ML20148D214
| ML20148D214 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 01/11/1988 |
| From: | Kintner L Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8801250348 | |
| Download: ML20148D214 (90) | |
Text
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JAN 1 1 1999
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Socket No. 50-416 DISTRIBUTION See attached sheet LICENSEE: System Energy Resources, Inc.
FACILITY: Grand Gulf Nuclear Station (GGNS), Unit 1
SUBJECT:
SU WARY CT OCTOBER 15, 1987 MEETING REGARDING INSERVICE INSPECTION (ISI) 0F THE REACTOR PRESSURE VESSEL The purpose of the meeting was to discuss the licensee's request for ISI relief for certain reactor pressure vessel (RPV) welds. is a list of attendees at the meeting. Enclosure 2 is a handout prepared by the licensee to describe ISI requirements for RPV welds, equipment and techniques available for ISI and limitations to GGNS Unit 1 RPV. is a copy of Relief Requests I-00015 and 1-00004.
The licensee had requested relief frcm certain RPV welds in Relief Request Nos. I-00004 and 1-00015.
The staff verbally informed the licensee that there was insufficient infertration provided to grant relief for Examination Category B-A welds in the RPV (Sheet 13 of Enclosure 2).
The licensee described the GGNS l' nit i reactor pressure vessel and access for ISI (Sheet 2 of Enclosure 2). The BWR-6 has access to the 3'-3" annulus between the biological shield well and the RPV.
There is access to the annulus from the top and the bottom so that inspection personnel do not pass through the annulus at the core elevation, where radiation exposure is high.
For the first refueling outage (RF01), the licensee built a man-lift for use during ISI.
However,it was found to be cumbersome and would have resulted in more exposure to personnel than would the use of ladders and scaffolds. Therefore ladders and
(
scaffolds were used during RF01.
The licensee described ASME Section XI Code requirements applicable to GGNS Unit 1 (Sheets 4 and 5 of Enclosure 2). The licensee pointed out that inspections of Category B-D welds cannot be deferred to the end of the 10-year inspection inter-val because of Note 5 in Table 'WB-2500-1 which allows such deferral if examinations are conducted from the inside surface.
However, BWRs are examined from the outside surface because of the cladding on the inside surface.
The licensee described equipment and techniques used in the examinations (Sheets 6-0 and 10 of Enclosure 2).
Typical interferences with equipment associated with a RPV ISI for BWRs were discussed (Sheet 9 of Enclosure 2). Such interferences are due to radiused areas which cause separation of the transducer from the vessel surface (Sheet 38), obstructions such as the vessel skirt (Sheet 39),
vessel nameplate (Sheet 40), nozzles in bottom head (Sheet 41) and insulation brackets (Sheet 43).
The licensee identified the Category B-A welds in Relief Request I-00015 (Enclosure 3, Sheets 1-34) and provided the following comments regarding these welds (Weld locations are shown on Sheet 11B of Enclosure 2).
8801250348 880111 gDR ADOCK 05000416 PDR L
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Seams DA, DB, DC and DD These welds in the bottom head are more than 50% inaccessible because of cerrponents installed in the bottcm tud (centrol red drives and in core instrunents).
t Seam AD This weld is 1.4% inaccessible because of the naneplate welded to the vessel.
Seam AE This weld is near the vessel flange which prevents examina-tion from the flange side.
Seams BB and BC Cutouts were made in these vertical welds for two nozzles, which prevent examination of the weld for about 15 inches above and below the nozzle centerline.
Seam BA A nozzle prevents complete examination. The licensee noted that Figure 11 in its submittal was incorrect and would be replaced.
Seams BH, BJ and BK Nezzles prevent complete examination. The staff noted that percentage of weld that is inaccessible was not reported in the submittal and requested that it be provided.
Seam AG Relief had been requested for this top head weld because of its proximity to the flange.
However, further consideration indicates that this weld can be examined from the inside surface, because the head is not clad.
Therefore, the request for relief from ISI requirements of this weld will be withdrawn.
Seams BM, BN, BP AND BR These longitudinal welds intersect with the circumferential weld that joins the shell ring to the flange.
Therefore, the portions of the welds near the flange cannot be fully examined from the flange side.
Seams DH, DJ, DK, DM, DN and DP Relief for these welds in the top head was requested because thEy intersect the head-to-flange weld.
However, as in the Seam AG weld, they can be examined from the inside surface of the head. Therefore, the request for relief from ISI requirements of these welds will be withdrawn.
Relief Request No. I-00004 is reproduced on Sheets 35-41 of Enclosure 3.
This RPV shell-to-bottom-head weld cannot be examined by automated equipment now avail-able because of the curvature of the bottom head.
Radiation in this area is high and exposure of personnel for manual examination of all the weld would be very high. As an alternative, the licensee is proposing to examine that area which had three recordable indicaticns in the preservice examination. The staff has no need for further information on Relief Request No. I-00004.
The staff requested that Relief Request I-00015 be revised to make the changes indicated above, i.e., delete requests for relief for top head welds and provide a corrected Figure 11. The staff's review will include the revised request.
6 Lester L. Kintner, Sr. Project Manager Project Directorate 11-1 Division of Reactor Projects I/II cc:
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r MEETING SUWARY DISTRIBUTION:
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c NRC PDR Lccal PDR PD21 r/f E. Adensam Project Manager Lester L. Xintner 0GC-B E. Jordan J. Partlow NRC Participants ACRS (10) cc:
Licensee / Applicant Service List j
5 o-ATTENDEES NRC SERI MEETING 10/15/87 NAME AFFILIATION W. Keo NRR/ DEST /MTEB
- 1. Bukulmez NRR/ DEST /MTEB/ Assignee M. L. Crawford SERI, Nuclear Licensing G. C. Sandlin SERI, Nuclear Licensing R. S. Lewis SERI, Nuclear Plant Enc.
S. C. Mortenson General Electric - NEB 0 J. W. Self General Electric - NEB 0 P., A. Courtney SERI Supv.(NDE)
M. Hum NRR/HTEB F. Litten NRR/MTEB W. Hazelton NRR/MTEB L. Kintner NRR, Project Manager
4 5
NRC - SYSTEM ENERGY RESOURCES, INC.
REACTOR PRESSURE VESSEL VOLUMETRIC EXAMINATION LIMITATIONS MEETING
,Bethesda, October 15, 1987 I.
INTRODUCTION (Crawford)
II.
DESCRIPTION of GGNS RPV (Sandlin) 9 III.
CODE AND REGULATORY COMMITMENTS (Sandlin)
IV.
CODE AND REGULATORY EXAMINATION REQUIREMENTS (Lewis)
V.
EQUIPMENT USED IN EXAMINATIONS (Self/Mortenson)
VI.
EXAMINATION TECHNIQUES (Lewis)
VII.
TYPICAL INTERFERENCES ASSOCIATED WITH A BWR EXAMINATION (Lewis)
VIII. AUTOMATED SCANNERS AND THEIR INTERFACE WITH PLANT (Self/Mortenson)
SYSTEMS AND STRUCTURES IX.
