ML20138J065
ML20138J065 | |
Person / Time | |
---|---|
Site: | Sequoyah |
Issue date: | 05/05/1997 |
From: | Hernan R NRC (Affiliation Not Assigned) |
To: | Kingsley O TENNESSEE VALLEY AUTHORITY |
References | |
NUDOCS 9705080005 | |
Download: ML20138J065 (45) | |
Text
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1 j g. % UNITED STATES *
- ,g NUCLEAR REGULATORY COMMISSION
't WASHINGTON, D.C. 20666 4 001 l
- *% *****/ May 5, 1997 I
- Mr. Oliver D. Kingsley, Jr.
4 President, TVA Nuclear and j Chief Nuclear Officer i Tennessee Valley Authority j 6A Lookout Place 1101 Market Street j Chattanooga, TN 37402-2801 ,
SUBJECT:
STEAM GENERATOR TUBE INSPECTIONS - SEQUOYAH NUCLEAR PLANT UNIT 1
[
Dear Mr. Kingsley:
1 On April 18, 1997, the NRC staff participated in several telephone conferences l with the TVA staff concerning the results.of TVA inspections of steam
- generator tubes at Sequoyah, Unit 1, during the Cycle 8 refueling outage. A
! list of participants is provided as Enclosure 1. Faxes provided by TVA prior to the call are provided as Enclosure 2. :
i Initially, TVA provided information to the staff that raised questions on two ,
j issues: (1) the emergence and detectability of a potentially new mode of steam i generator tube degradation at nondented tube support plate (TSP)
! intersections; and (2) the adequacy of the TVA's plans for assessing steam l generator tube degradation identified during the inspections. During phone
,! calls on April 17 and the morning of April 18, 1997, TVA informed the NRC i staff that potentially significant indications of primary-water stress i corrosion cracking (PWSCC) had been identified in nondented TSP intersections.
l Since tube denting has historically been the root cause for the development of PWSCC in steam generator tubing at TSP intersections, these findings appeared
- unique. In addition, TVA indicated that these defects were identified with a j more sensitive inspection probe that was used only on a limited basis during
! the inspections. Therefore, the NRC staff was concerned about the possibility
- of other tubes containing similar defects with less margins for structural and
! leakage integrity that may not have been identified during the general bobbin coil examinations.
On the afternoon of April 18, 1997, TVA provided additional information on the
{ issues discussed in the prior phone conversations. The issue regarding the detection and potential emergence of a new mode of steam generator tube j degradation was the result of a miscommunication during the previous
! interactions. According to TVA, the PWSCC indications that developed at TSP i intersections showed evidence of denting. Therefore, the NRC staff concluded i that these indications were consistent with this mode of tube degradation.
l TVA stated, during the phone calls, that the structural integrity -
?
estimating the flaw profiles using eddy current depth sizing technique. The i technique was previously qualified in accordance with the criteria provided by 1 the Electric Power Research Institute (EPRI). The staff raised the issue that l
l 970soso PDR ADOCK 05000327 9 o os EC E SEM ON 1 0 PDR i _ _.
Mr. O. Kingsley, Jr. this sizing technique may not have been adequately verified to confirm the accuracy of the approach. However, TVA stated that defects sized from tubes previously removed from a steam generator tube inspection at Sequoyah provided
, the validation of the technique. The NRC and TVA agreed to further discuss the validation of the eddy current sizing technique, the eddy current l inspection findings in the Cycle 8 refueling outage, and TVA's condition l monitoring and operability assessments in a future meeting. We await your further response to the scheduling of this meeting, i
Sincerely, l l
1 Original signed by Ronald W. Hernan, Senior Project Manager Project Directorate 11-3
- Division of Reactor Projects - I/II
- Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328
Enclosures:
As stated (2) cc w/ enclosures: See next page Distribution: l Docket File PUBLIC SQN Rdg. File S. Collins /F. Miraglia R. Zimmerman
- J. Johnson, RII ;
- S. Varga l
P. Rush .
G. Laints l S. Coffin OGC ACRS DOCUMENT NAME: G:\SQN\ LETTER.SG To receive a copy of this document, indicate in the box: "C" - Copy without attachment / enclosure "E" - Copy with attachment / enclosure "N" - No copy
.n DFFICE PD!I 3/PMAI , Poll 3/Ptt ;p l PDil 3/LA W L PDII-4/D , l r, EMCB / ,_ I l l NAME RHernen jy/M 'RMartid k/'I BClayton Mi/ FHebdon W J$trosnider\lY 04/74/9/' 04/yt{/97 TM DATE 04/)l//97 ' 04/0 4/97 04/10/97 3 }7 i 1 OFFiglALRECORDCOPY l
Mr. O. Kingsley, Jr. this sizing technique may not have been adequately verified to confirm the accuracy of the approach. However, TVA stated that defects sized from tubes previously removed from a steam generator tube inspection at Sequoyah provided the validation of the technique. The NRC and TVA agreed to further discuss the validation of the eddy current sizing technique, the eddy current inspection findings in the Cycle 8 refueling outage, and TVA's condition monitoring and operability assessments in a future meeting. We await your further response to the scheduling of this meeting.
