or any significant _ physical change of wires removed from tendons. 2.8 Testing of wires removed from tendons for yield strength, ultimate strength, and percent elongation. 2.9 Evaluation of test and inspection results to assess the general condition of the post-tensioning system and evaluate time dependent factors such as prestress losses and corrosion. 3.0 GENERAL REQUIREMENTS - 7 3.1 Tendon surveillance shall be performed 1 year, 3 years, and 4 5 years from the date of the structural integrity test (November 14, 1973) and at five year intervals thereafter. N
8-5 e' PROCEDURE / WORK PLAN TITLE:
, PLANT M ANU AL SECTION: NO:
~ '
I&C REACTOR BUILDING, TENDON
-PEPICPIC TEE-" SUP"rIEE "'re 'Sa' 61
#1 Li PAGE , _c 3o (
1,7-) " "I ARKANSAS NUCLEAR ONE aevisioN , oATE m,e,,o, _ J Wi# CHANGE DATE l 3.2 Tendon surveillance may be conducted during plant operation. 3.3 If the tendon surveillance is conducted during plant operation, no more than two hoop tendons and one vertical tendon or one dome tendon shall be detensioned at any given time. In the case of hoop tendons, if more than one tendon has to be de-tensioned at any given time, the distance between two deten-sioned tendons shall be a minimum of 40 feet. In the event that adjacent tendons must be checked, the original surveillance tendon shall be retensioned by the method as described in Section 8.1 of this procedure before any other tendon shall be detensioned. 3.4 The elapsed time between removal and replacement of sheathing filler from a tendon shall not exceed 3 weeks; during this period, tendon end anchor shall be protected with Viscosity Oil Company Visconorust 2090P or Visconorust 2090P-4. 3.5 All instruments used for the collection of data musp le calibrated prior to and after the tendon surveillance. o 3.6 No changes will be made in this procedure without the written approval of the ANO Plant Manager.
@O 4.0 SURVEILLANCE TENDONS Drawing 11406-14-C-2608, Sheet I thru Sheet 3, shows the surveillance years, the corresponding surveillance numbers and the recommended sur-veillance tendons for the life of the plant. During'each of the first.
three surveillance, a minimum of twenty-one (21) surveillance tendons have been designated per surveillance. They consist of ten hoop ten - dons, at least three in each of the three 240 sectors of the contain-ment; five vertical tendons; and six dome tendons, two in each of the three groups. The number of surveillance tendons in each of the suc-
~
ceeding surveillance years are nine (9) which consist of three hoop tendons, one from each 240 sector; three vertical tendons; and three dome tendons, one from each group. The recommended surveillance tendons may be varied provided that the selection based on a random ind representative basis and the total number of tendons in each of the different groups to be tested remains unchanged. ! - The tendon numbering system and tendon locations are defined on the design drawings for the post tensioning system. An index to these drawings is provided in Appendix D. e a wV,f
's .
N - ____ _ _ _ _ _ _ _ - . . _ _ _ _ _ _ _ _ _ _ _ . _
f3 -62 PLANT MANUAL SECTION: ' PROCEDURE / WORK PLAN TITLE: NO: I&C
. r ,
REACTOR BUILDING, TENDON
- If pretnnte Treve c0cvritr2McF 1304.91 F' ", f9Li PAGE 4 of 38 I
( h) > ARKANSAS NUCLEAR ONE aEvision 3 oarE 01'nais3 r- . CHANGE pc.3 DATE O2/09/83 5.0 ANCHORAGE AND SHEATHING FILLER INSPECTION. 1 5.1 Sheathing Filler The sheathing filler may be in liquid, gel or solid ferm. Complete removal of sheathing filler is not required provided j that all filler which has drained out or been removed during surveillance is replaced. Provisions shall be made to collect all filler which is removed in such a manner that the volume removed at each tendon is known and recorded on Data Sheet #1. 5.1.1 The containment exterior concrete temperature near
~
the tendon shall be recorded on Data Sheet #1. ' 5.1.2 Two identified one quart samples of sheathing filler ' shall be obtained from each of th'e tendons to be inspected (one from each end). 5.1.3 The following chemical tests shall be made' on one of the samples frem each tendon. The test methods outlined. in Appendix A of this procedure shall be used. Results of these tests shall be recorded on forms provided by
-s the testing laboratory. ,
A ,r CC/ A. Water Soluble Chlorides . B. Water Soluble Sulfides C. Water Soluble Nitrales D. Neutralization Number E. Water Centent by Weight I ~ 5.1.4 The test results shall be compared with the acceptance criteria outlined in Section 9.3. The second sample from each tendon shall be tested only if the test . results from the first sample do not meet the acceptance $" criteria. 5.1.5 The filler caps shall be removed from both ends of the ' ~ tendon and the color of the filler shall be compared to that of unused filler. If tan colored filler is found, a representative 1 quart sample of it shall be obtained. - The results of this test shall be recorded on Data Sheet
#1. If after 24 hours of storage the filler is still
- tan colored, it shall be analyzed as described in Section 5.1.3. ,
5.1.6 The completeness of sheathing filler coverage on the inside of the filler cap, bearing plate, buttonheads, ' anchor head, and shims shall be observed immediately [' '- after removal of the filler cap and recorded on Data - ,s Sheet #2. . , O
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.. n. nw.
g-y e PLANT M ANUAL SECTION: PROCEDUREfNORK PLAN TITLE: NO: I&C REACTOR BUILDING, TENDON , d'b w er!c TESTc S'2"r!LL +"?F n' n' "Ft$, O PAGE q ,c no
% ARKANSAS NUCLEAR ONE arvisioN h- .
CHANGE
- oArE DATE n,,e,,,e, 5.2 Inspection of Anchorage Components The tendon and anchorage components shall be cleaned using Viscosity #16 solvent or an ANO Plant QC approved equal.
After cleaning, the components shall be inspected. f l 5.2.1 Buttonheads shall be inspected for shape, cracks, corrosion and general appearance. During the initial surveillance, each buttonhead shall be inspected using a Go, No-Go Gage as shown in Figure 1 and data recorded on Data Sheet #1. 5.2.2 The anchor head, shims and bearing plate shall be inspected for corrosion and cracks. Data shall be recorded on Data Sheet #2. 5.3 Vertical Tendon Repacking Procedure c' 5.3.1 Repacking of the top and bottom caps for vertical tendons may be done using unheated sheathing filler material providing the amount of material drained off does not exceed 5 gallons for the top cap and 25 gallons for the bottom cap when the average tendon temperature, as determined from Figure 5, does not exceed approx-imately 70 F. When the average tendon temperature, as determined above exceeds 70 F and/or the amount of ~ filler drain from the bottom cap e,xceeds 30 gallons then an. air path should be bloun through the tendon sheath from the top to bottom. Heated sheathing filler material should be pumped through the tendon in accordance with the field filling procedure shown on drawing C2105 Note No. 4. _ 5.3.2 In repacking the top cap the depth of void for sheathing filler is to be checked using Figure 5 " Vertical Tendon Upper Cap - Temperature vs. Free Volume". When replacing - sheathing filler material with heated sheathing filler, the upper cap shall be removed af ter 24 hours and the free volume checked using the average temperature T3 as shown in Figure 5. 6.0 TENDON DETENSIONING _ 6.1 Ram Calibration All gages and rams used for tensioning and detensioning surveillance tendons shall be calibrated in accordance with the calibration requirements preser.ted in Appendix B. After initial calibration, gages and rams may be used throughout the surveillance without additional calibration. Recalibration will be required in cases where repairs have been done on damaged equipment. Calibration will be verified after the completion of all tendon surveillance.
; Y B-8 PLANT M ANUAL SECTION: PROCEDUREN/ORK PLAN TITLE: NO:
.jI I&C REACTOR BUILDING, TENDON
/9 wi
, c, ,,
PAGE .c ,o A "*6 ARKANSAS NUCLEAR ONE asvisios f v oATE e,,,,,e-p/ . CHANGE
~
DATE
' ' ~ ~
l 6.2 Safety
~
1 All personnel on work platforms during tensioning operations shall be familiar with and observe the following safety {; precautions: 6.2.1 Personnel shall not stand behind the rams while the rams are pressurized. 6.2.2 Personnel shall keep hands and fingers away from the j tendon and rams while the ram is pressurized except as required to remove and install shims, take liftoff readings, and make elongation measurements. 6.3 Detensioning Sequence Vertical tendons shall be detensioned from the dome. In the case of hoop and dome tendons, where tensioning is d6*ne from both ends of the tendon, a reliable means of communication between the crews on both ends of the tendon shall be provided. Ram force shall be increased or decreased at the same rate at
, each end of the tendon.
4
.(gr The detensioning sequence shall be as follows:
6.3.1 The containment exterior concrete temperature near the tendon shall be recorded on Data Sheet #3. 6.3.2 The number of effective wires shall be determined and recorded on Data Sheet #3. 6.3.3 The initial l'iftoff elongation shall be measured
' within +0.02 inches and recorded on Data Sheet #3.
, Elongation is the change in distance between the bearing plate and the anchor head.
6.3.4 The ram shall be attached to the tendon anchorage. The pressure gage shall be attached to the ram, - checked for damage, and the dial adjusted to zero pressure reading. 6.3.5 The liftoff force shall be measured repeatedly until three consecutive measurements are within a range of
~
100 psig. Eiftoff force is the minimum force at which .030 feeler shims located approximately 180 apart, can be moved between the anchor head and the bearing shim. The average of these three consecutive ('y'~)% A measurements shall be recorded on Line 5 of the ur s# Detensioning Section of Data Sheet #3.
%W
y- - . _ _ _ _ . _ _ _ . _ _ _ m , _ _ B-9 PLANT M ANUAL SECTION: ' PROCEDURE / WORK PLAN TITLE: NO: i
]
I&C
- proTO'"O "TrTr REACTOR BUILDING, TENDON c'_m'9 0 "Cr "n' e PAGE ,
_c no Eh ARKANSAS NUCLEAR ONE (A y) , aevisiON CHANGE
, care n,,,, DATE er, re, n o 'in e f o ,
A. An approved alternate method for determining the li~fts off force shall be that the liftoff force shall be _ measured repeatedly until three consecutive measurements are within 100 psig with lift off force being the minimum force at which shims can be moved by pounding with a hammer (approximately 24 oz.). The average of these three consecutive measurements shall be recorded on Line 5 of the
, Detensioning Section of Data Sheet #3.
l NOTE l l When the feeler shim method of determing lift-off is used, l l the lift-off force shall be based on the average of the two l l pressures corresponding to shim insertion. l 6.3.6 The shims shall be removed and the ' tensioning force shall be reduced to zero. 6.3.7 The tensioning force shall be increased to 1000 lbs. per. wire and the tendon force and corresponding elongation shall be measured and recorded on Data Sileet #3. This is necessary because the ram is calibrated for increasing loads only. 6.3.8 The ram force shall be reduced to zero, the pressure gage detached from the ram, and the ram detached from tendon end anchor. 7.0 TENDON WIRE INSPECTION 7.1 Broken or Missing Wires All wire in each surveillance tendon shall be visually inspected for suspect wires. A suspect wire is a missing buttonhead or,a
~
broken, loose wire not previously reported or any raised buttonhead.
, If a suspect wire is found, a continuity test shall be completed as noted in Section 7.1.1. ._ 7.1.1 A portion of the wires in each suspect surveillance "
tendon shall be inspected for continuity by pulling one end of each wire to be checked and observing the movement of the buttonhead at the other end. The groups 'of wires so tested and any broken or missing wires shall be shown on Data Sheet #2. Broken wires shall be removed and examined to determine cause of breakage. The number of wires checked for continuity
'shall be determined in the following manner:
7.1.2 A minimum of 62 wires in the suspect section of the . surveillance shall be checked for continuity. The wires checked shall be located in two 60 segments which are 180 apart as illustrated by segments A and B in Data ! Sheet #2. The two segments tested will be indicated by x circling those segments on Data Sheet #2. If only the 7 suspect wire is found broken or no broken wires are found .
~ in the first 62 wires checked, no further wire checking is required for that tendon.
l
. s
. B -/O PLANT M ANUAL SECTION: PROCEDURE / WORK PLAN TITLE: NO: .
I&C REACTOR BUILDING, TENDON
? - } "{}4
, . nrr:::: Trr-- m ' mitt:2mr
' ' n '- o' DE" d l-ARKANSAS NUCLEAR ONE CHANGE EsmN %E
~ DATE m,-,
~~
7.1.3 If any broken wires other than the suspect wire is l 3 detected in the first 62 wires checked in a particular i tendon, the number of wires checked in that tendon shall l be increased to 124. The additional wires checked shall be located in two 60 segments 180*~ apart as illustrated (- by segments C and D in Data Sheet #2. 7.1.4 If two of more broken wires are detected in the first 124 wires checked in a particular tendon, all the wires L in that tendon shall be checked for continuity. 7.1.5 If 3 or more broken wires are detected in a particular tendon, all the wires in the adjacent tendons on each side of the deficient tendon shall be checked for continuity. This section does not apply to tendon 32H14. l CAUTION f l Note Section 3.3 l 7.1.6 If both of the tendons adjacent to the deficient tendon contain less than three broken wires per tendon, the A' deficiency shall be considered to be unique and acceptable. 7.1.7 If either or both of the tendons adjacent to the deficient tendon contain three or more broken wires,. an engineering evaluation of possible degradation of the post tensioning system shall be nade and documented.