RELIEF REQUEST NO. I-00014 (Courtney/ Lewis)'
X.
RELIEF REQUEST NO. I-00015 (Courtney/ Lewis)
XI.
REVISION TO RELIEF REQUEST NO. I-00004 (Courtney/ Lewis)
XII.
SUMMARY
(Crawford)
J14 MISC 87101301 - 1 f
L
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II.
DESCRIFITON of GGtIS RW o
BWR 6, MARK III CDtTIAD@iDTP o
'IHE RW IS CONSIRUCIED OF (SEE FIGURE 1):
o' 4 Shell Rings o
Ibp and Bottaa Head o
35 Full Penetration Welded Nozzles o
4 Partial Penetration Welded Nozzles o
S Shell Circumferential Seams o
14 Shell Vertical Seams o
4 Bottcra Head Seams o
7 Top Head Seams o
32 Nozzle to Safe End' Welds o
8 Safe End to Safe Erd Extension Welds o
RW GJISIDE DIAMETER IS 22' 2" o
BIOLOGICAL SHIEID h"AIL INSIDE DIAMETER IS 28' 8"(SEE FIGURE 1) o CLEAPANCE BEIWEEN THE RW AND SHIELD WAIL IS 3' 3" o
BIOLOGICAL SHIEID WAIL CDtTPAINS PDIEIPATIONS WTIH MOVEABLE DDORS EVR ACCESS TO RW NOZZLES MiD PIPDiG.
o THE BIOIDGICAL SHIELD WAIL TERMINATES AT ELEVATION 173' 3",
(SEE FIGURE 1).
o ACCESS TO THE MOUIDS AREA IS PROVIDED THROUGH A MANWAY AT ELEVATION 124' 6", AND FRCti 'IHE TOP OF THE SHIEID WAIL.
o A PERSOt0IEL MAN LIFr WAS DISTALLED DJRDIG RF01 TO MDTIMIZE STAY TIME Di THE MihWIUS AREA.
o TD410PARY SCAFFOIDDiG MID IADDERS ARE UTILIZED WITHDI THE M01UIDS TO ASSIST ACCESS.
nrepres page 3 g
s
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III.
CODE AND REGUIATORY COMMITMDTTS o
10 GR 50.55a(g)(4) (i) o BASE CDDE: ASME SECTION XI 1977 EDITION, THROUGH AND DiCIDDDG SU!EER 1979 ADDDTDA, WITH I.ATER EDITIONS AS SHOWN BEIIH:
1980-WDTIER 1980 ADDD1DA, IWB-2500-1, EXAM CATEGORY B-F 1983-SUMMER 1983 ADDEMR, IWB-2500-1, EXAM CATD3ORY B-D (Relief Request I-00013) o RBIJIATORY GUIDE 1.150, REVISICH 1, "ULTRASONIC TESTDG OF REACIOR VESSEL WEI.DS IIJRDG ht.KVICE AND D1 SERVICE DISPECTICU" (Plurides additional goihlines on inspection of RPV welds, UI) o IURD3 0619, REVISION 1,
"IMR FEEIMATER lOZZIE AND CDtTTROL ROD DRIVE PEIURN LDIE !OZZIE CRACKDE" (Provides additional guidelines on inspection of W nozzle inner radius, CRD return line is capped on unit I) nrepres page 4 3
o l
I l
i IV.
CDDE AND PB3UIATORY EXAMINATION RECUIRDE2TPS o
RD3UIATORY GUIDE 1.150, REVISION 1, RD2UIRES:
o RW'S to be pericdically examined by volumetric techniques in accordance with Section XI of the ASME Code, which is incorporated by reference, o
Section 3.0 of the RB3. Guide provides reference to ASME XI, INA
- 2000, for scope ard extent of the ultrasonic entinations.
1 l
o ASME SECTION XI i
o INA-2000, provides general requirenents and examination
- methods, o
IWA-2200, requires the examinatior.
methcds in table IWX-2500-1 to be used as specificd.
o IWA-2400, provides two schedules for choice, program A or B, GGNS utilizes program "B".
o IWB-2412, "INSPECTION PROGRAM B", requires examinations to be ccr:pleted in accordance with IWB-2412-1 (see figure 2),
exmpt for those examinations that may be deferred until the end on an interval.
o Table IWB 2500-1 identifies welds ard cmponents by grouping them into examination categories, ard further divides them by item no.
5
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nrepres page 5 k
s IV.
CODE AND RD7JIATORY EXAMINATICH RD"UIRDETIS (continued) o Table IWB 2500-1 identifies 3 examination categories associated with volumetric examinations of a BhR RW:
- 1) B-A, Pressure retaining welds in reactor vessels
- 2) B-D, Full penetration welds of nozzles in vessels
- 3) B-F, Pressure retaining dissimilar metal welds o
Enhtion Category B-A (see figure 3) o Shell welds, circumferential and longitudinal o
Head wlds, circumferential and meridional o
Deferral of certain "B-A" welds until the end of the ten year interval is possible, (see figure 3).
o Examination Category B-D, program B, (see figure 4) o Nozzle to vessel welds o
Nozzle inner radius (NUREG 0619) o Due to exanination techniques of a BhB, defert '1, is not allcued (see figure 4 notes) o Examination Category B-F, (see figure 5) o Nozzle to safe end welds o
Deferral is not allowed (see figure 5) i o
IWA-2232, requires class 1 and 2 vessel wlds in ferritic mat'l greater than 2 in.
in thickness to be examined in accordance with Article 4 of ASME, Section 5.
i nrepres page 6 5
4 V.
ECUIM2TP USED IN EXAMDIATIOfS o
AUIQ4ATED RW INSPECTIGI SYSTDiS o
Blue Box (General Electric) o Ultra Imge, Smart Ur System (General Electric) o Blue Box Remote Inservice System o
Portable system utilizing vessel and nozzle scanners, o
The basic scanner asse:rbly package consists of a lucite block containirg the ultrasonic transducers. Channels are provided allowing water to flow under the transducer package to serve as an air tight couplant (see figure
- 6).
o The scannirg vehicle is attached to the vessel wall by four sets of individually mounted magnetic wheels.
These wheels can be rotated to various positions on the RW (see figure 7).
o Because the scanning vehicle is operated behird the shield kall, various guidance systems are used to control the direction of the scanners Irvement. Among these are; an accustic triangulation system, distance ard direction encoders and TV monitors.
o The nozzle scanner is assembled on a portable track that attaches to the nozzle. The */ehicle utilizes magnetic wheels and rotates around the razzle (see figure 8).
o Ib examine the required
- volume, the scanner is manipulated across the vessel areas to the extent possible.
o Ultra Image (see figure 9) o The Ultra Image has been utilized to examine the nozzle to safe end ard safe end to safe end extension welds.
o Scanner assembly attaches to safe end or pipe by a track
)
asserrbly (see figure 10).
o Scanning is acccrplished similar to nozzle device die' W above.
nrepres page 7 b
i
v.
axrImnir USED IN EXMDaTIGIS (continued) o TPRISDUCERS FOR BCTIH MANUAL AND AUIURTED SYSIIMS o
traneA m ns are used to direct the ultrasonic sound into the examination volu:ne.
o Typical transducer characteristics are:
o Ncninal frequency of 2.25 Mhz o
Cccron angles are 0, 45 and 60 degrees..
o Transducers are connected to the instrumnt through a series of coaxial cables, o
Liquid couplants are utilized betwen the transducer and the scanning surface for maintaining an air tight contact.
o Typical sizes of a transducer are shown in figure 11.
i l
nrepres pge 8 1
VI.
