ML19330B753
ML19330B753 | |
Person / Time | |
---|---|
Site: | Phipps Bend |
Issue date: | 07/28/1980 |
From: | Mills L TENNESSEE VALLEY AUTHORITY |
To: | |
References | |
NCR-M80-6, NUDOCS 8008050452 | |
Download: ML19330B753 (18) | |
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400 Chestnut St:19e 2:ver II July 23, 1980 Mr. James P. O'Reilly, Director Office of Inspection and Inforcement U.S. :Tuclear Regulatory Comission Region II - Suite 3100 101 "arietta 3treet Atlanta. Lc;;i.i 20303 tear Mr. O'2e111y:
?I!!??S 3T.: 7:CI.2AR ?LXiT UNITS 1 XiD 2 - 1~?CRT.GLZ DEFICI': ICY -
CORCP32 2.'?"C"'!CN 22C02DS (:!C2 :10 0 - 6 )
~niti.21 nocilia.'.:1:n s; :..a ;,u t ; 2ct r 2p o rt.:.::.a 22;.ci:ncy ias nada :.:
'. tic .2, 2egien ::, !. apac:ar 2. '7. iright ca .hy 20, 1930. T.:e fir:t intarta report was su'mitted o on June 19, 1980. In compliance with paragraph 50.53(a) of 10 C72 ? art 30, we are enclosing the final report j of the subject deficiency. If you have any questions regarding this subject, please call Jim Domer at 7TS 357-2014.
7ery truly yours, TZNNESSEI: 7ALLZY AUTECRITY L. M. Mills, Manager Nuclear Regulation and Safety Zaclosure cc: Mr. Victor Stello, Director (2nclosure)
Office of Inspection and Inforcement U.S. !!uclear 2egulatory Comission Washington, DC 20555 i
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1CCF350.55(e)
NCR M3C-o RE?CRT NO. 2 (F:NAL)
Cn May 20,1930, T7A infor:ed NRC-0IE Regien II Inspecter, R. W.
Wright, of a ;otentially reportable ccnditicn under 1CCyR50.55(e) regarding 12;reper inspection recceds. This is the final report on this deficiency.
Oescricticn of Ceficiency The require en:s of CA??-17, Quality Accurance Reccrds, state in part -
that " Inspection and test recceds shall, as a =ininns, identify the inspecter . . ." Ouring an audit at Phipps Send concucted by T7A, it was cheerved that inspecters signing OA documents did not perfer: all of the inspections fcr wnien he was signing. The :pecific area in whicn this practice was fcund was the inspection of reinforcing steel by the Civil ~uality Con:rol Grcup. A lead inspecter, wno has overall responsibility for the inspection of a particular activity, was signing the concrete placement fer= upon verbal confir=ation fec= his crew of inspectors and a final tcur of inspection of the ec= plated work activity. However, there was no docu=entation available that would identify the re=ainder of inspecters involved.
Safet? I:clicatiens Without the required identification of inspectors, there was no documentation available to provide assurance that the inspecters wno examined a specific activity were fully qualified to perform the inspection.
Corrective Action The designated lead inspector who is responsible for inspection of l reinforcing steel for a specific concrete pour and who is directly involved in the inspection activities shall verify that all areas have been inspected, sign and date the pour card, and identify in the signature block any other inspectors involved in the inspection. The inspector's signature indicates that all areas have been inspected in ;
accordance with applicable drawings, specifications, and procedures. !
A review will be conducted of all pour cards for Category I structures {
and the inspectors involved with the inspection of reinforcing steel shall be identified by initials er by unique nu=ber. TVA anticipates that this review will be ecmpleted by August 8, 1980. l l
.'se tion Taken to Prevent Recurrence Procedures will be reviewed and revised as necessary to reflect the above corrective action. Inspectors will be given the necessarf indoctrination in the procedures. In the future, inspections and documentation will be accomplished in the manner described above according to the revised procedures.
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Mr. Ja=es P. O'Railly, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Regien II - Suite 3100 101 Marietta Street Atlanta, Georgia 30303 Jear Mr. C'Reilly:
?HIPPS 3F20 NUC2'AR PIJ4iT CIITS 1.VQ 2 - REPORTA3LE DEFICIC;CY -
IMPRCPER IMSPECT!C:1 RECCRDS (UCR M30-6)
Initial notification of the subject reportable deficiency '.as cade to NRC-0!", Region II, Inspector R. W. Wright on May 20, 1980. In com-plianco with paragraph 30.55(e) of 10 CFR Part 50, we are enclosing the first interim report of the subject deficiency. T7A anticipates transmitting the next report on or before August 29, 1930. If you have any questicas regarding this subjects ~ ease c~ai1~J"is Do=er at FTS 357-2014.