~
7.2 Wire Removal Three tendon wires, one each from a hoop, dome, and vertical tendon, shall be removed of'r testing and inspection. The wire shall not be deformed permanently during wire removal. The curvature of the wire sample at sufficient length when laid free
- _ on a substantially flat surface shall satisfy the requirements as defined by ASTM-A-421 Standard. The procedure for wire removal and inspection is as follows:
7.2.1 Both ends of the wire to be removed for surveillance shall be marked and its location shall be recorded on the end anchor sketch form Data Sheet 2. The corresponding wire ends shall be identified by pulling at one end and observing which buttonhead moves at the other end.
Sh-// PLANT M ANUAL SECTION: PROCEDURE / WORK PLAN TITLE: NO:
- I&C REACTOR BUILDING, TENDON ,
DPDTODTA eccTe C f *D i *r T T Y .1 UP P inn ( 01 Qf-~ MU ' ARKANSAS NUCLEAR ONE PAGE aavisioN o oc ,o
, oirE m eas,o, i
l CHANGE
. DATE 7.2.2 The wire shall be pulled toward the end to be cut and a file shall be used to notch it approximately two inches from its end. The end which is to be cut j shall be recorded on Data Sheet #3 and #4 and the )
distance from the notch to the outside of the i buttonhead shall be measured within 10.02 inches and recorded on Data Sheet #3. 7.2.3 The wire shall be cut between the buttonhead and the notch. 7.2.4 The remaining portion of the wire shall be removed using the wire puller shown in Figures 2 and 3, and cleaned with solvent. The wire shall be visually inspected for corrosion, pitting or any significant physical change, and the results recorded on Data Sheet #4. The corrosion levels are defined on that sheet. The distance from the notch to the'outside of the buttonhead shall be measured within 1.02 e inches and recorded on Data Sheet #3.
, 7.2.5 The new and previous corrosion ratings shall be ; compared, and significant differences shall be noted. ;
l 7.3 Wire Testing - _ Tensile and elongation tests shall be performed on the 3 wires removed. One tensile test specimen shall be taken from each end of the wire and one at mid-length. Length of wire specimens shall be approximately 100 inches long. Additional specimens shall be taken from areas which have a corrosion rating two or more levels greater than the average description of the wire.
. Tensile tests shall also be made on at least one specimen from each broken wire removed. The test specimen shall be taken from atar the wire break and shall be approximately 100 inches long.
Data shall be recorded on Data Sheet #5. 7.3.1 In the event the tensile strength of the first wire is less than the minimum ultimate strength, an additional wire of the same tendon shall be removed
.for testing. Tendons with the same wire heat number shall be' identified. Engineering shall be notified immediately.
7.3.2 All lef t-over pieces of the testing wires shall be retained at the plant site until such time as the Tendon Surveillance Report is accepted by the NRC. %;O d' _-.___._m - - -
S-/ 2 PLANT MANUAL SECTION: PROCEDURE /WORX PLAN TITLE: NO: i' I'E _ _ _ - REACTOR BUILDING, TE M Q sidl 3 .
~ ARKANSAS NUC[E R ONE YE e sioN CHANGE 9 o^rE
' DATE
- ' ' ~ ' " "
8.0 TENDON RETENSIONING AND RESEALING - 8.1 Retensioning , Retensioning of the hoop and dome tendons shall be accomplished by stressing from bo.th ends. The vertical tendons shall be retensioned by stressing from the dome. All data and events which occur during retensioning shall be recorded'on Data Sheet #3. The retensioning procedure shall be as follows: 8.1.1 ThenumberofeffectiveAiresinthetendonduring retensioning shall be determined and recorded on Data Sheet #3. 8.1.2 The ram shall be attached to the tendon anchorage. The pressure gage chall be attached to the ram, checked for damage and adjusted to zero pressure reading. 8.1.3 The containment exterior concrete temperature near the tendon shall be recorded on Data Sheet #3. 8.1.4 The tensioning force shall be increased until average wire force is 1000 pounds per wire. The tendon force < and corresponding elongation shall be recorded on Data Sheet #3. { l 8.1.5 The tensioning force shall be increased until the average wire stress is 80% of the .specified minimum ultimate strength of the wire which is 08. x 240 ksi. I
- The maximum tensioning force and the corresponding elongation shall be recorded on Data Sheet #3.
8.1.6 Sufficient shims shall be installed to obtain a liftoff force equal to, but not less than, that meas' ured as per Section 6.3.5 less the effect of any reduction in the number of effective wires. If tensioning force drops below the desired liftoff force, the tendon force shall again be increased and recorded until average wire stress is 0.8fpu (which is 0.8 x 240 ksi)
~ before installation of shim. Any changes in the shim thickness shall be recorded on Data Sheet #3.
8.1.7 Liftoff force shall be recorded on Data Sheet #3 and final liftoff elongation shall be measured and recorded within 10.02 inches.
- 8.1.8 The ram shall be detached and a coating of Viscosity j _(
9-j Oil Company's 2090P, which is presently in the tendon i sheathing, or Viscosity 2090P-4, shall be applied to __ the tendon end anchorage. h
g-,3 1 PLANT M ANUAL SECTION: PROCEDURE! WORK PLAN TITLE: NO:
' I i
9 I&C REACTOR BUILDING, TENDON J fl k neornnyc -reme emr v r r mcr 3,ng n, "eLQ "l- ARKANSAS NUCLEAR ONE PAGE ,, .c no v{9 .? aevisio" CHANGE
, ATE DATE no n m, 8.2 Resealing Tendons s
The tendon resealing procedure shall be as follows: 8.2.1 Tendon filler caps shall be installed using new gaskets, washers, gasket sealant and teflon tape. 8.2.2 The tendon sheathing filler shall be refilled with Viscosity Oil Company's Visconorust 2090P-4 or Visconorust 2090P sheathing filler. The temperature of the filler at the filler pump shall be 120 F minimum. Filler which has been removed from the tendon shall.not be reused. Filler material shall be replac~ed by pumping through a hose attach-ed to the grease cap filler plug. All available valves, vents and drains shall be used during this operation to avoid the entrapment of air in the sheathing filler. Pump-ing shall continue until at least five gallons of filler without any air bubbles or visible foreigo' substances has come out of the outlet or vent farthest from the pump. 8.2.3 If less than 5 gallons of filler has been removed at each tendon end, filler may be replaced by pumping or
.G pouring into each end provided each end is vented to T. _) bleed out air.
8.2.4 The temperature and volume of sheathing filler installed in each tendon shall be estimated and recorded on Data Sheet #1, 8.3 Vertical Tendon Grease Repacking Procedure l 8.3.1 Repacking of the top and bottom caps for vertical tendons may be done using unheated sheathing filler material providing the amount of material drained off does not _ exceed 5 gallons for the top cap and 25 gallons for the bottom cap when the average tendon temperature, as deter-mined from Figure 5, does not exceed approximately 70 F. When the average tendon temperature, as determined above, exceeds 75 F and/or the amount of filler drained from the bottom cap exceeds 30 gallons, then an air path should be blown through the tendon sheathing filler from the top to bottom. Heated sheathing filler material should be pumped through the tendon in accordance with the field filling procedure shown on drawing C2105, Note No. 4. ,
~
8.3.2 In repacking the top cap, the depth of void for sheathing filler is to be checked using Figure 5 " Vertical Tendon Upper Cap - Temperature vs Free Volume".
;9 When replacing sheathing filler material with heated sheathing filler, (a" the upper cap shall be removed af ter 24 hours and the free volume checked using the average temperature T3 as shown in Figure 5.
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- - PtA NT. M ANUAl,SECTIONW = PROCEDURE / WORK PLAN TITLE: NO:
" REACTOR BUILDING, TENDON I&C .
_ )f "b eeetnp7c mecte cpevererince igna o1 E/9 h}j L ARKANSAS NUCLEAR ONE PAGE aavisioN 7 19 A# 38 o*TE 1 f) CHANGEre_2 DATE 01 aa,s, n?/no/g3 i
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8.3.3 The average temperature.T3 is the average value of the ambient temperature T1 and the average temperature inside containment T2 at the time when the sheathing filler is checked, removed, or added. T2 shall be obtained by averaging the reading of gages TE2401, TE2405, TE2409, '
. TE2413, TE2416 and TE2420.
9.0 EVALUATION OF DATA AND CORRECTIVE ACTION 9.1 Liftoff Forces The liftoff readings, taken as specified in Section 6.3, shall-be normalized using the formula as presented in Appendix C and evaluated in the following manner: 9.1.1 If the normalized liftoff force is equal to or greater than the minimum design prestress level in the tendon, as stated in Figure 4, the readings shall b,e recorded and surveillance continued. .' 9.1.2 If the normalized liftoff force is less than the minimum design prestress level in the tendon, as
, stated in Figure 4, the adjacent tendons on each .
, side of the defective tendon shall be checked for liftoff values and these recorded on Data Sheet #3.
l Caution l _ . l Note Section 3.3 l 9.1.3 If the normalized liftoff forces obtained from the two tendons adjacent to the defective tendon are equal to or greater than the design prestress level in the tendons, as stated in Figure 4. the readings shall be recorded on Data Sheet #3 and the deficiency shall be considered to'be unique and acceptable. 9.1.4 If either or both of the normalized liftoff fprces obtained from the two tendons adjacent to the defective tendon are less than the design prestress level in the tendons, as state'd in Figure 4, abnormal degradation of the post tensioning system shall be assumed and reported to the Nuclear Regulatory Commission. 9.1.5 A plot of the normalized average tendon wire force
- vs. time shall be prepared for each surveillance tendon. This plot is illustrated in Figure 4. When' a reasonable trend has been established, the force-time plot shall be extrapolated over the 40 year 1[L life of the plant. If the extrapolated curves for f4
""^
two or more tendons extend bevond the maximum or minimum design prestress levels, as stated in Figure 4, an engineering evaluation of possible degradation of the post tensioning system shall be made.
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e B-/ 5 PLANT M ANUAL SECTION: PROCEDURUWORK PLAN TITLE NO:
- l. s I&C REACTOR BUILDING, TENDON r I. nrnrnnrr ere-e erm.r vr v ,yre , , n ,, n, O "h ARKANSAS NUCLEAR ONE Ev'sion " MTI 3 n, ,e on kDv CHANGE DATE 9.2 Wire Tests
. , I Failure below the guaranteed ultimate tensile strength (11,780 lb.)
of any of the wire samples tested in accordance with Section 7.3
'~
shall be considered to be an indication of abnormal degradation ) of the post tensioning system, and shall be reported per {
; Section 10.0 of this' procedure, j 9.3 Sheathing' Filler Inspection The sheathing filler material shall be considered to be acceptable provided that the results of the tests performed on the samples fall within the following limits:
TEST LIMITS Water Soluble Chloride Less than 10.0 ppm Water Soluble Nitrates Less than 10.0 ppm ' . Water Soluble Sulfides L'ess than 10.0 ppm ' Water Content Less than 10% Dry Weight Neutralization No. Greater than 1 . 1 If the results of these tests faill outside the specified TP limits, one extra sample from each end of the tendon in question shall be taken and tested. If similar results are obtained, , the sheathing filler from which the unacceptable samples were taken shall be replaced. As stated in Section 5.1.3, the results of these tests shall be recorded on forms provided by the testing laboratory. 9.4 Evaluation of Previous Surveillance Records The tendon surveillance record for each tendon shall be compared
,_ with previous records to determine if:
A. Additional wires have broken since the last inspection; B. The liftoff wire force for each tendon has changed significantly; C. A change in wire corrosion status or sheathing filler has occurred; or D. A significant change in yield or ultimate strength or elongation under load at ultimate strength has occurred. If any of these conditions are present, a report shall be prepared indicating any reasons for observed results and recommending any remedial action necessary. m
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. PLANT MANUAL SECTION: F ROCEDURE! WORK PLAN TITLE: NO:
~
i I&C REACTOR BUILDING, TENDON oroTonvr tremq etmtevir prer *
,on,'os L-
- li1 PAGE , r, _c oo (f) o ARKANSAS NUCLEAR ONE aevisio" CHANGE
, o*Te n,re,,e, DATE )
o . 9.5 Corrective Action s [ If any indications of abnormal degradation of the post tensioning system are detected according to the above criteria, a program
'- for further investigation shall be initiated, the extent of the degradation determined, and the necessary corrective action
; implemented.