Sincerely, b.
Ronald W. Hernan, Senior Project Manager Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328
Enclosures:
As stated (2) cc w/ enclosures: See next page i
i 1
1
Mr. Oliver D. Kingsley, Jr. SEQUOYAH NUCLEAR PLANT
, Tennessee Valley Authority cc:
Mr. O. J. Zeringue, Sr. Vice Presi& ' Mr. J. T. Herron, Plant Manager Nuclear Operations Sequoyah Nuclear Plant Tennessee Valley Authority Tennessee Valley Authority 6A Lookout Place P.O. Box 2000 1101 Market Street Soddy Daisy, TN 37379 Chattanooga, TN 37402-2801 Regional Administrator Mr. Jack A. Bailey, Vice President U.S. Nuclear Regulatory Commission Engineering & Technical Services Region II Tennessee Valley Authority 61 Forsyth Street, SW., Suite 23T85 6A Lookout Place Atlanta, GA 30303-3415 1101 Market Street Chattanooga, TN 37402-2801 Mr. Melvin C. Shannon Senior Resident Inspector Mr. R. J. Adney, Site Vice President Sequoyah Nuclear Plant Sequoyah Nuclear Plant U.S. Nuclear Regulatory Le ission Tennessee Valley Authority 2600 Igou Ferry Road P.O. Box 2000 Soddy Daisy, TN ~37379 Soddy Daisy, TN 37379 Mr. Michael H. Mobley, Director General Counsel Division of Radiological Health Tennessee Valley Authority 3rd Floor, L and C Annex ET 10H 401 Church Street 400 West Summit Hill Drive Nashville, TN 37243-1532 Knoxville, TN 37902 County Executive Mr. Raul R. Baron, General Manager Hamilton County Courthouse Nuclear Assurance and Licensing Chattanooga, TN 37402-2801 Tennessee Valley Authority 4J Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801 Mr. Pedro Salas, Manager Licensing and Industry Affairs Tennessee Valley Authority 4J Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801 Mr. Ralph H. Shell, Manager Licensing and Industry Affairs Sequoyah Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Soddy Daisy, TN 37379 i
LIST OF PARTICIPANTS HE lYA J. Strosnider J. Smith P. Rush D. Goethcheus S. Coffin D. Hughes R. Martin J. Rupert L. Weins R. Adney S. Varga* R. Shell G. Lainas* C. Webber D. Goodin
- Part-time I
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l SEQUOhH NUCLEARPLANT . UNIT 1 CYCIE a REFUELING OUfAGE
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STEAM GENERATORINSFECHON STATUS A8 OF 4/15S7 l l i i e l Primary to secondary leakage prior injahutdown was 0.61 spd ; 1 ! = No post shutdown secondary side hydro was performed due to low primary to secondary side i leakage at the time ofunit shutdown. ? Steam generator areas examined, exps'naion criteria, ami pavbes Based on all active and potential dam $e mechanisms, the following areas are being examined UIC8. The inspection plan, technique, and personnel are appropriate for all active and potential damage wMnisms. ' 100% Mt. length bobbin examination Ni all 4 steam generators for initial screening and detection ofindications . 100% hot leg top of tubesheet RPC exkmination in all 4 steam generators with an ERPI Steam l l Generator Examination Guidelines, A;pendix H qualified rotating pancake coil (0.080 mid ! range!0.080 high frequency /0.115 mid fange) I 100% row 1 U bend RPC and 20% row 2 U-Bend RPC examinations in all 4 steam generators with a magnetic biased ZE1EC standard Row Idt2 U-Bend probe Plus point probes are being used for siding and for measuring crack profiles for structural integrity assessments in cordunction with in-situ pressurs testing. l Standard 3 coil RPC (2 directional and .080 mid range) for APC evaluations Unit 1 Cycle 8 Dested Tube SupperdPlate Inspeetlas l
. 8 Sequoyah unit 1 staam generators havefa total of4,010 dented tube suppon plate intersections greater than or equal to 5 kolts and 5,774 less than 5 volts. The following dont inspection is being perfonned using +P4 int probe (0.080 high hoquency/0.115 mid rarp+ point) ,
Gmeter Than 5 Vok Dent Inspectioni TVA sampled all dents greater than or equal to 5 volts at al TSP elevations (and lower TSPs) where, based on past inspections, degrahation has occurmd (derming a critical arca) ami performed a 20% sample of the next higer TSP elevation (a buffer zone) to bound the affected area. The buffer zone, in this application, is the next higher tube support plate elevation where no degradation has by observed. If the 20% buffer zone induded lean than 250 demed intersections, dented intersections wl!! be selected hom higher elevations until a totalof 50 tubes are selected. w 1.ense,enanmade jl 44/1737 i