Very truly yours, T212!ESSEE VALLEY AUTUCRITY L. M. Mills, Manager Nuciaar Regulation and Safety JAD: JEW:SCP Enclosure cc: l'.r. Victor Stallo, Director (Enclosure)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 cc (Enclosure):
APJIS, 640 CST 2-C J. R. Calhoun, 1750 CST 2-C A. W. Crevasse, 401 UBB-C H. N. Culver, 249A HBB-K W. P. Kelleghan, Phipps Bend C. F. Dilworth, W10C126 C-K H. S. Sanger, Jr., E11B33 C-K F. A. Szczepanski, 417 UBB-C i
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TEtitiESSEE VALLEY A'J TiiORITY Significant Condition Report Processing Record Sheet
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sli940 Date'Receivec by tiLS Title _
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- 2. tP.C-01E Region II Initial Notification lb Insper.or LdM 7/2o / 90 Date
$ .?x) f Sy tiLS Engineer 5 / 30 / TD Crnfirm tiotice Due
- 3. 50.55(e) Detemination: tionreportable ( )
Reportable %
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pyfiLSSupervjser Date
- 4. Part 21 Applies': Yes ( ) No(
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- Affirmative if 10CFR21 Worksheet, sections VI and VII are both affir ative.
- 5. A. Confirmation to flRC-0IE:
7e /3wt&Its To Inspector 5 /LP/80 Date B. tiotification to tiSRS of Reportable NCR's:
' )ld/ h h . 5/2E/f6 To Incividual Date C. Notification to OEDC Manager's Office of j / /
lewireportable NCR's: ME f@/d><,.3 J- 5(/7J/ fo To incivioual Date D. tiotification to Vendor if Part 4 Above is Affirmative: _-[_
To Individua,1 Date By NLS E g eer: b kk
- 6. Distribution of Reportability l
Detemination Package - 5f12fto l Date '
Includes Notification to OEDC Manager
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if Part 4 Above is Affirmative , . 3h"L.
NLS Engineer
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. L*N'TED STATES GO\*ERNMENT I. 217107'b n d um - TENNESSEE VALLEY AUTHORITY
<To . G.'F. "il.' Orth, Chief !!uclear Engineer, WlCC126 C-K FRO!.! .v.
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.oa, wv- 6, u.r -: ,,:..y6u. . 0. 3 The subject deficiency has been deter =ined to contain a "significant" OA Prcgra= deficiency. . Please -dete. ine */nather the condition described shculd be reported to the IIRC under the require:ents of 1CCFF.50.55(e).
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- ' 'Wlh 1 QUALITY ASSURANCE AUCIT NO. MSO-6 AUDIT DEFICIENCY SHEET DEFICIENCY NO.
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- 1. AUDITING ORGAraZATICN- ] OEOC [l EN DES CONST
- 2. AUDITED ORG ANIZATION: CONST - Phipps 3end Nuclear Plant & CONST CA STAFF LOCATION: Suracinsville. TN ACTIVITY: Inscection I
- 3. REQUIREMENT (S):
OAP?-17 RO. Quali:v Assurance Records Para 3.3. Inspection and tes: records shall, as a =ininu=, identify the inspector. ..
- 4. DE.:lC!ENCY(S):
Contrary to the above, the inspectors perfor=ing the inspections are not the ones signing the inspection records. This has been confirmed to be a generic l proble= within :his unit. Other units were not exa=ined at this ti=e.
Exa=ple: Concrete Placement form for Work Package No. H006-5C-1 1
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- g. . i% c ,n .-i y CONTACT (S): ~ Richard I.awson a
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1 Tom Evans l I
_ @ SIGNIFICANT C NONSIGNIFICANT Auditor (s): M/- w 1/ , (b & Date: 8 - /5 Ed M. Guity W. K. Anders Audited Organization Representative: MdIMA$/ Date: f/2/PS Titte: d:Se ! C E S W Cr d 7 (Signature signifies understanding. not necessarity, agreernent) ,
TVA 22003 (CEOC 178) . . . .