3 10.0 DATA REPORTING AND RECORDING
}
Any indication of abnormal degradation of the post tensioning system shall be -reported by provisions of the Technical Specifications. 11.0 ACCEPTANCE CRITERIA 1 The Acceptance Criteria shall be defined as meeting the requirements of l Sections 7.1.5, 9.1.1, 9.1.2, 9.1.4, 9.1.5, 9.2, 9.3 with the. exception of neutralization number and 9.4. - i
12.0 REFERENCES
. 1. CE Memo 83-05 dated January 16, 1983 w
W 4 W 4 a - d*
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Es -/ 7 PLANT M ANUAL SECTION: PROCEDURE / WORK PLAN TITLE: N O. r J 94 I&C oce rnm,r ,c, REACTOR BUILDING, TENDON c-v r r g.re ,
, , e ,. n, M L-T3 4
gAaE ,. -, ,, I{,) y
- ARKANSAS NUCLEAR ONE aevisioN CHANGE 2 oATE e,,n,,e, i DATE l Page 1 of 2 APPENDIX A s i PROCEDURE FOR LABORATORY TESTING 0F SHEATHING FILLER MATERIAL J' 1.0 GENERAL 1
This document specifies the procedures which shall be used for laboratory testing of sheathing filler. The laboratory to be used must be approved
- by AP&L.
A. The amount of water soluble chlorides, nitrates and sulfides which are leached from a given contact area between water and sheathing filler under standard conditions. B. The water content of the sheathing filler. The reserve alkalinity of the sheathing filler. C. .' This document does not relieve the testing laboratory of responsibility
.for conducting the necessary laboratory tests in a manner consistent with industry standards.
/ 2.0 WORK INCLUDED 21 one quart test samples will be sent to the laboratory for testing
~
in accordance with Section 3.0. The concentration of water soluble impurities and water in these samples should not exce'ed the following:
~
2.1 Chlorides - 10 ppm 2.2
- Nitrates - 10 ppm
._ 2.3 ' Sulfies - 10 ppm ;
2.4 Water (H2 0) - 10% Dry Weight
~
A report meeting the requirements of Section 4.0 shall be prepared. t - 3.0 { TEST DESCRIPTIONS Each sample of sheathing filler shall be mixed and then tested as follows: _ 3.1 Water Soluble Impurities A water extraction of each sample of sheathing filler shall be made and tested as follows: O l h[ 3.1.1 Using a spatula, coat the inside (bottom and sides)- of a 1 liter glass beaker with a 1/4-inch layer of
- 1 sheathing filler.
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,,, d ~/6 PLANT M ANUAL SECTION: PROCEDURE / WORK PLAN TITLE: NO: ,
- r. 'p I&C REACTOR BUILDING, TENDON '
l pep?c !C TEc*c c ' *"'"" !I ." 'C E a'
'c a '
r . Ei PAGE ,- ,c ,o L ]>
- l ARKANSAS NUCLEAR ONE aevision ; o*Te ' , , - , - ,
S,E CHANGE - DATE " ' ~ ' "" Page 2 of 2 APPENDIX A (CONT'D) \ 3.1.2 Fill beaker with distilled water at room temperature. I l 3.1.3 Heat the water to a controlled temperature of 100 F and maintain for four hours. Do not heat on a hot plate. Heat either in an oven or by use of an immersion heater so that the water will remain clear for tests. 3.1.4 Run a blank on distilled water. If titrate, use a micro-buret, 1 ml or 5 ml, with 0.01-0.05 ml graduation intervals. 3.1.5 Decant water and analyze for soluble ions. Test only
- for salts in leached water. The water analysis shall be as follows:
c'
'3.1.6 Chlorides (C1) by ASTM D-512.
3.1.7 Nitrate (NO )3 by ASTM D-992 Brucine Method or Cadmium Reduction Method. . D 3.1.8 Sulfides (S) by APHA (American Public Health Association) Standard Method-Methylene Blue. 3.2 Water Content - Water content (H2 O as percent of dry weight) shall be determined in accordance with ASTM D-95. 3.3 Neutralization Number Neutralization number shall be determined in accordance with ASTM D-664. - 4.0 REPORT Two copies of the report on laborat'ory testing of sheathing filler shall be submitted to Arkansas Power & Light Company, Little Rock, Arkansas. This report shall contain the following information: 4.1 Sample identification. 4.2 Concentration of water soluble chlorides, nitrates and sulfides within an accuracy of 0.1 ppm. f\ () 4.3 Concentration of water (H2 0) within an accuracy of 0.1 percent Q of dry weight of filler.
, 4.4 Neutralization number within an accuracy of 0.1 mg reagent per gram of filler.
B -/ 9 PLANT M ANUAL SECTION: PROCEDURE / WORK PLAN TITLE: NO: , _ I&C REACTOR BUILDING, TENDON M' Ls penTnqve meme e t -- g r i 3_ve t-19nr n1 O b: 1 PAGE 3, ,c no rk.]/ M- ARKANSAS NUCLEAR ONE acvision , o^TE n,,n1 ,e, 1 la-CHANGE DATE l l ' Page 1 of 3 APPENDIX B
\
RAM CALIBRATION REQUIREMENTS 1.0 GENERAL The ram calibration arrangement is generally defined on Drawing C-98, Rev. 4 which is included in this Appendix. Also included in this Appendix is the Ram Calibration Procedure. The arrangement shall be located on the concrete slab shown on FSK-C-975 Rev. 1. The following equipment is required for calibration: A. One tendon which is capable of a minimum force of 1,850,000 lbs. at 90% G.U.T.S. with an appropriate anchorage. The ram will be coupled to the tendon washer during calibration. The details of the tendon washer are shown on the post-tensioning system design drawings. An index to these drawings is provided in Appendix D. B. One load cell bearing plate. The details of this bearing plate ' are shown on Drawing SK-C-318, Rev. B, which is included in this Appendix. - C. One 2 millica pound capacity load cell, as a minimum, and calibrated 43 7 ) indicator for reading load cell force. The AP&L load cell is shown in Drawing 97052 which is included in this Appendix. This load 1 cell shall be supported by the support shown on FSK-C-974 Rev. O. { D. .10 sets of 4" shims, I set of 3" shims, or as required. E. Timber blocking as shown on Drawing C-98. The above equipment is in the possession of Arkansas Power & Light j Company, and may be used for ram calibration.
..._ )
1 2.0 RAM CALIBRATION PROCEDURES 2.1 Clean the ram of excessive dirt, oil, or other residue that may unduly affect the calibration accuracy.
'2. 2 The load cell will be set up so that the loads will be applied in a uniform manner.
2.3 The ram will be attached to the load cell and centered so that the loads will be applied concentrically and uniformly. 2.4 Fit ram to bearing plate and couple stub rod with tendon washer or attach calibrating tendon. v - ge
8-20 PLANT MANUAL SECTION: PROCEDUREA*/ORK PLAN TITLE: NO: I&C REACTOR BUILDING, TENDON .- y A- ..-,,n,,. - ,,,,,.c e,-..---uu.uyu ,,n, n, u s sv. w s -. . . + ,
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< ARKANSAS NUCLEAR ONE aevision CHANGE m,.[,DATE n,',,n', Page 2 of 3 APPENDIX B (CONT'D) 2.5 Connect calibrated indicator to load cell and balance and calibrate the indicator according to it's manufacturer's written instructions. j 2.6 Adjust shims in back of ram so that piston is positioned at 1/4 of its total travel distance from front of ram cylinder.
- 2. 7. Gradually increase ram pressure and record calibrated indicator readings at ram pressure of 1000, 2000, 3000, 4000, 5000, 6000, 7000, 8000, and 8200 psi. All data recording shall be taken to the nearest 2000 lb. and recorded on Data Sheet if6.
l NOTE l l The readings obtained at the ram pressure of 1000 psi l l'may not be utilized in the calculation of the ram' area. l 2.7.1 Gauge pressures shall not be reduced to meet a target increment once a target increment has been exceeded. Readings will be acceptable when they are within 100 psi g of the target increment. 2.8 DELETED j 2.9 Repeat Step 2.7 with ram piste'. positioned at 1/2 and 3/4 of its I
. total travel distance. j 2.10 During ram calibration a calibrated hydraulic pressure gauge having l the smallest reading equal to or less than 20 psi or a Eeise I Electronic Digital pressure indicator will be used. The hydraulic j pressure reading to the nearest 20 psi or the actual digital read- '
out will be recorded on the calibration form. 2.10.1 The load cell readout will also be entered onto the calibration record to the nearest 0.1 reading. ~ 2.11 All other information areas of the calibration form will be completely i filled in by the calibration technician or the witnessing agent. The form will be signed and dated. The calibration record will - then be handed over to the Contractor's Engineering Section for final computation. 2.12 After all calibration data has been recorded, the ram area will be computed as follows: A. Regression analysis will be used' to compute the ram area once initial, raw data, information has been documented e on the jack calibration record form (Data Sheet #6). The G h personnel performing the computation and verification checks will sign and date the. Calibration Form and the . computer printout.
. 23 - 1L /
PLANT M ANUAL SECTION: PROCEDURE / WORK PLAN TITLE: NO:
- I&C REACTOR BUILDING, TENDON t J' ocornnrc meeme creverrrixcr ions o, r3 /9 Ji PAGE 3o es og
- " "I ARKANSAS NUCLEAR ONE aEvisioN hp) 3 oATE e 4 ,0 o 2, ,
CHANGE DATE l
. Page 3 of'3 APPENDIX B (CONT'D) s
- 1. Computation will be performed by a computer. All data entered into the computer will also be printed 4' out. This data, as well as the computer results, will be verified by someone other than the person operating the computer. {
- 2. In the event that the computer is temporarily unavailable, computations may be performed manually observing the same methods being used by the computer.
These manual computations will be verified and/or ; corrected by a computer computation as soon as practical. the manual computations will only be l performed by the contractor's Engineering Department personnel. 4
- 3. Omitted readings, dropouts, are automatically considered by the computer. -
M9,s ,2.13 Acceptance Criteria ' A. Calibration shall be completed in such a manner that the implied force readings to the nearest 2000 lb. shall be obtained for this respective gate pressure readings. B. If the most probable total error, E, is greater than 2%, the jack will be recalibrates or more accurate gauges will be used to reduce the value of E to 2% or less. If the jack has any repairs performed that could affect the ram area, then that jack will be recalibrates. W 6 m 9
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T I&C
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REACTOR BUILDING, TENDON iG. C ARKANSAS NUCLEAR ONE __ PAG E _aevisioN 9 oats' .,, . . . , CHANGE DATE ~ ' ' ~ ' ' " " k
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' M' Fl- provnnTc eteme cim"rT r r wgr ,
, , n ,. o3 li PAGE on .c 3e
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f'-) h;;j ARKANSAS NUCLEAR ONE aevisioN ,oATE ,,,,o,- CHANGE p c _ f. DATE
. n o i, , f g3 Page l' of 4 l APPENDIX C.
FORMULAE FOR NORMALIZING FACTORS 1.0 NOMENCLATUPI j Lc = Initial liftoff force of surveillance tendon (ram area X pressure
+ calibration consta'nt) (kips)
L(1,7)= Liftoff force obtained at the i - 1 surveillance (kips) L ygg_7)= Liftoff force during retensioning at the i - I surveillance (kips) og= Number of hoop tendons tensioned prior to tensioning surveillance tendon (a vertical or a hoop) N h= Total number of hoop tendons n =
'" Totalnumberofverticaltendonstensionedpriorto.Iensioning surveillance tendon (a vertical or a hoop)
Nv = Total number of vertical tendons . N hs n d= Number of dome tendons tensioned prior to tensioning surveillance tendon (a dome) Nd= Total number of dome tendons N . Number of effective wires in tendon when initially installed WC= Ngg= Number of effective wires in tendon at i th surveillance Ng(g_37Numberofeffectivewiresintendonwhenretensionedduringthe r 1 - 1 surveillance. l _ SEh = Total elastic stress loss in hoop tendons during initial tensioning (ksi) i
'SEv = Total elastic stress loss in vertical tendons during initial s l
tensioning (ksi) l sed = Total elastic stress loss in dome tendons during initial tensioning (ksi) v = Poisson's ratio for concrete r8 am l --
x_ .q - . ,, , .. A#;" :. 5 14 9? * * ' ar te. ; , e>,. x
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PLANT M ANUAL,SECTION:whPROCEDUREN/ORK PLAN TITLE: NO: t I&C REACTOR BUILDING, TENDON
'^^' "'
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"" ~' ! L L)."C E PAGE na .r ao 6 ARKANSAS NUCLEAR ONE asvision o*Ts -,e, g,, ._ CHANGE , , DATE n n ', , , ina y . .
Page 2 of,4 APPENDIX C (CONT'D) , f pu
= Minimum specified ultimate strength of tendon wire (ksi)
- Ay =
Cross sectional area of one tendon wire (in2 ) F wc
= Lift ff f rce per wire when initially tensioned during construction j (kips) th l Fyf = Liftoff force per wire at i surveillance (kips).
= -l Fy ,(g_3) Liftoff force per wire after retensioning at the i - 1 surveillance (kips)
N Normalizing factor for the i th surveillance Fi =
= Normalizing factor for the i - 1 surveillance '
NF (i-1) . n .