EXAMDIATION TECWICUES o
ASME SECTION V, ARTICI.E 4 o
The volume of weld and base mat'l to be examined shall be as required by the referencing code section (ASME, SEC. XI, IWB-2500-1, see figures 12 thrtugh 18) o Two angle beams, having ncmtinal angles of 45' and 60' with respect to a perpendicular to the examination surface, shall be generally used.
o REG. Guide 1.150 also states that at least one beam angle should be perpendicular ( 15') to the weld / parent material interface (see figure 19).
o scanning of the examination volume shall be carried out from both sides of the weld on the same surface (see figure 20) o the exah. tion volume shall be scanned with angle beam search units directed both at right angles to the weld axis (T-scan) and along the wld axis (P-scan), each examination shall be performed in two directions.
o T-scan, Ultrasonic beams must pass through all the weld metal.
The adjacent base metal in the examination volume nist be ccmpletely scanned by two angle beams, but need not be ocmpletely scanned by both angles fremt both directions (see figure 21).
o P-scan, Search units shall be aimed parallel to the axis of the weld.
The ultrasonic beam must pass through all of the ex2Lhtion volume frcm1 two directions at 180' to each other (see figure 22).
o O'
or straight beam e.xaminations shall be performed on the entire volume of weld metal and adjacent base material to the extent required by the referencing code section.
nrepres page 9
4 VII.
TGICAL D7FERFERDiCES ASSOCIATED hTIE A EER D:AMDIATION o
AIHHOUGH 'IHE FUNDAMENTAL DESIGi OF 'IEE MARK ITI COtfrADMUTP ELIMDaTED 'IHE DuueudNCE POSED BY 'IHE BIOIDGICAL SHIELD h%LL Di PIOXIMITY 'IO 'IEE RPV, INHERENT DTIERFERDiCES IIJE 'IO RW DESIGi DUIIBTIS FULL ULTRASONIC EXAMDaTION (no Relief Request have been generate:1 as a resu't of shield wall interferences).
o RPV DESIG1 DTITM'ERDiCES DiCIUDE 'IHE FOLICWDIG:
o Radiused areas wLeh interrupt trandar interface with the scanning area. 'Ihis interruption causes a separation between the tran d a r ard the vessel surfaca air tight contact (see figure 23).
o Inherent obstructions that prevent placing the transducer at required pcsitions to obtain the eMry "W" dimersions for examining the full examination volume (see figure 24).
o RD2JLA'IORY GUIDE 1.150 DOICATES 'IHAT hEDI 'IHE REQUIRED VOIUMES HAVE !K7T BEEN EXAMINED FOR 'IHE REASONS IlSTED BELOW, 'IEE IlCDISEE IS REQUIRED 'IO AITLY FOR RFTM Di ACCDRDANCE WTIH 50.55a of 10 CFR.
o Near-field or other surface effects o
Volumes near interfaces between cladding and parent retal o
Volunes shadomd by laminar material defects o
Volumes shadwed by part gecmetry o
Volu:nes inamible to the transducer o
volumes affected by electronic gatirrj o
Volumes near the surface opposite the transducer 1
4 i
nrepres page 10 p
t VIII.
AUIO,!ATED SCANNERS AND DEIR IhTERFACE WIDI PIAh7 SYSTD!S AND SEUCIugS o
BASED ON DE USE OF DE RBK7FE 'IRACKLESS SCANNER IDR VESSEL hEDS AND 'I1E N0Z2LE SCANNER, AIDNG WITil TIE IMPIn@ ACCESS OF DE MARK III Q)hTAINMENT DESIGN, DE VEBSEL WEIDS HAVE ADEQUATE ATESS FOR OIYrIMU)!
EXAMINATIONS.
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AXIAL W ELD 9.
NOZZLE / VESSEL WELD 10.
SKIRT / VESSEL WELD FIGURE I
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L i TABLE IWB-2412-1 INSPECTION PROGRAM B inspection Period. Minimum Maximum i inspection Calendar Years of Examinations Examinations Interval Plant Service Completed, % Credited, % 1st 3 16 34 ' 7-50 67 10 100 100 2nd 13 16 34 17 50 67 20 100 100 3rd 23 16 34 l 27 50 67 30 100 100 4th 33 16 34 37 50 100 40 100 i l FIGURE 2 Ib
^ S78 TABLE IWB.2500-1 S79 EXAMINATION CATEGORIES EXAMINATION CATEGORY 8 A PRESSURE RETAINING WELDS IN, REACTOR VESSEL Estent and Frequency of Esarnination Esamination 1st Deferrat of Item Parts Requirements Esamination Acceptance Inspection ".Msive laspection Inspection to No. Esamened Fig. No. Method Standard Interval e a. 2nd. 3rd, 4th* End of later,at 81.10 Shett Weids votumet rec IW8-3510 A:t welds 8 Permiss bte 81.11 C.rcumferent.al IW8 25001 One besteine region weid',8 81.12 Longitud.nal IWB 2500 2 One beit!&ne reg.on weld 8.' 81.20 Head Welds Volumet tsC IWB3510 Accessiblea per,.gg.cie 81.21 C.rcumf erential IWB 2500 3 iength of Accessible length of one weldr (bottom nead) 3 81.22 Meredsonal IW8 2500 3 an weeds Accessible lengtn of one weldr ld 81 30 Snert to-Flange Weid IW8 25004 volumetr6c IW8 3510 Weid8 Weld 8 Pertness bw' C 81 40 Head to Flange Weld IWB2500 S Volumrte.c IWB 3$10 Weld 8 Weld 8 Perm ss.cres ~ and iuriare ~x 81.50 Repa.r Welds * = 81.S1 8eitlene region IWB 25001.2 Volumetric IWB3510 All weld One weld repair area Permess. bee y repaar areas j v.. Ex i C ) h.,, V. 1 C C j K ~2 4 w --Z Z l l v. I. i 1 NOTES-(1) Material (base metal) weld repairs where repair dep' 4 esteeds 10% nominal of the vessel waft. Bettline region entends for the length of the vessel thermat shecid, or eri the absence of a thermal shield, the effeClive length of reactor fuga atements. If the location of the repair is not pesillweiy and SCCwate87 f anowfi, then the individual shell plate. forging or sheti course cent a6ning the repair sha,' ke included. (2)inciudes essentiany 100s of the weid iengsk
- r (3) Sciect we d located at a design structural discontinu.