2 . l j 100% >=5 volt dented tube nupport plate latersections from H01 to H07 in steam gem atul 1,2, and 4 i - 100% >-5 veh dented tulm support plate intersections Rom Hol to H03 and a 20% random { sample ofH04 in steam generator 3 i 1 IAss Than 5 Valt Dent Inspection , i ' TVA sampled all dents less than 5 volts at all TSP elevations (and lower TSPs) where, base i i on past inspections, degradation has at: curred (defming a crition1 area) and performed a 20% i j buffer mne, in this application, is the 5ca(t higher tube s degradation has been observed. i j . 100% < 5 voit dented tube support pidte intersections from H01 to H02 and a 20% random i sample ofH03 in steam generators 1 s md 2 i 100% <$ veh dented tube support pie j e intersecdoitu num Hol to H03 and a 20% random sample ofH04 in steam generator 3 : 1 100% <5 volt dented tube support plak intersections Rom H01 to H04 and a 20% random t sample ofH05 in steam generator 4 l
- Number of Esans , I j 115 S!G.1 SIG2
. SIQ1 3/Q4
- Bobbin 3345 3306 3281 3275
{ 100% full-length j Top ofTubesheet Rotating 3345 3306 3281 3275 i ' Pancake Coil 100% 't -
>5 Volt DontedIntersecdon 1 618 48 598 2681 j + Point ;
i
' <5 Volt DentedIntersection ' 225 156 1772 j 2047 + Point
- U Bend Rotating Pancake . 103 .103 i
j 83 90 Coll i I j Espanales cdteda ' ! He only expensions that are possible ! re in the U. bend inspections and in the dont } inspections. i i k - i j w i.en. M '2 M/Im J e J
. . . . . . . , _ . . . --, . n. m ev. wr w w ++++ ****" * * *
- j U. Band Dwannalan Critari_a Ifone crack liks indication is identifist in the R2 sample,100% ofR2 U-bends in that 1
- ganarstor willbelaW.
i I If one crack like indication is identifisti in the expansion,100% of R2 U-bends in all generators will beinspected. 3 Denied TSP fatelon hanaainn dritaria - j Irindiostions are identified in the greater than or less than 5 volt dented intersection s
- buffbr zones, the sample will be exparsled in acconiance with Table 5 of pm. outage asses The bufer zone result classi6 cation as denned in TS Section 4.4.5.2 shall be utili=L when a sample aim is less than 200 th n only C-2 results apply.
,t ' i UIC8 Espansions , i ' Number l T.8Et El.Q ofExany
- Reason l <5 Volt Dented Intersection 3 515
} + Point One indication was l { > idatifiedin the l
- <3 Volt dented i -
intersection + Point sample at H04 l (
- Inspection Results To Date i
i. TotalProjoued Total l In Prooutage TotalPlugged Cumulative I Assessment U1C8 To Date Plunned Anti-vibration Bar Wear 10 ] 1 5 ! I j Cold Lag Wastage I
- 10 0 4 j
FWSCC at Dented TSPs - Circ 0 32 32 i PWSCC at Dented TSPs - Axial 95 140 1 187 ! PWSCC at U-Bend . 0 4 68 l ' PWSCC at TTS -Cire & Avtal 100 55 ! 238 ODSCC at Dented TSPs- Cire 87 32 ,i 56 j ODSCCat Dented TSPs- Axial 0 0 i 6 350 APC 248 APC 248 APC j ODSCC at TTS - Axial 30 2 6 4 Other -
.-.0 ._L g l MTW 332 267 612 w Ise m 4= 3 satim W
v
i l - , t j,, FERCENTPLUGGED (TO DATE) S/O 1 & 2 testing not complete ElGJ 2.2%
$gil 2.9% $$il 6%
E51.1 6.9%
- The most sign 16 cant indications identifled;to date have been screened in the in-situ candidates list l attar.had. .
t i {
- Rapair/ Plugging Plans All crack-like! i ndications and other volumetric indications (l.c., cold
! leg wastage, anti vbration bar wear) that equal to or exceed 40% through wall will be plugged. Stabilizars will be insudla! 16 all tubes with circumferential cracks that meet or exceed Westinghouse established stabhization criteria. '
- htage ' = assenment includ4s previous history "look backs" performed
- NewInspectionFindings:
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- Cirmudwential PWSCC associated with dented tube support plates was not piojected in the pre-outage damage assessment; To date,32 tubes have been identified.
t+o 4
- To date, Mt tubi lnity with axial PWSCC associated with dented tube mpport plates have been identi6ed, which exceeds the projection of 95 tubes Some of these tubes will be in-situ pressure tested to ve#y structural integrity at the end of tlw opa ating cycle. # g/ wn/5 7 - Steam Generatur U-Bend PWSCC was not projected, and to dateftubes have been identified. Two of these tubes are included in in situ prenure tests.