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- 5. AUDITORS RECOMMENDED CORRECTIVE ACTION (S):
- 1. Co: ply with the established require =ents.
- 2. Review all existing inspection records for the following:
- a. Have inspectors that perfor=ed the inspection sign the inspection records. _
- b. Reinspect or evaluate those that the above cannot be accomplished to verify adequacy of initial inspection.
- 6. CORRECTIVE ACTION PROPOSED AND IMPLEMENTED (including schecuted completion dates.
Include cause if deficiency is identified as significant.)
I CORRECTIVE ACTION VERIFIED:
Name:
Date:
TVA 72005 (OEDC.17S) 2 of 2 Pace
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DEER".ISATICS CF PE?CETA3II.!Tl INFCR.w.ATICN WCRKSHEET FCR
~10CFR50. 55 (e)
Plant ?!r] 2 so. y?c-6 Title 4 ii -._ ~ A. wh.2 se-A NLS Engineer J Z5_ NLS SupervisorQ',*c Reportaole .
C><r Date ,[;t,3 Vd Non-Reportable ( }
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A. The subject condition, had it remainec uncorrected, h k_'_ : 1) have affected adversely the safety of operations of the plant.
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- 3. The item h ) ( e ) considered significant as defined by 10 CFR 50.55(e).
O ig The condition n; resents a significant breakdown of a portion of the Quality Assu:an: Progra= for the plant.
% The con = .an :? presents a signifi: ant deiiciency in finsi design as approved and released for construction such that the design does not conform to (issued design criteria) (criteria and bases stated in the SAR) (conditions of the construction permit).
The condition represents (a significant deficiency in construction)
(significant damage) to a (structure) (system) (component) which will require extensive (evaluation) (redesign) (repair) to meet (issued. ,
design criteria) (criteria and bases stated in the SAR) (conditions ,
of'the construction permit) or to establish the adequacy of the (structure) (system) (component) to perform its intended safety function.
The condition represents a significant deviation from performance specifications which will require extensive (evaluation) (redesign)
(repair) to establish the adequacy of-a- (structure) (system) (component) to meet (issued design criteria) (criteria and bases in the SAR)
(comlitions of the construction permit) or to establish the adequacy of the (structure) (system) (component) to perform its intended safety function.
Explanation: #.e,M prM -ibm ?MN id"-s-
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C. Does the affected unit (s) have a CP? ( ) No-V Does the affected unit (s) have an OL7 K()YesYes K io D. Are there implications to other :aatters not included on the NCR or to other plants?
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E. Basis of reportability statement 4 ft 1/f2 1.n 'J- of.ds > .
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! I. Identification ~
Cc=plete each of the following four statements and give a basis for each,
- 1. The ite= d ( r:.37.c ; Cfailure to c:=pi'/ with the amended Ate =i: I:ie rgy Ac',. s.- ~7$, ICC.2, SNHL, OL, ASLB ruiing or other 1 /
[Sec. 21.1(a)) 3aais: P
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- 2. This item W Qs neQ 'a co=ponent =anufactured or produced offsite by others: mot:r, relay, cable, instru=ent, rack, pu=p, valve, support, vessel, design, analysis, test results, evaluation, er .
Basis: 1 #w em
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(Sec. 21.3(a)(d)(1)]
- 3. U) a portion of the facility constructed or This ite. d D'9 T~A or others:
produced onsite b building, housing, enclosure, vessel, system, earthwork, support, foundation, or other
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Basis: C
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.[Sec. 21.3.(d)(3)J 4 This item (3e-) a circumstance or condition that could contribute to a viola. ion of the plant technical specifications.
Basis:_ - //
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. [Sec. 21.3(d)(4)]
If the response to one or more of numbers I.1-4 is affirmative, go to sections II-V respectively until each section is completed then go to sections VI through X.
SP 301
II. Failure to Co= ply
, g 1. Identify the specific noncompliance indicated in I.1.
\ .
[Sec. 21.1(a)}
Background and/or explanation III. Cc=ponent (=anufactured or produced offsite)
- 1. The co=ponent is (hardware) (software). Descriptica
. (Sec. 21.3(a))
- 2. There (is) (is not) a departure from the technical requirements in a procure =ent document. Explanation (Sec. 21.3(c)]
- 3. The component (has)'(has not) been (delivered into TVA possession, j hardware) (officially transmitted to TVA, software).