- y. if any.
r (4) The inst.any selected *eios are to be reesamined during successive inspect 6on intervais. y tSIIf esanwnations are conducted from flange f ace, the remaleting volumetrtC emarrienations ter3 pared to be cos ' 1ed from westel wall eney og performed at or near the end of each anspectioninterval. ' ~ FIGURE 3 1, 4 4
S78 TABLE IV '500-1 (CONT'D) y EXAMINA.vN CATEGORIES Q EXAMINATION CATEGORY 8-D, FULL PENETRAfl0N WELDS OF N0ZZLES IN VESSELS-INSPECTION PROGRAM 8 h< W Entent and Frequency of Esaminstion Lw Enamination 1st Deferral of item Parts Requirements Enamination Acceptance inspection Successive Inspection Inspection to No. Enamined Fig. No. Method $tandard8 jnterval8 Interva's, 2nd. %d, 4the End of Intervat Read 9r Vessef 83 90 Nonle to Vessel Welds IWS 2500 F Volumetrec IWS 3512 All nearles' Alt nonles' Permisstle* B 3 100 Nonle Insede Radeus Secte IWB 2500 7 Valornetric Iws 3512 2.11 nonles' Att nonies' Pressurifer B3110 Nonie to Vesse: Wesos IW8 25007 Volumet re. IWB 3512 Asl norries' AH nonies' Permesse:e* 83 120 Nonle insade Radius Section IWS 2.*00 7 Votumet ac IWB3512 Au nonics' AH nonles' Steam Generators (Pesmary $sde) 7 83230 Nante to Vessel Welds IWS 2S00 7 Volumetric IWB 3512 As nonles' AH nonles' [ Perm.gs e * [ 83 140 Nonie Insede Radius Section IW5 2500 7 Voturnetrec IWB3512 Aal ~~ies' AH nonles' l y: Heit Esc *iangers 2 (Primary Side) y g B3150 Neule to Vessel Welds IWB 2$00 7 Votomet ric IWS3512 AN nonles' . Au nontes' Permissibiet ~ 83160 Notzie Inside Radows Secteon IWB 2500 7 vosumetrac M S3512 Au nonless AH noutes' l E E Z e t NOTES: (1)inciudes nonic to essei netd and adsacent areas of renie and vesset. = (2) 5taadards appry te ferret.c steel nontes..th enternat austenstat steet ctaddeg. (3) At least 25% but not more than 50% (cred.ted) of the nontes shalt be esam ned by the es. J st impection period and remamder by the end of e enspettson ontgeval (4) at least 25% Dut not more than 50% (credited) of the nontes shall be esamsped by the end cf 1st enspection peceod and
- he remamder by the end of 3rd enspecteen p#rsod of each enspecteor mterval.
I ($)If esamenataons are Conducted from 6nsade the component and f me nonle wehlf is esamened by strasght beam ultrasomC method from the nonle bore the rema n.no esamations requ. red te be conducted from the shed inside d.ameter may be performed at or near the end of each enspectica 6atervat. FIGURE 4 i - ~ ~. - - - ~ ~ ~ ' ' ~ 1
r W80 TABLE IWB-2500-1 (CONT'D) EXAMINATION CATECORIES EXAMINATION CATEGORY B-F, PRESSLIRE RETAINING O!S$tMILAR METAL WELDS Extent and Frequency of Enamination Examination 1st Octerral or lie.1 Parts , Requirements / Examination Acceptance inspection Successive Inspection tuspect.on to No. E xamined Fig. No. Metho1 Standard Interval' Intervsts, 2nd, 3rd, 4th' End of Inter =at 1 Reactor Vessel B510 Nominal Pepe Size > 4 in. Nott e-to-Safe End iWB-2500-8 Volumetnc IW B-3514 All welds' ' All welds' 2 l Butt Welds Surface i j 05.11 Nomg.sl Pipe Site < 4 in. I Nozzle ro-Safe End IW8-2500-8 Surface IWB-3514 All welds' 3 All welds' 3 e i Butt We'ds a I B 5.12 Nottle-to-Safe End IWB-2>00-8 Surface IWB.3514 All we'd5 8 All welds' 3 8 Socket Welds .e ? i i l i } i 4 i I Ii NOTES: I ) E=amenations are required of each safe end weld in each loop and connec'ing branches of the re '.1or coolant svstem-l (23 for the reactor vessel nozzle safe ends, the cuaminations may be performed coinCH3cnt with the vesset nozzle examinatiora required by Imawnation Category B-0. (3) Includes d,ss m. tar rnetal welds betneen combinations of: (a) carbon or low alloy steels to hsh alloy steels; (b) carbon or low alloy steels to high nickel alhys; (c) high alloy steels to high nicliel alloys. 1 FIGURE 5 i v. j
t f SHEAR WAVE.8ACKAGES es. g r -x r 1
- m=
's Ogc Jty 1 . CD s NORMAL P. SC AN vi w
- g AE PULSER u
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- 4
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- c we)
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O l DEFERPAL SLM&RY WEID SFR4 Dtf rtyAL ALIfWED nozzle to shell welds:
- N1A, N1B,
- N2A, 10
- N2B, N2C,
- N2D,
}O
- N2E, N2F,
- N2G,
}O
- N2H, N2J,
- N2K, 10
- N2M, N2N,
- N3A, 10
- N3B, N3C,
- N3D, 10
- N4A, N4 B,
- N4C, 10
- N4D, N4E, N4 F, 10
- NSA, NSB,
- N6A,
}O N6B, N6C,10, N8, 10
- N9A, N9B,
- N10, 10 N16
}O shell welds: DA, DB, DC, CO, YES AD, BB, BC, BA, YES BH, BJ, BK, 94, YES BN, BP, BR, YES ' nozzle to safe end welds: i
- N1A, N1B, N2A
}O TERJ
- N2N, N4A
}O THRU
- N4F, NSA,
}O
- NSB, N6A,
- N6B, 10 N9A, N9B,
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BNC CONNECTOR I I L DIRECTS O* Oo LONGITUDINAL I" 0 135" m TRANSDUCER IN WATERIAL SOUND WAVE ~ i Y 1 i i l l BNC CONNECTOR 3 45* 2 2 ), / 3 ) OIRECTS 45' I / SHEAR WAVE f / 1 IN MATERIAL o i 0 / 1 ~* ,1 4S* j 7, j'7 " 9 D ~ 2 c r c 1 L i3 rx SERRATED EDGE (FOR DAMPENING) j EXIT POINT \\ / / ) 2 DIRECTS 600 o SHEAR WAVE g[ / IN M ATERIAL ,/ R = = eaa / 7, 1 y (Ci i. Y L.- is A ?> m \\ EXIT POINT FIGURE 11 p
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T_. r- / ! .z. \\ E I 19 el t* 7' / ) i o E kw f uj d u n Y' /s /k E% 5 b h r-EX4M. VOLUME / q@ 5 f i Em E-r-g-u fr ~y O m2 ' AREA SCANNED AS REQUIRED i En ' TO EX AMINE VOLUME E-F-G.9 ' 2 e 5 ep \\ v 5 s
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Hl QUIRiiMENTS FOR CLASS I COMI'ONI.NI'S Fig. li\\ ll.2.W-4 I e i l l 1 i i i I 3 e t i i i l I i l 1 I m i I i I \\ i / I I t g A B -7 ti 3 -iN o. 4 o {pg -CIRCU M F E R E NTI AL g 4 T xw -lN v I _ g' C 0 ( t ) 5 CL ADDING NECTION XY W77 FIG. lWB 2500-4 SHELL-TO-FLANGE WELD JOINT S78 W18 FIGURE 15 1
Fig, lu ll 2.04 SliCTION XI - DIVISION I / \\