In situ Preuure Testing Plans - See attpched in-situ pressure testing screening criteria and candadates. Sequoyah has no plans for pulling tubes during UlC8.
- Per GL 95 05 and SQN TS change 96-D5, we are notifying the staffof tubes with PWSCC and outside diameter Axial Corrosion associated with intersections with < 5 volt dents. Seve total intersections were identified in 3 S/G's :
S/O l- 1 S/O 2- 0 , S/O 3- 5 SIG 4 1 l
- All affected tubes will be rimoved from senice o
ment of tube integrity for previous operating cycle and next operating cycle - All tubes tha lenge structural integrity will be in-situ pressure tested and results will be included in the condition monitoring assessment, wa== e 4 ,y , i I
. , , ey12/1986 08 58 **** PANAFAX UF-600 **** 14711106 P.07 1 i 1 We expect all oddy current, in eltu plossure testing, and repairs to be completed over the l weekend and manway dosure early, the week of April 21". i e u
- a d
e 9 0 E f i l rag g gewlaemA i
'S 84/17/97 !
. . 09/12/1986 08:59 **** PANAFAX l.F-600 **** 14711105 P.08 i
4 {. .. Sequoyah Nuclear Plant " Unit 1 Cy:le 8 Refueling Outage Program for Indications klontified with j 4
<2 Volt ljorizontal Cainponents l
During examination of tube support plate intersections with + Point technology, axial primary water stress corrosion cracking was identified that was not identified by bobbin coll. Bobbin goll data for indications detected with rotating j pancake coll were reanalyzed, and it was determined that bobbin ooil could i identify indications detected by the rotating coll. A change to the bobbin coil ! j { i evaluation guidelines was prepared to provide analysts training in detecting these signals. Tube support plate: Intersections with signal rotation off horizontal i 4 l with flaw-like characteristics in the differential or absolute tube support plate ! suppression require data analysts'to report the indications identified as RRC 3 l (retest rotating coil) calls. All hot ibg bobbin coil data was roanalyzed for tube j ; support intersection horizontal components. All RRCs identif,'ed in the review were tested with rotating pancake coll. The disposition of these RRCs were i
! either HDD (no degradation detected) or SAI (single axial indication).
Bobbin Analysis Review 1
- EQ Complete RRCs qalled 1
4 RRCs Confirmed
- 1 100 % 155 8
! 2 i 100% 77 5 3 100% 148 i 55 4 100% l 208 i 22 i I The setion plan for these calls is as follows. EPRI performed an independent I review of the data and the action plan and concurred with the plan (see attached review). l
- Actjon Plan l 1. Sort steam generator 3 database for RRC calls with associated SAI calls.
- 2. Determine the largest voltage indications t
i l 3. Determine the longest length trylcations !
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- 4. Son steam generator 4 databask for RRC calls with associated SAI calls.
j 5. Determine the largest voltage indications 2 e l ] lKs49M4//CAfforuMiselC , _ . _: l ' ~__ .
- 6. Determine the longest length I ications
- 7. Determine N steam generator 4 indications bound the largest indications in otsam generator 3.
- 8. Ensure there are at least 201 icatJons selected for sizing in steam generator 4. N not, then select'more indications in steam generator 3,1 and 2 for sizing. Retest tubes with EPRI Appendix H qualified techniques. If indications from steam generator 3 are required, size by existinD + Point data.
- 9. Size indication in steam gener0 tor 4 Row 33, Col 21.
- 10. in-situ pressure test steam gerhrator 4 Row 33 Col 21 to 6000 psi or maximum system pressure and leak test to 2500 psi plus adjustment for lamparature. ;
- 11. in-situ pressure test at least 5 5rgest (voltage, length, PDA, Max depth) indications (preferably from siebm generator 4) from step 8 to normal 3AP and main steam line break lealgige to prove that they are structurally insignificant and will not leak. ,
- 12. Devebp basis that the indicati4ns found in steam generator 4 Row 33, Col 21 is about or less than the 40$ plugging limit (NDE uncertainty la ~10%)
and is structurally insignificant. ;The larger indications will be detected with the current soreening program snd no expansion of the eddy program is warranted.
- 13. Review history to develop groMh rate for U108 RRC calls that can be identified in past eddy current dpts.
STATUS: , insitu leak and pressure testing willI bo done on 11 RRC re-review calls form the initial bobbin coli review and re review analysis. A total of 702 + Point exams i have been done on < 2 voit horizona' l component indications at tube support plate intersections. Three addition 01 tubes were identified with structurally insignificant PWSCC axialindloatl s and are being in-situ pressure tested. i i mapecew tcem I
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4 EPRI , ) ) Research inattute i Powering Prognss tnrough Innovative Sclutions April 15,1997 i j , i Mr. D& Yid E GoetCheus l i ! Manger, Steam Generator Technology Department Tamcasse Valley Authoriry, BR-5A C ' 1101 Market St.
