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{{#Wiki_filter:6.6 Inadequate Original Tensioning of Tendons | {{#Wiki_filter:6.6 Inadequate Original Tensioning of Tendons | ||
== Description:== | == | ||
Description:== | |||
Initial tensioning of tendons could lead to excessive stresses in the containment structure. | Initial tensioning of tendons could lead to excessive stresses in the containment structure. This is of particular importance as the CR3 containment dome did delaminate upon tendon original tensioning in 1976 (FM 6.6 Exhibit 4) as well as another Florida containment dome that delaminated at Turkey Point upon original tendon tensioning (FM 6.6 Exhibit 5). | ||
This is of particular importance as the CR3 containment dome did delaminate upon tendon original tensioning in 1976 (FM 6.6 Exhibit 4) as well as another Florida containment dome that delaminated at Turkey Point upon original tendon tensioning (FM 6.6 Exhibit 5).Excessive original tensioning can damage the concrete by generating localized micro-cracks and/or enhanced creep rates.Also, unbalanced or incorrectly sequenced post-tensioning can lead to high local stresses, micro-cracks and/or delamination. | Excessive original tensioning can damage the concrete by generating localized micro-cracks and/or enhanced creep rates. | ||
Data to be collected and Analyzed: 1. Review initial tendon force requirements (FM 6.6 Exhibit 1);2. Review initial tendon tensioning data (FM 6.6 Exhibit 2);3. Review first surveillance lift-off measurements (FM 6.6 Exhibit 3);4. Review original tensioning sequence (FM 6.6 Exhibit 7);Discussion: | Also, unbalanced or incorrectly sequenced post-tensioning can lead to high local stresses, micro-cracks and/or delamination. | ||
The issue of excessive pre-stress by design is included in FM 1.3 as it is a design feature (this is the hoop pre-stress equal to 1.6 times the accident pressure). | Data to be collected and Analyzed: | ||
The current failure mode deals with the field tensioning in excess of the pre-stress design.2/3/10 P- H , .Page 1 of 3 Daefeate to p=-w t b§t 1 Draft1 The initial tendon tensioning was sufficient to cause delamination early in the life of the containments in the case of the CR3 dome and the Turkey Point dome (FM 6.6 Exhibit 4 and FM 6.6 Exhibit 5). In both cases, issues of radial tensile stresses, tension-compression interactions, and limitations in the concrete tensile strength were indicated as root cause for the events.Samples of the original tendon tensioning sheets are shown in FM 6.6 Exhibit 2. The tensioning sheets contain the hydraulic pressure on the jacks while the tendon force is the number typically referred to. The relationship between the two numbers is linear and well-known. Each jack is calibrated and the linear relationship is slightly different for each one (FM 6.6 Exhibit 8). For the original tensioning jacks used by VSL, the approximate relationship is that 6,800 psi of hydraulic pressure at the jack is equivalent to a tendon force of 1,635 kips.Tendon 12V20 shows a lift-off force of 1785 kips at the first tendon surveillance even though the original stressing record does not indicate any special problem with this tendon (FM 6.6 Exhibit 9). Tendon 12V20 does not go around any penetration. | : 1. Review initial tendon force requirements (FM 6.6 Exhibit 1); | ||
The excessive force was recorded again at the second surveillance (1740 kips) before being re-locked off at 1630 kips during the third surveillance. | : 2. Review initial tendon tensioning data (FM 6.6 Exhibit 2); | ||
Tendons 45V3 and 56V1 lift-off measurements were also above the 1,635 kips.Besides the overstressing, the sequence of tensioning is important, both in terms of elastic shortening losses for the various tendons, and in terms of asymmetrical loading of the concrete. | : 3. Review first surveillance lift-off measurements (FM 6.6 Exhibit 3); | ||
The examination of the original detensioning sequence indicates that the CR3 containment was evenly loaded upon tensioning. | : 4. Review original tensioning sequence (FM 6.6 Exhibit 7); | ||
The key results here are that there was no indication at the time of the CR3 dome delamination, or since in regular surveillance activities, that the wall had delaminated, and that the CTL condition assessment analysis, using Impulse Response technology, showed there are no delamination in five of the six CR3 containment panels (FM 6.6 Exhibit 6, see Summary page 4 of 96).This indicates that original tendon tensioning by itself did not create the delamination. | Discussion: | ||
Verified Supporting Evidence: a. First surveillance lift-off measurements did detect 3 over-tensioned vertical tendons (FM 6.6 Exhibit 3);2/3/10 PW-Pr8 '12i..d 2009 Page 2 of 3 Draft1 Verified Refuting Evidence: b. Maximum tendon force is 1,635 kips (FM 6.6 Exhibit 1, page 5 of 5). This is as designed and not expected to create excessive tensile radial stresses (see also FM 1.3);c. Original tensioning sheets did not report any over-tensioned tendons;d. First surveillance lift-off measurements did not detect any over-tensioned hoop tendons (FM 6.6 Exhibit 3);e. There was no indication at the time of the CR3 dome delamination, or since in regular surveillance activities, that the wall had delaminated as well;f. The CTL condition assessment analysis, using Impulse Response technology, showed there are no delamination in five of the six CR3 containment panels (FM 6.6 Exhibit 6, see Summary page 4 of 96). This tends to indicate that original tendon tensioning by itself did not create the delamination. | The issue of excessive pre-stress by design is included in FM 1.3 as it is a design feature (this is the hoop pre-stress equal to 1.6 times the accident pressure). The current failure mode deals with the field tensioning in excess of the pre-stress design. | ||
2/3/10 P-H , . Page 1 of 3 Daefeate to t1h.m.r_* p=-w t b§t 1 Draft1 | |||
The initial tendon tensioning was sufficient to cause delamination early in the life of the containments in the case of the CR3 dome and the Turkey Point dome (FM 6.6 Exhibit 4 and FM 6.6 Exhibit 5). In both cases, issues of radial tensile stresses, tension-compression interactions, and limitations in the concrete tensile strength were indicated as root cause for the events. | |||
Samples of the original tendon tensioning sheets are shown in FM 6.6 Exhibit 2. The tensioning sheets contain the hydraulic pressure on the jacks while the tendon force is the number typically referred to. The relationship between the two numbers is linear and well-known. Each jack is calibrated and the linear relationship is slightly different for each one (FM 6.6 Exhibit 8). For the original tensioning jacks used by VSL, the approximate relationship is that 6,800 psi of hydraulic pressure at the jack is equivalent to a tendon force of 1,635 kips. | |||
Tendon 12V20 shows a lift-off force of 1785 kips at the first tendon surveillance even though the original stressing record does not indicate any special problem with this tendon (FM 6.6 Exhibit 9). Tendon 12V20 does not go around any penetration. The excessive force was recorded again at the second surveillance (1740 kips) before being re-locked off at 1630 kips during the third surveillance. | |||
Tendons 45V3 and 56V1 lift-off measurements were also above the 1,635 kips. | |||
Besides the overstressing, the sequence of tensioning is important, both in terms of elastic shortening losses for the various tendons, and in terms of asymmetrical loading of the concrete. The examination of the original detensioning sequence indicates that the CR3 containment was evenly loaded upon tensioning. | |||
The key results here are that there was no indication at the time of the CR3 dome delamination, or since in regular surveillance activities, that the wall had delaminated, and that the CTL condition assessment analysis, using Impulse Response technology, showed there are no delamination in five of the six CR3 containment panels (FM 6.6 Exhibit 6, see Summary page 4 of 96). | |||
This indicates that original tendon tensioning by itself did not create the delamination. | |||
Verified Supporting Evidence: | |||
: a. First surveillance lift-off measurements did detect 3 over-tensioned vertical tendons (FM 6.6 Exhibit 3); | |||
2/3/10 PW-Pr8 '12i..d 2009 Page 2 of 3 Draft1 | |||
Verified Refuting Evidence: | |||
: b. Maximum tendon force is 1,635 kips (FM 6.6 Exhibit 1, page 5 of 5). This is as designed and not expected to create excessive tensile radial stresses (see also FM 1.3); | |||
: c. Original tensioning sheets did not report any over-tensioned tendons; | |||
: d. First surveillance lift-off measurements did not detect any over-tensioned hoop tendons (FM 6.6 Exhibit 3); | |||
: e. There was no indication at the time of the CR3 dome delamination, or since in regular surveillance activities, that the wall had delaminated as well; | |||
: f. The CTL condition assessment analysis, using Impulse Response technology, showed there are no delamination in five of the six CR3 containment panels (FM 6.6 Exhibit 6, see Summary page 4 of 96). This tends to indicate that original tendon tensioning by itself did not create the delamination. | |||
== | == | ||
Conclusion:== | Conclusion:== | ||
We have not found evidence that the original tendon tensioning was done so incorrectly as to have been a contributor to the delamination, either alone or in combination with other factors. | |||
2/3/10 iUI-~k~ ; 'z~z..t~L2C.&JPage 3 of 3 Draft 1 | |||
pd,* 1,, | |||
JFM 6.6 Exhibit 1 | |||
__n~ NUCLEAR OPERATIONS ENGINEERING | |||
%Sff CRYSTAL RIVER UNIT 3 DESIGN BASIS DOCUMENT FOR THE CONTAINMENT SYSTEM CODE: NIA TAB: 1/1 ISSUE DATE: 11/8/85 Revision 3 Revision 4 Revision 5 Revision 6 Date 03-09-01 09-18-01 04-26-07 09-24-08 Design Engineer R. P. Schmiedel R. P. Schmiedel P. Winters Verification Engineer C. S. Sterner L. S. McGowan C. Pugh r_______,__ | |||
Supervisor G. E. Englert K. R. Wilson L. Santonastaso | |||
page 2 of 5 CRYSTAL RIVER UNIT 3 Page i of ii Rev. 6 Pmress Energy No DESIGN BASIS | |||
FM 6.6 Exhibit 3 page 1 of 4 MATA S'Fr? 6 ItF.STIIJSS FO'RCE CflmfIFRATICRN?EST I *~ | |||
REACTOR rATC M ILITT-OFF' CON. | |||
DTION LOCK-Ollr WC.Tr.XFlY Twtp* 1.%,tP. | |||
FT I'ALVIOUS 0 ITrD *GG AVC. Or S111.1 GAGE FINAL 6111H TI. LCrKfhP* | |||
roriLII.54rocs (IA raus. | |||
EI) thipp) 2PRE fliD.4) tE FCAE ll~~lfl ~ -OC FtSS.- | |||
IIALVIOUIS CIPTCINAL (KaI)NIP-) | |||
FORCE T"lCO~ESS (i. | |||
aF I A: % f 7 it 9 in I 1 17 11 14 1ý I lp 17 17~~- ___ -, - 4 4..4 | |||
~ | |||
Y.2. '.~ L. | |||
..2 2 lul a/ | |||
-r 3 a~2JAI | |||
.2a. | |||
7-- /- | |||
IOTE A: | |||
FOR.CECALCULATIQt4 (1) Force @ Lift-off - Jack Pressure z Jack PLston Ate& | |||
OR: (2) DetermLMv force from calibtattca curve MOTESt Leactor Building internal temperature will be read using Cl-2?&*TE or CI-173-TE (temperature read at Johnson Finel 1i-*) | |||
"UTZ C: | |||
Vice force (Column 8) is defined as followa: | |||
W.F. | |||
* Colu'n 7 163 - Column A of Dita %hect I NOTED: | |||
I.pccted lift-off force (colu-n 4) is defined As follow,: No. of effective wires at Instelletion (or previous inspectiou) | |||
FM 6.6 Exhibit 3 page 1 of 4 | |||
?EST M ILITT-OFF' CON. DTION LOCK-Ollr I'ALVIOUS 0 ITrD *GG AVC. Or S111.1 GAGE FINAL 6111H | |||
* Colu'n 7 163 -Column A of Dita %hect I | |||
I Ave. pradicted -le force ehown on Fla. I at time of noapection. | I Ave. pradicted -le force ehown on Fla. I at time of noapection. | ||
LSdOft. | LSdOft. | ||
I to 6 lusebr of buLtTeeO heairct to end of IeS'Hil.t l jTiWESS: Clear distance bhtvoea beekna plate end stream rAJ.VlQ-: | LOATIi*l: I to 6 lusebr of buLtTeeO heairct to end of IeS | ||
At time t Insetallation or'previoue murvtallenc CRICIIAL: | 'Hil.t l jTiWESS: Clear distance bhtvoea beekna plate end stream iLg washer. | ||
At time of etarting current survalllence. | rAJ.VlQ-: At time t Insetallation or'previoue murvtallenc 9. Contractor Review by: Date: | ||
i till | CRICIIAL: At time of etarting current survalllence. | ||
FM 6.6 Exhibit 3 page 2 of 4 | F.F.C. Approval by: vote: | ||
's~ _L _9 AMloY 121Y,17j L4 58 M-2 ... 71-7 _5.5 -i /Ar | i OAR till IN-" M - | ||
(1) Force ( Lift-off -Jack Presaure a Jack iisteo Are&OR& (2)Determtine force from caltbration curve | |||
FM 6.6 Exhibit 3 page 2 of 4 DATASI!ttt 7 PRI.ESTRFSA FORCECRIrFTRHAT3O,TqT. | |||
VERTICAL TEIMNS IsSrECtIOH TFAUOD / | |||
ILACTOR BATE | |||
*I[Tr-oF7 CONDIT010 LOCX.OFF RIM~ TE4? JIMF 1-.S?. ZY PREVIOUS EXP[C ED GAd AVG. OF SHIM GAGE VIAL SHR.f FO£CE LIFT-OFF FO)C t(S. i .ORCE I M WIRE O405 TICrIoESS (OIii. 15. FO(Cst (IC2i.ESS .F | |||
.. . .. . | |||
l~ts,. LOCATIO4 (ittr) % - iD I tI1 fus) -fuli ORCE FirWious ORTCIOAL (Ks0 (kips) (in. | |||
i 15. "~ 1._.yo L * | |||
* d a 1* !1 L | |||
1* l1 11 l& | |||
14 .1 - | |||
I*A* | |||
- - | |||
I | |||
... | |||
* | |||
, | |||
,' ,12 V/20 1 | |||
'Igg _/ 4'il_ | |||
/C/3j*- my,/' 57. | |||
.3 S.151 q.._ %q.ssrBv. u -71 | |||
/637 /Y9 63 Z- IkA /L7 16,21y~y~ 's~_L _9 AMloY 121Y,17j L4 | |||
: 5. 4Ejva _1_ | |||
/1q690 /q 7 o 58 M-2 ... 71-7 _5.5 -i /Ar Ac* | |||
1 -jE 1 "" | |||
RIOTEA: | |||
4-No rc FORC6E CALGIATION.: (1) Force ( Lift-off - Jack Presaure a Jack iisteo Are& | |||
OR& (2)Determtine force from caltbration curve NOTEB1 Reactor BuLlding iaterval temperature will be rud using CI-274-TE of CI*217-TZ (tieparacure read ac Joohsos facel It-I) | |||
I L.C, | |||
, NeLTOAL, mOTe C: | |||
Wirte Force (Column 8) it defined as lollows; W.I. - C oIi 7 4 O h I 163 - Column 4sof Data Sheet 2 "I 1NOTE 0: | |||
II "c' ;ý,Pj IJI Is C J ; S1. | |||
*6 V I Expected lift-off force (column 4) to defined at follows: 11., of effective wires Oi LtnaiaOIL4o1 (or prev IoA Inspection) | |||
* I Ave. predicaced wtre force shown on FIg. 2 et Limof Ienspectiof. | * I Ave. predicaced wtre force shown on FIg. 2 et Limof Ienspectiof. | ||
-tOCATi: T or B -top or bottom (ve tticol tendon)." | - tOCATi: T or B - top or bottom (ve tticol tendon). | ||
Clear distance beec bee ri plete and stressing waeser.SPw.-Ois: | " SAL'4*fdlQ*%SS: Clear distance beec bee ri plete and stressing waeser. | ||
At time of ttalli1ton Or ýrevlouo surveillance. | SPw.-Ois: At time of ttalli1ton Orýrevlouo surveillance. | ||
SCIIGLNAL* | SCIIGLNAL* At time of etecitng Currene Murveilleac*. | ||
At time of etecitng Currene Murveilleac*. | Cootrector Review by: oDam fPr.C. Approval by: _ Date: | ||
Cootrector Review by: oDam fPr.C. Approval by: _ Date: | 3 ",t, -r- o"' | ||
FM 6.6 Exhibit 3 page 3 of 4 DATA lvirq~ ZA 11('E C 1FRflPtAT101f MTS V.RICAL TlIfVIVItS ui | |||
FM 6.6 Exhibit 3 page 3 of 4 DATA lvirq~ ZA P*u1R*.*;rt;. 11('E C 1FRflPtAT101f MTS V.RICAL TlIfVIVItS ui PoxS EC.R= -00 TfON'IV, I r tIFr-OFF CM9IITtM4 L.OCK-OFF REACTOR Im0 Tr~4P_ DATE tN;jj TM I FAEVIOUS lXp Co CACE AVG. OF SHIM CAGd FINAL 5111J FORCE LIFT-"OFF, FORCE PRESS. FORCE 2 D1DS WIRE THTCKKFSS (in.) Pass. FORCE THICKXESS F I,. t*r'A.TIf' (AhI ..) (k614 (Vall Nos1) tkIr,} FORCE PIrVIOn's ORV:iIAL (Xqt) 1lkI) (N,) yMr. EXT. 7:TIALS | |||
.t 2 3 & $ 1 7 6, 9 t II. 12 13 I9 It 1 _, | |||
: 2. ~s | |||
OR: (1) Determine force from calibration curve | ~ ~~~ - j, 3 . 61 .f 'Zi 7 T _W3id .2: '~ _L1 o y-I-ED-/-- -t - - - | ||
I Ave. predicated wice fotcset bove on Fig. 2 at time of Inspection. | l. | ||
ln& washer.C.Contractor aeview by: Date: P.P.C. Approval by: Datle.1 1 3- a.A..a. | NMTA: | ||
FM 6.6 Exhibit 3 page 4 of 4 | OR: (1) Determine force from calibration curve building Inter*al temperature will be read using CI-27&-TE or Cl-275-TE (ceaperacure read at Jo*eson Panel 11-3) taetcor V1OTEC: | ||
TEST ITOP | Wrii Force (Column 9) La defined as followo: | ||
Tnflp MrSP. IKSP. AT i1 | W.F. - Col.-n 7 . | ||
(1) Force @ Lift-off -Jack Treasure Jlack Piston Aree ORS (2) DetermIne force from caltbracion curve | 163 - Column 4 of Data Sheet 2 VtOT£0: | ||
Ut'ecied lift-off force (Column 1.) is defined as followat N4o. of effective wires at installation (or previous Inspection) | |||
I Ave. predicated wice fotcset bove on Fig. 2 at time of Inspection. | |||
LOMaTICi: T or B - cop or bottom (w 'tical cendon). | |||
SHL't TH!ICKN:SS: CleAr distance beucca Ier plat* aolan tTe ln& washer. | |||
.M.;'IO$: At time of Itita llt::: or ureLous surveillanc C. | |||
CRIGL*.L: At time of starting current survetllsoce. | |||
Contractor aeview by: Date: | |||
P.P.C. Approval by: Datle. | |||
1 1 3- a.A..a. | |||