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REQUIRiiMiiNTS I OR CLASS I COMPONIENTS Fig, l u s.2500-8 , SURF. EX AM. ARE A' A-8 \\ io PROFILE OF VALVE 80DY, 1 [/ PUMP CONNECTION J VESSEL N0ZZLE, OR in? In. A,s /* B 9 v v 4 INNER SURFACE NOM. PIPE SIZE LESS THAN 4 IN. , SURF. EXAM. ARE A A-8 PROFILE OF VALVE BODY, ^ 4 VESSEL N0ZZLE, OR <- l ;-+ <-l -+ PUMP CONNECTION 2 EgA /* A A, / ', 0 s s v v l n h v W_ s tv f v v' p E a { kin in. u -iro L EX AM. VOL.m rC-O - E-F ' NOM. PIPE SIZE 4 IN. AND GREATER S79 FIG. !WB 25004 SIMILAR AND DISSIMILAR METAL WELDS IN PlPING FIGURE 18 \\
W O l. 2. l l / / r iso 2 15 / V / N / N/' WELD 1.1/2 VEE PATH
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EX AM.VOL. A-B-C-D v2, v2 k -e A.m a6 B t + 1 2 P O C D = = = / e/ l,/ 60 * // /' J, w l FOR A I" THICK WELD,"W" IS2 2.125" FOR A 6"THICK WELD,"W" IS x IO-l/2" FOR A 45* FOR A 6"THICK WELD, M" IS = 14-l/2" FOR A 60* FIGURE 21 4
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s Rl L-y u GRAND GULF NUCLEAR STATc.. DISMICE D!SNQ! mgm INSERVICE INSPECTION SEcrIQ: 4 8J3/Mj^/#E TEN YEAR PRDGRAM l RELIEF PKUEST GWiD GULF NUCLEAR STATIG! UNIT 1 PM.TTT RD;UEST NO. I-00015 PAGE 1 of 3 INSERVICE INSPECTION OF REACIOR PRESSURE VESSEL j WELDS I. Cccponen' : Reactor pressure vessel (RPV) v.a.eunents, welds c and u:estiated base material identified in table 1 j of this relf ef request. II. Ccde: 'Ihe unit 1 reactor pressure vessel was designed and fabricated to ASME Section III, class 1 regairenents. Applicable inservice inspections are to be perforred in ac x>rdance with Regulatory Guide 1.150 Revision 1 and ASME Section XI, 1977 Editim with Adden3a thrcogh and including Su=cr 1979. Also, Relief Requast No. I-00013 perr.its the use of ASME Section XI, 1983 Edition with the Sum 1983 Jddenda, Figare IWB-2500-7(b) for identifying the Ccde regaired exarination volu: c. j III. Ccde Regairements: Tchle IWB 2500-1, Examination Category B-D, B-A i and B-F, regaires sp2cified volumes to be exarined volumetrically at specified periods during the ten f year interval. Included in this vcluze is vaging degrees of base raterial adjacent to each weld that also reqaires exandnation. IV. Inferration to Due te geometric configurations of the GG!S Unit 1 support the reactor, certain ccde reqaired exarination deterranation that volumes, as depicted in ASME Section XI, cannot be the ccde examined to the extent of obtaining full ccde require:mnts are coverage. Table 1 pru/ ides a listing of the irpractical: affected ccrcponents and reactor preesure vessel welds with a detailed description of the cause and degree of the limitation. j Relief Request Nu-ber I-00014 prcr/ ides engineering rational addressing the limitations associated with the nozzle to vessel welds. 'Ihe discussions provided prior operating plant experience to justify that no further e.xamimtions were nemy and ad:litionally this was justified by reccgnizing that the feedwater nozzles are the lirdting case. Although 100% of the ccde volumes were not exar,ined for the nczzle to vessel welds, sufficient exardnation cwerage was obtained to detect any potential ccacking. ' l
GWiD GULF NUCLEAR STATCN D! SERVICE DISPECTIO!i PIqtJIFan'Is INSERVICE INSoECTION SECTIO!! 4 8l3'Og',ff TEN YEAR PROGRAM RELIEF REQUEST GPE'D GUIE NJCLEAR STATION UNIT 1 PD.TTT REQUEST NO. I-00015 PAGE 2 of 3 IV. Inform tion to A study of the welds listed in table 1 has support the shown that these weld locations are also detemination that b:nnded by the feethater nozzle discussions. the code ne stresses due to any expected loadirgs and reqairenents are corditions at these locations are b:nnded by irpractical: those at the feetater nozzle locations. (continued) Supporting the concept of the bounding is the fact that no indications have been found at any of the partially examined locations. In addition, it should be noted that a partial examination of each weld was obtained which included either all or a portion of the reactor pressure vessel inner surface. V. Specific relief Pemission is regaested to Wom ultrasonic regaested: exa-inations within the limitations described in table 1 of this relief regaest. VI. Reasons kty relief Relief as described within sht ii to granted should be granted: for the follcuing reasons: 1. h e entire reactor pressure vessel was subjected to an AS!G Section III hydrostatic test after fabrication. 2. We entire reactor pressure vessel will be subjected to system leakage test at each refueling outage and a systen hf e tic test each ins M ien intA % in accortance with the liquireme.'fa of ASME Section XI. 3. S e subject welds were vclumetrirally examined in accordance with ASME Section III during fabrication. f>
GRAND GULF NUCLEAR STA70N DISNCE DiSPEGQi NCE INSERVICE INSPECTION sEcrIoti a 8l3/i"//,f",[.. TEN YEAR PR'X3 RAM Pri m REQUEST GPJJiD GJLF h"JCLEAR STATIQi U!IIT 1 PFTM RIUJEST No. I-00015 PIE 3 of 3 VI. Reasons why relief 4. Sem is no history of service induced should be granted: flaws in these areas of the reactor pressure vessel
- other than those of the feedeter nozzles disleed in Relief Regaest Neber I-00014.
5. Se areas of the reactor pmssure vessel being examined are the limitire areas. 6. n e potential for initiation and propagation of crackirg has been discussed assuming both fatigue and stress corrosion crack.ing redads s. It i was concluded by the use of lir.iting analyses results perfomed for the ) feedwater nozzle blend radii, that cracking is unlikely at Grand Gulf 1 nozzle / vessel weld locations. In fact, even if it was hypothesized that these postulated cracks went urdetected, a crack length of 58 inches was reqaired before rapid crack grel were to occar during norml operation. It is unlikely that cracks of this size would go undetected. W erefore, a significant leak before break mrgin exists. l VII. Altemate testing: None g4.