- E---% TN 37402-2801 I.
l i
SUBJECT:
i Commt I. mas Than 2.Q VohsReview of PWSCC at Tube S l . j
Dear David:
t
' Itis reviewis based on an NDE perspectiw ,
s ased an on exanunadon resuhs, desmdation dewand with bobbin coil tru.drmed w technology, ed additional tests.
'Ibe inspection plan requires dents greater than 2.0 vohs e identifwl on buffer zooe of 20% at the cert elwation. %is samp
- Mon Guidelines, Revision 4.
1 Tube support plate PWSCC signals haw been confimed at Se technobm theb Tbs bubbin coil data for these indications were re quoyah Unit I by rotating coil analyzed and it was deternuned that coC caluanon guidelines was prepared, . eo with exampes of n graphic the h C J or absolute tube support plaza suppress report tbs change form. Data analyst trainmg was provided for the changes bM in the ev PWSCC degradation within tube support pint' e locations dancceed with rotunng coil technology prmsies a method i to ensure that a conser to khmefy posannallocatinns. Ibis is beood on available data ew; assembled at th apprammately 30% of the indications detected by bobbin coil are mafirmed amo understnod that one indicariou not estected by botein coil was dete technology. His in,re inostved an addMonal bobbin coil g analysis an with the kn imbeacon omissed in the rotanng coil exammation. w Detection o n coq could of the indicat deseadon and maMmm levelis not a vehm of I fb .
. Oe . " J -, 3st2 HA0 view Avens (90064395) + Pase Odhes arv 1M22
- Nw Aleu enamen.gia, qpt. anno Lasseuw. seas ses
- Westensen, DC 3DetHeer.15A
- O ;
Chasisen odisw asse Maans seat
- CWeset NC 2aa62,15A
- LEA 4 rea, o00tsf.ests
j Babbin coil PWSCC technique quali5cauan has rzeiwri ind.asey peer review and aca7m for ? desechan only at noneraa-M and non dented beenections. Based on #: work F h..sd by Westaghouse nn tiented locatior.s and provided in Appem!Ix A of the ODSCC akertste repair criteria, flaw desaction with bobbin coil should be possible at dentei locations less than 5.0 voks. Adetianal studies L ve been F.tv...id to deternune the minimum reliable Ms threshold for E 4= al components of the eddy current pignals. 'Ibese smdies have shewn that horizental compnnera less than 2.0 vohs cannot be reliably reported. Reliability is a function of the i
'=% fkun test to test by achieving the sare.c resuh. 'Mid Range Plus point technique qualification has also received industry peer review and scesptance for percent degraded area and inneth measureinsats for axial PWSCC in y tube support platz inter =5=E RECOMMENDATIONS:
Ngg. Igg - Estory aview of reported indicaticas frorn the prior inspection should be reviewed to dewlop a growth rate itindications were pmsent amluut daected Bobbin coil data tisw e mg---w signal arnplitude should be reviewed and cocelated for the cunen: and past outage. Mid range plus point d i dould be correlated based on percent degraded area and length if data ex:sts fmm the previous outage. ' Indications detec:ed which cor. rain an eddy current respec with a horizccialvu a-siIess than 2.0 vehs should consider the sigr.al amplinide, percr.at degraded area and axial length for in-situ presure toenna. + r - Tenn Pursue PWSCC alternate repair criteria for indications maH within the tube eupport plate. Consider pulhag tuben en suppert an ahernato repair enteria.
SUMMARY
Boed on the information provided, Sequoyah Urut 1 is meetmg the iment of tbc PWR S/O Examination GuiMH Qaalised techniques are used in the examination for d" and sizing. The approach for airing to gain infee for in-situ pressure testmg is the best available process known at this time. The ability to gain additional information on history avview will be subjective, , but will provide an inferred growth rate, s Sacacly, t Gary Henry Manager Sfr NDE EPRINDE Camer B Adney,TVA / CC-D. M TVA j
, C. Weky, Palo Aho M. Behruvpsn, Palo A!!o i . L Deusun, Palo Alto r
I INSITU PRESSURE TEST SEl,F.CTION CRITERIA l
%is selection criteria meets and exceeds the requirements of the draft EPRIIn-Situ Testing Selection Criteria for Circumfbrential and AxialIndications. See attached In-Situ Pressure Test Candidates. The selections are complete for steam Benerators 3 and 4 (6 in steam generator 3 and 10 in steam generator 4) and are not finalized for steam i
generator 1. In-situ pressure testing will not be performed in steam generator 2.
- 1. All indications w:th axial or circunkerential extents greater than Regulatory (kilde 1.121 criteria. Assuming 100% through wall. l
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- 2. All axial or cirmimferential extentsht er.ceed 80% through wall criteria
- 3. Indications with SAI and SCI that exceed 30% through wall criteria with indications intersecting
- 4. Axial indications with maximum voltage and exceed 80% through wall criteda
- 5. Circumferential indications with maximum voltage and exceed 80% through wall criteda l
l e i i r%
*I SQN UNET I CYCLE 8 IN-STIE PRESSURE 1EST CANDIDATES 04/t7 M 1:31 FM ;!