FM 6.6 Exhibit 3 page 4 of 4 it PAT4 5111'*" 8 PREST'RESS M CE. *IP4ATTO*! TEST ITOP TFlN" Ii VSPECTlN PERIO/D REACTOR DATE Tt"1W i Ir- T O... r . ..... ,,_______ -OI_________PI% Tnflp MrSP. IKSP. AT i1 PREVIOUS EXPECT'D CAGE Avc. OF SKI, MCAE FIN AL SHIMX FORCE LIFT-OFF TOACEj iPESS. ToI0Z 2 EMLS VIRi TNiiCKUS (Ia.) PUSS. FORCE TiI of (kill@) t( ) | |||
kil ( dpa) iP .1 (Vk*i PRCE P VIrOVS CR ,IC IAL (toil (k ir ICT, EXT I16 TnITTA ¶ S.I ,D I'/__ CAT._.* (Ih it. IA I1 3 6 5 6 1 8 9 if) t, lt "71~ /.c_£. ".,, ." ,, | |||
'; ic ." | |||
: 1. I3,/' /i -*-.-:.- z I,* | |||
2. | |||
_L7 3/ | |||
A', C. | |||
-! | |||
4 7 ; | |||
dýE 7d | |||
*/IO /,*.# IC ' | |||
12..L EX.r - L:n4 4.. +.,** | |||
*. -- 1,=4 | |||
: 65. -'4* ./ , __ "_*,"A " | |||
7.o | |||
",-* /+*/ "" -'"",.*. ,4/.* ',7o.-" ._ . -'. | |||
- l 4 -7. | |||
,--L 17' 41"-. .,.. .... ,,Z* _ | |||
: 90. 5..:/ | |||
NIOTE A: | |||
FORCE CALCIULATION/:(1) Force @ Lift-off - Jack Treasure Jlack Piston Aree ORS (2) DetermIne force from caltbracion curve NOT£E : | |||
Reactor Building internaL temperature vtil be read using C[-274-TE or Cl-271-ts (temperature rea2 at Johncon Panel 11.3) | |||
OT C: | |||
Wire Force (Column 8) is defined as fall*i-; | |||
W.F. -ColIn 7 163 - Column 4 of Dace Slheet 3 Expected lift-off force (column 4) Is deflied as folLows: It*.of elfeclive urts at Ifsalllatson (or previous Imprctioen) | |||
I Ave. predicted witi force shown on Fig. 3 at time of insplecton. | I Ave. predicted witi force shown on Fig. 3 at time of insplecton. | ||
LOCATIMl: | LOCATIMl: I to 6 - lumber of butiresa natcea to and of t cnd.ah SIManT ICi£ESSt Clear distance between basting pIate aud atrea sin~gwasher. | ||
I to 6 -lumber of butiresa natcea to and of t | Contirctor L .eiewby: Date: | ||
-OR'IGMAL: | " | ||
At time | FTEV1OUS; A: time of instllation or previous surveillance. | ||
-OR'IGMAL: At time oat strting curren- aurvelllance. F.F.C. AppTovel by; Date. | |||
... ~'.. | I " | ||
21, 1976 Mr. Ernest Volgancau, Director Directorate of Regulatory Operations U.S. Nuclear Regulatory Commission Washington, D). C. 2054S r() irvr&.!1I | |||
... .E ~'..y1*6 xhibit 4 page 1 of 8 Forida Power C. ri P , . | |||
A A T 10NApril. | |||
21, 1976 Mr. Ernest Volgancau, Director Directorate of Regulatory Operations U.S. Nuclear Regulatory Commission Washington, D). C. 2054S r() irvr&.!1I | |||
==Subject:== | ==Subject:== | ||
Docket No. 50-302 l)car Mr. Volganeau: | |||
Pursuant to I0CF-Ri0.5iS, we wish to follow up our verbal (telephone) notification of 4/19/76 regarding a separation in the concrete of the Crystal River Unit t13 containment structure dome. We have now documented the apparent extent. | |||
of this separation. To recap, the following i.s the sequence of events of the investigation. | |||
On Wednesday, April 14, 1976, while placing cinch anchors in t he dome concrete of the Reactor Building, it was noted that there appeared to be a hollow area about one inch beneath the surface. Investigation on Friday, April. 16, by saw cutting and removing a section of concrete approximately one foot. | |||
wide by three feet long, showed that the depth of. the hollow area went deeper as i.t went higher on the dome. By core drill-ing on Saturday and Sunday, April 17 and 18, it was further determined that the separation continued across the dome and went as deep as 15" and separated as much as 1-3/4 inches. | |||
By using acoustic methods, the lower perimeter of the separated area was determined to extend all. around the dome in pours I"G"t, "111" and "J"'. | |||
Our engineers are now evaluati.jg the present condition of the structure. | |||
Sketches marked I, I, Ill , IV, V, and VI illustrate the apparent extent of the separation as i ndicated by)the limit ed data avai.lable at this time. | |||
General Oeflice 3201 hi ty-fourth Steet South 0 PCO Box 1404P2 St PF(!rshWO, Fi0ri]_i 33u'3'-i` | |||
, FM 6.6 Exhibit44 page 2 of 8 | |||
.Mr. lrctVolgaiioau April 21, 1.976 We wi1.1 advise you when we have reached final. resolution of this problem. | |||
If you have any questions, please advise us. | |||
Very truly yours, J9g Rodge, | |||
*Asst. Vice President JTR/iw Attachments. | |||
cc: Mr. Norman C. Moseley D)irector, Region 11 | |||
\XV A\VA'~ | |||
-J | |||
* 1.,1cJ | |||
~; *' | |||
* FI~ | |||
I * *1. | |||
6.6 | |||
: 1) LoID--M,-PST FC | : 1) LoID--M,-PST FC | ||
* cote%.k | * AATf cote%.k RKA L-JE cjjKw6 | ||
: 4. Date buttonheaded Buttonheading NCR's | ,m-ýV (L*3 o. o v Ar"F i 972 71j6 4)-~'*rJ -ees 5AA (9"") f1b SkMIltfi 159 | ||
~~ 55 r-r--FF ~CKCEDv 69 TEcIM 3E(. UtfCA2 Lnrirr 47ZI K) Ax-ACEWTr 7TLJDC Lrr-r-OFF TAW907 716 | |||
Ultimate Pressure Unseated/Broken Wires Total ef 6. Date Bulk-filled Bulk-Fil Time since installation Inlet P1 | |||
FM 6.6 Exhibit 9 Sft@&e 3&V OF ýy Florida CRYSTAL RIVER UNIT NO. 3 ' | |||
IS7-sw rve ; / 4", Ce Power COAPORA? 1O0I REACTOR BUILDING PRESTRESSING SYSTEM TENDON HISTORY TENDON IDENTIFICATION NUMBER /2 V 21o) CUT LENGTH SHOP WASHER ID: PC CR FIELD WASHER ID: PC CR | |||
: 1. GAI/QA vendor inspection cover letter number-FPC D_LTE D | |||
: 2. Date tendon received on-site RNR Number | |||
KA'I _ Al___- ____/_-Lift-Off .-. 7A NA Shim Thickness/99; | : 3. Date installed in conduit Installation NCR's Wires removed Wires replaced Total Ineffective iires | ||
=lt--z 1_ _"/ ._ _ _. ..A -I Unseated/Broken.Wires | : 4. Date buttonheaded Buttonheading NCR's Bad wires Accept. Reheads Total Ineffective wires | ||
_ _ _ Total effective wires after stress-.ng 6.- Date Bul~k-filled " /98 Bulk-FiLllinz NCR's_______________ | / | ||
Time since installation | : 5. Date stressed Stressing NCR's Date restressed Restressing NCR's SHOP END FIELD END TOTAL Elongation (1500 psi to 80% ult.)-Pred./Act. | ||
' Inlet ?ressure -Outlet Temp.Date end c'aDs refilled: | / .... / ___N/A Lift-Off Pressure - Predicted/Actual Shim Thickness/80% Ultimate Pressure I . / _N/A Unseated/Broken Wires Total ef 'fective wires after stressing /6 | ||
Shop q / YZ Field ____Y_/99/_ | : 6. Date Bulk-filled Bulk-Fil lling NCR's Time since installation Inlet P1-essure Outlet Temp. | ||
Date end caps refilled: Shop Field | |||
: 7. Data compiled by * ;.y: */0 Organization FPz -- | |||
Date ? | |||
: 4. Date buttonheaded Buttonheading NCR's Bad wires Accept. Re-heads TotalIneffective wi 5.a. Date stressed Stressing NCMM's Date restressed Restressina NCR's | : 8. Additional Comments: 06biýt 0) CkeLcWe b,-ci4%1 Ap,, wa+/-s aze.AL/z~e 907 716 | ||
,, Ult-s. .Unseated/Broken Wires Total effective vires 6.: Date Bulk-filled | M6.6 Exh ibit 9 t:ýc:en, ? "-A Co .. T.. P I-:s: $ U s. :E, | ||
-Bulk-Filling NCR's Time since Installation NIA i | : 0. '- AEDN H:STO? | ||
Shop Field 7. Data compiled by Organization Date 8. Addiricnal Co--ents: .TE o. | I," . - - | ||
On m M 5: (0 CRYSTAL RIVER UNIT NO. 3 REACTOR BUILDING PRESTRESSING SYSTEM TENDON SURVEILLANCE RECORD TENDON NO. 12V20 | S1O ? .-.- R ID: PC CR FIELD WS-R ID: ?C CR | ||
-;,*, IDE:NTIFICATIO:N | : 1. GAI/QA vendor inspection crver letter _ D, AT L._ber-FC | ||
:CUME. 4'f 3 CT LENGTH /F? -/ShjOP W,,.'SR ID: PC /2/ CR 7 7 (, FIELD ID: PC / i- C) CR 2 Z/1. CAI/QA vendor inspecticn cover letter n:-uber-FFC I qc/0 DATE ____/ | : 2. Date tendon received on-site ?,HR N-ber | ||
: 3. Date installed in conduit Installation NCR's Wires removed Wires replaced Total Ineffective w-ires | |||
/'63 6. Date Bulk-filled II 7 Bulk-Filling iNCR's 16P7 Time since installation Y , Inlet Pressure /&O. Outlet Temp. /23 Date end caps refilled: | : 4. Date buttonheaded Buttonheading NCR's Bad wires Accept. Re-heads To-tal TIeffective wires | ||
Shop Field 7. Data compiled by Zi. , <- Organization | : 5. Date stre.ssed Stressing NCR'ss Date restressed Restressing NCR's TOP.. | ||
>c5"--.-.Pate _ __/77 8. Additional Co-ments: (Q.) | SHOP END FIELD END TOTIAL Elongation (1500 psi to 80% ult.)-Pred./Act. KA'I _ Al___- ____/_ | ||
SHOP WASHER ID: PC CR FIELD WASHER ID: PC 1. GAI/QA vendor inspection cover letter number-FPC I D.2. Date tendon received on-site RMR Number 3. Date installed in conduit Installation NCRs Wires removed Wires replaced _ Total Ineffective | - Lift-Off zt.'*. .-. /7440**r/ | ||
'4. Date buttonheaded Buttonheading NCR's Bad wires Accept. Reheads Total Ineffective wi 5. Date stressed Stressing NCR's Date restressed Restressing NCR's | 7A NA Shim Thickness/99; =lt--z ?--*.-. 1_ _"/ ._ _ _. .. A -I Unseated/Broken.Wires _ _ _ Total effective wires after stress-.ng 6.- Date Bul~k-filled " /98 Bulk-FiLllinz NCR's_______________ | ||
/ ! /Lif t-Of f Press .r.e | Time since installation ' Inlet ?ressure - Outlet Temp. | ||
/Actual ILW)~______N/A | Date end c'aDs refilled: Shop q / YZ Field ____Y_/99/_ _ | ||
Ultimate Pressure / ., _ N/A 14-tOV/Unseated/Broken Wires (.J M) Total effective wires after stressing 112-6. Date Bulk-filled I-/-78 Bulk-Filling NCR's Time since installation Inlet Pressure Outlet Temp.Date end caps refilled: | : 7. Data conpiled by:- Organization S-Date .j-zz //*a | ||
Shop Field A-A.AFP(.7. Data compiled by Organization Date _____ _____ | : 8. Additicrnal Cc-ants: L OFr o' 'LY_ 61-r 7-ý LJý- t ýýC OArie 0or- L IF--r /A c.r-c, ra r ._ _ _ _ _ _ _ _ _ _ _ _ _ | ||
1.tJS(IED r2LS7 S LJ ? | L r o r- r it -- -y , ' | ||
CA7T. */. o2~ es o1~Ed~ 3A'IE5 WiC | |||
r?~3) LOCC- OFF VWC16(O4M.C A Pro 907 716 | M6.6 Exhibit 9 | ||
-n 03 m x CRYSTAL RIVER UNIT NO. 3 REACTOR BUILDING PRESTRESSING SYSTEM TENDON SURVEILLANCE RECORD TENDON NO. 45V3 | *~. pgeýý of 13. | ||
OfI. *:" | Fol-da ~., Is - - I'2P | ||
iD: PC /2- / CR | ",'7:; 1 - ,- ** | ||
; /00S,0 DATE 3/,P/7y 2. Date t'.P- receiv'iJ cz-si:e 2- Z0O Num.ber J7 Z 5- 7 3. Date installed in conduit I-/7- | ~ PowEr RLACTOR BUIL:7 O. . SYSTLEM 7E'., 7 S- TV | ||
2;/8 -//2' // I | -1 NDON~ I D'ENT 1 1CAT !C!, XNU ýS ZR 12 VZo a:,T LEN' SHO? W',.AS-"R ID: PC CR 777IEL)D WASER ID: PC CR. | ||
Ultinate Pressure /A /7770 9y / N/A Unseated/Broken Wires 0 Total effective wires after stressing | : 1. GAI/QA vendor inspection cover letter n--er--PC _ DATZ | ||
/3 6. Date Bulk-filled I. -Bulk-Filling NCR's Time since installation 9 'n"nJ Inlet Pressure //t / Outlet Temp. / | : 2. Date tendon received on-site __ .YR N~ber | ||
Shop Field.7. Data corpiled by -e e/,-/ Organization 4-i'i,, Date ___' | : 3. Date installed in conduit Installation NCR's Wires renoved Wires replaced Total Ineffective | ||
_ DA 2. Date tendon received on-site RMR Number 3. Date installed in conduit Installation NCR's Wires removed Wires replaced Total Ineffective | : 4. Date buttonheaded Buttonheading NCR's Bad wires Accept. Re-heads TotalIneffective wi r es 5.a. Date stressed Stressing NCMM's Date restressed Restressina NCR's TOP .- | ||
-4. Date buttonheaded Buttonheading NCR's Bad wires Accept. Reheads Total Ineffective | SHOP KEND FIELD :ND TOTAL A1 Elongation (1500 psi to 80% ult.)-Pred./Act. | ||
/ I /Lift-Off P......6 -Predicted/Actual 41,i//6S -N/A L-C-b~f- FOAfL eGfQLZA Shim Thickness/80% | "'I"/ ' /A F cf Lec-x.ovor GE -_ | ||
Ultimate Pressure N/A Unseated/Broken Wires U | J 'b- Lift-Off *r P/ i,'/_tzl (iQIP-S) / | ||
/ 7~8Bulk-Filling NCR's________________ | Shim ThPic.ness/ ,, Ult-s. . __.___ _/_ N/A Unseated/Broken Wires Total effective vires after stressing 6.: Date Bulk-filled - Bulk-Filling NCR's Time since Installation NIA i ?ress-ure | ||
Time since installation Inlet Pressure Outlet Temp.Date end caps refilled: | -let Outlet Temp. | ||
Shop ____ ___ Field /141 7. Data compiled by 7- -Organization FP 70 Date ____________ | Date end caps refilled: Shop Field | ||
: 8. Additional Comm~ents: | : 7. Data compiled by Organization Date | ||
5Th't9T() | : 8. Addiricnal Co--ents: .TE . | ||
22LyS | : o. -o r0 L*_EO a - A7 ILAO KIjP.5 PIC-/a Al0. ?-337L. | ||
: 4. Date buttonheaded Buttonheading NCR's Bad wires Accept. Reheads Total Ineffective wi 5. Date stressed Stressing NCR's Date restressed Restressing NCR's | On m | ||
/ /Lift-Off Pressure -Predicted/Actual | M 5: | ||
/ N/A Shim Thickness/80% | (0 CRYSTAL RIVER UNIT NO. 3 REACTOR BUILDING PRESTRESSING SYSTEM TENDON SURVEILLANCE RECORD TENDON NO. 12V20 LIFT OFF CONDITION RETENSIONING Inspection Avg. Shim Elong- Total Avg. Shim Elong- Total Reactor Bldg. | ||
Ultimate Pressure / N/A Unseated/Broken Wires Total effective wires after stressing | Period and Force Force Thickness ation Effective Force Force Thickness ation Effective Temperature OF | ||
/63 6. Date Bulk-filled Bulk-Filling NCR's Time since installation Inlet Pressure Outlet Temp.Date end caps refilled: | : n. Com~ent. | ||
Shop Field 7. Data compiled by h. Organization | 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 Original T 1598 15" I2Jj/8" N/A N/A N/A Stressing 1/28/75 B N/A N/A 4" N/A 163 N/A NIA N/A N/A NIA N/A N/A Is t 121t T 1785 15" NIAK 1785 15"1, A 1. l lft-off high - | ||
adjaceint tendons tested B NIA ALL 4" HLA_ | |||
(2-) -cy | Ifil- VA' HIA_ 4" IA- i16_ U1 1m_* 2. Hairline cracking at Bott. Anchorage 2_nd T 1740 15" N/A 1740 15._ NJA 1. Lift-off only 4/11/80 B N/A~ N/A N/A11K 216 N A NIA. 4"L VAL& 1UL 71* 76 | ||
(.0)CRYSTAL RIVER UNIT NO. 3 REACTOR BUILDING PRESTRESSING SYSTEM TENDON SURVEILLANCE RECORD TENDON NO. 56VI LIFT OFF CONDITION RETENSIONING Inspection Avg. Shim Elong- Total Avg. Shim Elong- Total Reactor Bldg.Period and Force Force Thickness ation Effective Force Force Thickness ation Effective Temperature OF Date Location (kips) (kips) (in) (in) Wires (kips) (kips) (in) (in) Wires Int. Ext. Comments 1 2 3 4 5 6 7 8 9 10 11 12 13 14 Is Original | '* | ||
0) 0 | |||
FM. | |||
CRYSage Vo7 REACTOR BUI LI)!:i Prj.. I 3 | |||
ESSI.G SYSTEM page 77 of 13 | |||
: °'~" *" T~;''*'I: -;, | |||
*, IDE:NTIFICATIO:N :CUME. 4'f 3 CT LENGTH /F? - / | |||
ShjOP W,,.'SR ID: PC /2/ CR 7 7 (, FIELD WAE.-*iR ID: PC / i- C) CR 2 Z/ | |||
: 1. CAI/QA vendor inspecticn cover letter n:-uber-FFC I r*. qc/0 DATE ____/7_ | |||
: 2. Date tcndorn receivc,, on-site - // 7'?/ RMR Number 36F1/ | |||
: 3. Date installed in conduit 7 "Z3- 7A Installation NCR's Wires removed _ _ Wires replaced _ Total Ineffective wires 0 | |||
: 4. Date buttcnheaded I-Z/- )9 Buttonheading NCR's Bad wires _ Accept. Reheads 0 Total Ineffective'wires 0 | |||
: 5. Date stressed 9 Stressi re ng ,CR's Date restressed Restressing NCR's SHIOP EN;D FIELD E'ID TOTAL Elongation (1500 psi to 807; ult. )-Pred. /Act. 1Z AY/ 121- I/ZAI /Z 1. | |||
*ft-Off Pressure - Predicted/Actual 0 / 110 / N/A 77 7 1/AI" / N/A Shim Thickness/80% Ultiznate Pressure Unseated/Broken W.ires __ Total effective wires after stressing /'63 | |||
: 6. Date Bulk-filled II 7 Bulk-Filling iNCR's 16P7 Time since installation Y , Inlet Pressure /&O. Outlet Temp. /23 Date end caps refilled: Shop Field | |||
: 7. Data compiled by Zi. , <- Organization >c5"--.-. | |||
Pate _ __/77 | |||
: 8. Additional Co-ments: | |||
( | |||
C 7 71A Q.) | |||
FM 6.6 Exhibit 9 | |||
/Ir . Vr--Ir C_ | |||
_* Florida CRYSTAL RIVER UNIT NO. 3 Power REACTOR BUILDING PRESTRESSING SYSTEM TENDON HISTORY TENDON IDENTIFICATION NUMB~ER $Ks V 3 CUT LENGTH____ | |||
SHOP WASHER ID: PC CR FIELD WASHER ID: PC CR | |||
: 1. GAI/QA vendor inspection cover letter number-FPC I ATE D. | |||
: 2. Date tendon received on-site RMR Number | |||
: 3. Date installed in conduit Installation NCRs Wires removed Wires replaced _ Total Ineffective wires | |||
'4. Date buttonheaded Buttonheading NCR's Bad wires Accept. Reheads Total Ineffective wi res | |||
: 5. Date stressed Stressing NCR's Date restressed Restressing NCR's SHOP END FIELD END TOTAL Elongation (1500 psi to 80% ult.)-Pred./Act. / ! / | |||
Lif t-Of f Press LO"z-4Csr .r.e d*rt. | |||
FZOrf - Predicted /Actual ILW)~______N/A" Shim Thickness/80% Ultimate Pressure / ., _ N/A 14-tOV/Unseated/Broken Wires (.J M) Total effective wires after stressing 112- | |||
: 6. Date Bulk-filled I-/-78 Bulk-Filling NCR's Time since installation Inlet Pressure Outlet Temp. | |||
Date end caps refilled: Shop Field A-A. | |||
AFP(. | |||
: 7. Data compiled by Organization Date _____ _____ ____ | |||
: 8. Additional Comments: 1.tJS(IED r2LS7 S LJ ?vmAJC6 (/2- ? | |||
i) w~t? FIFO) 0--T ON) STflLSStrAJ( &VALSHEt&L 4 fi 57n#I. COOO CAT. / | |||
&"tQg HA12C,ec-gbSVW~ CA7T. */. o2~ es o1~Ed~ 3A'IE5 ~WiC | |||
: 2) /1mlZL1~t cjptcxcDr/6 (1,C55 TfliW O.0ooj A &flv-^y 4,1'6'e~htRA& r?~ | |||
: 3) LOCC- OFF VWC16(O4M.C A Pro 907 716 | |||
-n 03 m | |||
x CRYSTAL RIVER UNIT NO. 3 REACTOR BUILDING PRESTRESSING SYSTEM TENDON SURVEILLANCE RECORD TENDON NO. 45V3 LIFT OFF CONDITION RETENSIONING Inspection Avg. Shim Elong- Total Avg. Shim Elong- Total Reactor Bldg. | |||