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g-2f., PLN JTMANUALSECTIO't PROCEDUREN/06( PLAN TITLE: '. NO. f p f6C REACTOR BUILDING, TENDON , b' FIPI^ ': ~T2** ?~II.U_"E - PAGE o
' la ARKANSAS NUCLEAR ONE aEvisia r
oa' C - s ;, CMNar DATIL ' 2 Page 3 of 4 V' PEND 1X C (CONT'D) 2.0 GENERAL i i ln To provide a common base for :va:panten, lif toff forces must 'ee normalized
, to account for elastic stress les.; during initial installation (a fur.ctan :
; of ths post-tensioning sequence) and liftoff force'deviatian from the bzse ]
value. The base value for ir.itial lif toff forces (at time of initial' tensioning) is taken as the force goducing an average vire s:ress of
.0.73f u.
'l The base value for the i surveillance is the normalized force i
'for t?ie i - 1 surveillance. The normalized focce is equal to the measured i force liu]tiplied by the normalizing factor. e
?-
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- x. ., + a. a . . . .La r 4 43- 2,7 PLANT MANUA1. SECTION: ' PROCEDURE / WORK PLAN TITLEf NCh, .,
L >: I&C REACTOR BUILDIM, TENDON r""!?"!C T"ST:
?'"".T !11.'.'TE i-4 2 ^ ' #
4 1 PAGE . .- e n I- --
. ARKANSAS NUCLEAR ONE i y fcs4 evisi=Hot
_ ~5DATE 0 sf 4, . ,4 ,g, _ g, , , , n , Page 4'e,f 4 APPENDIX C (CONT'D) l 3.0 FORMULAE 1 3.1 Normalizing Factor for First Surveillance (i = 1) , 3.1.1 Dome Tendons 4
, 0.73 f
; 'N = P" l-F1 Fq. C-1
'f, N -A
~
c d d 3 E Ng Ay aN d
' d ;
c ! 3.1.2 Hool. Tendons ' O.73 f e' c N = Pu - g1 ~ Eq. C-2 T- N -n Nv - n v c h h 3 ,y g, . E
/ NA w w N h. N t
v L C h v i 3.1.3 Vertical Tendons . 0.73 f -l N = Pu F1 Eq. C-3 L N y -n N -n c v n h g , y g E E Nw /'u N v N h c v h 3.2 ' Normalizing Factbrs for Subsequent Surveillance (i >1) Hoop, _ Vertical and Dome Tendons: N NF.= N f.(1 - 1) '(i - 1) x wr(i - 1) Eq. C-4 1 br (i - 1) . Nw (i - 1) - or
~
NF.1
=N F.(1 - 1) F . (i - 1)
W - Eq. C-5 wr(i - 1) 3.3 Normalized F.iitoff Force per Wire F.=F.N. wi F
~
[. N1 i Eq. C-6
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PROCEDURE / WOR % PLAN TITLE: NO: ,
- PLANT M ANUAL SECTION:
* " REACTOR BUILDING, TENDON
, y y I&C ,
^' ^'
TEF:C" " T:5T~ '"'" T !!L.":C E PAGE or ,c oc L atvism" d oATr - , , - , , - e ? ARKANSAS NUCLEAR ONE , CHANGE " DATE i Page 1 of I APPENDIX D n' 1.0
~
GENERAL The following drawings describe the elements of the post-tensioning system relevant to tendon surveillance. These drawings are available from Arkansas Power & Light Company. L Prescon Dwg. No. Dig, Description - I A04, A05, A06 Anchor Details A07 Tendon washer and shim details A08 Deadend plate-bottom vertical PH02, PH03, PH04 Horizontal tendon numbering system PH06, PH07, PH08 and tendon locations DPO4, DP05, DP06 Dome tendon numbering system and .
- l, ,he
- DP07, DP08 tendon locations PV01, PV02, PV03 Vertical tendon number system and PV46, PV41 tendon locations Bechtel Dwg. No. Dwg. Description A-501 Architectural -
Reactor Building Developed Elevations
& Details C-2608 Sh 1,2,3 Reactor Building Tendon Surveillance Schedule I g r _
l ( I s [ e_ i
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r- , I&C REACTOR BUILDING, TENDON , n, J provnnic ,reme ermetrywer , o n i. d Jl PAGE n, ,c no b M l- ARKANSAS NUCLEAR ONE aevisioN 2 oATE n,,n,,e, CHANGE DATE Page 1 of I Data Sheet #1 TENDON SURVEILL1NCE , SHEATHING FILLER REMOVAL & INSTALLATION } t Tendon ~No. Location FILLER REMOVAL DATE
" BY l (1) l Date Removal Started l l l (2) l Exterior Concrete Temperature (F ) l l 1 (3) l I I l (4) l Total Volume Removed (gal) l l l (5) l Color Change Observed j i l
l-(6) l Sample Taken l l j FILLER INSTALLATION DATE BY gj-l (1) l Date filler Cap Installed j l l (2) l Date Filler Installed l l l (3) l Exterior Concrete Temperature ( F) l l l (4) l l l _ l (5) l Filler Temperature at Pump ( F) l l l (6) l' Filler Temperature at Outlet Cap ( F) l l l (7) l Total Volume Installed (gal) l l l (8) l Installation Pressure (psi) l l
. i 1
1
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Approved: ) i Date: i k ho l
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s-r I&C REACTOR BUILDING, TENDON M'r g, . n n,
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, B -31 PLANT M ANUAL SECTION: PRCCEDURETWORK PLAN TITLE: NO:
I - I&C REACTOR BUILDING, TENDON l ! . . trovnnve "Prc+e et*DtrTTT Wer PAGE i n n t.-- n1 hi nn er no f
" l ' ARKANSAS NUCLEAR ONE aevisioN , oATE n,,n,,
._ . CHANGE DATE l
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------------------------y B-3 3 PLANT M ANUAt SECTION: PROCEDURE / WORK PLAN TITLE: NO:
- , I&C REACTOR BUILDING, TENDON '
' M penvnnte we me etmt7Tv r s ure. 4ene os A Li
~ ~ ' ' ~
,/] PAGE ei -c oc
"~'"l- ' ARKANSAS NUCLEAR ONE aavisio" o*Te ,,e, fb'./ - CHANGE DATE Page 1 of 1 Data Sheet #4 ARKANSAS UNIT I
- TENDON SURVEILLANCE WIRE INSPECTION DATA i
Tendon Identification Date Tendon Inspected By: Wire Length <(Uncut BH to Notch) Location Where BH Cut O' ..- 50' BH END i 50' 100'
<- 100' 150' ,
150' , 200' 1 200' 250' 250' 300'
*Specify locations of the three wire test samples on Data Sheet #2.
l'- 1/gn _ li _ on CORROSION #1 Bright Metal, No Visible oxidation LEVEL #2 Reddish Brown - No Pitting , fs #3 0 Pitting < .003" l #4 .003" Pitting 1 006"
#5 .006" Pitting 5 010" ; Approved By: Date:
I u ._- - _ .
p; "--~,r: 7.~T ,4. . - , . - . ' -
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PLANT M ANUAL SECTION: PROCEDUREfWORK PLAN TITLE:
~
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BF^CIRBg(( DING, TENDON PAGE aevisioN
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-t o ATE ~
~~
(k)
""6
' ARKANSAS NUCLEAR ONE CHANGE DATE Page 1 of I
. _ Data Sheet #3 ARKANSAS UNIT I TENDON SURVEILLANCE t'
(1) Tendon No. (2) Location (3) Date l l l 1 (6) By l (4). Jack No. (5) Gage No. l 1 1 DETENSIONING ACTUAL MEASURED i . DESCRIPTION l l (1) l Ext. Concr. Temperature ( F) l 1 l l l (2) __ l No. Eff. Wires l l (3) l Check Gages (Zero) l l e j l (4) _l Measure Shims l- (5 ) _ l Obtain Lift-Off Pressure (psi) l l* l l l (6) l[DepressurizetoZero psi) l l l (7) l Pressurize to 1000 lb/ wire ( l
> l (8) l Measure Elongation *- l l
l (9) l Depressurize to Zero l l . :i{b/ l (10) l_Remcve Ram l l l (11) l Was Inspec Wire Cut at This End? l l l l l (12) l Length Outside BH to Notch l l l l (13) l_ Check Continuity RETENSIONING l l (1) l Ext. Concr. Temperature ( F) .i l l l'(2) l No. Eff. Wires l l lm j (3) l Check Gages (Zero) l psi) l l l (4) _ l Pressurize to 1000 lb/ wire ( l_ l l l (5) l Measure Eloneation** l j (6) -l Pressurize to .8fpu( psi) l l l
~
l (7). l Measure Elongation at .8fpu l l l l (8) l Shim to New Lift-Offs l l l (9) I a) New Lift-Off l l l (10) l b) New Shims
- New lift-off is approximately' equal to that measured during Detensioning less the effect of any reduction in the number of effective wires.
** Elongation is the distance from the outside face of the bearing plate to the inside face of the anchor head.
Approved: _ Date:
.di.. .,
_ _ . . __ -M. %
W ' R r i.- :..- , .:T . . . . . ., ,. ..a 3
~
- s-33
. PLANT M ANUAL SECTION: PROCEDURE / WORK PLAN TITLE: NO:
> I&C REACTOR BUILDING, TENDON
* , , n i_ n3 ntn7gn!g w cac g'y'E !!_7 ' '" t -
PAGE ,c no [ 1. 1 l-(b')^ ' ARKANSAS NUCLEAR.ONE aevisioN CHANGE
, 0*Te DATE n,,e,,e, .
Page 1 of 1 ; Data Sheet #4 ARKANSAS UNIT I TENDON SURVEILLANCE WIRE INSPECTION DATA o Tendon Identification Date Tendon Inspected By: Wire Length <(Uncut BH to Notch) Location Where BH Cut 0' 4' 50' BH A/ [3 END 50' 100' czy
- 100' ,
150' 150' 200'
'W 200' 250' 250' 300'
*Specify locations of the three wire test samples on Data Sheet #2.
I - 1/8" - l' - 0" i CORROSION #1 Bright Metal, No Visible Oxidation LEVEL #2 Reddish Brown - No Pitting A #3 0 Pitting < .003" A/
#4 .003" Pitting 1 006"
'i-(
#5 .006" Pittirig $ .010" Approved By: Date:
\
7 . - - . . ,
~
g-3s PLANT M ANUAL S ECTION: PROCEDURE / WORK PLAN TITLE; N O. . 7- li I&C REACTOR BUILDING, TENDON ,
. [: .,. _., _, _ c._._......- ,--, ,,
p ._.._-.. ._s .- v. u.-'.w- -- p g.)= '" I ARKANSAS NUCLEAR ONE aevisio" CHANGE c o^tE
~ DATE m,,,,,e-
' ' ~ ~
Page 1 of 1 Data Sheet #5 l l i i 1 ARKANSAS UNIT I l l . TENDON SURVEILLANCE TENDON WIRE TEST l (1) l Tendon Identification l l l (2) l Sample Number j - l l (3) l Date Wire Tested l l l (4) l Date Recorded by: l l j (5) l Measure Wire Diameter (in.) l l l (6) l Measure Gage Lengthlin.) l l l (7) l Calculate 0.9% of Gage Length (in.) l l l (8) l Measure Distance I.D. Tag to Ram End of Specimen (in.) l l l (9) l Increase Pressure to psi
- l l l (10) l Zero load l l g l (11) l Increase Pressure to psi ** and Set Dial 1 l
l Indicator at -0.9% of Gage Length l l l l (12) l Increase Pressure Until Dial Indicator Shows l l l l 0.00" Extension. This is the 1% Yield Point ' l l l l Pressure l l
. l (13) l Record 1% Yield Point Pressure (psi) l l l (14) l Record Ruler Reading ,at 1% Yield Point (in.) l l (15) l Record Pressure at Wire failure (psi) l l l (16) l Record Rule Reading at Failure (in.) l l l (17) l Record Distance Between Wire Break and j l l l Ram End of Specimen l l
- The pressure applied in Step (9) seats the stressing washer onto the BH. '
** This pressure equals 0.1% of Gage length (0,1% Yield Point Pressure). -
6 W s ~ _h._
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'yc Aa 5 * ;si
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gm,yg;: ;3 ,, 3 j B-3 5 NO: PLANT MANUAL SECTION: PROCEDURE / WORK PLAN TITtE: REACTOR BUILDING, TENDON L 9h I&C -- t3
, ace ,, ,
aevisioN ~: ol'E -,,,, -- 6 ARKANSAS NUCLEAR ONE CHANGE ,[ , DATE o,
,,,n; Page 1 of 1 Data Sheet'#6 RAff/ JACK CALIBRATION RECORD .