GRAND GULF NUCLEAR STATION IFEERVICE INSPECTIOti REQUIRFMDTPS INSERVICE INSPECTION SECTION 4 RELIEF RIGIESP Sf/JLE,"," TEN YEAR PROGRAM GRAND GUIF NUCIFAR STATION l UNIT 1 RELIEF PEOUFSr 110. I-00015 TABTE 1 PAGE 1 OF 7 l M HEID_I.D _CATECORY _ITD4 f30. DE"fRIPTIOff OF_EXAMINATI_ON_ LIMITATION 2 Nozzle IU B-D B3.100 %e PU nozzle contains 121-3/8" diameter holes drilled and tapprxl 3-1/4" dem into the nozzle face. %ese holes pment primry ultrasonic waves from reaching the bom region of the nozzle inner radius (see figure 1). Nozzle N8 B-D B3.100 Same as the 10 nozzle. Seams; B-A Bl.22 %e RW bottom head is u.uhucted of four side plates and one center plate which are joined by four welds. Following preservice DT, DB, examinations, a total of 255 holes were bored into the bottom DC, DD head ascenbly into which the following cxmponents were installed: 193 control rod drives, 58 incore tubes, 2 N15 drain lines,1 N11 and 1 N18 corn differential pressure lines. In addition to these, the RW skirt is welded approximately 6 indles below the seam that attaches the shell to the head and an insulation bracket is mounted approximately 4 to 6 inches below the support skirt to bottom head weld that further restricts access to the four welds. the following portions of each weld is accessible for examimtion: DA - 44.4%, DB - 44.47,, DC - 17.2%, DD - 17.2% Seam; B-A Bl.11 we vesec1 mme plate is located at 0* on the vessel,12 inches above the centerline of weld "AD". We plate has a 7 inch radius, AD is constructed of 1 inch thick carbon steel and is weld <xl to the number 4 shell ring with a 1/2 inch fillet weld. We location of l the plate prevents full weld coverage with the 60 T-Scan (angle 4 beam transverse to the weld axis) from two directions.
cRAND GULF NUCLEAR STATION INSEINICE INSPECITON REQUIRENF2 TIS INSERVICE INSPECTION SECTION 4 srsrru mur sesacts, mc. TEN YEAR PROGRAM RELIEF RDOUESP GRAND GU1F FUCIFAR STATION UtTIT 1 RELIEF RFUJF5P FO. I-00015 TABIE 1 PAGE 2 OF 7 @_DS WEID__I. D._ CATEGORY JTFM_flO. _ DES _GI_PTI_ON OF DOWINATION IMROt] Seam; B-A Bl.11 %e limitations exist for a total of 12 inches, 6 inches each Ao side of code plate centerline (see figure 2). continued Saam; B-A Bl.30 %e "AE" weld seam joins thd number 4 shell ring to the RIV AE flange. %e physical configuration of the flange prec1tx3es cxxplete examination coverage of the code recpired volurm. %e code voltne is examined with limitations from the shell side only, access from the flange side of the weld is totally prohibited (see figures 3 and 4). We following provides the details of the volinnes examined conpared to the code rrquired volume. 2 Code Volume: 84.35 inches 2 W1d Volume: 15.06 inches Examination Coverage Obtained: code weld volgime volp in-examined in examinal 0* 42.47 50.3 12.58 83.5 45*-T 66.56 78.9 14.04 93.2 60*-T 71.48 84.7 14.09 93.5 45*-P 42.47 50.3 12.58 83.5 60*-P 42.47 50.3 12.58 83.5 Y, 4 O
O O GRAND GOtf NUCLEAR STATION Iry;FRVICE INSPECTION REQUIRNTIS INSERVICE INSPECTION SEcrION 4 NSc$.% TEN YEAR PROGRAM RELIEF RIUJFSP GRAND GUIF NUCIFN1 STATION UNIT 1 RELTEF RD}JIST NO. I-00015 TABTE 1 PAGE 3 OF 7 _ CODE hT'ID_I. D. CATDGO_RY TITN_NO. DFT_4RIIFION OF EXAMINA'RON_LIMI_TATION Nozzles: B-D B3.90 %e N4 nozzles are located on shell ring number 3,17 inches.from N4A, N4C the N13 nozzles. %e close proximity of the N13 nozzles limits N4D, N4F the automated examimtion to a "W" dimension of 14 inches for approximtely 44* of the N4 nozzles circumference. %is limitation prevents the 60* T-Scan from examining all of the requirrd axle volume (see figure 5). Supplemental mnual 60-examimtions would obtain coverage of the limited area, however due to the radiation levels encountered at' the first refuel outage (3 R/HR) and the fact that the volume not examinal by the 60* scan is examimd by the 45* T-Scan, 45* and 60* P-Scan and the 0* scan, it is not practical to perfom the supplemental examinations. Nozzles: B-D B3.90 Examination of 4 recirculation inlet nozzles is limited due to N2D, N2C interferences from the two N9 Jet Punp Instrumnt nozzles located N2J, N2K approximately 14 inches from the affected N2's. Ris portion of the circumference that is not accessible to the automted scanner is examimd mnually, but the 14 inch limitation prevents complete coverage with the 60* T-Scan (see figure 6). Nozzles; B-D B3.90 %e two N9 nozzles are located between and just below four of the N9A, N90 N2 nozzles creating the same limitations for the N9 nozzles as discusral above for the N2's (see figure 7). Smms; B-A Bl.12 % e two welds are vertical seams in the ra ber 1 shell ring. BU, IC After the performnoe of preservice, cutouts wre made into the two vertical seams for installation of two N2 nozzles. i
canno cutr noctr_AR STATION INSERVICE INSPECTION RQJIRNPS INSERVICE INSPECTION SEcrION 4 N'5NcS.7$ TEN YEAR PROGRAM RELTCF RWIFSP GRAND CUIT NUCIEAR UPATION l UNIT 1 t RELIEF RWJFSF NO. I-00015 TABIE 1 PAGE 4 OF 7 _ COW EEID_I.D. _ CATEGORY _ITDT NO. DESGIMON OF EXAMINARON_LIMITATI_Ot! D Seams; B-A D1.12 mis resulted in partial removal of the vertical scam weld metal and replacement ith nozzle to vessel weld metal (oorle category BB, DC B-D) as shown i figures 8 and 9. Geometric configuration is sur-h continued that the nozzle weld and seam ds are one ir *ba name for mrtain areas. %e same limitations that prew. examinations of the nozzle weld from the nozzle side also prevents the examination of the vertical seam from the nozzle side (reference relief request I-00014). We limitation encompasses an area of 15.5 inches above and below the N-2 nozzle centerline. We 0* does examine across the weld and a portion of the base metal on the nozzle side (see figure 10). A portion of the weld and nozzle side base metal was not examined with'the 45* and 60* T-Scans from the nozzle side (see figure 9). A portion of the base metal on the nozzle side was also not examinod with the 45* anr160* P-Scans (see figure 11). %e same conditions dancribcd for the "BB" and "DC" seams exist Seam: B-A Bl.12 except that the cutout in for a N1 nozzle and the limitation is DA for the 45* and 60* P-Scans from the nozzle direction caly (see figt .,gg{ le r 3 shell Scams; D-A Bl.12 %e 3 searx., are longitudinal welds located on ring. Due to the location of various nozzles, limitations have 111, ni, been created that ptrvents the 60* T-Scan from examining the full BK code volume of the weld metal. De close proximity of the nozzles associated with the geometry prevents an adequate placemnnt of the probe to obtain the code required coverage (see figure 12). %e below table providos the restricting nozzle anr1 tho 1innar N inches of weld that is subject to the limitation. 4