Period and Force Force Thickness ation Effective Force Force Thickness ation Effective Temperature OF Date Location (kips) (kips) (in) (in) Wires (kips) (kips) (in) (in) Wires Int. Ext. Comments 1 2 3 4 5 6 7 8 9 10 I1 12 13 14 IS Original T J9 jL j4' N/A N/A N/A Stressing 9/30/74 B N/A N/A 4" N/A 163 N/A N/A N/A N/A N/A N/A N/A 1st 1 T 1678 14" N/A 1678 14" N/A 1. Hairline crackling at but t om ancl'horrage B N/A N/A 4" N/A 163 N/A N/A 4" N/A 162 103 63 2. One wire removed CD (D | |||
0 CA) | |||
OfI. * | |||
:",4""" FM Et i.9 CRYST", PIVER t" 'T tNO. 3 page 10of 13 REACTOR E P7"LDL'G Pf, YSS1NG S'YS':EM 1 1_.JF-ICAT ION ;:'-ZL R 5a , / CUT LE-"GTH /8 - | |||
SHOP WX;,37-.?. iD: PC /2- / CR FELD WASHER ID: PC FI'/ /Z 0 CR /73-I. GAI/Q.',.r.J:r insp c-tion c,,'r lettcr nu-ber-FPC ; /00S,0 DATE 3/,P/7y | |||
: 2. Date t'.P- receiv'iJ cz-si:e 2- Z0O PP*R Num.ber J7 Z 5- 7 | |||
: 3. Date installed in conduit 7'/ I-/7-Installation NCR's Wires rcmoved _ Wires replaced _ Total Ineffective wires O | |||
: 4. Date b.ttcnhead2d 7- Buttonheadin; NCR's Bad wircs _ Accept. rc':2ads Total !ne: fective wires | |||
: 5. Date stressed k 30 -F 7 tressing ,'_CP,_s Date reszressed Restressing NCR's SHOP ElD FIELD END TOTAL | |||
~Elongatticn (13030 psi to SC" ult.)-?rej./Act. 2;/8 -//2' // I NA /A8 it-Off Pressure - rredicted/Aztual 6800 /1?_*To'_ N/A Shim Thic:-ncss/80% Ultinate Pressure /A /7770 9y / N/A Unseated/Broken Wires 0 Total effective wires after stressing /3 | |||
: 6. Date Bulk-filled I. - Bulk-Filling NCR's Time since installation 9 'n"nJ Inlet Pressure //t / Outlet Temp. /_____ | |||
Date end caps refilled: Shop Field | |||
.7. Data corpiled by -e e/,-/ Organization 4-i'i,, | |||
Date ___'__7__ | |||
: 8. Additional Co*-nents: | |||
907 716 | |||
FM 6.6 Exhibit 9 SM u'71 Af*d( | |||
FPJEri, .J CRYSTAL RIVER UNIT NO. 3 PoweraAT,0tTENDON C0Apo REACTOR BUILDING PRESTRESSING SYSTEM HISTORY TENDON IDENTIFICATION NUMBER S6 V / OT LENGTH SHOP WASHER ID: PC CR FIELD WASHER ID: PC CR | |||
: 1. GAI/QA vendor inspection cover letter number-FPC _ DA ATE | |||
: 2. Date tendon received on-site RMR Number | |||
: 3. Date installed in conduit Installation NCR's Wires removed Wires replaced Total Ineffective wires | |||
-4. Date buttonheaded Buttonheading NCR's Bad wires Accept. Reheads Total Ineffective wilres | |||
: 5. Date stressed Stressing NCR's Date restressed Restressing NCR's SHOP END FIELD END TOTAL Elongation (1500 psi to 80% ult.)-Pred./Act. / I / | |||
Lift-Off P......6 - Predicted/Actual 41,i//6S - N/A L-C-b~f- FOAfL eGfQLZA Shim Thickness/80% Ultimate Pressure N/A Unseated/Broken Wires U*" iOarf'otal effective wires after stressing | |||
: 6. Date Bulk-filled / 7~8Bulk-Filling NCR's________________ | |||
Time since installation Inlet Pressure Outlet Temp. | |||
Date end caps refilled: Shop ____ ___ Field /141 | |||
: 7. Data compiled by 7- -Organization FP 70 Date ____________ | |||
: 8. Additional Comm~ents: 5Th't9T()r 22LyS jwc (12--7-77 J)J D tz PIiLo i2-usr &NW 512F55D&J U~iey poiJ,9e z)Q'ba-opr- r-oac Oos-s-r) | |||
: 3) tf~l i.,w4 CA4JKV 4 ~ (tSS TYAA m & D'z ") AT B0VPZ>1 0V'Ch0,e,46(1/2-" | |||
I 907 716 | |||
FM 6.6 Exhibit 9 I s- SurzoriuAkicE | |||
;f60 Florida CRYSTAL RIVER UNIT NO. 3 Power REACTOR BUILDING PRESTRESSING SYSTEM TENDON HISTORY TENDON IDENTIFICATION NUMBER 56 V / CUT LENGTH SHOP WASHER ID: PC CR FIELD WASHER ID: PC CR | |||
: 1. GAI/QA vendor inspection cover letter number-FPC _D | |||
*TE | |||
: 2. Date tendon received on-site RMR Nuober | |||
: 3. Date installed in conduit Installation NCR's Wires removed Wires replaced Total Ineffective wires | |||
: 4. Date buttonheaded Buttonheading NCR's Bad wires Accept. Reheads Total Ineffective wi res | |||
: 5. Date stressed Stressing NCR's Date restressed Restressing NCR's SHOP END FIELD END TOTAL Elongation (1500 psi to 80% ult.)-Pred./Act. / / | |||
Lift-Off Pressure - Predicted/Actual / N/A Shim Thickness/80% Ultimate Pressure / N/A Unseated/Broken Wires Total effective wires after stressing /63 | |||
: 6. Date Bulk-filled Bulk-Filling NCR's Time since installation Inlet Pressure Outlet Temp. | |||
Date end caps refilled: Shop Field | |||
: 7. Data compiled by h. *" Organization __ | |||
Date __/_ _7_F | |||
: 8. Additional Comments: (2-) ed bi4 -cy ,yAeao " | |||
111A -'f'ry- S~r eI/Hcam e - /l6 e 6~cf 907 716 | |||
(.0) | |||
CRYSTAL RIVER UNIT NO. 3 REACTOR BUILDING PRESTRESSING SYSTEM TENDON SURVEILLANCE RECORD TENDON NO. 56VI LIFT OFF CONDITION RETENSIONING Inspection Avg. Shim Elong- Total Avg. Shim Elong- Total Reactor Bldg. | |||
Period and Force Force Thickness ation Effective Force Force Thickness ation Effective Temperature OF Date Location (kips) (kips) (in) (in) Wires (kips) (kips) (in) (in) Wires Int. Ext. Comments 1 2 3 4 5 6 7 8 9 10 11 12 13 14 Is Original T1 1784 14" 13/16" N/A N/A N/A 1. Two original lift-off Stressing 1699 pressures were recorded in tendon history 8130/74 B W1A. 1A& 4 N /iAL lu N/A N/A N/A N/A N/A N/A N/A 1 T 1719 14"~ NIA 167011 I. flairl 1ii crackltig ot b_ NLA /AL botLom anchorage 12/9/77 4" _WlA h161 _Lf 6_ | |||
2 nd T 1707 14"~ bJA 1K 14" | |||
: 1. One wire removed | |||
-RIA 2. Water Inside tendon 4/3/80 B N/1A N/A CD 0)}} |
Revision as of 08:01, 13 November 2019
ML102870283 | |
Person / Time | |
---|---|
Site: | Crystal River |
Issue date: | 02/03/2010 |
From: | - No Known Affiliation |
To: | Office of Information Services |
References | |
FOIA/PA-2010-0116 | |
Download: ML102870283 (71) | |
Text
6.6 Inadequate Original Tensioning of Tendons
==
Description:==
Initial tensioning of tendons could lead to excessive stresses in the containment structure. This is of particular importance as the CR3 containment dome did delaminate upon tendon original tensioning in 1976 (FM 6.6 Exhibit 4) as well as another Florida containment dome that delaminated at Turkey Point upon original tendon tensioning (FM 6.6 Exhibit 5).
Excessive original tensioning can damage the concrete by generating localized micro-cracks and/or enhanced creep rates.
Also, unbalanced or incorrectly sequenced post-tensioning can lead to high local stresses, micro-cracks and/or delamination.
Data to be collected and Analyzed:
- 1. Review initial tendon force requirements (FM 6.6 Exhibit 1);
- 2. Review initial tendon tensioning data (FM 6.6 Exhibit 2);
- 3. Review first surveillance lift-off measurements (FM 6.6 Exhibit 3);
- 4. Review original tensioning sequence (FM 6.6 Exhibit 7);
Discussion:
The issue of excessive pre-stress by design is included in FM 1.3 as it is a design feature (this is the hoop pre-stress equal to 1.6 times the accident pressure). The current failure mode deals with the field tensioning in excess of the pre-stress design.
2/3/10 P-H , . Page 1 of 3 Daefeate to t1h.m.r_* p=-w t b§t 1 Draft1
The initial tendon tensioning was sufficient to cause delamination early in the life of the containments in the case of the CR3 dome and the Turkey Point dome (FM 6.6 Exhibit 4 and FM 6.6 Exhibit 5). In both cases, issues of radial tensile stresses, tension-compression interactions, and limitations in the concrete tensile strength were indicated as root cause for the events.
Samples of the original tendon tensioning sheets are shown in FM 6.6 Exhibit 2. The tensioning sheets contain the hydraulic pressure on the jacks while the tendon force is the number typically referred to. The relationship between the two numbers is linear and well-known. Each jack is calibrated and the linear relationship is slightly different for each one (FM 6.6 Exhibit 8). For the original tensioning jacks used by VSL, the approximate relationship is that 6,800 psi of hydraulic pressure at the jack is equivalent to a tendon force of 1,635 kips.
Tendon 12V20 shows a lift-off force of 1785 kips at the first tendon surveillance even though the original stressing record does not indicate any special problem with this tendon (FM 6.6 Exhibit 9). Tendon 12V20 does not go around any penetration. The excessive force was recorded again at the second surveillance (1740 kips) before being re-locked off at 1630 kips during the third surveillance.
Tendons 45V3 and 56V1 lift-off measurements were also above the 1,635 kips.
Besides the overstressing, the sequence of tensioning is important, both in terms of elastic shortening losses for the various tendons, and in terms of asymmetrical loading of the concrete. The examination of the original detensioning sequence indicates that the CR3 containment was evenly loaded upon tensioning.
The key results here are that there was no indication at the time of the CR3 dome delamination, or since in regular surveillance activities, that the wall had delaminated, and that the CTL condition assessment analysis, using Impulse Response technology, showed there are no delamination in five of the six CR3 containment panels (FM 6.6 Exhibit 6, see Summary page 4 of 96).
This indicates that original tendon tensioning by itself did not create the delamination.
Verified Supporting Evidence:
- a. First surveillance lift-off measurements did detect 3 over-tensioned vertical tendons (FM 6.6 Exhibit 3);
2/3/10 PW-Pr8 '12i..d 2009 Page 2 of 3 Draft1
Verified Refuting Evidence:
- b. Maximum tendon force is 1,635 kips (FM 6.6 Exhibit 1, page 5 of 5). This is as designed and not expected to create excessive tensile radial stresses (see also FM 1.3);
- c. Original tensioning sheets did not report any over-tensioned tendons;
- d. First surveillance lift-off measurements did not detect any over-tensioned hoop tendons (FM 6.6 Exhibit 3);
- e. There was no indication at the time of the CR3 dome delamination, or since in regular surveillance activities, that the wall had delaminated as well;
- f. The CTL condition assessment analysis, using Impulse Response technology, showed there are no delamination in five of the six CR3 containment panels (FM 6.6 Exhibit 6, see Summary page 4 of 96). This tends to indicate that original tendon tensioning by itself did not create the delamination.
==
Conclusion:==
We have not found evidence that the original tendon tensioning was done so incorrectly as to have been a contributor to the delamination, either alone or in combination with other factors.
2/3/10 iUI-~k~ ; 'z~z..t~L2C.&JPage 3 of 3 Draft 1
pd,* 1,,
JFM 6.6 Exhibit 1
__n~ NUCLEAR OPERATIONS ENGINEERING
%Sff CRYSTAL RIVER UNIT 3 DESIGN BASIS DOCUMENT FOR THE CONTAINMENT SYSTEM CODE: NIA TAB: 1/1 ISSUE DATE: 11/8/85 Revision 3 Revision 4 Revision 5 Revision 6 Date 03-09-01 09-18-01 04-26-07 09-24-08 Design Engineer R. P. Schmiedel R. P. Schmiedel P. Winters Verification Engineer C. S. Sterner L. S. McGowan C. Pugh r_______,__
Supervisor G. E. Englert K. R. Wilson L. Santonastaso
page 2 of 5 CRYSTAL RIVER UNIT 3 Page i of ii Rev. 6 Pmress Energy No DESIGN BASIS DOCUMENT SYSTEM NAME: SYSTEM CODE:
CONTAINMENT N/A REVISION LOG Revision/Date Description 0 /11-8-85 Initial Issue 1 /07-25-94 Complete re-issue and incorporation of Temporary Change #296 as shown by revision bars.
2/11-18-99 Incorporated Temporary change #539 and #954.
Text from T.C. # 539 was not incorporated due to being superseded by T.C. # 954.
3 / 01-02-00 Incorporated Temporary change #1180 as shown by revision bars.
4 /09-18-01 Incorporated Temporary change #1115 as shown by revision bars.
5 /04-26-07 Incorporated Engineering Change 66751 RO as indicated by the change bars on pages 14 and 25.
6 /09-29-08 Incorporated Engineering Change 71342 as indicated by the change bars on page 12.
Tab 1/1, Revision 6
page 3 of 5 CRYSTAL RIVER UNIT 3 Page ii of ii Rev. 6 ProgressEnery DESIGN BASIS DOCUMENT SYSTEM NAME: SYSTEM CODE:
CONTAINMENT N/A DESIGN BASES INDEX FOR CONTAINMENT Section Title Page DE FINITION ......................................................................................................................................................... 1 G E NE RA L ............................................................................................................................................................ 2 Ma te ria ls .................................................................................................................................................. 2 Design Conditions ................................................................................................................................... 8 FO UNDATION MAT ........................................................................................................................................... 22 PROTECTIVE RETAINING W ALL AND CANTILEVER SLAB ...................................................................... 24 TENDO N GALLERY .......................................................................................................................................... 25 CYLINDRICAL W ALLS, HAUNCH, AND BUTTRESS ................................................................................... 26 R ING G IR D E R ................................................................................................................................................... 30 D O ME ................................................................................................................................................................. 32 LINE R ............... :................................................................................................................................................. 35 PENETRATIONS ............................................................................................................................................... 38 EQUIPM ENT ACCESS SHIELD STRUCTURE ........................................................................................... 43 Tab 1/1, Revision 6
page 4 of 5
_Progress Energ CRYSTAL RIVER UNIT 3 Page 1 of 44 Rev. 6 r EDESIGN BASIS DOCUMENT SYSTEM NAME: SYSTEM CODE:
CONTAINMENT N/A DEFINITION The Containment Structure is classified as a Class I structure because:
- 1. Its failure might cause or increase the severity of a loss-of-coolant accident (LOCA).
- 2. Its failure might result in an uncontrolled release of radioactivity.
- 3. It is vital to safe shutdown and isolation of the reactor.
In addition, the Containment Structure provides shielding from the fission products which could be airborne in the building under accident conditions.
The containment is composed of those elements listed in the Table of Contents for this Design Basis Document.
The Reactor Building is a concrete structure with a cylindrical wall, a flat foundation mat, and a shallow dome roof. The foundation slab is reinforced with conventional mild-steel reinforcing. The cylindrical wall is prestressed with a post-tensioning system in the vertical and horizontal (hoop) directions. The dome roof is prestressed utilizing a three-way post-tensioning system. The inside surface of the reactor building is lined with a carbon steel liner to ensure a high degree of leak tightness during operating and accident conditions. Nominal liner plate thickness is 3/8 inch for the cylinder and dome and 1/4 inch for the base.
The foundation mat is bearing on competent bearing material and is 12-1/2 feet thick with a 2 feet thick concrete slab above the bottom liner plate. The cylindrical portion has an inside diameter of 130 feet, wall thickness of 3 feet 6 inches, and a height of 157 feet from the top of the foundation mat to the spring line. The shallow dome roof has a large radius of 110 feet, a transition radius of 20 feet 6 inches, and a thickness of 3 feet.
Tab 1/1, Revision 6
page 5 of 5 CRYSTAL RIVER UNIT 3 Page 15 of 44 Rev. 6 DESIGN BASIS DOCUMENT SYSTEM NAME: SYSTEM CODE:
CONTAINMENT - GENERAL N/A PRESTRESS FORCE SOURCE VERTICAL HOOP DOME Vert Hoop Dome Pattern 144 94 hoops 3 sets 2 sets tendons 3 tendons of 35 of 6 3 8 6,10 per hoop tendons tendons Radius 807.375' 812.375' 720.375' 720.375' 3 7 6 Spacing 35.23" 13" 30" 30" 3 5 4 Prestress Level 457 K/ft 829 K/ft** 820 K/ft --
Specified 1 1 1 Immediate 1868 K/ 1868 K/ 1868 K/ -
/O 1-21l]
t.tJ IT4Z O ~j I . .. JJ&WL.............,.......
14 ...... d....... ....... ad.......
I Lockoff tendon 1635K/
tendon 1635K/
tendon 1635K/
tendon 646K/
9 9 9,10 Min. Req'd at 40 1149 K/ 1252 K/ 1215 K/ 2 2 2,10 years I tendon tendon tendon
- 415K/ft for lower 10 feet of wall
- GUTS = Guaranteed Ultimate Tensile Strength = 2335K/tendon (A = 9.723 in2, fu = 240 ksi)
Sources:
- 1. SP-5583
- 2. Memo: J.F. Fulton to J.C. Herr, "CR3 Tendon Surveillance - FSAR Technical Specification 4.6.1.6 -
Required Minimum Average Tendon Force for the Repaired Dome", 2/15/80, plus attached calculations for W.O. 04-4762-099.
