TMI-11-060, Response to a Request for Additional Information - Relief Request RR-10-01 Concerning Control Rod Drive Housing Examinations Associated with the Third Inservice Inspection Interval: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
 
(Created page by program invented by StriderTol)
Line 3: Line 3:
| issue date = 04/05/2011
| issue date = 04/05/2011
| title = Response to a Request for Additional Information - Relief Request RR-10-01 Concerning Control Rod Drive Housing Examinations Associated with the Third Inservice Inspection Interval
| title = Response to a Request for Additional Information - Relief Request RR-10-01 Concerning Control Rod Drive Housing Examinations Associated with the Third Inservice Inspection Interval
| author name = Helker D P
| author name = Helker D
| author affiliation = Exelon Corp, Exelon Generation Co, LLC, Exelon Nuclear
| author affiliation = Exelon Corp, Exelon Generation Co, LLC, Exelon Nuclear
| addressee name =  
| addressee name =  

Revision as of 21:54, 10 July 2019

Response to a Request for Additional Information - Relief Request RR-10-01 Concerning Control Rod Drive Housing Examinations Associated with the Third Inservice Inspection Interval
ML110960228
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 04/05/2011
From: David Helker
Exelon Corp, Exelon Generation Co, Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RR-10-01, TMI-11-060
Download: ML110960228 (9)


Text

10 CFR 50.55a TMI-11-060 April 5, 2011 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No.DPR-50 NRC Docket No.50-289

Subject:

Response to a Request for Additional Information

-Relief Request RR-10-01 Concerning Control Rod DriveHousingExaminations Associated with the Third InserviceInspection(lSI)

Interval

References:

1)Letter from P.Cowan (Exelon Generation Company, LLC)to U.S.Nuclear Regulatory Commission,"Submittal of Relief Request RR-10-01 Concerning Control Rod Drive Housing Examinations Associated with the Third Inservice Inspection (lSI)Interval," dated October 13, 2010 2)Letter from P.Bamford (U.S.Nuclear Regulatory Commission) to M.Pacilio (Exelon Generation Company, LLC),"Three Mile Island Nuclear Station, Unit 1-Request for Additional Information Regarding Relief Request RR-1 0-01, Control Rod Drive Housing Examinations Associated with the Third Inservice Inspection Interval (TAC NO.ME4882)," dated March 16, 2011 In the Reference 1 letter, Exelon Generation Company, LLC (Exelon)submitted for your review a relief request associated with the third InserviceInspection(lSI) interval for Three Mile Island Nuclear Station (TMI), Unit 1 requesting relief from Table IWB-2500-1, Examination Category B-O, Item Number B14.10, which requires volumetric or surface examination of the pressure retaining Control Rod Drive (CRD)butt welds in 10%of the peripheral CRD housings.In the Reference 2 letter, the U.S.Nuclear Regulatory Commission requested additional information.

Attached is our response to this request.There are no regulatory commitments in this letter.

Response to a Request for Additional Relief Request RR-10-01 April 5, 2011 Page 2 If you have any questions concerning this letter, please contact Tom Loomis at (610)765-5510.Respectfully, David P.Helker Manager-Licensing Exelon Generation Company, LLC

Attachment:

Response to a Request for Additional Information

-Relief Request RR-10-01 cc: Regional Administrator, Region I, USNRC USNRC Senior Resident Inspector, TMI USNRC Project Manager,[TMI]USNRC ATTACHMENT Response to a Request for Additional Information

-Relief Request RR-10-01 Response to a Request forAdditionalInformation Relief Request RR-10-01 April 2011 Page 1 Question: 1.Regarding page 2 of the relief request, paragraph 2, provide the specific type(s)of examination(s), Le., visual (VT-2), dye penetrant (PT), magnetic particle (MT), ultrasonic (UT), etc., referred to in the statement"...six (6)CRDs not in the periphery were examined" The six (6)CRDs not in the periphery examined in 2001 were examined using the dye penetrant (PT)method.Question: 2.Regarding page 2 of the relief request, paragraph 2, provide the specific type(s)of examination(s), Le., VT-2, PT, MT, UT etc., referred to in the statement,"A review of lSI[inservice inspection]

data for examinations of welds"A","B", and"C" completed since 1986 identified no degradation." Response: Table 1 below provides specific examination history, nondestructive examination (NDE)methods, coverage, and results data for"A","B", and"C" CRD weld examinations completed since 1986.Drawing 1 D-ISI-RC-011 (Figure 1)has been included with this response in order to provide additional information on the weld locations both in terms of elevation, azimuthal and radial location on the reactor vessel closure head.Question: 3.Regarding page 2 of the relief request, paragraph 2, the second sentence states,"There were no examination limitations reported for these welds." Please clarify this statement.

Does it refer to the accessibility of the welds for examination or that there were no defects in the welds?Response: Table 1 has identified that examinations completed were acceptable to ASME Section XI requirements (no degradation was noted).Examination coverage was in accordance with ASME Section XI requirements with the one exception noted in Table 1 and Figure 2 for a 1987 UT examination for weld CRD-151.In this case, an accompanying liquid penetrant examination was completed providing additional NDE coverage for the small area not examined during the UT examination.