I CONTPACT/PART No. : I_ PROJECT: Register No. l
! l Jack Description Tons _ PSI l flax. Pressure l Theoretical Ram Area Register No. Constant j l Calibrating Device Used Register No. l l Calibrating Gauge Description I
i l Ram Position - l Other Data or Remarks y l Run No. I* _l t l Actual Gauge i Load Cell l l 1 Test increment l Reading PSI Readout i l l Target PSI l l I I i I I 1 I I . I I .' ' I I I l I I I I l I Run No. Ram Position l I
' I I I I
b I I I I I I I I I l i
' l I I I
i I I ' I I l 1 l Ram Position l I Run No. I I 1 i l
- 1 I I
i I I I I I I i i I l I i' I I l I i 1 l l Calculation of Ram Area - Readout x Load Cell x Constant * + PSI (Gauge Date:Reading) 1 Date: Witness: [ l Calibrated By: sq. in. Agency: l LG l Computed t!ean Ram Area Verif. By: Date: I T I Computed By: Date: I (di,/ l
Title:
Title: I I Comments: I I l l Readings noted with an asterisk l- have not been used in the computation of the ( P l mean area. I
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t 2-36 WNYW44UAt$ECT!PWPROCEDURENIORKT't.ANTITLE:- 9(O ~
-M fi 9 I&C er o t an t e- Trc+c REACTOR BUILDI!!G, TENDON cttpyrvi t itr r 1764.01
{ O l PAGE t e ,, e oc in ""' ARKANSAS NUCLEAR ONE aEvisiOs = oars n, aa == {u/ 1 . CHANGEer , DATE n>fno/om FIGURE 1 I 9 l o o _.,- n O i O o O'O . . O O l' oO .
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.. ' IDENTIFIC ATIOli o '. ' . ' . NU;SER
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- 1. DELETED
- 2. HOLES SHALL BE SIZED AFTER HEAT TREATING.
~
- 3. HOLE DIAMETERS SHALL BE CERTIFIED PRIOR TO ALL TENDON SURVEIILAMCE BY USING CALIBRATED EQUIPMENT.
- 4. EACH GAGE SHALL HAVE AU IDENTIFYING HUMBER.
1-3 l i Q." mm.s. L'.l.- _ _ _ - _ _ _ _ .
6 - 3 'I
- PLANT M ANUAL SECTION: :.a PROCEDUREfWORK PLAN TITLE: NO:
; N I&C
} REACTOR SUILDING, TENDON .
crerrnir *re-e ct'rtrr ti T ttve r il 1mna_of PAGE tc as se
- 6 ARKANSAS NUCLEAR ONE aevision , o^rE
~
a,ence=, wr cHANGEer_7 DATE n>fnc/co e.w , FIGURE 2 HEAD SEE DET. r l l SLEEVE
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4 NOTE:
- 1. THE NUT WITH THE PULLING RING WELDED TO IT MAY BE REPLACED WITH AN EYE NUT.
- 2. THE ANCHOR HEAD I!UST EE PUSHED INTO THE TRUNPET TO GIVE A CLEAR DISTANCE OF AT LEAST ONE FOOT SETWEEN BUTTONHEADS AND ANCHOR HEAD IN ORDER TO USE THIS TOOL. THIS PERNITS THE WIRES TO NOVE APART SO THAT THE TOOL WILL SLIP OVER THE BUTTONHEADS.
- 3. DELETED i
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~ ' -
ISC REACTOR BUILDING, TENDON i 's
._.,.,-..i m,......-
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- l- ARKANSAS NUCLEAR ONE C.i !
h aevision CHANGE 1 o^te DATE i. FIGURE 3 . RE A!.1 TO SUIT _ 3 9 5. + coal BUTTC?. HEAD Page 1 of 1 osa. - coo m' l
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PLANT M A NVAL SECTION: PRCCEDURE/ WORK PLAN TITLE: NO: _' , ;r t 9A I&C REACTOR BUILDING, TENDON e._._ ,.. m.
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. .~seTi&%: , .:. w s : , . . . , . . ., r&T C-/ 10 YEAR PIrlSICAL SURVEILLANCE OF THE ARKANSAS NUCLEAR ONE' - UNIT 1 PRIMARY REACTOR CONTAINMENT BUILDING APPENDIX C: INRYCO JACK CALIBRATION PROCEDURE i i a e e o l 4 l l l
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Y 10
6 - 2. Procedure Number iuality y Control Procedure e Imyco an inland Steel company JACK CALIB. eege or Peges 1 1 5 ct ( CALIBRATION - EQUIPMENT a) QYA N CONTROL to '.' H ~ 6.5
- 1. PURPOSE:
The following procedure shall be used as the means of calibrating or determining l the area of hydraulic stressing jacks.
- 2. RESPONSIBILITY
- 1. The Supervisor, Quality Engineering or his designee shall be responsible for the witnessing, documenting and reviewing the activities of the procedure.
- 2. The Supervisor, Nuclear Engineering or his designee shall be responsible for the calculation of jack calibrations.
- 3. The Fie'id Equipment Manager shall be responsible for' equipment set-up and providing personnel to operate the equipment for ram data acquisition.
- 3. PROCEDURE
- 1. ' Clean the ram of excessive dirt, oil, or other residue that may unduly affect the calibration accuracy. . .
- 2. The load cell or testing machine shall be set up so that the loads will be applied in a uniform manner. -
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- 3. The ram shall be attached to the load cell or testing machine and centered so that the loads will be applied concentrically and uniformly.
- 4. For 1000 ton jacks, the target increments shall be about 1000 psi while about 500 psi target increments are used for the 1400 ton jacks. Note that target increments can vary according to accuracy requirements. These target increments shall be entered on Form 1.12.1 (See Attachment 1) by the Quality Engineering Inspector. The jack or ram shall then be loaded to these target pressures.
- 1. Cauge pressures shall not be reduced to meet a target increment.once a target increment has been exceeded. Readings shall be acceptable when they are within 100 pai of the target inc reme n t.
i
- 2. A minimum of three runs shall be made.for each of the required target increments. These runs will occur at about 1/4, 1/2, and 3/4 of the i
total ram extension for*each ram. *
- 3. The maximum ram pressure has been pre-determined by Engineering for each size ram to be calibrated and should not be exceeded, to avoid damaging the ram or to provide reference points that are not relevant. '
4 w () r APPROVED FOR ISSUE Revision: A Date: G-24-83 [MC
, , Supersedes:
Procedure Page Date Issued 8.S. p y /] j g/,,w no, b c780.17-50 Septembd 1976 INRYCO. Inc.
J d-3 Procedure Number tuality Contro Procedure e '=va an inland Steel company '^'* ege "N" 2 5 eege s [ ' ct CALIBRATION - EQUIPMENT gA gt CONTROL Effective Date g, _7,,c, , g 3
- 3. 4. 4. Readings of the load cell readout and the pressure gauge shall be taken at the same time.
I 5. For 1400 ton jacks, the minimum pressure to be used shall be 1000 psi. This value may be manually discarded if in the judgement of the Super-visor, Nuclear Engineering (or his designee) the 1000 psi readings are i distorting the calibration equations.
- 5. During ram data a.cquisition a calibrated hydraulic pressure gauge having the smallest reading equal to or less than 20 psi or a Heise Electronic Digital pressure indicator shall be used. The hydraulic pressure reading shall be taken to the nearest 5 pai or the actual digital readout shall be recorded on the calibration form.
- 1. The load cell or testing machine readout shall be entered onto the calibration record to the nearest 0.1 reading.
- 6. All other information areas of the calibration form shall be completely filled in by the calibration technician or the witnessing agent. Th e fo rm shall be signed and dated. The calibration record will then be handed over ,
to the Engineering section for final computation.
- 4. COMPUTATION OF RAM AREA f) hM Rsgression analysis shall be used to compute the ram area, once the initial raw data has been d-cumented on the Jack Calibration Record Form. The personnel parforming the computation and verification checks shall sign and date the Calibration Form and the computer printout.
- 1. Computation shall be performed by the computer. All data entered into the computer shall also be printed out. This data, as well as the computer results, shall be verified by someone other than the person operating the computer.-
- 2. In the event that the computer is temporarily unavailable, computations may be performed manually observing the same methods being used by the computer. These manual computations shall be verified and/or corrected by a computer computation as soon as practical. The manual computations shall only be performed by the Inryco Engineering Department personnel.
- 3. Omitted readings, dropouts, are automatically considered by the computer.
An explanation shall be found in Attachment 2, Section 8. C v APPROVED FOR ISSUE Revision: A Date: (o- 2.4 - t,3 hh. ' Supersedes: Procedure Page Date Issued 1.5. M /myA No. b 780.17-1d Septembe/1976 INRYCO. Inc.
c+ Procedure Number iua ity Control Procedure 4> 'arva an inland Steel company
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CALIBRATION - EQUIFMENT hALIffCONTROL _
- 5. CALIBRATION DOCUMENT DISTRIBUTION After completion of the verification check of the ram area calculations, the following distribution of the calibration record shall be made.
- 1. The original calibration record shall be sent to Quality Engineering for retention in the calibration file. '
A. Quality Engin'eering shall prepare a shipping documentation package for the stressing jacks or other rams and submit copies of this package for inclusion in the:
- 1. Contract Management Files.
- 2. Engineering Jack Calibration Files.
B. Copies of the calibration record shall be distributed to:
~
- 1. Contrac t Management or Coordinators / Project Managers. ,
- 2. Equipment Maintenance, Jack Number File, fS 3. Equipment Maintenance, Jack Calibration File.
C., At least one copy shall accompany the stressing Jack or small ram for shipment to the field. This ' copy shall be retained in the appropriate Quality or Documentation File on site. APPROVED FOR ISSUE Revision: A Date: G -2 9 -83 gh . Supersedes: g,3, Pro edure Page Date Issued @ 780.17-10 Septe/oer 1976 JNRYCO. Inc.
C .5 Procedure Number a ua ity Control Procedure 4 inrva an inland Steel company '^f 3 " Pege s 4 -5 _hiect Section Effective Date CALIBRATION - EQUIPMENT QUALITY CONTROL _ g _ gcy - %
- 6. OTHER CONTROLS .
- 1. Calibration stickers or any other calibration information may or may not be applied to the rams. The nature of the jacks plus the constant handling make it very difficult, if not impossible, to retain any markings or temporarily attached devices. ,
- 2. Calibration frequency and recall control shall be found in the appropriate Procedure. .
- 3. Requirements for other conditions mandating recalibration shall be specified in the Quality Assurance Manual or appropriate Procedure.
- 7. DOCUMENTATION The calibration of a ram shall be documented on the Ram / Jack Calibration Record Form 1.12.1 or a similar document. The computation shall be in the form of computer printout sheets.
- 1. All documents generated by this procedure shall be filed per Procedure .
'QC 1.3.2.
- 8. APPENDIX n
7 Attached to this procedure are the following documents that shall detail the computation of ram force as a function of gauge pressure using Linear Regression cad computation of errors. Appendix 1 - Ram / Jack Calibration Record Form Appendix 2 - Jack Calibration Using Linear Regression
- APPROVED FOR ISSUE Revision
- A Date: G - 2.ct - 83 h . Supersedes: I
'r ,
Procedure Page Date Issued E. S . A,f.o.- No. b @ 780.17-10 Septemt$er 1976 IfiRYCO, Inc.
6-fc Procedure Number Lua ity Cof1 trol Procedure e 'arva an inland Steel cornpany Jg7" Pe9es
*5 5 ' 'ct Section Effective Date CALIBRATION - EQUIPMENT QUALITY CONTROL (c Z/1 -t$ 'S
- 9. DEFINITIONS
- 1. A ram is defined as the piston part of a force pump. It is the area of the piston which is to be measured by the means of calibration.
- 2. A jack is defined as the entire force pump with the various' attachments that permit it to pull or lift. For Post-Tensioning operations the applied force pulls one end of a tendon.
- 10. . OWNER WITNESSING
- 1. Where the project documents require the witnessing of ram calibration. Inryco shall notify the Owner or his agent to perform the witnessing.
- 1. If it is acceptable to the Owner, Inryco shall have an independent inspection / laboratory source, who is acceptable to the Owner, perform the witnessing function.
- 2. Where the project documents do not specify a witnessing requirement, Inryco may or may not provide witnessing, at Inryco's option.
- 11. WITNESSING ACTIVITY Tha witnessing activity consists of a visual observation of those operations that are h casociated with the calibration of the ram.
- 1. The witness shall be a qualified individual from'an independent inspection or laboratory source.
- 2. The witnessing function shall consist of:
.1. Verifying that the information posted on the calibration form is representa-tive of the device being calibrated. '
- 2. Verifying the readings 'taken of the ' load cell readout and pressure gauge a,t each increment. l
, l 1
- 3. Signing the Calibration Record Form in the Witness Area attesting to the '
accuracy and acceptance of the raw data being entered. .
- 4. Rejecting any activity not in conformance with the accumulation of the raw calibration data or not in compliance with Section 1 of this procedure.