- 3. G/C, Inc. Structural Calculation FC 1.01.7/2
- 4. G/C, Inc. Structural Calculation FC 1.01.7/50
- 5. Prescon Shop Drawings
- 6. G/C, Inc. Structural Calculation FC 1.01.17/0
- 7. G/C, Inc. Structural Calculation FC 1.01.8/30
- 8. G/C, Inc. Structural Calculation FC 1.01.8/4
- 9. ACI 318-63, Sec. 2606.
- 10. G/C, Inc. Report, "Reactor Building Dome Delamination, Final Report," December 10, 1976.
Reason:
The prestress forces provided in the vertical, dome, and hoop directions are sufficient to eliminate tensile stresses in the shell due to membrane forces resulting from design loads. Prestress losses due to such factors as shrinkage, concrete creep, steel relaxation, elastic shortening of the concrete, and friction were considered in the determination of prestress levels.
Tab 1/1, Revision 6
- 3. t'l2 CRYST;'L P, R U,4T NO. 3 page 1 of 11
- R-"..... . .... SYSTEM TENEU* HISTOPY IDELoTIFICATIO NUMBER
- /3 / *3 CUT LENGTH /_-S-/ __
- Hop-iw II-'sER 1D
- . PC /2,0 CR 393 FIELD WASHER ID: PC /2.-2 CR /2 '"
I. GAI/Q,\ v.endor inspection cover letter n'--ber-FPC 0 ?_____/? DATE 2,4/1_7_/"
I. Date tendcn received on-site /Z -3 " 3 RNR Nuber 3r "0
- 7
- 3. Date Insa'lel_ d in ccnduii: A// 79 Installation NCR's_,_
Wires removed 0 Wires replaced _ Total Ineffective wires (
'.. Date buttcnhac2ed _ /7-;71 Buttoriheadin; NCR's Bad wires 0 Accept. Eeleads 0 Total Ineffective wires 0
- 5. Date stressed / ZV- 7S Stressing NCR's Date restressed Restressing NCR's SHOP END FIELD END TOTAL
~ongatio-i (13500 Psi to 80-4 ult.)-Pre--. /Act. 9 '/ y 6. ý/1, ryy C~~17/
" "t-Off Pressure - Predicted/Actual 7-7 7/a, 66dO f/A Shim Thickness/80% Ultimate Pressure 6' ( */,7*o N/A Unseated/Broken Wires L Total effective wires after stressing /_
- i. Date Bulk-filled P-2?- 7- Bulk-Filling NCR's Time since installation e - /*" Inlet Pressure /Z111 Outlet Temp. 13a Date end caps refilled: Shop Field
, ._._... .
- 7. Data compiled by " *-- .- 'i--. Organiza tion __. _
Date Y-./7_ _
- 3. Additional Cozents:
_____ 0/' 71r;
7, *,F;
- "'~""*l, OFibit 2 CRYST;,L STpage urO.
P I','ElPI 3 p;C 2 of 11
" *ZI... RPEACT -.. .. , . .7SI 'J SYSTEM
1HO?-VtitER ID: PC / Z/ CR ' 4 / FIELD. WASIIER ID: PC /Z / CR ;93
- 1. CAI/QA vendor inspection cover letter' nu-ber-FPC i _ _ __ __ _DATE _-/___/___
- . Date tendon received on-site /2 "3 -3 PRMR Nu=ber 3S* ?7
,. Date iistalled in ccnrj-,it Al 74" Installation NCR's Wires removed _ _ Wires rcElaced 0 Total Ineffective wires 0 Date buttc-.hea~ed - /7 -7Y Buttonheadin; NCR's Bad wires 0 Accept. ,e s3s 0 Total Ineffective wires 0
- 3. Date stressed 3-I - 7r Stressing NCR's Date restressed Restressing NCR's SHOP El;D FIELD END TOTAL
- ++.ýl ,-?.,I.So-, /?+./ to.,.,,.
(8kongation (1.500 psi to 802 ult.)-Pred./Act. 4- S/£' 0 ,"
t-Off Pressure - Predicted/.%ctual 6800 1 7s *?oV0 0 N/A Shim Thickness/80. Ultimate Pressure 6/&/7 7 0 /7 90 N/A Unseated/Broken-Wires 0 Total effective wires after stressing 1_- _
i,. Date Bulk-filled 7 7-Z 717 Bulk-Filling NCR's Time since installation 6 x*,,o?'t-4 Inlet Pressure /i.P J" Outlet Temp. _________
Date end caps refilled: Shop. Field
}. Data co-piled byI 2 e dtbyQ, Organization I,.-,.
Datle _1_1_-_77
- 3. Additional Co=nents:
I? N t ')
I--FV'6 MAbit 2I CRYSTAL RIVER UNIT ';n. 3 page 3of11
- .. R A-F.AC7c r:.'c-;
P!_iK:.;.
p ,I. SYSTEM ID7_:;EIFICATION N;UM2ER /3 5 CUT C LENGTH - /0
,)R8VS5HER ID: PC /'. / CR ',0 FIELD WASEER ID: PC /2Z CR /277 I. GAI/Q,\ vendor inspecticn cover letter nuzber-FPC i it? IV DATE Z/_/7__
Z. Date tendon received cn-site /Z-3-73 RMR Nu-ber JrO -0 "
- 3. Date irstalled in ccnduit , -2?- 7-Y Installation NCR's Wires e:noved 0 Wires replaced 0 Total Ineffective wires 0
.. Date buttcnheaded ?-/7-79A Buttonheafin; N;CR's Bad wires _ Accept. ehea*s 0 Total Ineffective wires 0
. Date stressed 7% Stressir, :CR's Date restressed Restressing NCR's SHOP El-D FIFLD END TOTAL
( onzation (1500 Dsi to -Cult.)-Pred./Act. 5'/i/'* - / /0;I/lyk t-Off Pressure - Predicte*i/lctual 6 1
/(740 " 67/0 1&7 N0A Shim Thickness/80% Ultiz-.ate Pressure _'7__ 7 _/ 74,4O N/A Unseated/Broken Wires 0 Total effective wires after stressing /63
. Date Bulk-filled 9-27-71/ Bulk-Filling NCR's Time since installation 6 ,*,/,A/ Inlet Pressure. Outlet Temp.
Date end caps refilled: Shop Field
- 7. Data compiled by
- ______ Organization Ij*-C-Datte Ce-/e7 7
- 3. Additional Cooents: ____ __________ ___ __
0n7v 711
SHEET /2 AoF Z8 FM 6.6 Exhibit 2 page 4 ot 11
-*
- Florida CRYSTAL RIVER UNIT NIJ. 3
-.,r.d0 Power REACTORR BUILDING RV PrF.STRESSING SYSTEM Q,6O" TENDON H1STORY
..IDON IDENTIFICATION NUMfBER 4"2 H-3 0 CUT LENGTH /,, -
SHOP WASHER ID: PC /.2-/ CR Y_56 FIELD WASHER ID: PC /Z2 CR //M3
- 1. GAI/QA vendor inspection cover letter number-FPC E P?2o DATE Z/Zo/7y
- 2. Date tendon received on-site /- - RMR P Number _ ___________
- 3. Date installed in conduit /-/17 -? Installation NCR's Wires removed _ Wires replaced 0 Total Ineffective wires :
- 4. Date buttonheaded 2 - ;?" Buttonheading NCR's Bad wires 0 Accept. Reheads C Total Ineffective wires 0
- 5. Date stressed Z Z*-?" Stressing NCR's Date restressed Restressing NCR's SHOP END FIELD END TOTAL Elongation (1500 psi to 80% ult. )-Pred./Act. 4/ 4'/4 f/Ai .r* /e /,o 5 l-r Lift-Off Pressure - Predicted/Actual k70 /107 11p0 12,f-0 N/A Shim Thickness/80% Ultimate Pressure //Y 7.70 a f -e N/A Unseated/Broken Wires 0 Total effective wires after stressing /6
- 6. Date Bulk-filled 7-3/-7-/ Bulk-Filling NCR's Time since installation ! ,,po Inlet Pressure Z. '3" Outlet Temp. /4/
Date end caps refilled: Shop Field
- 7. Data compiled by4!!! Ognzto ______________
Date _ /_/
- 8. Additional Comments:
907 716
SHEET /25 OF Z.S 4 Florida FM 6.6 Exhibit 2 Power
(,RYSIAL RIVER UNII NO. 3 RLEAGIOR BUIDIN Pid STPESSINCG SYSTEM pa- -T71 TENDON HISTORY T&WON IDENTIFICATION NUMBER -/2 "/3/. CUT LENGTH / 5" - 7 SHOP WASIIER ID: PC /'Z/ CR 3C
- FIELD WASHER ID: PC / _ CR /Z33 I. GAI/QA vendor inspection cover letter number-FPC I _,_ sr DATE 111-_-1 __3
- 2. Date tendon received on-site /0 -y - 7 :3 RMR Number 3 335- r
- 3. Date installed in conduit /-Z P- 7-v Installation NCR's Wires removed _ Wires replaced 0 Total Ineffective wires 0
- 4. Date buttonheaded -2S--7'y" Buttonheading NCR's Bad wires _ Accept. Reheads _ _ Total Ineffective wires _
- 5. Date stressed 2-/.3 -7J_ Stressing NCR's Date restressed Restressing NCR's SHOP END FIELD END TOTAL Elongation (1500 psi to 80% ult.)-Prcd./Act. 3 5_4 At/
Lift-Off Pressure - Predicted/Actual 6,'20 / 700 jO 45 KS-/1 N/A Shim Thickness/80% Ultimate Pressure £ /7?I/ f / 77 1- N/A Unseated/Broken Wires 0 Total effective wires after stressing /63
- 6. Date Bulk-filled 7-.3/ - 71Y Bulk-Filling NCR's Time since installation 6. ,,o,7/ Inlet Pressure 22. ' Outlet Temp. /120 Date end caps refilled: Shop Field
- 7. Data compiled by_ ___ Organization Date 7
- 8. Additional Comments:
907 716
SHEET /26 OF 283.
FM 6.6 Exhibit 2 page 6 on 1 Florida CRYSTAL RIVER UNIT NO. 3 Power REACTOR BUILDD:G PPVSTRESSING SYSTEM TENDON HISTORY J--E.DON IDENTIFICATION NUMBER 112 H-/* Z CUT LENGTH /5--s -
SHOP WASHER ID: PC_/Z/ CR .- 6Y FIELD WASHER ID: PC /2 C0 CR /23
- 1. GAI/QA vendor inspection cover letter number-FPC I F?2 0 DATE Z1/20/17y
- 2. Date tendon received on-site /- - 7V/ RMR Number 3_ 5-_ _ _ _ _
- 3. Date installed in conduit /1/? -17 " Installation NCR's Wires removed _ Wires replaced _ _ Total Ineffective wires _
- 4. Date buttonheaded 6-27--7 1 Buttonheading NCR's Bad wires 0 Accept. Reheads 0 Total Ineffective wires _
- 5. Date stressed 2-Z9- - 7s Stressing NCR's Date restressed Restressing NCR's SHOP END FIELD END TOTAL Elongation (1500 psi to 80% ult.)-Pred./Act. / /:- fl4- / 5-,.-" /6j* /C" Lift-Off Pressure - Predicted/Actual 6HO /'r- 6720/*' N/A Shim Thickness/80% Ultimate Pressure (Il 7r-/0 7$;, / 7 -'7 N/A Unseated/Broken Wires 0 Total effective wires after stressing /163
- 6. Date Bulk-filled a"*-79 Bulk-Filling NCR's rHme since installation Z WP,1P1W4f Inlet Pressure / 51"' Outlet Temp. /57 Date end caps refilled: Shop Field
- 7. Data compiled by Organization Date _ _ _ _ _ _ _ _ _ _ _ _ _
- 8. Additional Comments:
907 716
FFi6-, B6, ibitP2 CRYSIAL. :IVE N ER 3 page 7 of 11
- - .REACIORU : P '1; FSSI., SYSTEM 1D'Z'.,TIIFICATI*O :,UMEER /2 V 2- CUT LENGTH /3t _
SHOP W,5K:. ID: PC /Z / CR 6W_ __ FIELD WAcSER ID: PC I.O CR L3?.
I. GAI/QA vendor ifnsection cover letter, number-FPC 1 95"7 DATE Z/z______
- 2. Da:e tendon re:eiveý '.n-site /- 1 -79Y .1R 1,umber -3 G
- 3. Date installed in ccr.duit 7- 37-4 Installation NCR's Wires removed 0 Wires replaced 0 Total Ineffective wires
- 4. Date buttcnheaded 32"7-79 Buttonheading NCR's Bad wires 0 Accept. Reheads 0 Total Ineffective'wires
- 5. Date stressed /9-/P -79 Stressing NCR's Date restressed Restressing NCR's SHOP E';D FIELD END TOTAL Elongation (1500 psi to 8O?' ult.)-Pred. /Act. Az i_/Z~f // - Z MZ~
ift-Off Pressure - Predicted/Actual 4600 / 740o5'0 N/A Shim Thickness/80% Ultimate Pressure /3j/77V0 , / , N/A Unseated/Broken Wires 0 Total effective wires after stressing /6
- 6. DaLe Bulk-filled /0-Z3-74 Bulk-Filling NCR's Time since i.Istallationn Inlet Pressure 1a ,s Outlet Temp. /Z-46 Date end caps refilled: Shop Field
- 7. Data compiled by -_--- " "_Organization_
Date 2 _ __/_ _ _
- 8. Additional Co_--ents:
-~.~-r ---- ~ --- - -- -M ; 716
page 8 of 11 F66 ExhA2 CRYSrTIA, PIVER I:' I W0. 3 REACIOR i-U1L1I..:G Fr:1 rpnss1,. SYSTEM TFU1C: "i; y
'IDuY:;TIICATION""U:4 S Z'R / 2 V 3 CUT LENGTH / y-- '_ 6 SHOP A3,R ID: PC /Z/ CR S_9_7 FIELD WASHER ID: PC /Z CR /7(o
- 1. GAI/QA vendor inspecticn cover letter number-FPC 1 995_ / DATE _71_21_17Y
- 2. Date tendon recei':e2 cn-site 1-16 - 7Y1 PMR Nmbe r 0~3
- 3. Date installed in conduit 7 74' Installation NCR's Wires removed 0 Wires replaced 0 Total Ineffective wires
- 4. Date buttcnheaded 7" Y - 74/ Buttonheadin g *NCR's Bad wires 7 Accept. Reheads 9 Total Ineffective'wires 3
- 5. Date stressed '7 -Z 7 - 71 Stressing NCR' s Date restressed Restressing NCR's SHOP El;, FIELD END TOTAL Elongation (1500 psi to 80% ult. )-Pred. /Act. / /Z/79*e M/0 Y . /7jY //Z 76 :P
!it-Off Pressure - Predicted/Actual 68OO /7Do AP./ "- f' N/A Shim Thickness/80%. Ultimate Pressure /3 /1/7770 " 00"/ . N/A Unseated/Broken Wires 0 Total effective wires after stressing /&3
- 6. Date Bulk-filled /0 -Z 3 -7y Bulk-Filling NCR's Time since installationr)34 Inlet Pressure /f# "2/ Outlet Temp. /2 2 Date end caps refilled: Shop Field
- 7. Data compiled by Organization Pace 117
- 8. Additional Co--znents:
q,07 71r,
, ' FMi*6"Ehit*2 4A
, 6 CRYSr, R ' ' L- :*vE1 I ,,n'1 C1 tn.
0 3 page 9 of 11
,I:ACIRt K' ilUI L1)!1: P12!: .C S;SIEH 5.:I*S 1u2;VI-IFCATO1:; NU:3ER /. t 'ICUT LENGTH ,/ '- 7 SHOP WASHER ID: PC /Z/ CR 77 FIELD WAS*iR ID: PC /Z0 CR L(&7
- 1. GAI/QA vendor inspecticn cover letter n1.;er-FC g ___ _s_ _ DATE 2/Zf/,I
- 2. Date tendon received en-site / -_o__ 7-*_ MR Number (P_0 7 3
- 3. Date installed in conduit 7 Z9 Installation NCR's Wires removed 0 Wires replaced 0 Total Ineffective wires 0
- 4. Date butteroheaded ? 7 - 79y Buttonheading NCR's Bad wires _ _ Accept. Reheads Al Total Ineffectivewires /
- 5. Date stressed -/A/ - 7V/ Stressing NC.R's Date restressed Restressing NCR's SHOP EuD FIELD E':D TOTAL Elongation (1500 psi to 80% ult.)-Pred./Act. I/1111,,44 A/X,AI- 1 1t/g ,ZY ft-Off Pressure - Predicted/Actual 674O 685 r _______" __" N/A Shim Thickness/80% Ultimate Pressure f77Z*o L " N/A Unseated/Broken Wires Total effective wires after stressing / Z
- 6. Date Bulk-filled 7 Bulk-Filling NCR's '
Time since installation6 .*dWoj/*fj Inlet Pressure /0 /40 Outlet Temp. /2 o Date end caps refilled: Shop Field
- 7. Data compiled by *"*I2 *: Organization _-_
Date _ _ _ __
- 8. Additional Co-.--7ients:
....*O _7 )5 .. ..._
page T1-fD"T l M 6.6 Exhibit 2 fE, 1),R Toma 4r CRYSTAL RIVER U!:IT NO. 3
),06 'N,,;*l REACTOR BUILD!";G PRLS; RESSING SYSTEM
'.00
'4 TEN~DON IILSiOR1Y TENDON IDENTIFICATION NUIIBER
- CUT LENGTH / ' -
SHOP WASHER ID: PC /*/ _ CR , 3/ FIELD WASHER ID: PC_____ CR ___"-
I. GAI/QA vendor inspection cover letter number-FPC 9 /__/_0 DATE _________-.--
- 2. Date ten6on received on-site 9 /3 7/ PMR Number 63 7*-K 2
- 3. Date installed in conduit 7,/ Installation NCR's Wires removed 0 Wires replaced 0 Total Ineffective wires 0
- 4. Date buttonheaded /0 Buttonheading NCR's Bad wires £ Accept. Reheads V Total Ineffective wires 0
- 5. Date stressed //- 7- 7L/ Stressing NCR's
- Date restressed Restressing NCR's SHOP END FIELD END TOTAL
- longation (1500 psi to 80% ult.)-Pred./Act. , //7 /
Lift-Off Pressure - Predicted/A~ctual OXi , 700 sv'ol a V0 N/A Shim Thickness/80% Ultimate Pressure 7771 I
i4 Z77o N/A Unseated/Broken Wires Total effective wires after stressing /*,Z
- 6. Date Bulk-filled 4 7-7. Bulk-Filling NCR's Time since installation /1)0,wl,"1) Inlet Pressure a *_1 . Outlet Temp. 6_ d Date end caps refilled: Shop Field
- 7. Data compiled by _ ___ _ _Organization__._______
Date _E509 717
- 8. Additional Co.-a.nents:
page 11 of 11 DO"" ).. u ls CRYSTAL RIVER U1.7f NO.
to. 1 "-0 ,ier REACTOR BUILDING PVES; :ESS1NW. -"tST:M TFI.,N) HIS.JRY TENDON IDENTIFICATION NU,"BER 9 /07 CUT LENGTH /28-SHOP WASHER ID: PC / * / CR ._, FIELD WASBES 13: ?C CR 9 7-I. GAI/QA vendor inspection cover letter number-FPC I 1/c/? DATE '/h
- 2. Date tendon received on-site 3-/3- 74/ Rl1 u rr '175"
- 3. Date Installed in conduit - 7-74' Inst.'lattor, NCRfs Wires removed 0 Wires replaced 0 Total Ineffective wires 0
- 4. Date buttonheaded /0 - 2 - 71J Buttonheadilt "("R's Bad wires £ Accept. Reheads 0 'coal Ineffective wires 0
- 5. Date stressed 1/--/a-74 Stressing sl __.'__s
-1Date restressed Restressing ;,CR's SHOP L',D FIELD END TOTAL e".ongatioii (1500 psi to BG~ult.)-Pred./ACL. / j/4 ?)/gi Lift-Off Pressure - Predicted/Actual *#/_/_'?QO9 4'/O,,?9.0 N/A Shim Thickness/80% Ultimate Pressure L.// / /??T'O N/A Unseated/Broken Wires 0 Total effective wires after stressing /1 3
- 6. Date Bulk-filled _ ___ _.__ Bulk-Filling NA4-3's ...... _/___
Time since installation /10.ne,A^._/ Inlet Pressure Outlet Temp. __'____
Date end caps refilled: Shop Field
- 7. Data compiled by _.e Organ;.... ior D.3t e 1 /77 03
- 8. Additional Coi--nents:
FM 6.6 Exhibit 3 page 1 of 4 MATA S'Fr? 6 ItF.STIIJSS FO'RCE CflmfIFRATICRN?EST I *~
REACTOR rATC M ILITT-OFF' CON.