O GRAND GULF NUCLEAR STATION RUNCE DISPECTIOT NTFS INSERVICE INSPECTION SECTION 4 RELIEF RIUJEST $8Cjf% TEN YEAR PROGRAM GRAND GJIE NUCIFJ\\R STATIOff INIT 1 RELIEF RDQUFST 10. I-00015 TABIE 1 PAGE S OF 7 _ COD _E hu D_I.D. CATIEORY _TITNlJO. _ DES _CRIPTIOi OF_ EXAMINATIOT 1TMITATI_ON 3 Scams; B--A Bl.12 It11d_I.D. Rostrictirn Nozzle Inches Limited DI, IU, HI NSA 31 BK IU N6C, NSB 70 continuM BK N13D 18 Seam; D-A Bl.40 RW seam "1G" joins the RW top head to the top head flange. Due to the geometric configuration of the flange, the accessible ac volume that is available for ulatrasonic examination is limited as described below and shown in figure 13. 2 Total Code Volume 44.3 in 2 'Ibtal Weld Volume & HAZ 9.8 in2 Weld Volume Limited to One Directional Scan 6.5 in2 Total Base Material 35.5 in 2 l Base Material irwrecessible (geometric configuration) 4.1 in Note: Dimensions are taken frun a cross sectional view of the code volume. Nozzle to D-F BS.10 Due to the geometric configuration of the nozzle to safe end assmbly, full code coverage cannot be obtainM frun two safe directions. Examinations are performed with either shear wave, welds:NIA& refracted longitudinal wave or both due to the cocplex bi. and N1B,N2A trimatellic structurers of the nozzle to safe enr.1 assably. thru N2N, N4A thru N4 F, NSA&B, NGA,IEC N9ASB
GRAND GULF NUCLEAR STATION INSERVICE INSPECTIOi NITS INSERVICE INSPECTION SECTION 4 'l'/Me$"% TEN YEAR PROGRAM RELIEF REQUEST GRAND GUIF IUCIEAR STATION UNIT 1 RELTEF RFUJEST 10. I-00015 TABIE 1 PAGE 6 OF 7 _QDE EELE I.D _CATDGORY XfFM_to. PMIETION OF EXAMINATION IRgTATI_Or] 2 Nozzle to B-F B5.10 Curstly, examinations are performed utilizing automted systems, the coverage of an automated examination is more safe limiting than that of a manual examination. 'Ibe coverage report welds:NIA& provided in figures 14 through 19 indicates the additional N1B,N2A coverage that can be obtain6d in the event future examinations thru N2N, N4A thru am performed with manual techniques. N4F,NSA&D, N6A,B&C l N9A&B continued: Seams; B-A Bl.12 'Ihese four longitudinal welds are located in shell ring number four arxl intersect with circumfemntial weld that joins the shell IN, BN, DP, BR ring to the vessel flange (seam AE). 'Ihe vessel flange does not 4 permit full ultrasonic coverage of the code volume when performing the 45 and 60* P-Scans freq the flange surface. 'Ihc P-Scan is performed with the sound beam oriented parallel to the weld axis, and the transducer maneuvered over the entire length of the weld except at the interrAxtion to the AE seam (see figure
- 20). At a crocs sectional view of the weld axis, the code volume is approximately 1,256.5 scpare inches, the unexamined areas are 52.7 sq. inches or 4.2% for the 60* and 30.1 sq. inches or 2.4%
for the 45*. 'Ihese areas are examined by both the 45* and 60* T-Scan from tuo directions and a P-Scan from the Shell surface. ,s
GRAND GULF NUCLEAR STATION DEFRVICE RFIMOi 6N INSERVICE INSPECTION sEcrIOrt 4 $$$I.'%. TEN YEAR PROGRAM PEI.YEF RTUJFST GRAND GUIF NUCIEAR STATION IRIIT 1 RELTEF RFUJFSP ?O. I-00015 TABIE 1 PACE 7 OP 7 WDE WETD I.D. _CATFTORY _I_T_FM 10. _D@gR_TPTIai OF EXAMINATIOT LTMITATION - Scams; b-A Bl.22 'Ihese six meridiml welds are located in the top head arrl III, DT, DK intersect with the cirannferential weld that joins the vessel top fri,Iti, DP head plates to the vessel head flange (scam AG). 'Ihe vessel head flange does not perinit sufficient access to perform a ti a directional P-Scan examination of the intersection atw. At a cross sectional view of the weld axis, the code volumr is approximately 414.0 square inches, the unexamined anas are 6.8 sq. inches or 1.6% for the 45* and 10.78 sq. inches or 2.6% for the 60*. 'Ihese areas are examined by both the 45* and 60* T-Scan from two directions and a P-Scan fran the shell surfaen (see figure 21). I i 4
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GRAND GULF NUCLEAR STATION DISERVIG RISMON WE INSERVICE INSPECTION SECTION 4 ll'%cC,'% TEN YEAR PROGRAM RELIEF REQUGT "v, NO ZLE i N4 NOZZLE THIS AREA.lS LIMITED TO"W"OF I4" APPROX. 44* DUE TO THE LOCATION i4" =i OF THE NI3 NOZZLES ~ n FIGURE 5 SCALE: I /10 PAGE I OF 2
GRAND GULF NUCLEAR STATION nGERVIG UGNQi NITS INSERVICE INSPECTION SEcrION 4 %l$jj,'% TEN YEAR PROGRAM RETJEF RFQUEST N4 NOZZLE 't LIMITED TO"W"OF 14" FROM APPROX. 44' DUE TO LOCATION OF N13 NOZZLES. I ,\\ I ~~ t I f o / Nf3 l ' W, I I e 45' d VESSEL A I i ( I/2T_ WELD 1 I i FIGURE 5. i N4N ARE A NOT EFFECTIVELY SCALE I/4 \\N EXAMINED BY GO' T-SCAN PAGE 2 OF 2 D
O cnano cutr NUCLEAR STATION DISERVICE RIGITCTION RBQUIRF14EUIS INSERVICE INSPECTION SFrPION 4 N'sNc$.",'. TEN YEAR PROGRAM RELIEF RDQUEST E N2 yjZZLE NOZZLE THESE ARE AS OF THE EXAMINATION VOLUME WERE SUPPLEMENTED BY A MANUAL EXAMINATION x N_ / A N / / /N N \\ / f i,.N 's'. / \\ j N2 N / LIMITED SCAN FOR APPROX.40* Y DUE TO LOCATION OF N9 NOZZLE f LIMITED SCAN FOR APPROX.40 DUE TO LOCATION OF N9 NOZZLE N9 NOZZLE FIGURE 6 SCALE: 1/10 PAGE I OF 2 C 4
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GRAND GULF NUCLEAR STATCN DISETCE DISPEGO'; Wm.nr INSERVICE INSPECTION SECTIO:t 4 llj'$j;f1'. TEN YEAR PR'X3 RAY RELIEF RDtf7R T N i I l 1 WELD BB I -) I i I I l e.s:," A i l I l l i l l t i l i 1 l l \\l l l 1 i l iI / I I n2E curouT 20" 14.i" l i l i I I y \\ \\ \\ 17.6 9" l i 9 WELO WIDTH \\ I I I i i \\ / I l I FIGURE 8. i/2T-q 4 1-
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cRano cutr NUCLEAR STAsION IfGI3NICF. ITEPECTIOtr RIUJIRDID.% INSERVICE INSPECTION SECTION 4 ll,'[c'^s.,N. TEN YEAR PROGRAM RWEP W e SCAN PATHS OF BB WELD FOR P-SCANS OTILIZING 45* 8 60* WFLD E N2-E NOZZLE [ ...;'f 1 i[ l I l l C s l l l. I I i X l i I l l o 1/2 t I/2 t 4 FIGURE II. AREA NOT EX AMINED DUE TO NE AR FIELD EFFECTS.