SG ItOW CG, ANGE VG.T3 IND LOCATON 04ARACIBttZNf10N SIZE CRFTDIEA DISPO6fl10te!D ' lI 36 67 i 305 1.2R SCI NIS .II PWSCC HIS CRC ' MAXDEFni= ' 305" SCI DO M70 DESITU- L CRCEXT* +P0tVT NDD FLDA= FALIECALL DUE 360"PDA= TO GKEETRY I 48 33 66 8.46 SAE H13+.36 OtKCC Ht3 I MAX DEFDi= .318"SAI , IENGDi= ! HEA= I 44 57 51 I.91 SAI H13.61 PWSOC HTS MAX DEPTH = .61r SAI IRNGTH= MDA= 2 12 25 55 6.74 SCI HIS.I4 PWSCC HTS CRC AVG %TW=58 ONEOFTHE DO N(7TINSITU- L MAX DEPDf- M% IAIM ST DOES N(7t ORC EXT-19" V0t.TAGE SQs EXQED 50% MAXDEFHfOlt 2 17 238' EXTENT I 35 64 0.46 SAf HEIt .31 DDSCC TSP
.- . . . . - -. . - . . - - - _ _ , , AVG DM2_%__ _ . Mr SAI. . ___ . tri wrr atmi_ __. . i y y y EXCEED 80%
MAXDEPDIOR ['
.45" LENGTH 3 1 36 63 1.M SAE H97+IO.26 PWSCC U-BEND MAX DEPTW=65% .58tr SAI IN4TIU1EST- '
IENGTH=.75 EXCGDS.48" i FLDA=50.77% IINGTH ; 3 6 62 56 0.41 SAI HDI .12 ODSCCTSP MAX DEPTH = 98% .4M" SAI DO NOTINSTIU- ! IENGIH=.45' ODSCC UNDER FIDA=49.78% THE TSP- APC ' APPLIES ! 3 10 79 47 9.55 SCI HDI+.11 ODSOCTSP CIRC MAX DEFIM 63% SAI/ SCI DO NUTIN5 flu- l CRC EXT =40" DOESNOT 45 1.65 SAI 151.10 FW50CTSP FIDA=37.7% EX ED80% [ 360"PDA=4.19% MAX DEPE4 OR ! MAX DEFIH=54% 238' EXTENT IENGTH=.29" j l i FIDA=32.14% [ r- _- ;_im e i t i I __ __ __ . _ _ . __ ________._i
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SQN U iT 1 CYCLE E IN-SITI PRESSURE TEST CANDIDATES 04n6/97 6:17FM , SG ItOW COL ANGLE VOLTS IND LOCATDN OIAMCIERIZATION MZE OETUtfA DISPOSm0NED 3 11 59 4s I.32 *SAI Hel.C PWSCC13P MAX DEFIW=4f% SAFSCI DO NOTINSml- @ , I.ENGIM .17 DOESNOT U L SS I.11 SCI Hel+.Il ' PWSCCTSP CIRC HDA=32.12% EXOMiD27% d : MAXDEFDf42% CIRC EXT-loo" MAX DEFIM OR 238'EXTDrT f( FIBA=18.4% , 360"PDA=5 I2% @ i 3 14 65 ' 51 0.77 SAT HDI .14 PWSCC TSP MAX DIFI11-67% .412" SAI DO NOT IN$nt;- @ ! IING m=.1r DOES NU1 SI 0.86 SAI HCt+.24 PWSCC TEP ILD: 4 2.26 % EXCIED Sp% g l MAXDEFIH OR *
.43r*I s iGi W 3 14 73 36 4.21 SAI 191+.6 PWSCC TSP MAX DEFIH=76% .575" SAI INSTIU TEST-MDA=56.5% RRC IDEN11FIED ! . . - -6, -. - _ _ . . ..