DTION LOCK-Ollr WC.Tr.XFlY Twtp* 1.%,tP.
FT I'ALVIOUS 0 ITrD *GG AVC. Or S111.1 GAGE FINAL 6111H TI. LCrKfhP*
roriLII.54rocs (IA raus.
EI) thipp) 2PRE fliD.4) tE FCAE ll~~lfl ~ -OC FtSS.-
IIALVIOUIS CIPTCINAL (KaI)NIP-)
FORCE T"lCO~ESS (i.
aF I A: % f 7 it 9 in I 1 17 11 14 1ý I lp 17 17~~- ___ -, - 4 4..4
~
Y.2. '.~ L.
..2 2 lul a/
-r 3 a~2JAI
.2a.
7-- /-
IOTE A:
FOR.CECALCULATIQt4 (1) Force @ Lift-off - Jack Pressure z Jack PLston Ate&
OR: (2) DetermLMv force from calibtattca curve MOTESt Leactor Building internal temperature will be read using Cl-2?&*TE or CI-173-TE (temperature read at Johnson Finel 1i-*)
"UTZ C:
Vice force (Column 8) is defined as followa:
W.F.
- Colu'n 7 163 - Column A of Dita %hect I NOTED:
I.pccted lift-off force (colu-n 4) is defined As follow,: No. of effective wires at Instelletion (or previous inspectiou)
I Ave. pradicted -le force ehown on Fla. I at time of noapection.
LSdOft.
LOATIi*l: I to 6 lusebr of buLtTeeO heairct to end of IeS
'Hil.t l jTiWESS: Clear distance bhtvoea beekna plate end stream iLg washer.
rAJ.VlQ-: At time t Insetallation or'previoue murvtallenc 9. Contractor Review by: Date:
CRICIIAL: At time of etarting current survalllence.
F.F.C. Approval by: vote:
i OAR till IN-" M -
FM 6.6 Exhibit 3 page 2 of 4 DATASI!ttt 7 PRI.ESTRFSA FORCECRIrFTRHAT3O,TqT.
VERTICAL TEIMNS IsSrECtIOH TFAUOD /
ILACTOR BATE
- I[Tr-oF7 CONDIT010 LOCX.OFF RIM~ TE4? JIMF 1-.S?. ZY PREVIOUS EXP[C ED GAd AVG. OF SHIM GAGE VIAL SHR.f FO£CE LIFT-OFF FO)C t(S. i .ORCE I M WIRE O405 TICrIoESS (OIii. 15. FO(Cst (IC2i.ESS .F
.. . .. .
l~ts,. LOCATIO4 (ittr) % - iD I tI1 fus) -fuli ORCE FirWious ORTCIOAL (Ks0 (kips) (in.
i 15. "~ 1._.yo L *
- d a 1* !1 L
1* l1 11 l&
14 .1 -
I*A*
- -
I
...
,
,' ,12 V/20 1
'Igg _/ 4'il_
/C/3j*- my,/' 57.
.3 S.151 q.._ %q.ssrBv. u -71
/637 /Y9 63 Z- IkA /L7 16,21y~y~ 's~_L _9 AMloY 121Y,17j L4
- 5. 4Ejva _1_
/1q690 /q 7 o 58 M-2 ... 71-7 _5.5 -i /Ar Ac*
1 -jE 1 ""
RIOTEA:
4-No rc FORC6E CALGIATION.: (1) Force ( Lift-off - Jack Presaure a Jack iisteo Are&
OR& (2)Determtine force from caltbration curve NOTEB1 Reactor BuLlding iaterval temperature will be rud using CI-274-TE of CI*217-TZ (tieparacure read ac Joohsos facel It-I)
I L.C,
, NeLTOAL, mOTe C:
Wirte Force (Column 8) it defined as lollows; W.I. - C oIi 7 4 O h I 163 - Column 4sof Data Sheet 2 "I 1NOTE 0:
II "c' ;ý,Pj IJI Is C J ; S1.
- 6 V I Expected lift-off force (column 4) to defined at follows: 11., of effective wires Oi LtnaiaOIL4o1 (or prev IoA Inspection)
- I Ave. predicaced wtre force shown on FIg. 2 et Limof Ienspectiof.
- tOCATi: T or B - top or bottom (ve tticol tendon).
" SAL'4*fdlQ*%SS: Clear distance beec bee ri plete and stressing waeser.
SPw.-Ois: At time of ttalli1ton Orýrevlouo surveillance.
SCIIGLNAL* At time of etecitng Currene Murveilleac*.
Cootrector Review by: oDam fPr.C. Approval by: _ Date:
3 ",t, -r- o"'
FM 6.6 Exhibit 3 page 3 of 4 DATA lvirq~ ZA P*u1R*.*;rt;. 11('E C 1FRflPtAT101f MTS V.RICAL TlIfVIVItS ui PoxS EC.R= -00 TfON'IV, I r tIFr-OFF CM9IITtM4 L.OCK-OFF REACTOR Im0 Tr~4P_ DATE tN;jj TM I FAEVIOUS lXp Co CACE AVG. OF SHIM CAGd FINAL 5111J FORCE LIFT-"OFF, FORCE PRESS. FORCE 2 D1DS WIRE THTCKKFSS (in.) Pass. FORCE THICKXESS F I,. t*r'A.TIf' (AhI ..) (k614 (Vall Nos1) tkIr,} FORCE PIrVIOn's ORV:iIAL (Xqt) 1lkI) (N,) yMr. EXT. 7:TIALS
.t 2 3 & $ 1 7 6, 9 t II. 12 13 I9 It 1 _,
- 2. ~s
~ ~~~ - j, 3 . 61 .f 'Zi 7 T _W3id .2: '~ _L1 o y-I-ED-/-- -t - - -
l.
NMTA:
OR: (1) Determine force from calibration curve building Inter*al temperature will be read using CI-27&-TE or Cl-275-TE (ceaperacure read at Jo*eson Panel 11-3) taetcor V1OTEC:
Wrii Force (Column 9) La defined as followo:
W.F. - Col.-n 7 .
163 - Column 4 of Data Sheet 2 VtOT£0:
Ut'ecied lift-off force (Column 1.) is defined as followat N4o. of effective wires at installation (or previous Inspection)
I Ave. predicated wice fotcset bove on Fig. 2 at time of Inspection.
LOMaTICi: T or B - cop or bottom (w 'tical cendon).
SHL't TH!ICKN:SS: CleAr distance beucca Ier plat* aolan tTe ln& washer.
.M.;'IO$: At time of Itita llt::: or ureLous surveillanc C.
CRIGL*.L: At time of starting current survetllsoce.
Contractor aeview by: Date:
P.P.C. Approval by: Datle.
1 1 3- a.A..a.
FM 6.6 Exhibit 3 page 4 of 4 it PAT4 5111'*" 8 PREST'RESS M CE. *IP4ATTO*! TEST ITOP TFlN" Ii VSPECTlN PERIO/D REACTOR DATE Tt"1W i Ir- T O... r . ..... ,,_______ -OI_________PI% Tnflp MrSP. IKSP. AT i1 PREVIOUS EXPECT'D CAGE Avc. OF SKI, MCAE FIN AL SHIMX FORCE LIFT-OFF TOACEj iPESS. ToI0Z 2 EMLS VIRi TNiiCKUS (Ia.) PUSS. FORCE TiI of (kill@) t( )
kil ( dpa) iP .1 (Vk*i PRCE P VIrOVS CR ,IC IAL (toil (k ir ICT, EXT I16 TnITTA ¶ S.I ,D I'/__ CAT._.* (Ih it. IA I1 3 6 5 6 1 8 9 if) t, lt "71~ /.c_£. ".,, ." ,,
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NIOTE A:
FORCE CALCIULATION/:(1) Force @ Lift-off - Jack Treasure Jlack Piston Aree ORS (2) DetermIne force from caltbracion curve NOT£E :
Reactor Building internaL temperature vtil be read using C[-274-TE or Cl-271-ts (temperature rea2 at Johncon Panel 11.3)
OT C:
Wire Force (Column 8) is defined as fall*i-;
W.F. -ColIn 7 163 - Column 4 of Dace Slheet 3 Expected lift-off force (column 4) Is deflied as folLows: It*.of elfeclive urts at Ifsalllatson (or previous Imprctioen)
I Ave. predicted witi force shown on Fig. 3 at time of insplecton.
LOCATIMl: I to 6 - lumber of butiresa natcea to and of t cnd.ah SIManT ICi£ESSt Clear distance between basting pIate aud atrea sin~gwasher.
Contirctor L .eiewby: Date:
"
FTEV1OUS; A: time of instllation or previous surveillance.
-OR'IGMAL: At time oat strting curren- aurvelllance. F.F.C. AppTovel by; Date.
I "
... .E ~'..y1*6 xhibit 4 page 1 of 8 Forida Power C. ri P , .
A A T 10NApril.
21, 1976 Mr. Ernest Volgancau, Director Directorate of Regulatory Operations U.S. Nuclear Regulatory Commission Washington, D). C. 2054S r() irvr&.!1I
Subject:
Docket No. 50-302 l)car Mr. Volganeau:
Pursuant to I0CF-Ri0.5iS, we wish to follow up our verbal (telephone) notification of 4/19/76 regarding a separation in the concrete of the Crystal River Unit t13 containment structure dome. We have now documented the apparent extent.
of this separation. To recap, the following i.s the sequence of events of the investigation.
On Wednesday, April 14, 1976, while placing cinch anchors in t he dome concrete of the Reactor Building, it was noted that there appeared to be a hollow area about one inch beneath the surface. Investigation on Friday, April. 16, by saw cutting and removing a section of concrete approximately one foot.
wide by three feet long, showed that the depth of. the hollow area went deeper as i.t went higher on the dome. By core drill-ing on Saturday and Sunday, April 17 and 18, it was further determined that the separation continued across the dome and went as deep as 15" and separated as much as 1-3/4 inches.
By using acoustic methods, the lower perimeter of the separated area was determined to extend all. around the dome in pours I"G"t, "111" and "J"'.
Our engineers are now evaluati.jg the present condition of the structure.
Sketches marked I, I, Ill , IV, V, and VI illustrate the apparent extent of the separation as i ndicated by)the limit ed data avai.lable at this time.
General Oeflice 3201 hi ty-fourth Steet South 0 PCO Box 1404P2 St PF(!rshWO, Fi0ri]_i 33u'3'-i`
, FM 6.6 Exhibit44 page 2 of 8
.Mr. lrctVolgaiioau April 21, 1.976 We wi1.1 advise you when we have reached final. resolution of this problem.
If you have any questions, please advise us.
Very truly yours, J9g Rodge,
- Asst. Vice President JTR/iw Attachments.
cc: Mr. Norman C. Moseley D)irector, Region 11
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FM 6.6 Exhibit 5 page 1 of 2 FLORIDA PdWER AND LIGhT0 GO14FANY tUIUCE PO~flt EWIT 3 DOCKET NO. 5-0-250
,cON;,rTTv1ENMT9 R-1ORT, S 11~98MC 0164 41*44
FM 6.6 Exhibit 5 page 2 of 2 1.0 INTRODIJCMOt Th1a raport describes' th6 'Tutrk~y Taint Uhit .3 cantainm~atdocdl ntn of tho dome concerte duziing post tensi~oning. of teiiidons, the. supbsequen t, Th vwe§tisAtlbn and- aalyslo qf this Oheznbfehaic, dAd 'theý reyoair and tiist pvrog .p Uwhea about, two thirds; of theý Adbite tenrddps -had, been tensione'd it ",gi notdl -
that co ~rete cac~kifto aiid,.sehing, fi2ller leak~ige,'T~ 4wase develon Ond that in sob6i areas of- dfe dornre, the- cencrete felt sprlnagy ýwhcan valked on.
The ,doin~w a srck 'ith a" ~1d ge bý idv in, 'boine area',,it :squndod ais if it wer holow. Tie concret~e was locally removed Ini sone, of thaes- areas, and sha11owi (approxima'tely 112" to 4") deal~ination planaa, were found ruinring alimost gar-alliel with 1,h0e gutf ace,ý but. eveowa~lly Inte-eting tt.~ A tiull invpst-1,ation Was begun to,,deeterninie bboth the extent and Cau~se of the delaintiofts,~ anmd to. wver the following,
- 2. Core SIArPl~ig
- 3. Cooczete Romoval.
- 4. Rpterislsa Pr~oe~rties
- 5. Anqlyais 'of Loadb During Con'strue tion As a result of the ta~vestigation., it has, been detaminend that insufficient, conact ,ra int the southaeni portion of the, mridionaj. constru~ction, jarit and arout~d tbe: ventilation blqdekoutsý, itoether, with .unbalanced. pdst-tensio nS.'
10,0,0 were, the' vl.or esAu64e of thi6 dealainationý.. After the, pqis-enai ning was complete, the~rp gwas- no evidence, thath dome was nqt capable ,of indeftnitely resIsttn~g -the ,applied%loads cttmensioning thare w~ias no do ecnrabLe loss I dt ,
the te~iorh foi cea du6- to thed'edlamnation.
.Concrete rep1dt=6nt procedures uebe rprdcdwl nJd foii ckations to the original placemient procedures shown to be. desirable. during the analysis of the delaininatiorn causes7.
The com~pleted daome will meet por fo~riancce raquirie~ntns arA the adequacy w'ill be denionst rated during structural testz.
The firsi of T. Y.Lii, kulka, Y'an afnd. Associate, the consultant i n -the 'desIign, of the containment, h~as participated In :the. Investigation program, and: ,the 1-1
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DESIGN ANALYSIS/CALCULATION 1 G+
OTel.
Power Crystal River Unit 3 CORPORATION Page (C1 DOCUMENT IGENITIFCATION NO. REMISON Calculation S-95-0082 1 ATTACHMENT C ORIGINAL TENDON STRESSING SEQUENCES NOTE The original tendon stressing sequences as determined at the time of original tendon installation are still utilized in various calculations and procedures for the tendon surveillance program. Reference I1 contains tendon stressing sequences and related information which was used as a basis for this calculation effort. As part of this calculation, this original stressing information was tabulated in an Excel spreadsheet to allow for faster sort/select capabilities and easier determination of the stressing sequence for an individual tendon. Information from the Reference 1 Calculation, as related to stressing sequences, was tabulated and included within this Attachment. The data was input by the sequence number and then verified with the source input. In addition to the basic sort by sequence number to match the input data, a second sort was generated from the same data to represent the sort by tendon number.
Note that during the input and tabulation of the stressing sequences for this calculation, some minor errors were discovered in the base data. These items are noted and explained in the attached information, along with any assumptions made in the use of the data.
Also note that the original stressing sequences as tabulated and presented herein, as well as the Original Stressing Liftoff data in Enclosure 9 of SP-182, Revision 11, have not been updated to reflect those tendons detensioned and retensioned since the original tensioning effort. (The original stressing liftoff values have been routinely presented within Surveillance Procedure, SP- 182, Enclosure 9.) As more and more tendons become retensioned in the future, there will be a resulting effect on elastic shortening, normalization factors, as well as related calculations which may need to be considered in future efforts.
1I RET: Lk a, nEW K~ur NUWW EngIl~eemg e~s 6" RU: LUfaof ftro REW Nud~ew rqFnlneen
FM 6.6 Exhibit 7 page 2 of 23 Florida Power Corporation - Crystal River Unit No. 3 DOC 10:S-95-0082 Reactor Building Prestressing System ATTACHMENT C Dome Tendons PAGE C2 Stress Sequence Sorted by Sequence Number Sequence Tendon Tendon Tendon Tendon Tendon N Tendon Tendon NoIo O z o o No.
I D130 0 21I1 "' D331 "
2 D128 D3215 D327 3 D 123 D219 D323 4 D"115 0223 D319
_ _ 0D231 _D311 7 D107 D235 0307 8 0303 9 D207 D335 10 D135 11 D139 D203 D341 12 D141 0204 D338 13 D210 D333 14 0133 0213 0329 15 D129 0217 D325 16 D125 D321 17 D121 D225 0317 18 0117 0229 D313 19 0113 0233 0309 20 D109 0238 D305 21 D105 D301 22 D104 0240 0302 23 0101 0236 D306 24 0106 0232 D310 25 D110 D314 26 D118 D122 0228 D318 D322 D326 27 0126 0132 D134 0212 D216 D220 0224 27 D330 28 D138 0140 0205 D208 D222 0226 D334 28 D336 0337 D340 29 D116 D120 0124 v127 D131 D136 0209 29 0230 0234 0237 032 D332 30 D202 D206 D214 0218 D304 D308 D312 30 D316 D320 D324 31 D108 0112 32 D102 D103 D114 D137 D201 D221 D239 32 D241 =339 Note:
Data extracted from Reference 11 calculation information attached.
FILE:DOME.XLW (STRESSEQ) 15-Mar-96 12:08 PM
FM 6.6 Exhibit 7 page 3 of 23 Florida Power Corporation - Crystal River Unit No. 3 DOC ID:S-95-0082 Reactor Building Prestressing System ATTACHMENT C Dome Tendons PAGE C3 Tendon [
Stress Sequence Sorted by Tendon Number Sequence No Tedoo ,o. Sequence O TednO Sequence o
D10 23 0201 32 0301 21 0102 32 0202 30 0302 22 0103 32 0203 t1 D303 8 0104 22 0204 12 0304 30 0105 21 D205 28 ' 306 20 D10S 24 0206 30 0306 23 0107 7 0207 9 0307 7 DIos 31 0208 28 0308 30 D109 20 0209 29 owe 19 0110 25 0210 13 0310 24 0111 5 D211 1 0311 6 0112 31 0212 27 0312 30 D113 19 0213 14 0313 18 D114 32 0214 30 "314 25 D115 4 0215 2 0315 S 0116 20 0216 27 e18 30 0117 18 0217 15 0317 17 0118 28 0218 30 0318 28 0119 8 0219 3 0319 4 0120 29 0220 27 0320 30 D121 17 0221 32 D321 1I 0122 28 22 28 0322 26 0123 3 0223 4 0323 3 0124 29 0224 27 0324 30 0125 18 =226 17 0325 Is 0126 27 0o 28 c32 26 D127 29 0227 5 0327 2 0128 2 D228 26 D328 29 0129 15 0229 18 0329 14 D130 1 0230 29 0330 27 D131 29 =1 6 D331 1 0132 27 02 24 = 29 0133 14 D233 19 0333 13 0134 27 0234 29 334 28 D013 10 0235 7 0335 9 0130 29 0236 23 033 28 0137 32 0237 29 0337 28 D138 28 D238 20 0338 12 0139 11 0239 32 0339 32 0140 28 D240 22 0340 28 0141 12 0241 32 0341 11 FRLE:DOMEXLW (STRESSEQ) 15-Mar-96 12:08 PM
FM 6.6 Exhibit 7 page 4 of 23 Florida Power Corporation - Crystal River Unit No. 3 DOC ID: S-95.0082 Reactor Building Prestressing System ATTACHMENT C Hoop Tendons PAGE C4 Stress Sequence Sorted by Sequence Number Sequence No.
Tendon NO.
Tendon No.
[ Tendon No.
Tendon No.
Tendon Tendon No. No.
Tendon 1 511H05 2 131447 51H.47 .....