Response to a Table 1 CRD Examination Summa Examination Coverage Notation Examination Results indications Response to a Request Relief RR-1 1 3*CRDID CRD lSI WeldExamExam No.*Weld 10**10 No.Year Method Examination Coverage Notation 51 A CRD-151 1987 PT No limitation noted I A 51 I A CRD-151 1987 UT 0°no limitation.

45°one sided limitation (see Fiqure 2).PT No limitation noted limitation noted No limitation noted 1 D-ISI-RC-011 CRD location identification number**1D-ISI-RC-011 Enlargement"A" and Elevation View weld location identification Examination Results indications Figure 1 Drawing 1 D-ISI-RC-011 8 7 6 5 4 3 IIO-:)l:!-ISI-QI 1lSI wan 10.MOo&4A e C CI/l)-I92 0 E (bi-92 65 A CRO-I93 e CMl-I94 C CRo-l9D 0 E RR-I95....CAl>-95 B CRl)-197 10 CRn- 0 Rl+-197 E Rtt-196 67 A, ClIl-I99 a CRIJ'200 C CRl)-201 0 E 1lH-201 1 68 A cRtl-202 B c;llC>-203 C" 1 69 A, B C'lQ-2C6'C'CIlD-207.0 RI!l-206 E 11&-207 SkETCM TNI-I DRIVEw.:,-':- G: ";LlSI wELD 10.MOo=<tM-,&!,""'-'64 56.CRll--166 B CRO-'57 C CIlD-I6801+167-'58 57*

B C CJ:lo-i7l

....17 I 58*CRD-In B CRO-I73 C eRO-17.,:::173'".CRD-I75 B CR[}ol76 C eRD-l77 ,R1+116 I....,71 w.CRD-I?8 B C CRO-Ie<),

...*'80 61 AB C Cll\)ole:l

\

62 ': C CRO-I96.::::85.186 63.A CIIl-187 B CRO'lee C CltO-189R'Hfl>l"'He9 2 L b,.:i.l IMG.-el't.

CJ.C rru.

lHl$"5*:cv......;nr...:-IS[n...........1 ClIO 151.wELO CllO 151 W£L.O 10."" 10.No.11).....,0.MOo 1 37*CllO-IO'i i"6*B¢FI>-IIO B C CRO-I1I C 0'1&+-110 5;., oE Rl+-Itl 38*CRO-II2 147 1 A Clll>--139 ICRll-113 B CIIl-100 CRO-II4&'c CRC>141 0 Rt+ll,3 0 Rt+140 E Rt+-1I4 E*Rt+t04..CRl>-115 I"ll*CRl}-142 8 CRC>-Ii 6 8 CR[)-I43 C CRC>-117 X C CRC>-I44\

o Rl+-l43 D"'I44 40*CRlH 18 49*

B CRll-119 8 CRQ-'.6\C CRl>-120C eRD-I.741*CRC>-121 1110*CRD-148 8 CFl)-I22 8.C¢!I)-I23 C CRll-l$O::.0'1lH-I22/i:JE o;;.i;'42 A*CI1O-12.51.A 88."¢rID-126/'\C CRD-I53 ,

.

43 A CRO;127 52 A CROf B CRD-I28.!CRD-55\CC CRD-i,(,.i-b..A CRD-I3C 53 A CRl>-157 B CfW!3,1 B C'CRD-132 C CRO-I5'9 fi:.

45 A CRO-I33,.CRD-160eRCH61 CRD-1521<1+134/i\Q RIl-l61 1._RH-i35 E R.<-I62 CI/O-I04

'*104 1 iX.'1lIl-105;'

CRXl96 RtI-0e61 a 1M0tf7 ClOD-roo'CRe-IOI 1*;101'-1-" 1*102.CRIJ-oeB CRD-0e9 C RC-<l9C!1i+Oii91";:.Yl YRD-0940Ri+Q98 E Rl-Kl9l.'----;;-J---'-;;;;--;;="'i u_ICRO-IO!CRC>-IOl"tHO?fi::, t.RH-IO I'291 A B C ii*,E

-

c;......HOl..l5l'W.a., Ctl:t)loo14..._..-DWO.NO.*,.

..,8 bTl'1 I...........

5{j'........--..l***B g ii'I'III

!.?':

c;r..GQl L I...I jUVl.JP-"..0/

("""""-"-

y:!'P.>"'t.CS)6.."'" C>><AL.----..4:'ru.x 7 ,Ca),.-IIOLn CT'fP,...p.l__N---t--[WATtoN-viEW I'OA

..

..l.0\.T.lMQ.

so:.

Z TOP VIEW

,-"

...ta" TO..-n*1-4/'I-------.::nJCl.

..........

36 15 10!l\fi./'t 22 58 12 I, 41.6968'.-40 39 26 2'13 6'7.p 62 1" 42 1 2.D 67" 9I\49 44 43 11 B It!".s-4:3021 7-!:I7 n"61 2 I It\+'I 63 0 60* 34 IT 66'"....6*58' 27'" 21'P.31-,.-\53 I.65" 33 1 6-50"*48....20...32..*"" 46 51 18i__w 8A B o c Figure 2 Weld CRD-151 45 Degree Examination Coverage Sketch