- 3. The witness does not verify the actual computation of the ram area as this is a computer controlled function based on the "JKCALNR9 Jack Calibration Program".
h APPROVED FOR ISSUE Revision: A Date: M2,9-63 h r h , Supersedes: Page Date Issued Procedure E. S . g /o,yh No. b E780.1)-10 SepteIber1976 INRYCO, Inc.
d.-7 ATTAC1UENT #1 RMi/ JACK CALIBRATION RECORD FORM
. % ) Inryco an inland Steel company D
RAM / JACK CALIBRATION RECORD Form OC l.12.1 g PROJECT " CONTRACT /PART NO. Jack Description Size Tona Regieter No-Theoretical Ram Area ' Max. Pressure PSI Calibrating Devica Register No. Constan't Calibrettaw Caude Resister No. 11a t e Amw Data By WITNESS Haan Ram Araa sq.in. K. Kipe Agency
- Data Computed By QC Che'ck Title Date Level Date Target PSI Cauee R edine PSI l Load Cell Readout
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CO M NTS RUN POSITION I . i j i l kUN_ _ FOSITION ,,, I I
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C-6 ATTACHMENT # 2
. JACK CALIBRATION USING LINEAR RECRESSION an inland Steel company
- 1. THEORY OF LINEAR REGRESSION The theory of Linear Regression, which uses the principle of Least Squares to obtain the line of best fit, shall be used to determine the relationship between rem force and gauge pressure. The equation of such a line is y = a + bx =
prediction' ram force, where b'= n E (xy ) - (Ex)(Ey )= slope of the line of best fit (regression n E (x4) ,- (E x)Z line) a = .y- bx = y - intercept of the line x= ' (T.x)/n = mean of all x-readings (gauge pressures) y= (ry)/n = mean of all y-readings (measured ram forc'es) n= number of pairs of x, y readings. All readings for all three ram positions will be considered together.
- 2. COMPUTATION OF RESIDUALS (ERRORS)
For each gair of readings, the residual quantity unexplained by regression, Y res. = y - y, will be determined. The percentage residual will also be s datermined as E 1 =(Y res/'y) x 100. Notethat9isthepredictedy-reading using the linear regression equation. 3.* OTHER ERRORS
- All other errors due to calibration such as interpolation, accuracy and/or repeatability of the Standards . certified by the National Bureau of Standards, repeatability of gauges used in calibration or in the field, etc. shall be listed on co6puter print-out. As a minimum, the following items shall be considered.,
- 1. AT JACK CALIBRATION'
- l. Error in Standard (varies between repeatability of 3 pai to maximum guaranteed value of 10 psi).. .. use S=(K+.003)ksi or ac tual value.
4 4 t2tles
- Previous A A at g g -tet - B % "" '*" / \ Reviston: /O\ G- E9 - 63 Page l c f" 9 y M4.204 10 nuvescer A W tharCO. Inc.
dL-9 ATTACHMENT # 2 . JACK CALIBRATION USINC LINEAR RECRESSION an inland Steet company
- 3. 1. 2. Interpolation error of calibration gauge against which the jack is compared with the standard....use (Cc/2R)'ksi or ac tual value.
- 3. Accuracy and repeatability of calibration gauge = 0, since the calibra-tion gauge is adjusted to match the Standard each time.
- 2. AT CAUGE CALIBRATION
- 1. Interpolation e rror in Mas ter. . . . . . . . use (Cm/2R)ksi or ac tual value.
- 2. Interpolation error in Field Gauge. ..use (Cf/2R)ksi or ac tual value.
- 3. Ac curacy o f Ma s te r. . . . . . . . . . . . . . . . . . . us e M=(S + Am)ksi or ac tual value.
- 4. Accuracy o f Fie ld Gauge. . . . . . . . . . . . . . use F=(S + Af)ks i or ac tua l value.
- 3. AT FIELD USE OF CAUGE
- 1. Interpola tion e rror. . . . . . . . . . . . . . . . . . us e. (Cf/2R)k si or ac tual value'.
- 2. Ac c ur a cy. . . . . . . . . . . . . . . . . . . . . . . . . . . . . us e E= (M + Af )k s i o r ac t ua l va l ue .
- 4. DEFINITIONS s .
K = Actual calibration value of Standard. . S = Error in Standard (traceable to NBS).
- C = Smallest Cauge scale face reading. (Graduations)
A = Manufactured guaranteed accuracy. , M = Calibrated accuracy of Master Cauge.
, F = Calibrated accuracy of Field Cauge. '
E = Calibration error in field. R = Degree of Interpolation that the gauge is being read. m = Denotes Master Cauge. f = Denotes Field Cauge. ! c = Denotes Calibration Cauge. ! b3tiv3 . Previews 1 0: gf g y g3 sevision: Revision: A Page l
/O\ G-M-63 $ C l" i
) ;M,204 10 m v moer 1984 lhRlW . anc. l l
ATTACHMENT #2 JACK CALIBRATION USING LINEAR REGRESSION h' cn inryco inland Steel comp . D.5. 3 ERROR CALCULATION - EXAMPL_E ' Let K = .002 kai; Ce = .010 kai; Cm = .050 ksi; cf = .050 kai; M = ( 005 + .025) or .030 kai; E = (.030 + .050) or .080 kai S = (.002 + .003) or .005 kai; Am = .025 kai; Af = .050 kai. R =.2 F = (.005 + .050) or .055 kai
- 1. From the above list of values the most probable sum of the "other" l errors shall be calculated as the square root of the sum of squares.
For the stated values. Eo = t, )[(errors)2=+.1040kai
- 2. The most probable error will be calculated as a percentage of the maximum gauge reading, for example:
Maximum gauge reading = 7.6 kai (7,600 psi) The mos't probable error as a percentage of the maximum gauge reading = E2 = .1040 x 100 = 1.37%
- D 6. COMBINED ERRORS
- 7. 6
' The residuals from the regression (jack calibration errors) shall be combined with the "other" errors t'o result in the most pro'bable total error.
Most probable total error, E=q[E 1 2
+E2 2 3, ,
- 7. RECALIBRATION If the most probable total error, E is greater than 2%, the jack shall be recalibrates or more accurate gauges shall be used to reduce the value of E to 2% or less. If the jack has any repairs performed that could affect the ram area , then that jack shall be recalibrates.
~~ . s- , , estive * . Pre.tous A A a: g 6-t.q g3 aev i s taa : /__\ sevtsion: /o\ 6-29-8 1 Page
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) 164.204-40 tuave= Der (wa2 IARfCD. inc.
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-ATTACHMENT # 2 8
, f )Inrycoan tnland Steet company JACK CALIBRATION USING LINEAR REGRESSION 8.. OMITTED READINGS (Computer Dropouts) '
.During the calibration of the ram using the Jack Calibration - Linear Regression Program - JKCALNR9 simultaneous readings of the gauge pressure and the ' load cell indicator are taken. If plotted, these readings would form a scatter diagram from which a "line of best fit" could be drawn. If the most probable error exceeds 2%, then the computer program locates the one data po, int that was furthest from the prediction line and assumes this point to be in error.
'Iherefore this " error" point shall be automatically discarded by the computer and recomputed'as stated in the JKCALNR9 program. If more than one-third of the points are eliminated in this manner, the data is considered unsatisfactory and recalibration performed. .
/
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10 YEAR PHYSICAL SURVEILLANCE OF THE ARKANSAS NUCLEAR - ONE'- UMIT 1 PRIMARY REACTOR CONTAINMENT BUILDING ' 4 ,'T' APPENDIX D: SHEATHING FILLER REMOVAL & J INSTALLATION DATA SEEETS 1 6 j/ g s E o 0 e f [j' __n _>Ga _ _ _ . _ . _ _ _ _ _ _ _ _ _
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-PLA NT M ANU AL SECTION: ' PROCEDURffWORK PLAN TITtE:
I&C NO; J ,. ""'*4 REACTOR EUILDI :G, TE.'. DON m - . - - c <. c..........-
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cQ NN@ i ARKANSAS NUCLEAR ONc l lPAGE i aevisio~
.c 3e o^ s -'ee l CHANGE DATE
_ Page 1 of 1 1
/Q y,. Data Sheet #1 TENDON SURVEILLANCE J
in ~Shi.ATh1NG FILLER REC 10 VAL & INSTALLATION Tendon No. \/-tQ,._ Locati.on J ,_ FILLER RE!!0 VAL DATE S-)) %, BY O ,.u o\ 4 .M ,' m rJr. J l l (1) l Date hemoval Started (, l (.2) l Exterior Concrete Temperature (f") l q .t ) . g l I l73) l __l typ fe l ( (4) l Total Volume Removed (gal) l , 1 W ca l. l (5) l Color Chance Observed l_ _ , __,, l j~T6) l Sample Taken l ANS I _l Koe, l FILLER INSTALLATION ' l DATE a , /i . R3 BY.Ib.. $-ore,2,g d ((, ' l (1) lDatehiller[ Iastalled l (2) l Date filler l [asca p d l n -// . v- g - l l (3) l Exterior Corcrete Temperature ('f) __
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I (4) l .l g4os l 1 l (5) l Filler Terrerature at h.mu ( F) l l_ l_16)..__l. filler.2emperature at Outlet Cap (*F) 4//o l l'(7) l Total VoTun installed (salJ ~l i '4 /> . l t J, (8) l Installatic.n Pressure l psi) / </c. , / l [ /4 ../ g!,,3,/ r._g/ ) 7 / .- 59.3 98 P t T2 <f 2 'P
= T3 = 5q G 7 'l*r= 2.
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3g PLANT M ANU AL SECTION: l FRO'.d' OUFij/WOAK PLAN TITLE: NOi c ' ;; 9 I gh e&C. i rermec -re-e l' REACTOR eiet- vrr mer BUILDING, TENDON . C_;. "g 6 Pace , ,, ,, en, ni ARKANSAS NUC! EAR ONc aevisioN o^Te e,m,,- 2, CHANGE DATE Page 1 of I
/#ye TENDON SURVEILLANCE SEATIG"G FII_.LER REMOVAL & INSTALLATION i-Tendon No. ///S Loeacion d'-fLLED'-//C4Z) _
FILLER REMOVAL DATE 2 - //- 8' 3 BY -f A"J _ -l
- l. (1) l Date Removal Started l (2) l Exterior Concrete Temperature (F )
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1 1 Approved: geC.,-y/m Date: 3 /63 ---- , ,- . C M c M r> b /. YQ '>u f { one. 3p;/n / O , l
_ __ - -- - - -------- -----~--~~ '~ b-4 PLANT M ANUAL SECTION: PROCEOURE! WORK PLAN TITLE-I&C NO:
- J 1;J '"] e ornner -1 e- e-REACTOR BUILDING, TENDON e . - , , - v r . . .c r.
m y L@ PAGE n- ,r ao ARKANSAS NUCLEAR ONE aevi=N - oars - ~ , CHANGE DATE
~ Page 1 of I
//7,y Data Sheet #1 TENDON SURVEILLA' ICE D
s SHEATHING FILLER RE.'! OVAL & INSTALLATION Tendon No. \/ - 2K
- Loca tiori shnn
, FILLER REMOVAL t DATE A-i0- v3
. . BY ( b ,,; t .S e b e t u <-if g l (1) l Date Removal Started l (2) l Exterior Concrete Temperature F") i o fo-g3 l l (3) l l 93 S' p l l (4) l Total Volume Removea tcal) l _ l l (5) l Color Chance Observed l $/q e,1) l l N o,uVc l (6 )~ l Sampic Taken . l l yes / ny. l v FILLER INSTALLATION DATE 2-[6 n BY ( b ,:\ h .t - l (1) _l Date Filler Cao Installed l (2) l Date filler Installed i 1- 1(_)- W3 l l (3) l Exterior Concrete Iemoerature ( F) l 2 -/,:, sr :::, l l (4) l { r; 3 'fr-l 1 l (5) l Filler Temperature at Pump ( F) 1 l
] (6) l Filler Temperature at uutlet Cap ( F) l ,(//,:/
l l (7) l Total Volume Installed (gal) l ,. /4 l E ] (8) l Installation Pressure (psi) ~l 2 %, c <, / l l 4f.. ,.M?-y/,,/ Ct/ l
, l*/= El 31'V ' ' L
k - T3 = so. 67Y c;= yn/n x I
I l Date- wn/./ ] - f -
PLANT M ANUAL SECTION: h-fo i ' PROCEDUREN/ORK PLAN TITLE: I&C-j i; __neer nec re e REACTOR BUILDING TE.'T20N fiO'.