3 35H45 35H47 4 13H41 13H43 35H43 51 H45 5 35H41 51H43 6 13H37 13H39 35H39 511H39 511H41 7 13H35 35H37 51H35 511"37 a 131H33 35H35 511H31 511"33 9 13H29 131H31 35H31 35H33 511H27 51 H29 10 13H27 11 13H25 351H25 351H27 35H29 12 13H23 35H23 51H25 13 13H21 35H19 35H21 511H21 51123 14 35H17 51H17 51H19 15 13H17 13H19 35H15 51H15 16 13H13 35H13 511Hl SIH13 17 13H09 13H11 35H11 51 H09 18 51H07T 19 13105 1310H7 35H0 35107 35149 51103 20 131-01 13H03 351"01 35H(03 511H01 21 42H01 46H01 461403 6214101 22 421403 42H05 46H5 2HO3 23 42H07 461407 461"09 62HI05 62H07 62H09 24 42H09 42H11 46H11 46H13 62H11 62H13 25 42H13 46H15 62H15 62H17 25 42H15 46H17 62H19 27 421417 42H19 46H19 621H21 28 461421 4813 62H23 29 421421 42H23 48H25 621425 30 42125 42127 62127 62H29 31 421429 461427 481429 461430 621431 32 42131 461431 46H33 62433 33 42H33 42H35 461435 62K35 34 42H37 461437 621437 35 42H39 461439 46H41 62H39 62H41 36 42H41 42H143 46H43 46H45 62H43 37 42H45 46H47 62H45 38 42H47 46H40 46H42 46H44 46H46 62H44 62H46 38 62H47 39 42H40 42H42 4214 42H4 461H38 62H38 62H40 39 62H42 40 421436 42H38 461432 46H34 46H36 621436 I FILE:HOOP.XLW (STRESSEQ) 15-Mar-96 12:16 PM I
FM 6.6 Exhibit 7 page 5 of 23 Florida Power Corporation - Crystal River Unit No. 3 0OC ID:S-95-0082 Reactor Building Prestressing System ATTACHMENT C Hoop Tendons PAGE C5 Stress Sequence Sorted by Sequence Number Sequence Tendon Tendon Tendon Tendon Tendon Tendon Tendon No. No. No. No. No. NO. No. No.
41 421430 42H32 42H34 46H26 46K28 621H28 62H30 41 62H132 62H34 42 42H20 42H22 421424 42H26 42H28 461124 62H22 42 62H24 62H26 43 42H16 42H18 46H22 62H1 621120 44 42H110 42H12 42H14 46H18 461120 62H12 621114 44 62H16 45 421104 42H08 46H12 461114 461116 62104 62H06 45 621108 62H10 46 42HO2 46H06 46H08 46H810 621102 47 13H44 13H45 13H46 46H102 46H04 48 13H38 13H40 13H42 51 H44 51 H46 49 13H32 131H34 13H36 351H42 351H44 351146 51 H38 49 511H40 51 H42 50 351H40 511H32 511H34 51H.368 ,
51 13H24 131126 13H28 13H30 35H36 35H38 52 131H22 5111t28 51"130 53 13116 13H18 131120 5sH26 54 13H10 13H12 131114 35H30 35H32 35H34 55 13-102 131104 13H06 13108 351124 351H26 35H28 56 35H18 35H20 35H22 511H20 51122 51 H24 57 35H12 35H14 35H16 51H16 51118 58 35H06 35H08 35H10 51H110 51H12 511114 59 38H02 35H04 51H04 51H106 51108 60 13H15 421106 511H02 Note:
Data extracted from Reference 11 calculation information attached.
FILE:HOOP.XLW (STRESSEQ) 15-Mar-96 12:16 PM I
FM 6.6 Exhibit 7 page 6 of 23 Florida Power Corporation - Crystal River Unit No. 3 DOC ID: S-95-0082 Reactor Building Prestressing System ATTACHMENT C Hoop Tendons PAGE C6 Stress Sequence Sorted by Tendon Number Tendon . Sequence Tendon N. Sequence Tendon1 1.Sequence No. j No. No. No. No. j No.
1301 20 35H01 20 42H0i 21 13H02 55 35802 59 42H02 46 13H03 20 35H03 20 42H03> 22 13H04 55 35H04 59 42H04 45 13H05 19 35H05 19 42805 22 13H06 55 35H06 58 42H06 60 13H07 19 35H07 19 42H07 23 13H08 55 35-08 58 42H08 45 13H09 17 35H09 19 42809 24 13H10 54 35H10 58 42H10 44 13HI1 17 35H81 17 42H11 24 13H12 54 35H12 57 42H12 44 13H13 16 35H13 16 42H13 25 13H14 54 35H14 57 42H14 44 13H15 60 35H15 15 42H15 26 13H15 53 35H16 57 42H16 43 13H17 15 35H17 14 42H17 27 13H18 53 35H18 56 42H18 43 13H19 15 35H19 13 42H19 27 13H20 53 35820 56 42H20 42 13H21 13 35H21 13 42H21 29 13H22 52 35H22 56 42H22 42 13H23 12 35H23 12 42H23 29 13H24 51 35H24 55 42H24 42 13H25 11 35H25 11 42H25 30 13H26 51 35H26 55 42H26 42 13827 10 35H27 11 42H27 30 13H28 51 35H28 55 42H28 42 13829 9 35H29 11 42H29 31 13H30 51 35H30 54 42H30 41 13H31 9 35H31 9 42H31 32 13K32 49 35H32 54 42H32 41 13H33 8 35H33 9 42H33 33 13H34 49 35H34 54 42H34 41 13H35 7 35H35 8 42835 33 13H36 49 35H36 51 42H35 40 13H37 6 35H37 7 42H37 34 13H38 48 35H38 51 42H38 40 13H39 6 35H39 6 42H39 35 13H40 48 35H40 50 42H40 39 13H41 4 35H41 5 42H41 36 13H42 48 35H42 49 42H42 39 13H43 4 35H43 4 42H43 36 13H44 47 35H44 49 42H44 39 13H45 47 35H45 3 42H45 37 13H46 47 35H46 49 42H46 39 13847 2 35H47 3 42H47 38 FILE:HOOP.XLW (STRESSEQ) 15-Mar-96 12:16 PM
FM 6.6 Exhibit 7 page 7 of 23 Florida Power Corporation - Crystal River Unit No. 3 DOC ID:S-95-0082 Reactor Building Prestressing System ATTACHMENT C Hoop Tendons PAGE C7
.*trm-* *enmpng'e Sorted hi, Tendon Numbe~r Tendon endon Sequence Tendon Sequence No. No. No. No. NO. No.
46H01 21 51H401 20 62H01 21 46H02 47 51H02 60 62H02 46 46H03 21 511"03 1i9 62H03 22 46H04 47 511-104 59 62H04 45 46H05 22 51H-0 1 62H05 23 40H06 46 51HW08 59 621H06 45 46H07 23 51H07 18 62H07 23 46H108 46 511408 59 621"08 45 461"09 23 51H09 17 62H09 23 46H10 46 51H10 58 62H10 45 46H11 24 511H11 15 62H141 24 48H12 45 51H12 58 62H12 44 46H13 24 511H13 16 82H113 24 46H14 45 51H14 58 62H14 44 46H15 25 51H15 15 62H15 25 46H16 45 51H16 57 62H16 44 46H17 26 51117 14 62H17 25 48H18 44 51H18 57 62H18 43 46H19 27 51H119 14 62H19 26 461"20 44 51 H20 56 62H20 43 41-H21 28 511H21 13 621K21 27 48H22 43 511"22 56 62H22 42 46H23 28 51H123 13 621H23 28 481-24 42 511424 56 62H24 42 46H25 29 51M25 12 621425 29 46H26 41 511"128 53 62H26 42 46H27 31 51 H27 9 62H27 30 48H28 41 811"28 52 621H28 41 46H29 31 511H29 9 62H29 30 46H30 31 51H30 52 62H30 41 46H31 32 511431 8 62H31 31 46H32 40 51H32 50 621H32 41 461"33 32 511H33 8 62H33 32 461434 40 511H34 50 621434 41
,,46H35 33 511H35 7 62.H35 33 46H36 40 51 H38 50 621H36 40 461H37 34 51 H37 7 621H37 34 46H38 39 51 H38 49 621438 39 46H39 35 51H39 6 62H39 35 46H40 38 51H40 49 621H40 39 46H41 35 51H41 6 62H41 35 46H42 38 51H42 49 62H42 39 46H43 36 51H43 5 .62H43 36 46H44 38 51 H44 48 62H44 38 46H45 36 511H45 4 H2145 37 461-46 38 511H46 48 62H46 38 46H47 37 511H47 2 62H47 38 FILE: HOOP.XLW (STRESSEQ) 15-Mar-96 12:16 PM i
FM 6.6 Exhibit 7 page 8 of 23 Florida Power Corporation - Crystal River Unit No. 3 DOC lD.S-95-0062 Reactor Building Prestressing System ATTACHMENT C Vertical Tendons PAGE C8 Stress Sequence Sorted by Sequence Number Sequence Tendon Tendon Tendon Tendon Tendon Tendon Tendon NO.- No. NO. No. No. No. No. No.
1 12V13 23V01 45V11 56V01 2 12V19 23V05 45V17 56V05 3 12V21 23V09 56VO9 4 23V13 34V01 56V13 6iV1 5 23V17 34W65 56V21 61V09 6 23V21 61\V05 7 12V01 34V15 45V01 61V13 8 12V05 34V18 46V05 61V17 9 12V07 34V21 45V09 61V21 10 12V15 23V03 45V15 56V03 11 12V17 23V07 45V19 56V07 12 12V23 23V1 1 45V23 56'VI 1 13 23V15 34V03 56V15 61VW3 14 23V19 34V07 56VI9 61W7 15 56V23 61V11I 16 12V03 34V13 45V03 61V15 17 12WO9 34V19 45V08 81V19 18 34V23 4'V10 61V23 19 23\02 23V04 45V06 45V12 20 12V14 23V06 23V08 46W2 45V14 45V16 45V18 21 12V18 12V22 12V24 34\02 45V20 45V22 22 45V13 45V24 61\02 61V04 23 12V16 23V10 23V12 23V16 34V04 34V10 5bV22 23 56V24 24 23V14 23V18 23V20 23V22 23V23 23V24 56V14 24 56V16 56V18 56V20 25 12\A6 34V12 34V22 34V24 61\06 616 __.V__.
26 34V06 34V17 34V20 61VI0 61V12 61V14 61V16 26 61 Vi 81V22 61V24 27 12VO2 12V04 5602 5604 56V6 56VS 56V12 28 12VO6 12V10 12V11 12V12 34V14 34V16 56V10 29 56VI1 61V20 30 34\A)8 34V9 45V04 45\07 45V21 31 12V20 34V1 I Note:
Data extracted from Reference 11 calculation information attached.
FILE:VERT.XLW (STRESSEQ) 15-Mar-96 12-20 PM
FM 6.6 Exhibit 7 page 9 of 23 Florida Power Corporation - Crystal River Unit No. 3 DOC 1D0S-95-0082
/
Reactor Building Prestressing System ATTACHMENT C Vertical Tendons PAGE C9 Stress Sequence Sorted by Tendon Number "uence Te Sequence Tendon Sequence No. No. No. No. No. No.
12V01 7 34V01 4 56V01 1 12V02 27 34V02 21 56V02 27 12V03 16 34V03 13 56V03 10 12V04 27 34V04 23 56V04 27 12V05 8 34V05 5 56VO5 2 12V06 25 34V06 26 56V06 27 12V07 9 34V07 14 56V07 11 12V08 28 34V08 30 56M8 27 12VO9 17 34V09 30 5OV09 3 12V10 28 34V10 23 56V10 28 12V11 28 34V11 31 56Vil 12 12V12 28 34V12 25 56V12 27 12V13 1 34V13 16 56V13 4 12V14 20 34V14 28 56V14 24 12V15 10 34V15 7 56V15 13 12V16 23 34V16 28 56V16 24 12V17 I1 34V17 26 56V17 29 12V18 21 34V18 8 56V18 24 12V19 2 34V19 17 56V19 14 12V20 31 34V20 26 S6V20 24 12V21 3 34V21 9 56V21 5 12V22 21 34V22 25 5622 23 12V23 12 34V23 18 5BV23 is 12V24 21 34V24 25 5SV24 23 23\01 1 45\01 7 61VOl 4 23V02 19 45V2 20 61V'2 22 23Vo3 10 45M 18 61VO3 13 23V04 19 45V04 30 61V04 22 23V05 2 45V05 8 61V05 6 23VO6 20 45V06 19 81VO6 25 23V07 11 457 30 61V07 14 23V08 20 45\8 17 MoV0e 25 23V09 3 45V09 9 8iVO9 5 23V10 23 45V10 18 61V10 26 23V11 12 45V11 1 61V11 15 23V12 23 45V12 19 61V12 26 23V13 4 45V13 22 61V13 7 23V14 24 45V14 20 61V14 26 23V15 13 45V15 10 61VI5 16 23V16 23 45V16 20 61V16 26 23V17 5 45V17 2 61V17 8 23V18 24 45V18 20 61V18 26 23V19 14 45V19 11 61V19 17 23V20 24 45V20 21 61V20 29 23V21 6 45V21 30 61V21 9 23V22 24 45V22 21 61V22 26 RLE.VERT.XLW (STRESSEQ) 23V23 24 45V23 12 61V23 18 15-Mar-96 12,20 PM 23V24 24 45V24 22 61V24 26 i
CwwmIm S.95400 FM <r6 Exhr 4.ki 1. dc4 ge 10ý
!'A~ 7 IV = 3 a-cxa-
.r J
- . D33, .jQ.JlD 130 .1 7 D4.L4 D I/-,
0Z3)3.D 1/,3" 4. 3 / V-S 3)1*
._23/p'*
3 3 D Z.,1.1 7 -D1 0 -1./ .3 P-7. 0330 d2 a/. -(
1231D-/T D3(9)-O~//
.3 D*, = r "
3 p ;1 -, D1 9, 2-9, 3 -
D33. D- O t 3_. _D AL 3Dn_______ D. ; 3 no/ a __
-D-3-1 9 1) A03 vs-7. L.*a 7)",Ota.t DI",.,/
.__ /7
.*~~~~~~~~ _306*A_*/o/D3* 1`, 1
-
..... Z_.._23, 3o_6_.,_. 33j0 /3,0,"aLt*.- ._L _l,.D3
-L" -1__+4 o1*
a,,~.::DQA 3 O o_.
FM 6.6 Exhibit 7 C*a~9?-"23 Ae o
fa Afteikum C PWgeC13 TABLE 3-7 ACTUAL TENDON STRESSING LOG Date j)ThI1 [*Tendons 10-25-74 D331 10-30-74 D211 10-31-74 D130 11-4-74 0215 11-5-74 Dl128 11-7-74 D327, D219 11-8-74 D323, D123, D319 11-11-74 D223, DI15, D227, D315, Dl1, D311, D119 11-12-74 D231, D107, D235, D307, D239*
13-74 DI03*, D102 11-14-74 D207, D303, D135, D201*, D335 11-15-74 D139, D339* D341, D203, D141 11-18-74 D204, D338, D137*, D133, D210, 0333, D213 11-19-74 D329, D129, D125, D325, D217, D121 11-20-74 D221*, D225 D321 11-21-74 D117, D317, DI13, D313, D229, D109 11-22-74 D233, D309, D105 11-25-74 D238, D24i1 D305, D301 11-26-74 D302, D104, D101, D240, D236, D231 11-27-74 --1306, D310, D314, D106, D110, D114*
- nI2-2-74 -0118, D122, D318, D228, D322, D326 12-3-74 D224, D333, D216, D220, D132, D212, V126, D134 12-4-Y4 D138, D208, D334, D336, D337, D34C, D140, D205, D222, D226 12-5-74 D230, D332 D234, D328, D237, D136, D131, D!27, D209, D124, D120, D116 12-6-74 D206, D320, D324, D316, D312, D308, D304, D202, D214, D218 12-9-74 D112, D108. N2ol 12-10-74 D137 12-11-74 D114, b102 12-12-74 3-31-75 0339 4-2-75 e D241
- Denotes tendons which were detensioned and retensioned at a later date to satisfy Nonconformance Reports.
I;LI 1O*A i 4ff-24 Revised: 12-10-76
FM 6.6-Exhibit 7 . ;7 b Pape C12
/
10-9-74 23V14, 23V18, 23V20, 23V22, 23V23, 23V24, 56v14, 56V16, 56V18, 56V20 10-10-74 12V6, 34V12, 34V22, 34V24, 61V6, 61V8, 10-11-74 34V6, 34V17, 34V20, 61VIO, 61V12, 61V14, 61V16, 61V18, 61V22, 61V24 10-14-74 12V2, 12V4, 56V2, 56V4, 56V6, 56V8, 56V12 10-15-74 12V8, 12VIO, 12V11, 12VI2, 34V14, 34V16, 56V10 10-16-74 61V20 10-18-74 .56V17 10-31-74 45V4, 45V7 11-11-74 45V21 1-25-75 34V8, 34V9 1-27-75 34V11 1-28-75 12V20 1L41 TOTAL
- FM 6.6 Exhibit 7 CL? .614..
Pap C13 V.:t No. 2 12VIII , 3PV16. 12V161, 12V20, )2V? >2 24 ivi 16 6lv,1V~, v2., 61ivh 61V16, 6l~1vn 6).Vd'o, 61V22, 61V21 Liu2.drnr, t N'o. 3 56V2,' 56V4t. 56V6, 56V8, 56V10, 56v)?-, 56vils, 56V)6, 56v183, 56V20, 56V22, 56V12 1 1, 4~.5V2, 43VI4, '4ýV6, lI.5V8, 115v10,. 11t5V).2.
guadrnnt: ;o. h.
45v)4,* 45vi6, 1 s5vl8, 4J5V20, 115V22, 45V24, 34-V2, 34~V4, 3V2, 31f2~
CONTINGENCY PLAN Sequence 1 throu.h 181 If we are unable to complete the stressing -
(if a tendon 'in n .ivcn sequence', a tendon one or two spaces away v:i3I be stressed in its stead. ' This wi.l complete the sequence.
A tendon will be considered stressed when lift off is achieved within the specificd pressure limits.
If we are unab).e to place the minimumn It" shim, the stressing will be performed il accordance with the procedure no-ed on drawing PV-3Ij for all tendons in that cataCory B]. Dfome Tendons Each dome tendon shall be stressed from both ends simultaneously "usi.11g "t)o(2) sets of stresF-n.5i equi'rent. The teydons r,.ay be stro.,ssed nin-ly, in pairs of three at a ti;,e. The dome tend'n.:
sha)ll be stressed in the folloving t-equence from sequence N!o, 1 thr'ouL.-h Sequence No. 41. All the tendons in.one. sequence must be stressed before the next sequence is stressed. A tendon %%-ill be considered stressed when lift off is achieved within the specifled pressure limits.
Socue nre No.
1- D)211 1)331
- 2. D2 15 D327
- 3. DI123 D219 D323 It. L1344 0 15 D223 D)319 D227 D)311 D3).5
- 6. ))231 1)3] 1
- 7. D)235 D)301
- 8. D)107 D239' 1)303
- 9. D207 D)335
.r
FM 6.6 Exhibit 7 page 14 of 23Q"' 1.7d C) 10.
1).. ar 0 1 D339
!L-44)T: 0 3 3)341
.1 Cacuakaw"S.~-n~
Aaltcimm X
- 12. .Dae603P' 0 4 Z4g-319O3 v Page C14 c
- 13. ~7 D333
- 14. J)21.3 D329
- 15. D237 D325 3.6. D221- D32).
- 13. 1)2215 D) 3).7 306. .3.,.13O/, D229 D313 1.9. D233 D309
- 20. JI.4PA.3 Fr D305
- 21. .J.e~jp jo/ I D241 D301
- 22. D)24 0 D302
- 23. D236 )306
- 24. OO D3A ])232 ,,310 D
D5.