-[Sec. 21.3(d)(2)]
- 4. The component (has) (has not) been (installed) (used) (operated).
[Sec. 21.3(d)(2)]
IV. Portion of a Facility (constructed or produced on site)
- 1. Identify the portion of the facility. Description Id-.lma MLA. nGD s '. ) s I, w .1., u !a.a &n dale 4*J, ~ L - Main' .s M e, +A HJw &
. dt. ;. .[Sec. 21.3(d)(3)]
! 2. The portion of the facility constructed by TVA (besh ( as M been transferred to PCTrR. [Sec. 21.3(d)(3)]
The portion of the facility constructed by others (has) (has fp3. not) been (installed) (used) '(operated). [Sec. 21.3(d)(2)]
L V. Tech:Spe: liolatien rm
- 1. The :per: ting I.icense M (has not),been issued. [Sec. 21.2(d)(4)]
VI. Su.marv -
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- 1. 'The ::n:ition % W '(does not) involve a failure to comply, potential techni:21 specifica .il. . ..lada or deficiency within the meaning of 10CIR21. Affirmative if and only if one or more of the following sequences-are all affirmative:
.M d I.1 M _ I.2, III.2, and III.3
_>J.cn I.2, III.2, and III.4
_.5;<. I . 3, IV . 3 M I.4, V.1 VII. Substantial Safety "anard The condition-f. E_; h oes a h nvolve a substantial safety hazard (affir=ative if and only.if the response to one or = ore of sections VII.
I through 3 is affir=ative).
- 1. The conditi:n ( 4 0 $ es no @ involve @ a n: ;; ::fer e e p::u : u: '
l es - ; licensed saterial. 3 asis: '7!--
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- 2. The condition (Je s)' involve a major' deficiency involving ( L ;;n: ; e.c,n) '.in.5. e .. x.) (an: Cushs licensed facilities or material. Basis: -rs' hwJ
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- 3. The condition (does) koes net) involve a major degradation of essential safety-related systems, structures, or components.
Basis: '??, ,c.auh'd ibs s44k. M fa.A e f. JJ
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.'-4 . u- ~,6K VIII. 10CFR50.55(e) Reportability
- 1. This item has been determined C,) -(act :: he) reportable and reported under 10CFR50.55(e). I. the item has been reported under 10CFR50.55(e), give the day of reporting 5-/2.o /a o .
(Sec. 21.11(b)(1)] -
IX. Adequate Reporting-
- 1. The condition.Q (-has:notLbeen adequately reported. Basis:
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X. 10CFR21 Reportability p
- 1. This condition (4,) dreportable under 10CFR21. (Affi=ative if and only if items VI and VII are both affi=ative and item IX is negative)
XI. 10CFR21 Applicability
- 1. This condition (Ss4 is not applicable under 10CFR21. (Affirmative if and only if item VI and VII are both affi=ative).
- 2. The - ador, supplying the component or portion of the facility, (es.) t (is not to be notified of this condition for consideration of reporting generic i plications to NRC under 10CFR21 (specifically 10CFR21.21(b)(3)(VI)}. (Required only if item XI.1 is affi=ative) .
- 3. The written report to NRC filed under '.CCFR50.55(e) (s) (b nM required to contain the information listed under 10CFR2,1.213o)U).
[ Required only if ite= XI.1 is affir=ative. Note - see listing of 10CFR21.21(b)(3) require =ents on definition sheet.]
- i. . Notification of this condition (4s) j required to be sent to the nana!;er of CRDC. (Required on y u ite: XI.1 is affi=ative).
0+finiti m
- 1. Moderate Esposure - radiation doses due to exposure to licrased saterial exceeded (3.$ ares in unrestricted aress) (25 area to plaat personsci).
- 2. Release - radioactive material has been released to an unrestricted ares la encess of 5 0 times the limits of Appendix 8. Table 11. 10CTH20.
- 3. Major :eficiency eundations or circumstances exist which unde? riormal operating conditions ur anticipated transient. could contrshute ta exceed-ing a nafety limit or cause as accident and could result an a moderate exposure.