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SHEATHING FILLER FI.'!0 VAL & INSTALL $ TION Tendon No. V-73 tocation SAco , FILLER FIMOVAL DATE S//z.//gr z BY _/1rn a l Re b ,v. <L (M(o" M mPro e-E bb.v kr., (b.u Tn 6 ,- - . d (1) l Date Remoial Startea 4
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l( l Exterior Concrete Temoersture tF ) l _ h // u / s- ; ~
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l SdWb adof l l (4) l Total Volume Removea teal) @dv' l (5) l Color Chan e Observed l _
/'6 c/a/ l llto; l Samote Ta. ken 4/O.,v5,1_(.)op dp ?Ao *%e su . / ~G,, (r9' l i ko.s (12en o, o/o c, )
b& CN I gg FILLER INSTALLATION 2//6/rf9
~
DATE ' s m 54ccb. BY /2, ,,, / %Ai - ,,sh; v l (1) l Date filler Cao Installeo l (2) l Date Filler Installea i f2/er/m l j (3) l Exterior Concrete Temperature ( F) l n /A.r/ n _! l (4) l 1 Wi*# 1 l (5) 1 I l (6) ll Filler Temoera ture a t Pumo ( of) Filler Temperature at Outlet Cao ( l N/A l l (7) F) { y/4 l (8) ll Installation Total Volume installea leall Pressure Iost> l ,q ui , ,,, /s l
~l l (,,J,) f) .do4 ~l Approved: M ,.,f(',
Date:
~
3/h%/.5-g \ s 1 i O 9
s . h-7 ) PLANT M ANUAL S ECTION:
""j PRCOEDUREN/ORK PLAN TITLE:
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-6 n- : no ARKANSAS NUCLEAR ONE aevisio" - oarE as. <e, CNANGE DATE Page I of I Data Sheet #1
/a TENDON SURVEILLANCE SHEATHING FILLER ret! OVAL & INSTALLATION l
i Tendon No. Y73 Location M M f/ / /E4 B FILLER REMOVAL DATE 2- / Y- ?3
. BY /A ~-A l (1) l Date Removal Started g-/t/-r:3 l (2) l Exterior Concrete Temperature if )
l r l l (3) l l 7 +r op: l l (4) l Total Volume Removed (cal) l l l (5) l' Color Change Observed l y 6,:s t . l l (6) l Sample Taken l 7//# A'/ggj:e fregy).4/evg l kj,97672
- Fcu,U.O l VES l
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To 3 c2 .of N47EK C4M.f #pr ARoua THE AringS g) 1 g FILLER INSTALLATION DATE BY 3 -/5 ' 6'"3
/MC 3 /, ,_
l (1) l Date Filler Cao Installed l (2) l Date Filler Installed [ z z-/5 -9 3 l l (3) l Exterior Concrete Temperature ( F) l /s-93 I l (4) l [ /g, <>/=' l l (5) l Filler Temperature at Pumo i F) l l l (6) l Filler Temperature at Outlet Cao ( F) l l g/* l 1 (7) l Total Volume Installed (eal) ' l l (8) l 6 C,4 L. l Installation Pressure tpsi) l /pp49) -perfz 4 l d o /- /) l [/:57679'+ 72 : +'4 ' , 33 = 5y, gn
,gj,.,
T/ p//b T2: Q; 3 3 ,_ q q,,gg ,,,,,,, 2. Approved: ((4 Date: 7/9-/f:-3. , CHECKEb By*
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,b g PLANT MANUAL SECTION:
PROCEDUP EMORK PLAN TITLE: HQ: I&C F L nen mnre ereve REACTOR BUILDING, TENDON cinne ri y wre d l a ARKANSAS NUCLEAR ONE PAGE ae vis m N n3 _s no
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eunon n, CHANGE DATE Page 1 of 1 IC ;<a Data Sheet //1x TENDON SURVEILLANCE SHEATHING FILLER REMOVAL & INS'IALLATION Tendon No. 7 l H 4l , Location Shop FILLER REMOVAL , DATE 2.-3-93 BY A sl (b -., wo . a l (1) l Date Removal Started j l (2) _l Exterior Concrete Temperature (F ) 2.-3-33 l l (3) l l 3 7 c' F l l l (4) ~l Total Volume Removed (gal) l l (5) l Color Chance Observed l 3 /2 GAL l l (6)_ l Sample Taken l vc v s- l l yEs l .(' h FILLER INSTALLATION DATE 2 W-93 BY EA s.;z j_ (1) j Date Filler Cap Installed l (2) _ l Date Filler Installed l 2. / - 9 3 l l (3) l J -2 2 -y3 l Exterior Concrete Temperature ("F) l
! (4) 1.
l 6Pcp l l_(5) l Filler Temperature at Pump ( F) cestgel_ m.4 20c'p / 4 7 n,?v.9 ) l l (6) l Filler Temperature at Outlet Cao (*F) ( -g l l (7) l~(8) l Total Volume Installed (cal) l 3 'z c4L l l Installation Pressure (psi) l AOu M D l l Approved: #M. M Date: 5/V/$2 O'CCMb MW-87 h,x Yh/[' SSAr3 e*
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PLANT MANUAL SECTION: b-9 __
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- PROCEDURE / WORK PLAN TITLE: HO:
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/Cyg TENDON SURVEILLANCE SHEATHING FILLER REMOVAL & INSTALLATION Tendon No. 2!H4/ Location #/EL 3 FILLER REMOVAL
, DATE 2 - F-F 3 BY MsE l_(1) l Date Removal Started 2 - ; y3 l
l __ (2 ) l Exterior Concrete Temperature (F ) l S y u /- l l (3)- l _ l_ l l .__ (4 ) l Total Volume Nemoved (gal) l .5 c, r<c l l_ (5) l Color Change Observed l l_(6) l Sample Taken l aows l l yES l FILLER INSTALLATION DATE 2-4-s 3 BY [h,d \ 5-be,o # a l_ (1) l Date Filler Cap Installed l 2. 9 ; _ (2) __l Date Filler Installed 2-2t 4 3 l l33) l l Exterior Concrete Temperature ( F) 1 70*r f% 4_ l l (4) l l l l l _( 5) l Filler Temperature at Pump ( F) /&, 'F l l (6) l Filler Temperature at Outlet Can (*F) l j Mo'r h+ .xvv/ l l (7)_ l Total Volume Installed (eal) l 2V4 6- 4 L . l
- l __ (8) _
l Installation Pressure (psi) j /avd N4fpED l l l Approved: -m/e Date: 3/F/ Fe_. wkCAEO Bf 12K IM ' am O a4cAn ff' m
PLANT M ANUAL SECTION:
. b-/O l',e .J og""4
'_ PROCEDURE / WORK PLAN TITLE:
!&C Nd ee- - -n v r -re e REACTOR BUILDING, TENT;0N {)
.- ' 'qej em. v r e u.-e
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CHANGE DATE ! Page 1 of 1
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/0vA Data Sheet //1 TENDON SURVEILLANCE SHEATIIING FILL R REI!0 VAL & INSTALLATION Tendon No. 3IIl/5 -
Location SHOP FILLER RE.'!0 VAL DATE 3- /-9 3 BY A&w4. l (1) l Date Remova t Startea l (2) l Exterior Concrete remoerature (F ) l 3-l-V3 l l (3) l l_ 4 Y 0,# l l (4) ] Total Volume Removec t eal) l _ l l (5) l Color Chance Observea l 2 8,/z c, A t l l.(6) l Samole Taken l A't 4/E l __ l J'6.S l FILLER INSTALLATION DATE S- 2,9- 3 ' 9 ST #9"yA /-1.-- l (1) l Date Filler Cao Inst llea
] (2) l Date Filler Installea 'l _3.2-Y3 l l (3) i s Oss l (4) ll Exterior Concrete Ieccerature ( F) l cty #F' l
l l 15) l Filler Temperature at Pumo ( F) l r ic/c J'~ os l l (6) l Filler Temperature at Outlet Cao (*F) l ' r / 31 e /- 9/a /n l J (7) l ' /d . (3 , ,, lt l (8) l Total Volume Installed teal) l V _l l Installation Pressure tosi) l Af,,.,f] l
/% & n ,j . l J ,
9 Approved: [ief #
' Date: 3/r/ w CHCCtcm N y
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34/o #
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1 J" I PROCECUREN/ORK PLAN TITLE: Nb d 1; M, e&C e r-nec e e REACTOR BUILDING, TENDON -
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v ARKANSAS NUCLEAR ONE TaE=N , o4TE a-,e, CHANGE DATE Page 1 of I l Data Sheet #1 V
/M<g TENDON SURVEILLANCE J
! SHEATHING FILLER REIIOVAL & INSTALLATION I Tendon No. %) 14 if Location &L] FILLER REMOVAL DATE ili/93 BY k st f ,&.,1, A ,' V l (1) l Date Removal Started l (2) l Exterior Concrete Temoera ture (F ) l 2,/ l / 5 % l l (3) l l Mf I l (4J l Total Volume Removec (eal) l l l (5) l Color Chance Observed l _
% coj l l (6) l Samole Taken i hp G I l_ Pa c, I
FILLER INSTAU.ATION DATE o,/2/93 ' BY Dwa \ $sce nk , l (1) l Date Filler Cao Installed l (2) l Date Filler Installea l 4/o /gt l
~3/b/gi l (3) l Exterior Concrete reaperature ( F) i l
l (4) l l 49 7 l l (5) l Filler Temperature at Pumo ( F) l l l (6) l Filler Temperature at Outlet Cao ( F) l _ l OnQ'r l l (7) l Total Volume Installed (call Ub 3/q/g,
~ ) c7(. o p-l l (8) l Installation Pressure (esi) -q 7A m4 . 3,nl l
_l Q ,,,,# o y V J l 4 'A CL dck CoM . Approved: /[rNare Date. _,j&/F93 . CHECKED Ry .,n
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PLANT M ANUAL SECTION: b-/3 y
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PROCEDUREAVO AK PLAN TITLE: REACTOR BUILDING, TENDON NO:
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- PAGE 6- .. 3e ARKANSAS NUCLEAR ONE 1R EVIE10N oATE n,..,,.'
ICHANGE DATE Page 1 of I
/C ,,r TENDON SURVEILLA','CE Data Sheet #1 v
SHEATHING FILLER REMOVAL & INSTALLATION Tendon No. 3Oh A Locatidn & 4] FILLER REMOVAL DATE_ a/e s/gx BY j (,,,a) 5,.1,, . , g lc, a l (1) l _ Date Removal sta rtec l (2) l Exterior Concrete femoerature tF") ( 2 /.u/ q.3, l l (3) i l_ Agos ' l l (4) l Total Volume Removea ten 1) I I l (5) l Color Cnanze Ooserveo l 2 % ,. , / v l l ( o-) l Afo,,f; l Samote Taken i pec-l l FILLER INSTALLATION DATE 3/Mgi ~ BY f_ Lord SA,,,-d; J l (1) l Date Filler Cao Insta11ec l (2) l Date filler Insta11ec l 2/'g'/gq S3 l l ( .3 ) l 9h l (4) ll Exterior Concrete Tercerature i F) l l 73ap l l (5) l Filler Temperature at Pumo i F) l _ l l (6) l Filler Temperature at Outlet Cao ( F) l /Ga p l l (7) l a q */- l (8) ll Total Volume Insta11ec (ealJ l l o% f c,a /c Installation Pressure tosi) l /sy ,,,/ p;/~ ~c / l l
/
Approved: _ [dy. f. Date: 3/$ f/* gn.,
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= ; PLANT M ANU AL SECTION: h-/+
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/6'ye Data Sheet #1 TENDON SURVEILLANCE SHEATHING FILLER REMOVAL & INSTALLATION i
Tendon No. 82///9' - Location SRcP ] FILLER REMOVAL DATE 2-22-S'3 L BY CAM r . 3 ~ L l (1) l Date Removal Startec l 2 - Z Z. C'3 l (2) l Exterior Concrete Temperature tFa) l g,6 cp 5 l l (3) l l l }. l (4) l Total Volume Removea (eal) l 2 ca t l d l (5) l Color Chanze Observed i vovE l j . (6.) l Sample Taken l l YTS . l FILLER INSTALLATION DATE 2 -2 2. - S'3 ' BY M de @. l (1) } Date tiller Cao Installed l 3 - 2. 2 - e 3 ] l (2) l Date Filler Installed l Afg/v es /.W /26. l J l (3) l Exterior Concrete Temperature ( F) l M /' l l (4) l l l l (5) l Filler Temperature at Pumo ( F) l / c79 "# l l (6) _ l Filler Temperature at Outlet Cap ( F) l /S/,ep' l l (7) l Total Volume Installed leal) l l (8) l Installation Pressure (psi) l 3 '/a m /e l l j f. m / /J,,,,,c ; // l ; v l' l Approved: & //M2 Date: $~/kN e c ncKED Bb , M M M d ,' [ g/Wrt3 OSTE j 1 o e
4 b-/ 5 PLANT M ANUAL S ECTION: PROCEDUREAVORK PLAN TITLE: NO: ' '
- I&C REACTOR BUILDING, TENDON d ..i h4 ocornnre reme em rrr r u ce
" q6 g gage ,- -,,o 4,' n, i ARKANSAS NUCi_E:AR ONE aevisio" CHANGE
- o^re ' 'e e DATE l
Page 1 'of 1 '
/8xe TENDON SURVEILLANCE SHEATHING FILLER REMOVAL & INSTALLATION Tendon No. S2#/9 Location 7/E4b l l
FILLER REMOVAL DATE 22-r.37 . . . / ; BY w
- m. fX46 zu dr'
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l (1) l Date Removal Started l Z-2 2 - S".3 l l (2) l Exterior Concrete Temperature (f ) l 6 3 "F- l l (3) l l l l (4) l Total Volume Removed (gal) l z '/2. s A L l l f 5) l Color Change Observed l A>co r l l (6) l Sample Taken l Ves . l FILLER INSTALLATION DATE 22 ,, BY M , Y/ E fn y,/4-AV er l (1) l Date Filler Cap Installed l 2-22-93 l. l (2) I Date filler Installed l 3.g.gg j3p ,gs. l l (3) l Exterior Concrete remuerature ( F) l Ac3e p- l l (4) l l
~
l l (5) l Filler Temperature at Pume ( F) l /7D*p l l (6) l Filler Temperature at Outlet Cap (of) l j,c,2 6p l l (7) l Total Volume Installed (sal) l g '4 y/c l l'(8) l Installation Pressure (psi) l g,,s 4,L,.,./ l V~ Approved: f[mgr Date: 3/W83 , _ caecleo av:ftLd4b? ,d ORTE. 3Nk3 / Q O - [ .