)114 D228 1) 4
- 26. D)118 D224 D310
- 27. D122 D220 D322
- 28. D126 D216 D326 29.. D130 D212 - D330
- 30. D134 D208 D334
- 31. AA*-7 D130 D204 D338
- 32. D140 D222 D340
- 33. D136 D226 D)336
- 34. 1)132 D2'30 D332
- 35. D128 D2311- D328
- 36. D124 D238 D324
- 37. D120 D202' D320
- 30. D116 D206 D)316
- 39. D1I12 D210 W)312
- 40. M.dOB D214 1)308
- 41. 11104 D218 D304 Continqcency Plan eqonc ".c
.lo. I tlrouc!h N*o. 21, If we are unable to complcte f;t1'm.;iZ9lg of ;A teoncon in a given ;equcjic-c, the clo,;c!t pra-ctical adjacent tendon, no moiec thian two tendons away, in thc:
m nmc s oe:ie s .ill bc strcsscd'in its; ,tcad (Iucnce. to complct c the .c-q t
.2 )roucj3 1q. 33.: If we are untmal, to comtplci the urc (niiwj of a ten.1on iJn a givcn sccjucncct, the cioa;cst rC ypractica]. tendon in tUic swi- scrixu will. be ircll:c~d iit:
st.ca;d Lo ccmipl tet the !:;cqucnce. In l.l.' ,mhea'1 tiio, Ohe xrmila-,il-i :i q ';t , c ; :; J ' ) iay 1)p 'c, ,.'cJ.d Up to t-w o ( 2 ) :;e :q en cL : j n a d VaU of th1e *i nc:.Ol11lj] c -l. y -C L
(. Ii. t;:;um
]iL n .
FM 6.6 Exhibit 7 C1IATI2' Cipage 15 of23
]~1~5ItGCaicudiasS-95-41M TVN1)0~ I~
Page CIS Cp--
Tntroctuct i on:
The intent of this chapter is to outline the proccclurc to be followed in !;Lrcssing the vertical, dome and hon ::ontal tcnclonr; . Time sequence in .,h~ch the inclividluil tendons are strescud is specified. Duo to t] 1 e nmwy cooIM.3'uction re)a t0ecd prol.Icn~ t1c Ow-trossing crcevs mny have to contend 'wi.h, a decgrce of flexibility iln proceecding w.,t.] the strces-insj of n particmuliir scqcuence is provided to minimizc dclays jin the Stressing operation.
6.2 Stresý;ncj Seqncncc:
A. Vertical Tendons The verical tendons shall be stressed from the top end only, usin9 four (4) set,.: of strcssi.ng equipment. The tendons will be Ltressc.
in the follo,;iny sequunce fxom Sequcnce No. I throurgh Scquence No.
- 18. Al). the tendons in one -;equence must be stresses bfore the nc>:t sequence is started to.be stressed. After 50% of the Vertica' tendons are strcssed, (following'sequence No. 18) the rewaining tendons in each quadrant may be Ftressed in a Fandoin sequenL;c (1 R1am working in each quadrant).
- .2V13' 6 Sequence No.
1/-
- 2. 23V5 12VIT/I 56V 5 45V17
- 3. 23V9 32V21v 56V9K 4-5V-2 I
- 4. 23V13 w 61V].-o At6.
- 5. S23V17-' 6 1V4?q 34V5
- 6. 23V21v' 34V9 12Vl1- 61v13 45VI1 34ViT'
- 7. 6 IV 173
- 8. 12VS - 6 1v i17 4 5V 5'. 34V171
- 9. 12Vk 7 61V21- 4 5V 9, 34V21-
- 10. 2 3V 3 ' 12V15' S6V 3wa 45V1.5
- 1. 2 3V 7 ~ 12V 1-S17 5CiV 7L. ,15V) 9-
- 32. 2 3VI1 V 1 2V 23. SiV 11. 45V23"
- 13. 2 3V 15 6)V3- 56V) S~- 34V3-"
- 34. GIV7 , !;CAr19. 34V 7 QBV19- -
315. 56V 23-16.. 12V3- 61V-5 - 4 5V 3, 34v),5 ,:;
l.I .23V2-, 23V4, 23V6, 23\'fl, 2_3V)(1, 23V12, 23VI.1, 2-`Vi..6 23\']I 23\120, :v:.,
3V 2, v~ 2v-1, ).,!v(" 1-2vi, 12V )2v) 0, )\
-- /
, 'I
N 0.0 r*4,4 1444CakcginUm ,P.ag 06. ge 165ot 6
, -S-954)
Af .xnib,,, .* _
/ 7.B v. vt.4-,/
.. * .-,5-V ,, . ,.- 9 .
V 14 L- f 4 5- V16 44' o 4 V ,I cL *L ,
S40-3 4 ; ' ,,
-4A-I.I g.v ,. __ /;__ _ 34_
__ __ __ ,
7:,--
- ~ _________A
...... i v;.o *q y - !k5.-h--,,,/;__
. .. _-_.
_- . . .
_.. .. . . .. .. . . . . . .
..
__
AOeu,OR .,
Z t_
- __q/_
.. . . .. _ _. . . .. .. . . . _. _ . . . .. ...
.. *0,-_
- ___* ! , -Z' Jt oP _ _
._4J
__ ___ U7~f44Cd~I~~
I
FM 6.6 Exhibit 7 pagea6?ds-oo, Aftedow c Page C17 ACTUAL TENDON STRESSING LOG Vertical Tendons Date 8-30-74 56V1 9-3-74 12V13, 23VI 9-4-74 23V5, 45VIl 9-9-74 12V19, 56V5 9-10-74 12V21, 23V9, 45V17, 56V9 9-11-74 23V13, 34VI, 56V13, 61VI 9-12-74 23V17, 23V21, 34V5, 56V21, 9-13-74 12VI, 45VI, 61V5, 61V13 9-16-74 12V5, 45V5, 61V17 1.
9-18-74 34V15, 34V18 9-19-74 12V7, 12V15, 12V17, 23V3, 23V7, 34V21 5 45V9, 45V15, 45V19, 56V3, 61V21 9-20-74 12V23, 23VII, 34V3, 45V23, 56V7, 56V11, 56V15, 61V3 9-23-74 23V15, 23V19, 34V7, 56V19, 6 1V7 9-25-74 56V23, 61Vll 9-27-74 12V3 9-30-74 45V3, 61V15 10-1-74 12V9, 34V13, 34V19, 34V23, 45V8, 45VI0, 61V19, 61V23 10-2-74 23V2, 23V4, 45V6, 45V12 10-3-74 12V14, 23V6, 23V8, 45V2, 4* 5V14, 45V16, 45V18 10-4-74 45V20, 45V22 10-7-74 12V18, 12V22, 12V24, 34V2, 45V13, 45V24, 61V2, 61V4
(
10-8-74 12V16, 23VI0, 23V12, 23V16 34V10, 56V22, 56V24, 34V4
FM 6.6 Exhibit 7 Page Cie m.2oo Tendons Date 1-23-74 I 51H5 12-26-74 13H47, 51H47 3;
12-27-74 .34'H45, 351147 12-31-74 13H41, 13H43, 35H43, 51H45 S.
1-2-75 35H441, 51H43 4
1-3-75 13H37, 13H39, 35H39, 511139, 51H41 1-6-75 7 13H35, 35H37, 51H35, 51H37 1-7-75 13H33, 35H35, 51H31, 51H33 1-8-75 13H29, 13H31, 35H31, 35H33, 511127, 511129 1-9-75 /0 13H27 1-10-75 !1 13H25, 35H25, 35H27, 35H29 1-14-75 13H23, 35H23, 51H25
/3 13 1-15-75 V1-2121, 51H21, 51H23, 35H212 35H 19 1-16-75 35H17, 51117, 51H19 1-17-75 /4. 13H117, 13H19, 351H15, 51H15 1-20-75 13H13, 351113, 51H1, 51H13 1-21-75 /7 13H9, 13HI1, 35H11, 51H9 1-22-75 It. 51117 1-23-75 /9 13H5, 13H7, 35H5, 35H7, 351 1-24-75 13H1, 13H3, 35H3, 35M1, 511 1-29-75 42HI, r2115, 4 6113, 62H1 42H3, 42H5 , 46H5, 62H3 1-30-75 f ..#
FM 6.6 Exhibit 7 C* eS'2ef 23',
- 9 L, Pate C19 1-31-75 - 42H7, 46H7, 46H9, 62H5, 62H7, 62H9 2-3-75 42H9, 421I11, 461111, 46H13, 62HII, 62H13 2-4-75 42H13, 46H15, 621115, 621117 2-5-75 t-4 42H15, 46H17, 62H19 2-6-7-5 2-1 42H17, 42H19, 46H19, 62H2!
2-7-75 46H21, 46H23, 62H23 2-10-75 42H21, 42H23, 46H25, 62H25 2-11-75 30 42H25, 421127, 62H27, 62H29.
2-12-75 31 42H29, 46H27, 46H29, 46H30, 62H31 2-13-75 3 - 42H31, 46H31, 46H33, 62H33 2-14-75, 3 42H33, 42H35, 46H35, 62H35 2-17-75 .4 42H37, 46H37, 62H37 -
2-18-75 !,5 42H39, 46H39, 46041,( 64H41 2-19-75 3 42H41, 42H43, 46H43, 46H45, 62H43 2-20-75 37 42H45, 46H47, 62H45 2-25-75 3 42H47, 46H40, 46H42, 46H44, 46H46, 62H46, 62H47, 62H44 2-26-75 3f 42H40. 42H42, 42H44, 42H46, 46H38, 62H38, 621140, 62H42 2-27-75 40 42H36, 42H38, 46H32, 46H34, 46H36, 62H36 2-28-75 4-( 42H30, 42H32, 421134, 46H26, 46H28, 62H28, 63H30, 62H32, 62H34 3-3-75 +-. 42H20, 42H22, 42H24, 42H26, 42H28, 46H24, 62H22, 62H24, 62H26 3-4-75 43 42H16, 42H18, 46H22, 62H18, 62H20 3-5-75 44- 42HI0, 42H12, 42H14, 46H18, 46H20, 62H12, 62H14, 62H16 3-6-75 4-.," 42H4, 42H8, 46H12, 46H14, 461116, 62H4, 62H6, 62H8, 62H10, 3-7-75 4.4 42H2, 46H6, 46H8, 46H10, 62H2 3-10-75 #7 13H44, 13H45, 13H46, 46H2, 46H4 3-11-75 13H38, 13H40, 13H42, 51H44, 51146
FM 6.6 Exhibit 7 Page C20 3-12-75 4-? 13H32, 13H34, 131136, 35H42, 35H44, 35H46, 51H38, 51H40, 51H42 3-13-75 351140, 511H32, 51H34, 511H36 3-17-75 '5,1 13H24, 13H26, 13H28, 13H130, 35H36, 35H38 3-18-75 13H22, 51H28, 51H30 3-19-75 S3 13H16, 13H18, 13H20, 51H26 3-20-75 5-4. 13H10, 131112, 13H14, 35H30, 35H32, 35H34 3-21-75 13H2, 13H4, 13H6, 13H8, 35H24, 35H26, 35H28 5.';
3-24-75 35H18, 35H20, 35H22, 51H20, 51H22, 51H124 3-25-75 S'7 35H12, 35H14, 351116, 51H16, 51H18 3-26-75 ,.."V* 35H6, 35H8, 351110, 51H10, 51H12, 51H14 3-27-75 ,,5- 35H2, 35H4, 51H4, 51H6, 51-18 3-28-75 5 lH2 go 3-31-75 42116 C. 11-20-75) 131115
FM 6.6 Exhibit 7
---e,,j@ ft 23 '
Past C'21
,mqe0nceirc 1!p. 32 throupkb 7o . 41: If N.1e cC uzaiblc to coplfete t'c .ntrc:,3i.n. of a ten*don in a given bc'quencc , the clo!cn-it practical tendon in the same ucrics wi],] bu strcý;ed in it:
utead to com*p3.cte thius scquence. In the meantime, streS-Aing may procccd up to four (4) sciqueneccs in advance of thU incompletLc.y t tendon.
C. ]lorizonta). Tcmdonn Each horizontal tendon shall be strcesscd from both ends si-mul.taneously using two (2) sets of strcssinjg equipment.
Ti 0 horizontal tendon shall be stro-sed in the follrwing sequencc from sequence no. I through scquence no. 48.
All the tendons in one sequence must be stressed before th next sequence is stressed. After 50;. of the horizontal tendons are stressed (following sequence no. 48) the rc'maj ing tendolis in -each buttress %.,illbe stressed in the buttl sequcnce shovni. A tendon will be con.;idcrcd stressed '*:hc; lift off is achieved ,ithin the specified j.re;-.:-*ure limits Odd 1%umbered Buttresses
, "Sequence "N~o. I. -131147 351147 511147
- 2. 13)145 351145 511145
- 3. 13114 3 351143 5.-11,13
- 4. 13H41 3511-1I 511141
- 7. 131139 351139 511139 1.
131137 351137 51M137 13i135 351135 511135 7.
- 28. 131133 351133 511133
- 9. 131131 351131 511131
- 10. 131129 351129 511129
- 11. 131127 351127 511127
- 12. 131125 351125 511125
- 13. 131123 351123 53.11123
- 14. 131121 35112]. -511121.
3.5. 13113.9 35110.9 5111)9
- 21. 131117 1 Sill 7 511117
- 17. ".' 13M.37 1311)5 351197 5111.5
- 35113.5 3.311.3 51113
- 19. 13113.i 3511)7 35119. 5111))
- .% 20.
fm < 21.
351H5 53113
('
22.
35115 51115
- 23. 5)113 35113
- 24. 1.3111 51111 Mlove .to even nwi .¢(:,t- ,'- ;1(1 :.~Lrc~;:; JOLUCJ up.
FM 6.6 Exhibit 7
$u.2',_'n cr- T,*n, Agenset C2 _
- 25. 24111 4 c)11] 62)11 Page C*22 45})3 52113
- 20. 24113 46115
- 27. 24115 62115 24117 46117 6 2117
- 20. 4G119
- 29. 24119 461111 62119
- 30. 24111] 621111 3). 241113 4.6]113 G21113 32, 241115 461I5 621115
- 33. 261137 451117 621117
- 34. 241139 4G1119 621119
- 35. 241121 461-21 621121
- 36. 24H23 461123 621123
- 37. 241125 461125 621125
- 36. 241127 461127 621127
- 39. 241129 621129 461131 621131 40, 241131
- 41. 241133 451133 621133
- 42. 241135 4,Gi 35 621135
- 43. 241137 .46113"7 621137
- 44. 241139 4 GH 39 521139
- 45. 241141 461141 S21141
- 46. 241143 451143 621143 46114 5--.-. 621145-G B.
E 241147 461147 "621147 Buttrens 24 Sc-'cucncct 2411-16, 241144, 241142, 241140, 24H38, 241136, 24113,!, 2i1.132, 241'30, 241120, 241126, 241121, 2..1, 2,21 241136, 241114, 241112, 24110, 241.18, 24115, 24114, 24112 Miuttrcr, 46 Sc.cuecn(:: .f4 Gl4G6, 461144, 461-1412, 4611,10, 46T]'36, 461136, 1 4,1132, '61130, 46112C, 461126, 461124, 461122, 4'61120, 461118, 453115, 4GI111,, 461112, 46HI0, 4U61318, 4GH1G, 4614',, 4.GM12
]lhiros' 62 Scricncer: 621146, 621144, 62114-2, 621140, 621138, 621136,
('?1124, 621132, 6:<1130, G2H3-, 621;26, 6 }.24, 621122, 621120, 621113, C2}IfG, 62111,1, G2]112, 521110, G2I!, G21iG, G211-1, 62112 MAl)"Ir . 1.Il3 . , . 13112, 13114, 13H1, 13118, 331110, 131112, 131114, 131134, 33113G, 131130, 131122. 1'!124, 13i125, 13 (., 131130, 131132, 131110, 131142, 331144, 131,1I6 35112, 35114, 351l6, 35118, 351130, 351172, 31;,1114, it, 3511)5, 353110, 351120, 351122, 35H!24, 351126, 3!,112t, 351130, 351132, 34!13'1, 353136, 351338, 351140, 3',142, 351;48-, 3511-16 i
Is
FM 6.6 Exhibit 7 pq 3 /3 2fIh S-9*J.46ej AlhmmC=uuialm Page C23
',flI]h, 531l.It;, 51lt.o, 5] 22, 5)t2k, 51:3116, 5M.121, 511130, 511132, 51t~l, 511136, 5111311, 51]wi , ý1,1142, 51}5144, 51 Ili 6.
CONrT114GENCY MLAN Sprnincc No. 1 throuri i11g. 11, EXcept for sequence lio. I and r'o 25, tewidonrs way bc L-tre;,-ed sin-ly, in pairs or three at a time.
Oin sCoquonce N'o. 1 and rNo. 25, all threc tendon,
- hall be stressed mult.ai-jeou*y. IF wie are unable to complete the stress;inig of a tendon or tendons in a given sequence, vie will procced to the next rcquenec and octrktivue to stress the tendons in that sequence .;here practical. This s 3).imited to one (1) sequence beyond the ufl-stressed tendon or tendons.
)':,'H ,:wi..ence 1 1"!o. 4-. Tendons may be strcssed sinl.]y, in pairs or Ui,'ce a. a time. 'If -.,ce arc, unable to complete the strcssin- of any tendons; in a buttress sequence v.e will proceed to stress the rcmaining tendons 3n that buttress, limited to tvelve (12) teudons beyond the unstressed tendon.
FM 6.6 Exhibit 8 page 1 of 2 w25T11 YEAR SURVEILLANCE OF THE POST-TENSIONING SYSTEM ATForida APoress E Power ompr CRYSTAL RIVER NUCLEAR PLANT UNIT 3 AProgress Energy Company IV. HYDRAULIC JACK CALIBRATIONS Precision Surveillance has developed a program for calibrating hydraulic jacks utilizing regression analysis (PSC Procedure QA 12.8.G-WV). This is a process where a straight line is mathematically best fitted to a set of data points (in this case, force verses gauge pressure). This results in calculating ram area (slope) and constant (y-intercept) for each jack calibration. Completed calibrations for all of the hydraulic jacks used are contained in Appendix C and are summarized in Table VII.
A before and after comparison of the stressing jacks' ram areas revealed that none of the jacks' calibrations varied by more than 0.62% indicating that they were in a properly calibrated status.
Note that the force exerted by a jack can be calculated as follows:
Force = Area x Pressure + Constant (F) (in2 ) (KSI) (K) 25
page 2 of 2 FM 6.6 Exhibit 8 c , C C 25TH YEAR SURVEILLANCE OF THE PoSr-TENIONISSYSTEM AT THE CRYSTAL RIVER NUCLEAR PLANT FloridaEnergyPower Company UNIT 3 AProgress TABLE VII: HYDRAULIC JACK CALIBRATIONS JACK BEFORE SURVEILLANCE FORCE AFTER SURVEILLANCE FORCE MAX VARI ID DATE AREA CONSTANT (Fi) DATE AREA CONSTANT (F0) PRESSURE %
(in') (kips) I I (in 2) (kips) 8752 4/6/01 331.036 -11.329 1,809,369 1/9/02 331.018 -12.836 1,807,763 5500 0.09 I'.J 8783 8/1/01 333.733 -9.037 1,893,241.1 1/9/02 335.843 -9.335 1,904,970.1 5700 0.62 8833 8/1/01 334.599 -3.885 1,903,329.3 1/8/02 332.645 -4.175 1,891,901.5 5700 0.60 7711 1/9/02 1.654 0.104 14163 1/17/12 1.642 0.158 14115 8500 0.34 RAM 7711 USED FOR WIRE TESTING
"0O CRYST,',L PRIVER W:;! I NO. 3 page 1 of 13 REACTOR BUILI)!N::, P[I'.* F.*:zSSICG SYSTEM TE:;7O:. i" ,. _ _ _ __"
I-
- ,IDZ:JIFICATION ... 3. Z 0 CUT LENGTH /J'
- SHOP WASHER ID: PC / .- I CR 5-87 FIELD WA5-IER ID: PC /7.0 CR t,91
- 1. GAI/Q. vendor inspecticn cover letter nurzber-FC
- _____"__DATE Z S/ 7Y
- 2. Date tendon received cn'-fzite /Z-7Y RMR Number 376097-7
- 3. Date installed in conduit 7 ?