IENGTH=.4r .. _ _ . . . . __.__ . .E mrrm w , . . . _ _ . .R j EXAM E 'IS 77 30 1.93 SAI HDt .16 FWSCC13P MAX DEFT =48% .476* SAI DO NOTINSITU- E IENGrn=.3r DOESN00 RDA=26.lf% EXCEED RG 1.121 , 61 .72 SAI H0l +.55 FWSCCT3P MAX DEFIW=39% 2 ! IENGIH=1.2" l [ 16 67 57 2.13 SAI H01 23 PWSCCTSP RDA= IS.4% I i . . MAX DITIB-100% .476"SAI INSTIU 1EST- [ IINGHf=.71* EXCEEDS.48' MDA41% l; LENGTH AND RRCIDENTW1ED ! ININITIALBC Exc. .. 3 16 83 51 1.9 SAI HDI .58 PWSCC ISP SAI/5CI INSmf1EST- % 53 1.02 SAI HDI .17 PWSCCTEP RRC IDENTTRED d i Se 0.76 SAI HDI+.64 PWSCCTSP MAX DEF1M=79% IN INITIAL BC U l IENGTH=.3" EXAM N ! 39 .52 SCI Hol+.22 FWSCCTSP ORC MAX DEFIR-43% i CRC EXT =35* ? PDA=52.57% E j f 1 memewmensimman4= 2 t, _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _- _4
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{ SQN UNIT I CYCLE 8 IN-SITU PRESSURE TEST CANDIDATES 04/t6/97 6:33 PM ^ t SG ROW COL ANGLE VULT5 IND LOCATION OIARACTERIZATION SIZE CIUTERIA 6 3 30 7I N 2.23 ' SAI IW2 .43 FWSCCTSP MAXDEPnkS4% OtE OFTIE INSITU TIST-iENcnw.5s- LARGEST RRCIDENDFIm FLDA=35% VOLTAGESAfs IN REVIEW OFBC i DATA AND , EXNns .43-IINGTH 3 40 32 34 2.16 SAI HIS+4.94 PWSCC ffT3 MAXDEPHk25% .445" SAI DO N(FrINSITU - i LENGDk DOESN0fT ' ILDA= EXCFFn30% [ MAXDEPTH 4 1 21 19 0.79 SAI H02 .27 PWSCC TSP MAX DEPRf-41% .521' sat INSi% TEST-IENGUk.33' NCyr DETIKTED FLDA=38.5% BY BCIN THE OIUGINALOR REVIEW. ! EXCFFDS A8' ' IINGTH 4 1 84 31 2.35 SAI HU7+10.13 FWSCC U-BEND MAX DEFDi=96% INSITU TEST- l
$9 6.2 SAI HD7+11.24 FWSCC U-BEND IENG'H=.9r .125'SAI EXcFFDS .48' .
FIDA=74 4% LENGn1 4 2 25 48 9.'39 SAI HO3+.33 PWSCCTS8 MAX DEPDf=44% .468* SAI DO NUTINSTIU-IENGHf= 35" DOES NOT PLDA=29.9% EXcRFn .48-IINGTH I 4 3 45 43 1.07 SAI 151 +.01 FWSCCTSP MAX DEN 1% .53" SAI INSHU TEST-LENGTH =.5T EXCFFDS .48" PLDA=3I.3% IINGTH N(Fr RRC i , t I w e s s emim Ane 3 i
SQN UNIT I CYCLE 8 IN-SITU PRESSURE TEST CANDIDATES 04/16F1 6:34 PM l SG ROW (XX, ANGtE V0t,T5 IND LOCATON CHARACTERIZATION SIZE CRTIERIA DISPOSTDONED
'4 6 31 85 .85 SAI ' HO44.14 PWSCC 'I3P MAX DEFIH4?%
SAFSCI INSITU TEST 30 2.I I SAI HD4.IS IENGTH=.19' MCI / SAT ATHDI
% 1.13 SCI H04 .05 REA=43.6% DIAT 45 1.32 SAI HeI +.13 PWSCC TSP MAX DEPHI=74% INERSECTS 30 .9 SCI H01.09 IINGUf=.26 AND >90% MAX ILDA=41.1% del'HI PWSCC TSP CIRC MAX DEPHk71%
CIRC EXT 41* ILDA=36.3% 360*PDA=6% PWSCCTSP MAX DEPTH =90% IENGUE.25" R.DA=69.8% PWSOC T3P CIRC MAX DEFHf-56% GRC EXT 4P . i
@6gg, ~ >
360*PDA=43% 4 9 '27 40 .87 MAI H03+.14 PWSCC Ti* MAX DEFDt43% DO NOT INSITU-43 1.21 MAI H01.16 LENGHb.43' .52T SAI DOES NOT FLDA=39 6% EXCEED .49" PWSCC TSP MAX DFPTHM9% t.ENGTII IINGTib.19' IMA=34.7% 4 11 41 55 2.06 SAI HOI +.20 PWSCC TSP MAX utruf=49% .464' SAI DO NOT INSIIU-LENGTib.31" IX)ES NOT l
! HDA=21.4% EXCEED .43
Mu DeFn =49% LENGn< LENGUh.43" FLDA=34.6% 4 12 27 74 3.98 SCI Niko7 PWSOC HTS CIRC MAX DEFni=92% ONEOFTHE INSTIU TEST-CIRC EXT =43' LARGEST EXfTrn 30% FIDA=46.7% VOLTAGESCIs MAX DEPTH 367'PDA=5f% I W alathummadse a
O SQN UNIT 1 CYCLE 8 IN-SITU PRESSURE TEST CANDIDA~IES 04/17&T 129PM -
- l SG It0W CtL ANGEE VM.13 IND 14 CAT 10N ORARACHDUZATION SI2E OtITERIA DISPOSITIONED e,
'4 12 32 : 51 523 SCI i HTS.14 PW50C CIRC MAXDEFI1949% ONE OF1NE ' DONOTINSTIU 8 Y CIRCFXiv4s* IARGEST DOES NOT Pt.DA=30.2% VOLTAGE SQs EKGED 30% .' i 360"FDA=4.0% MAXDEF111 ll 4 14 28 40 0.79 SAI HB2.45 PWSCCTSP MAX DEFRb55% .42r sal DO NOTDESTIU-LENGDb.I3' DOES NOT c FIDA=37.5% EXGED.48" .