4 Major Cegrad tion = conditions or cirewastances esist whtch, under oormal operating conditions se accident conditions due to other causes, and in conjunction with an independent stugle, active f ailure, could have resulted la bott a tailure to perform a safety f unction and a moderste exposure.
- 1. 10CTR21.21(b)(3) Requiresents:
(3) The written report required by this paragraph shall include, but need not be lietted to, the followsng information. to the extent knoat (1) Nace and address of the indiv'idual or andivtduals informing the Carnission.
(ii) Identification of the f acility, the activity, or the bast e com.
ponent supplied for such facility 3r even activity within the
"" United States whic*t ' ails to comply or contains a stef ect.
(iii) Identificatton of the firm centructing the f aciltty or supply-ing the banic coeponent which f ails to cumply or contenna a defect.
(iv) Nature of the defect or f ailure to cocply and the safety hazard shich La created at could be created by such defect or failure to ec= ply.
(v) The date on which the information of such defect or fatlere to comply was obtained.
(vi) In the case of a basic component which centains a defect er f as ta to comply the nueher and location of all sugh s oapanents tn use at. supplied for. er being supp1ted for one or more f acilities or activities subject to the regulattoos in this part.
(vii) The corrective action which has been, is betes or will be taken; the ossae of the indivudual or organisation respansible for the action; and the length of tsoe that has been er wall be taken to complete the setten.
(viii) Any advice related to the defect er failure to co-ply about the facility, activity, or basic coeponest that has been, is being, or will be given to purchasers or licensees.
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TENNESSEE VALLEY ACTf0YI'IT ,D L -
To L. M. Mills, Manager, Nuclear Regulation and Safety, 400 CST 2-C / f' s
/ '.p FCO?! Cecrge ?. Dilwcrth, Chier Nuclear Engineer, W10C126 C-7 OV o.uz JUN 181980 i.'/.,
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SU BJ ECT: ?HI??S .3END :u..
UC'.IAR
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..,CU'iITS 1 AND 2 - IMPROPER INSFECTICN RECORDS m.e.e c. .e. . 0. i e e. ~u
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Attached is cur approved report on the subject nonconfor:ance for your forwarding to NRC-CIE Region II. The NRC-0!E Inspecter, R. W. Wright, was notified initially on May 20, 1980. We expect to supply you with additional information by August 22, 1980. If your etaff has any ques:10ns on this natter, have the contact S. R. Stout, extension 4395, who is the contact on this catter for OEDC. An advance copy of the attached approved report was transmitted to J. 5.
Wills of your staff :n June 16, 1980.
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George F. Dilworth '
SRS:C3 Attachment oc (Attachnent):
H. N. Culver, 249A HES-K J. P. Knight, W12330 C-K J. L. Parris, WilC126 C-K H. C. Russell, W5C126 C-K 1 M. N. Sprouse, W11A9 C-K '
MNS:CG -- ' "m 1819n0 l
cc (Attachment): '
W. P. Kelleghan, Phipps Bend CONST (3) l MEDS, E4B37 C-K H. H. Mull, E7324 C-K E30165.04 i
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- .v.s JUN201980 REGULATORY STAFF
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Buv C.S. Savines Bonds Rceularly on the Payroll Savines Plan
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ENCLOSURE PHIPPS BEND NUCLEAR PLANT UNITS 1 AND 2 IMPROPER INSPECTION RECORDS 10CFR50 55(e)
NCR M80-6 f
REPORT NO. 1 (INTERIM)
On May 20, 1980, TVA infor=ed NRC-0IE Region II Inspector, R. W.
Wright, of a potentially reportable condition under 10CFR50.55(e) regarding i= proper inspection records. This is the first interis report en this deficiency. TVA anticipates transmitting the next report on er before August 29, 1980.
Description of Oeficiency Ouring an audit at ?hipps Eend ccnducted by TVA, it was observed that inspectors signing QA docu=ents were r;ot the persens actually ccnducting the inspections. The specific area in which this practice was found was the Civil QC group. Apparently, a lead inspecter was initialling the ecc. crete placement form upon verbal confir=ation from other inspectors. Centrary to the require:ents of OAPP-17, Revision 0, Cuality Assurance Records.
Corrective Action The Civil CC inspection program is being reviewed to determine what enanges are required to bring it into compliance with applicable require =ents. TVA will also investigate this concern at other construction sites. Additional information will be provided in the final report.
E30165.c4
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