.b ~n, PLANT M ANUAL SECTION: PROCEDURE /NORK PLAN TITLE: NO:
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TENDON SURVEILLANCE SHEATHING FILLER RE:10 VAL & INSTALLATION ; Tendon No. 82N /5' . Location SNoP FILLER REMOVAL 'DATE 2-24-9-3 BY #4wgm l (1) l Date Removal Started ( t-Z.4-93 l (2) l Exterior Concrete Iemoerature (F ) l 6 6 I: l l (3) l- I l l (4) l Total Volume Removea teal) l 2.W GAL. l l (5) l Color Chanze Observed l No A/6 l l-(6) l Samole Taken l v6T - l l FILLER INSTALLATION DATE 2-2.5-93' BY p'.:* W*' e sr l (1) l Date Filler Cao Installed ~l 7-Z.5-93 l,(2) l Date filler Installed l 3 St 3 , w #f l l (3) l Exterior Concrete Temperature ( F) l 7s ",e-I l (4) l l l l (5) l Filler Temperature at Pumo ( F) l (>eb -f6 # l l (6) l Filler Temperature at Outlet Cao (oF) l /4r y *p _ o d /r l l (7) l Total Volume Installed (eal) l Q mA. l l (8) l Installation Pressure (psi) l A ,,/ ,0f, ,,, ,, ,,,./ l l Approyed: [d,,, -d Date: 3/e/@2- ,. _. , CMCxcoBh ' sa.bh ' -Q' wr a N sa / O
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l- , l PLANT M ANUAL SECTION:
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- PROCEDUREN/ORK PLAN TITLE:
I REACTOR BUILDING, TENDON NO: l_ m&C,-1, -ce l,53ligJty r e , - . m . ., . , g e, NL {PAGE m- .e 90 . _' ARKANSAS NUCLE:AR ONE taevisio" - o^'" ' -
'e- i l CHANGE DATE Page 1 of 1
/C iv .e TENDON SURVEILLA';CE Data Sheet #1
- SHEATHING FILLER RE:!0 VAL & INSTALLATION Tendon No. 3 2 # /A'
._ Location & 4-/ FILLER REMOVAL DATE o /cq /p t BY h ir] sche ,,, ,g,
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l (1) l Date fiemoval Started n /a y/9 9 l (2) l Exterior Concrete remoerature tF ) l l l (3) i 1 A7 *rr l l (4) l Total Volume Removea tcall I I l (51 l Color Change Observeo l 1m/ I i " Alena. l ( ti) l Samole Taken l l W e, l FILLER INSTAt.'.ATION DATE 3/dM/e3 BY ( b ,i g,4r, v ,,g; l (1) l Date Filler Cao installed 2/ac-le 2, l (2) l Date filler Installea i l l (3) 3/3/Rs l 1 Exterior Concrete Temperature ( F) l l (4) l l 7905 l l (5) l Filler Temocrature at Pumo ( F) l l l (el l Filler Temperature at Outlet Cao (of) [ /C/ 7 p l l (7) l Total Volume Insta11ea teal) l / rop l l (8) l Installation Pressure (esi) { n '/u M l l / /., y / /Q., m M, -/ 1 _
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j App roved: /Megz Date: y/f-/t-3
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{} ' ARKANSAS NUCLEAR ONE % Tasvisio" , o^1E e, ,e, CHANGE DATE Page 1 of I
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SHEATHING FILLER RE!! OVAL & INSTALLATION Tendon No. S'1// 4 '2, - Location ,%n FILLER REMOVAL DATE o /c c//om BY Chien_ %h_ , u .-1, , l (1) l Date Removal Started j l~[2 ) ,o /ccyg g l l Exterior Concrete remnerature ( fo) l (3) l l c,rg "/ ' l l (4) l Total Volume Removec (eal) l l-l (5) l Color Chanze Observea l_ 3 '4/ m]. l j.(6) l Samole Taken l A /f a ' / l l / /n l FILLER INSTALLATION DATE __. 3/9/5r3 - O. BY fl., ,d/ S A- ,y e[ ' _ J' l (1) l Date Filler Cap Installed .l l (2) l Date filler Installed 2 - Z y- S-3 l l (3) l Exterior Concrete Temperature ( F) l A /q /g g l l (4) l 1 7e> 9 l l (5) l Filler Temperature at Puma ( F) { l
/ 9'g *p l
l~(5 ) l Filler Temperature at Outlet Cao ( F) [ l l 17) /3/ap l Total Volume lastalled teal) ~l l l (8) l Installation Pressure (psi)
- y. A m /,.
l l 4 / /3,, M,,,.)._ l Approved: ,(Isi$ h m M . Date: .7/f/S'3 O l e 4
'y:$ <
- _ ~ . _ - = - m-- - l
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- ' gg l, . - PLANT M ANUAL SECTION: PRCOEOUREN/ORK PLAN TITLE: NC:
I REACTOR BUILDING, TENDON I-ld.7;h I e&Cee rnnvr -e e e m - t r . t.c c -,, n,
~% ae3 PAGE n- ,c eo r D ARKANSAS NUCLEAR OMc atvisio" QHANGE
- o^tE DATE i[
1. Page 1 of I Data Sheet #1
/d no TENDON SUR1"dILLANCE J
SHEATHING FILLER REMOVAL & INSTALLATION
~ ~
Tendon No. S.2 // 4M_ - Location &/ FILLER REMOVAL DATE BY S/au/em h sto\ G hr-ta sk
~
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~" I l (1) l Date Removal Started j <> / o u / g A l l (2) l Exterior Concrete Temperature tE ) l ggoc- l l (3) l l l l (4) l Total Volume Removed (cal) l T/2m} l 1
l (5) l Color Chance Observed l D/A \J l .! j.(6) l Samole Taken l A/o l,
~
FILLER INSTALLATION DATE 3/3/g3 6, 3 _. ... BY {A.,,f fL L , M ' ; y . . . -
~
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l (1) l Date Filler Cao Installed 1 2 - 2. '/- 8.3 l l (2) l Date Filler Installed l 3/A/vm l l (3) j Exterior Concrete Temperature ('F) l ;r, 705 / l l (4) l. l l l^(S) l Filler Temperature at Pumo ( F) l / 9'.2 " # l l (6) l Filler Temperature at Outlet Cap ( F) l 23/ep l l (7) l. Total Volume Installed (gal) l 3'& no/c l (8) l Installation Pressure (psi) l /4y u) W,, m w/ lI. .
~
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l
.. ~
s . . Approved: M Date: 3/8-/9'3
/ /
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~ + -
PLANT M ANUAL SECTION: h-20 _) PROOECURENIORK PtAN TITLE: NO: } 4 ;oN t ICC REACTOR BUILDING, TENDON '
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"- 6 ARKANSAS NUCLEAR ONE PAGE laevisio" n-
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l i Page I of 1 i Data Sheet #1-
/Ov'M TENDON SURVEILLANCE SHEATl!ING FILLER REMOVAL & INSTALLATION Tendon No. 32H'/Y -
Location SheP . FILLER REMOVAL
- DATE 2-13-33 BY ff A s l (1) l Date Removal Started l (2) l Exterior Concrete Temperature (F ) l Z-2 3-93 l l (3) l l $6*p l l (4) l Total Volume Removed (tal) l l
l (5) l Color Chance Observed l 2 Ga c l l.(6) l Sample Taken l /Pcs6 l l FES - l FILLER INSTALLATION DATE A/ac//97 BY Lhu>( m AA-,,si.*- l (1) l Date Filler Ca7 Installed ! l (2) l Date filler Installed I '2/o uR 4 l l l (3) l Exterior Concrete Temperature ( F) l ~g /S/SP9 d>' /2< l l (4) l l 7/"# ~ l l (5) l Filler Temperature at Pump ( F) l l l (6') l Filler Temperature at Outlet Cap ( F) l /e//o p l l (7) l Total Volume Installed leal) { /260p l l l (8) l Installation Pressure (psi) l O *u < , /e. l l A/,~J 4 ,m.,L/J l j g l l 1 Approved: ((mM% $ Date: 3/g} W ., ont M , 4 l _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _
l L . h.gl PtANT MANUAL SECTION: __
.
- I&C PROCEOURE/ WORK PLAN TITLE: N O.
'e)i;ha l- ceo rnnre -re re REACTOR BUILDING, TENDON e r e t v r . y.--
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,n, n, fj'N ARKANSAS NUCLEAR ONE Nvision 5 ^o'S A a, ~,
ICHANGE DATE Page 1 of I l
//L. Data Sheet #1 l TENDON SURVEILLANCE v'
) SHEATHING FILLER REI! OVAL & INSTALLATION l Tendon No. .S.O /-/vu Location _ go/r/ FILLER REMOVAL DATE 1/aq/73 BY ( %_ ,o1 Ly, .,, A-y l (1) l Date Removal Started l (2) l Exterior Concrete Temperature if ) I l gop/yg l ef;o p l (3) l_ l l l (4) l Total Volume Removed (gal) __I l l l (5 ) l Color Chance Observed n '/a noj. l 1.(6) _ _1._ Sample Taken l ' J/-)f l l (rog [ FILLER INSTALLATION DATE A /o ///9g J BY /1., ,,igj [,.b,.., A,, W l (1) l Date filler Cap Installed l (2) l Date Filler Installed I o/4v/99 l l (3) N/h/#3 ~ l l Exterior Concrete Temperature ( F) l l (4) l l GQo/' l l (5) l Filler Temperature at Pumo ( F) l l l (6) l /95*f l Filler Temperature at Outlet Cap ( F) ._ l l (7) ). Total Volume Installed tgal) [ /Sydp l l (8) l Installation Pressure (psi) l 3 +v n efe l No m/ #fd, m od, l l Approved: /MM-Date: g /g ,-lg% 4 o % O #
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/ Ova TENDON SURVEILLANCE SHEATHING FILLER RE!!0 VAL & INSTALLATION Tendon No. AD303 Location SHOP FILLER REMOVAL DATE 2-9-83 ,
BY #fm A { l (1) l Date Removal Started l .. 2 - rf C5 3 l (2) l Exterior-Concrete Temperature (F") l _g 2 c F l { l (3) l l l l l (4) l Total Volume Removea (eal) l f l V V2. G M t- l l (5) l Color Chanze Observed l Aeo,vE l (6) l Sample Taken l ygS l l, I FILLER INSTALLATION DATE 2.cy-83 BY pfw.& j i l (1) l Datic Filler Cao Installed i 2.-9-93 l (2) l Date Filler Insta11ec l 2-22-S_3 l l (3) l Exterior Concrete Temperature ( F) l 6-("F
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l (5) l Filler Temperature at Pumo ( F) l l (6) l Filler Temperature at Outlet Cao ( F) l 2c o "T: (su DRee l v l o - / 90 *7~ l l (7) l. Total Volume Installed (eal) l 2 W o.q t l l (8) l Installation Pressure (psil l PoeREb l l Approved: g#4<g% Date: g/r/%3 ,,, , CNd~C/2D # h m C f N /.?fpc gre e sea 'y Q
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/#rA TENDON SURVEILLANCE SHEATHING FILLER RE:! OVAL & INSTALLATION Tendon No. 7&O2 -
Location SNOE FILLER REMOVAL DATE ?. - 1 6 - F 3
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FILLER INSTALLATION DATE 2-1l-83 %?r. BY #wP 5-(1) l Date Filler Cao Installed . l Z l- Y3 1 (2) l Date Filler Installed l %/a /93 l l (3) l Exterior Concrete Temperature ( F) l 69 */:' l l (4) l l l %d l (5) l Filler Temperature at Pump ( F) I con 7 l ,4 l (o) l Filler Temperature'at Outlet Cao ( F) l
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- PROCEOUREAVORK PLAN TITLE:
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Location __ p / c z. h FILLER FIMOVAL DATE Z ? 3 BY / 2 ,.,,./ q ,- ,_.m -
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- 10 YEAR PHYSICAL SURVEILLANCE OF THE ARKANSAS NUCLEAR ONE - UNIT 1 PRIMARY REACTOR CONTAINMENT BUILDING 2- -
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') APPENDIX E: TENDON END ANCHOR DATA SHEETS 1
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