EE N CITI 5, 4 14 29 40 1.3 SAI H02+.16 PWSCC"I3P ' MAXDEPTH=84% INSITU TEST-LENGHf=.34' HORIBONTAL j! FLDA49.1% CXDWOME:NT- j[ ENrvmu 80% _t MAXDEPHI J! 1 4 14 40 69 4.23 SCI HTS.27 PWSCCHTS GtC MAX DEFHMTK ONE OF TIE DO NOTINStTU 3' CIRC EXT =35' LARCEST TEST-DCES NOT ?e HEA=51% VOLTACE sos EXQED Sr% 5 ' 360"PDA=S% MAXDEFIM 4 I4 63 53 . 1
.33 SAI HD2+.00 FWSCCT3P MAX DEPDi=86%
LENGTikX
.579* SAI RRC INSHU TEST-EXQEDS 80%
fl ( ILDA40% MAX DEFIH AND jl , 67 .56 SAI HD2 .32 ODSCCTSP MAX DEPUf43% RRC il IENGTH=.51' ! MDA=61.8%
' SB .43 SAI HD2 .05 FWSCCTSP 4 17 44 50 1.15 MAI H02+.12 FWSOC15P MAX DEPDl49% MAIGCI DO NUTINSHU -
LENGHk.35* .887 SAI "IEST-DOES NUT I FIDA=3I% EXCEED 30% 17 1.66 MAI H02.10 FWSOCTSP MAX DEFDMSE% DIFni LENGTH =.38' '. I FLDA=41% . 90 Hp2.19 34 0.67 FWBCCTEP CstC MAXDEPDh57% CBtC EXT =47' {l FLDA4.7% [ 360"FDA=3.3% tw- 5 j i
.l SQN UNIT l CYCLE 5 IN-SITU PRESSURE TEST CANDIDATES 0446/97 6:37FM l SG ROW C(X, ANGLE VOLTS IND LOCATTON CHARACTERIZATION SIZE CRTIERIA DISIOSTHONED '4 24 30 47 I65 SA) 552.07 Fw;bCC TSP MAXDEFnf=61% .7.% DOIK7TINSm1 !
IENGTH=.49" 1EST-DOES NOT FLDA=41.5% EXCEED 30% 4 25 32 58 CEI SAI MAX DEPIW 1192+33 FWSCC TSP MAXDEFnb49% .413 DO MyrINSITU LENCnk.5" TEST-DES N7r FIDA=18% EXGED 3D% 4 26 11 43 1.33 SAI IR11.33 MAXDEFIH PWSCC TSP MAX Ders14-61% .446 DO NOT INSml-IENGTH .26' RRC DOES NOT FLDA=41.3% EXGED .48' 4 26 15 48 0.?4 SAI LENGIM H02-33 PWSCC 75P MAX DEPTH =49% SAI,' SCI DO NOT DfSin;- IENGTM=.28' DOES NOT M.DA=30.7% EXfTFD 80% 48 9.57 SCI IW2+.26 FWSCCT5P CIRC
' MAX DEPR1=f9% MAX DEFIH CIRC EXT =S7' ILDA=13%
4 360"PDA=I.85% 33 21 47 .55 SAI Hol+.00 PWSCCIT MAX Dtra tI=91% SAltKyr IN STIU TEST-IENG"71=.25" DETECHD IN EXCEDS 80% F_' DAe66.8% 2" REVIEW OF MAX DEPTH. i BC DATA NOTRRCINBC 4 36 26 REVIEW 53 .54 SAI ' H01.01 PWSCC TSP MAX DEPHb84% .534' SAI INSITU TEST-LENGHN.27" NOTCALLED FIDAW.3% RRCIN DATA 4 36 42 58 2.96 SAI REANALYSIS IN126.6I FWSCCTSP MAX Ut:M M=97% l.28S" SAI INSTRI TEST-IENGTib 24' RRC RRC AND FLDA=43.7% (RIGINAL MAX DEFDi=95% LINGTH IENGHb.29' EXCEEDS .48' FLDA=81.3% t __ _ "51 m den 6 _ _ _ _ _ _ - . _ . _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . -.__--___________-m. - . _ _ _ . _ _ - _ . - _ _ _ _ _ _ _ _ _ _ _ _ . .
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