- Installation sNC's Wires removed 0 Wires replaced 0 Total Ineffective wires 0
- 4. Date buttenheaded 7-3 -7 Y/ Buttonheading NCR's Bad wires 0 Accept. Reheads Total Ineffective'wires
- 5. Date stressed ' Stressing S-8 NCR's Date restressed Restressing NCR's SHOP E;D FIELD E.'ID TOTAL Elongation (1500 psi to 80'. ult.)-Pred./Act. 12 5 8 /y S ,Y4 / /Z4/J?
.. .ft-Off Pressure - Predicted/Actual O 4 -I/7O N/A Shim Thickness/80% Ultimate Pressure /7/ 10 ,f / N/A Unseated/Broken Wires Total effective wires after stressing /c3
- 6. Date Bulk-filled /30 - Bulk-Filling NCR's Time since installationa/tr#'l/+Y Inlet Pressure /Y S Outlet Temp./30 Date end caps refilled: Shop Field
- 7. Data compiled by XQ Organization Pate f
- 8. Additional Coznents:
907 716
FM 6.6 Exhibit 9 SR X '03F L/ /
I '(r 54AI E4 _rLW VC Florida CRYSTAL RIVER UNIT NO. 3 Power REACTOR BUILDING PRESTRESSING SYSTEM TENDON HISTORY TENDON IDENTIFICATION NUMBER 12 V 2IZ CUT LENGTH SHOP WASHER ID: PC CR FIELD WASHER ID: PC CR
- 2. Date tendon received on-site RIR Number
- 3. 'Date installed in conduit Installation NCR's Wires removed Wires replaced Total Ineffective tires
- 4. Date buttonheaded Buttonheading NCR's Bad wires Accept. Reheads Total Ineffective wiz ,es
- 5. Date stressed Stressing NCR's Date restressed Restressing NCR's SHOP END FIELD END TOTAL Elongation (1500 psi to 80% ult.)-Pred./Act. / / /
Lift-Off PresI - Predict, 7 - N/A Shim Thickness/80% Ultimate Pressure(l) /5"L . _/ - N/A Unseated/Broken Wires ( (CSA4*D 11B(P*'Total effective wires after stressing' 7 '
- 6. Date Bulk-filled 2_/-K Bulk-Filling NCR's ____
Time since installation Inlet Pressure Outlet Temp.
Date end caps refilled: Shop 2I-7t Field A.
- 7. Data compiled by j *Zi .. . Organization FPc Date S`5--76
- 8. Additional Comments: ),J5P,6CfF8 Fi2S S ijV.er c*
tjjj (/-2/2-77)
- 1) LoID--M,-PST FC
- AATf cote%.k RKA L-JE cjjKw6
,m-ýV (L*3 o. o v Ar"F i 972 71j6 4)-~'*rJ -ees 5AA (9"") f1b SkMIltfi 159
~~ 55 r-r--FF ~CKCEDv 69 TEcIM 3E(. UtfCA2 Lnrirr 47ZI K) Ax-ACEWTr 7TLJDC Lrr-r-OFF TAW907 716
FM 6.6 Exhibit 9 Sft@&e 3&V OF ýy Florida CRYSTAL RIVER UNIT NO. 3 '
IS7-sw rve ; / 4", Ce Power COAPORA? 1O0I REACTOR BUILDING PRESTRESSING SYSTEM TENDON HISTORY TENDON IDENTIFICATION NUMBER /2 V 21o) CUT LENGTH SHOP WASHER ID: PC CR FIELD WASHER ID: PC CR
- 1. GAI/QA vendor inspection cover letter number-FPC D_LTE D
- 2. Date tendon received on-site RNR Number
- 3. Date installed in conduit Installation NCR's Wires removed Wires replaced Total Ineffective iires
- 4. Date buttonheaded Buttonheading NCR's Bad wires Accept. Reheads Total Ineffective wires
/
- 5. Date stressed Stressing NCR's Date restressed Restressing NCR's SHOP END FIELD END TOTAL Elongation (1500 psi to 80% ult.)-Pred./Act.
/ .... / ___N/A Lift-Off Pressure - Predicted/Actual Shim Thickness/80% Ultimate Pressure I . / _N/A Unseated/Broken Wires Total ef 'fective wires after stressing /6
Date end caps refilled: Shop Field
- 7. Data compiled by * ;.y: */0 Organization FPz --
Date ?
- 8. Additional Comments: 06biýt 0) CkeLcWe b,-ci4%1 Ap,, wa+/-s aze.AL/z~e 907 716
M6.6 Exh ibit 9 t:ýc:en, ? "-A Co .. T.. P I-:s: $ U s. :E,
- 0. '- AEDN H:STO?
I," . - -
S1O ? .-.- R ID: PC CR FIELD WS-R ID: ?C CR
- 1. GAI/QA vendor inspection crver letter _ D, AT L._ber-FC
- 2. Date tendon received on-site ?,HR N-ber
- 3. Date installed in conduit Installation NCR's Wires removed Wires replaced Total Ineffective w-ires
- 4. Date buttonheaded Buttonheading NCR's Bad wires Accept. Re-heads To-tal TIeffective wires
SHOP END FIELD END TOTIAL Elongation (1500 psi to 80% ult.)-Pred./Act. KA'I _ Al___- ____/_
- Lift-Off zt.'*. .-. /7440**r/
7A NA Shim Thickness/99; =lt--z ?--*.-. 1_ _"/ ._ _ _. .. A -I Unseated/Broken.Wires _ _ _ Total effective wires after stress-.ng 6.- Date Bul~k-filled " /98 Bulk-FiLllinz NCR's_______________
Time since installation ' Inlet ?ressure - Outlet Temp.
Date end c'aDs refilled: Shop q / YZ Field ____Y_/99/_ _
- 7. Data conpiled by:- Organization S-Date .j-zz //*a
- 8. Additicrnal Cc-ants: L OFr o' 'LY_ 61-r 7-ý LJý- t ýýC OArie 0or- L IF--r /A c.r-c, ra r ._ _ _ _ _ _ _ _ _ _ _ _ _
L r o r- r it -- -y , '
M6.6 Exhibit 9
- ~. pgeýý of 13.
Fol-da ~., Is - - I'2P
",'7:; 1 - ,- **
~ PowEr RLACTOR BUIL:7 O. . SYSTLEM 7E'., 7 S- TV
-1 NDON~ I D'ENT 1 1CAT !C!, XNU ýS ZR 12 VZo a:,T LEN' SHO? W',.AS-"R ID: PC CR 777IEL)D WASER ID: PC CR.
- 1. GAI/QA vendor inspection cover letter n--er--PC _ DATZ
- 2. Date tendon received on-site __ .YR N~ber
- 3. Date installed in conduit Installation NCR's Wires renoved Wires replaced Total Ineffective
- 4. Date buttonheaded Buttonheading NCR's Bad wires Accept. Re-heads TotalIneffective wi r es 5.a. Date stressed Stressing NCMM's Date restressed Restressina NCR's TOP .-
SHOP KEND FIELD :ND TOTAL A1 Elongation (1500 psi to 80% ult.)-Pred./Act.
"'I"/ ' /A F cf Lec-x.ovor GE -_
J 'b- Lift-Off *r P/ i,'/_tzl (iQIP-S) /
Shim ThPic.ness/ ,, Ult-s. . __.___ _/_ N/A Unseated/Broken Wires Total effective vires after stressing 6.: Date Bulk-filled - Bulk-Filling NCR's Time since Installation NIA i ?ress-ure
-let Outlet Temp.
Date end caps refilled: Shop Field
- 7. Data compiled by Organization Date
- 8. Addiricnal Co--ents: .TE .
- o. -o r0 L*_EO a - A7 ILAO KIjP.5 PIC-/a Al0. ?-337L.
On m
M 5:
(0 CRYSTAL RIVER UNIT NO. 3 REACTOR BUILDING PRESTRESSING SYSTEM TENDON SURVEILLANCE RECORD TENDON NO. 12V20 LIFT OFF CONDITION RETENSIONING Inspection Avg. Shim Elong- Total Avg. Shim Elong- Total Reactor Bldg.
Period and Force Force Thickness ation Effective Force Force Thickness ation Effective Temperature OF
- n. Com~ent.
1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 Original T 1598 15" I2Jj/8" N/A N/A N/A Stressing 1/28/75 B N/A N/A 4" N/A 163 N/A NIA N/A N/A NIA N/A N/A Is t 121t T 1785 15" NIAK 1785 15"1, A 1. l lft-off high -
adjaceint tendons tested B NIA ALL 4" HLA_
Ifil- VA' HIA_ 4" IA- i16_ U1 1m_* 2. Hairline cracking at Bott. Anchorage 2_nd T 1740 15" N/A 1740 15._ NJA 1. Lift-off only 4/11/80 B N/A~ N/A N/A11K 216 N A NIA. 4"L VAL& 1UL 71* 76
'*
0) 0
FM.
CRYSage Vo7 REACTOR BUI LI)!:i Prj.. I 3
ESSI.G SYSTEM page 77 of 13
- °'~" *" T~;*'I: -;,
- , IDE:NTIFICATIO:N :CUME. 4'f 3 CT LENGTH /F? - /
ShjOP W,,.'SR ID: PC /2/ CR 7 7 (, FIELD WAE.-*iR ID: PC / i- C) CR 2 Z/
- 1. CAI/QA vendor inspecticn cover letter n:-uber-FFC I r*. qc/0 DATE ____/7_
- 2. Date tcndorn receivc,, on-site - // 7'?/ RMR Number 36F1/
- 3. Date installed in conduit 7 "Z3- 7A Installation NCR's Wires removed _ _ Wires replaced _ Total Ineffective wires 0
- 4. Date buttcnheaded I-Z/- )9 Buttonheading NCR's Bad wires _ Accept. Reheads 0 Total Ineffective'wires 0
- 5. Date stressed 9 Stressi re ng ,CR's Date restressed Restressing NCR's SHIOP EN;D FIELD E'ID TOTAL Elongation (1500 psi to 807; ult. )-Pred. /Act. 1Z AY/ 121- I/ZAI /Z 1.
- ft-Off Pressure - Predicted/Actual 0 / 110 / N/A 77 7 1/AI" / N/A Shim Thickness/80% Ultiznate Pressure Unseated/Broken W.ires __ Total effective wires after stressing /'63
- 6. Date Bulk-filled II 7 Bulk-Filling iNCR's 16P7 Time since installation Y , Inlet Pressure /&O. Outlet Temp. /23 Date end caps refilled: Shop Field
- 7. Data compiled by Zi. , <- Organization >c5"--.-.
Pate _ __/77
- 8. Additional Co-ments:
(
C 7 71A Q.)
FM 6.6 Exhibit 9
/Ir . Vr--Ir C_
_* Florida CRYSTAL RIVER UNIT NO. 3 Power REACTOR BUILDING PRESTRESSING SYSTEM TENDON HISTORY TENDON IDENTIFICATION NUMB~ER $Ks V 3 CUT LENGTH____
SHOP WASHER ID: PC CR FIELD WASHER ID: PC CR
- 1. GAI/QA vendor inspection cover letter number-FPC I ATE D.
- 2. Date tendon received on-site RMR Number
- 3. Date installed in conduit Installation NCRs Wires removed Wires replaced _ Total Ineffective wires
'4. Date buttonheaded Buttonheading NCR's Bad wires Accept. Reheads Total Ineffective wi res
- 5. Date stressed Stressing NCR's Date restressed Restressing NCR's SHOP END FIELD END TOTAL Elongation (1500 psi to 80% ult.)-Pred./Act. / ! /
Lif t-Of f Press LO"z-4Csr .r.e d*rt.
FZOrf - Predicted /Actual ILW)~______N/A" Shim Thickness/80% Ultimate Pressure / ., _ N/A 14-tOV/Unseated/Broken Wires (.J M) Total effective wires after stressing 112-
- 6. Date Bulk-filled I-/-78 Bulk-Filling NCR's Time since installation Inlet Pressure Outlet Temp.
Date end caps refilled: Shop Field A-A.
AFP(.
- 7. Data compiled by Organization Date _____ _____ ____
- 8. Additional Comments: 1.tJS(IED r2LS7 S LJ ?vmAJC6 (/2- ?
i) w~t? FIFO) 0--T ON) STflLSStrAJ( &VALSHEt&L 4 fi 57n#I. COOO CAT. /
&"tQg HA12C,ec-gbSVW~ CA7T. */. o2~ es o1~Ed~ 3A'IE5 ~WiC
- 2) /1mlZL1~t cjptcxcDr/6 (1,C55 TfliW O.0ooj A &flv-^y 4,1'6'e~htRA& r?~
- 3) LOCC- OFF VWC16(O4M.C A Pro 907 716
-n 03 m
x CRYSTAL RIVER UNIT NO. 3 REACTOR BUILDING PRESTRESSING SYSTEM TENDON SURVEILLANCE RECORD TENDON NO. 45V3 LIFT OFF CONDITION RETENSIONING Inspection Avg. Shim Elong- Total Avg. Shim Elong- Total Reactor Bldg.
Period and Force Force Thickness ation Effective Force Force Thickness ation Effective Temperature OF Date Location (kips) (kips) (in) (in) Wires (kips) (kips) (in) (in) Wires Int. Ext. Comments 1 2 3 4 5 6 7 8 9 10 I1 12 13 14 IS Original T J9 jL j4' N/A N/A N/A Stressing 9/30/74 B N/A N/A 4" N/A 163 N/A N/A N/A N/A N/A N/A N/A 1st 1 T 1678 14" N/A 1678 14" N/A 1. Hairline crackling at but t om ancl'horrage B N/A N/A 4" N/A 163 N/A N/A 4" N/A 162 103 63 2. One wire removed CD (D
0 CA)
OfI. *
- ",4""" FM Et i.9 CRYST", PIVER t" 'T tNO. 3 page 10of 13 REACTOR E P7"LDL'G Pf, YSS1NG S'YS':EM 1 1_.JF-ICAT ION ;:'-ZL R 5a , / CUT LE-"GTH /8 -
SHOP WX;,37-.?. iD: PC /2- / CR FELD WASHER ID: PC FI'/ /Z 0 CR /73-I. GAI/Q.',.r.J:r insp c-tion c,,'r lettcr nu-ber-FPC ; /00S,0 DATE 3/,P/7y
- 2. Date t'.P- receiv'iJ cz-si:e 2- Z0O PP*R Num.ber J7 Z 5- 7
- 3. Date installed in conduit 7'/ I-/7-Installation NCR's Wires rcmoved _ Wires replaced _ Total Ineffective wires O
- 4. Date b.ttcnhead2d 7- Buttonheadin; NCR's Bad wircs _ Accept. rc':2ads Total !ne: fective wires
- 5. Date stressed k 30 -F 7 tressing ,'_CP,_s Date reszressed Restressing NCR's SHOP ElD FIELD END TOTAL
~Elongatticn (13030 psi to SC" ult.)-?rej./Act. 2;/8 -//2' // I NA /A8 it-Off Pressure - rredicted/Aztual 6800 /1?_*To'_ N/A Shim Thic:-ncss/80% Ultinate Pressure /A /7770 9y / N/A Unseated/Broken Wires 0 Total effective wires after stressing /3
- 6. Date Bulk-filled I. - Bulk-Filling NCR's Time since installation 9 'n"nJ Inlet Pressure //t / Outlet Temp. /_____
Date end caps refilled: Shop Field
.7. Data corpiled by -e e/,-/ Organization 4-i'i,,
Date ___'__7__
- 8. Additional Co*-nents:
907 716
FM 6.6 Exhibit 9 SM u'71 Af*d(
FPJEri, .J CRYSTAL RIVER UNIT NO. 3 PoweraAT,0tTENDON C0Apo REACTOR BUILDING PRESTRESSING SYSTEM HISTORY TENDON IDENTIFICATION NUMBER S6 V / OT LENGTH SHOP WASHER ID: PC CR FIELD WASHER ID: PC CR
- 1. GAI/QA vendor inspection cover letter number-FPC _ DA ATE
- 2. Date tendon received on-site RMR Number
- 3. Date installed in conduit Installation NCR's Wires removed Wires replaced Total Ineffective wires
-4. Date buttonheaded Buttonheading NCR's Bad wires Accept. Reheads Total Ineffective wilres
- 5. Date stressed Stressing NCR's Date restressed Restressing NCR's SHOP END FIELD END TOTAL Elongation (1500 psi to 80% ult.)-Pred./Act. / I /
Lift-Off P......6 - Predicted/Actual 41,i//6S - N/A L-C-b~f- FOAfL eGfQLZA Shim Thickness/80% Ultimate Pressure N/A Unseated/Broken Wires U*" iOarf'otal effective wires after stressing
- 6. Date Bulk-filled / 7~8Bulk-Filling NCR's________________
Time since installation Inlet Pressure Outlet Temp.
Date end caps refilled: Shop ____ ___ Field /141
- 7. Data compiled by 7- -Organization FP 70 Date ____________
- 8. Additional Comm~ents: 5Th't9T()r 22LyS jwc (12--7-77 J)J D tz PIiLo i2-usr &NW 512F55D&J U~iey poiJ,9e z)Q'ba-opr- r-oac Oos-s-r)
- 3) tf~l i.,w4 CA4JKV 4 ~ (tSS TYAA m & D'z ") AT B0VPZ>1 0V'Ch0,e,46(1/2-"
I 907 716
FM 6.6 Exhibit 9 I s- SurzoriuAkicE
- f60 Florida CRYSTAL RIVER UNIT NO. 3 Power REACTOR BUILDING PRESTRESSING SYSTEM TENDON HISTORY TENDON IDENTIFICATION NUMBER 56 V / CUT LENGTH SHOP WASHER ID
- PC CR FIELD WASHER ID: PC CR
- 1. GAI/QA vendor inspection cover letter number-FPC _D
- TE
- 2. Date tendon received on-site RMR Nuober
- 3. Date installed in conduit Installation NCR's Wires removed Wires replaced Total Ineffective wires
- 4. Date buttonheaded Buttonheading NCR's Bad wires Accept. Reheads Total Ineffective wi res
- 5. Date stressed Stressing NCR's Date restressed Restressing NCR's SHOP END FIELD END TOTAL Elongation (1500 psi to 80% ult.)-Pred./Act. / /
Lift-Off Pressure - Predicted/Actual / N/A Shim Thickness/80% Ultimate Pressure / N/A Unseated/Broken Wires Total effective wires after stressing /63
- 6. Date Bulk-filled Bulk-Filling NCR's Time since installation Inlet Pressure Outlet Temp.
Date end caps refilled: Shop Field
- 7. Data compiled by h. *" Organization __
Date __/_ _7_F
- 8. Additional Comments: (2-) ed bi4 -cy ,yAeao "
111A -'f'ry- S~r eI/Hcam e - /l6 e 6~cf 907 716
(.0)
CRYSTAL RIVER UNIT NO. 3 REACTOR BUILDING PRESTRESSING SYSTEM TENDON SURVEILLANCE RECORD TENDON NO. 56VI LIFT OFF CONDITION RETENSIONING Inspection Avg. Shim Elong- Total Avg. Shim Elong- Total Reactor Bldg.
Period and Force Force Thickness ation Effective Force Force Thickness ation Effective Temperature OF Date Location (kips) (kips) (in) (in) Wires (kips) (kips) (in) (in) Wires Int. Ext. Comments 1 2 3 4 5 6 7 8 9 10 11 12 13 14 Is Original T1 1784 14" 13/16" N/A N/A N/A 1. Two original lift-off Stressing 1699 pressures were recorded in tendon history 8130/74 B W1A. 1A& 4 N /iAL lu N/A N/A N/A N/A N/A N/A N/A 1 T 1719 14"~ NIA 167011 I. flairl 1ii crackltig ot b_ NLA /AL botLom anchorage 12/9/77 4" _WlA h161 _Lf 6_
2 nd T 1707 14"~ bJA 1K 14"
- 1. One wire removed
-RIA 2. Water Inside tendon 4/3/80 B N/1A N/A CD 0)