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OUE TO GEOMETRIC CONFIGURATION S$o \\ WELD VOLUME LIMITED TO N-ONE DIRECTIONAL SCAN ar*N \\\\ ~~~ BASE MATERIAL IN ACCESSIS ,,y/Q FOR Oc SC AN w 0 ,/p/ / / / / ! 1 4 l l c, g4.75 SPN'E 0\\U \\ FIGURE 13 9p
cue outr nuctea sinc" D!SDWICE DISPECTIO!i REgJIpa.:nns INSERVICE INSPECTION SECTIO:1 4 llj'fLjf",(( TEN YEAR PROGRAM PrTrrr REgJnsT GPJJiD GJLF NUCLEAR STATION UNIT 1 Prr TTT PRUEST NO. I-00015 N1 RECIROJLATION U M NOZZII 70 SAE DID WELD LIMIIATIONS T. FLOW = 45'SW NOZZLE i SAFE END I INCONEL BUTTER NI Total code volu ne at a cross sectional view is.95 in2 o Auto ated techniques utilizing a 45' shear wave obtains two directional coverage of an area egaal to.17 in o Also, a 45' and 60' refracted longitudinal (RL) wave is utilized that obtains one directional coverage of the entire code volume scanning from the nozzle side. o The cross hatched area received the one directional coverage frun the nozzle side, the re:ainirg area was examined fren two directions utilizing the shear wave. Panual examinations will provide two directional coverage of the veld o and nozzle base raterial, the availabh "W" dirension on the safe end side of the weld is insufficient to obtain full coverage of the safe end raterial. FIGJRE 14
GAAND GULF NUCLEAQ STATP p g g pg g g; g INSERVICE INSPECTION sEcrIa7 4 8/,'g^,f",$ TEN YEAR PR') GRAM priTre p p m GPA'O GUIE NUCUR SIATIO:2 UhTI 1 FFTTTT PEUEST ID. I-00015 N2 RECIRCULATIQi DilET }OZZIE 'IO S7d2 DD k' ELD LIMITATIGG l // FLOW = SAFE END NOZZLE INCONEL BUTTER ,/ INCONEL BUTTER a. ~ 60*RL / /4 5' R L I t i 2 Total code voltrne at a cross sectiomi view is.846 in Autcrated techniqaes utilized a 45' and 60' RL wave for the o exa,ination of the N2F ard N2H to obtain cxrpls ' e cxde voltrac coverage frcxn one direction with bcth angles. 'Ihe rtrnaining N2 rozzles (A,B,C,D,E,G,J,K,M,N) wert: e:Cuned o ccrpletely frcxn one direction with only the 60' uus to excessive noise received with the 45' trarMmm Panual exa:nimtions can provide two directioml onerage of the o area represented by the y32% for the 60' and.642 inhatching, this ku1]d irprge total code coverage to.271 in or or 75.6% for the 45*. If the presently available 45' transtacers are irproved to rotaco o noise levels, future exa:nimtions will include the 45' fer inproved cxwcrage. FIGURE 15
GRAND GULF NUCLEAR STATCN p g g pg g gy g INSEfulCE INS ECTION sEcTIon 4 g3' ;g",$ TEN YEAR PROGRAY pn m RKUEgr ,g GRAID GUIS NUCEAR STATIO:: UhTT 1 FNM REUEST 10. I-00015 N4 FEED WATG Di1Er ICZZE 'ID SAFE DO WEI.D LDITATIO!G l l 1 SAFE END NOZZLE FLOW INCONEL BUTTER INCONEL BUTTE $ '60*RL /45'RL i Total ccde volu e at a cross sectional vies is.70 in2 o Autcr:nted tecimiqJes utilizirg a 45' and 60' RL wave obtaiaed cmerage of the ccde volu e frcra cne direction only (safe erd side). o Manual exa:ninations will prtnide coverage from two dire;tions for d the area identified above by the cross hatching,.36 in or 51.4% of the total code volu o. FIGURE 16
cwo outr NucuAR sTATc ' DMCE Disma: gas INSERVICE INSPECTION SECTIQt; 4 l8,rf;g",$ TEN YEAR PROGRAY prim pgm 3 GFJJ?D Gulf NUCIIAR SIATION U!,T T 1 PDM RD;UEST NO. I-00015 N5 CDRE SE1AY 'IO SAFE E?D WEI.D LNQ;S l ll SAFE END N0ZZLE FLOW /, INCONEL BUTTER N,H /# A> 60* R L 45'RL Total code volu o at a cross sectiomi view is.72 D;2 Automted techniqaes provides a 46' shear wave from the safe end j side ogtainire two dirwtiod ca/erage of an arn egaal to .33 in or 46.6% of the total code volume. Also, a 45' ard 60* RL wave emination frcn the safe end side is perfoM obtaining one directional coverage of the total code volu-e. Area receiving exarination frcn one direction only is 53.4% of the code volume. Ma:Tc.al eminations with PL wave will ircrease two directiomi gL ccr/arage by 18%. FIGUPI 17 g
GR A*C GULF NUCLE 44 STATON pg g p;gggg; INSERVIE INSPECTION SEcIcon 4 8'3rg;y',. TEN YEAR PROGRAY prim pgt;tgr [ GRAND GJIT ITJCEAR STATION UNIT 1 P"TF RD2UEST 10. I-00015 N6 RESIDJAL HEAT RDDVAL / 101 PRESSURE 'CDRE DUECTION SAFE D?D TO IDZZE KT1D LIMITATIONS SAFE-END NOZZLE FLOW I-N INCONEL BUTTER l
- GO' R L
/ 4 5' R L l l 2 Total code volume at a cross sectional view is.93 in l Autmated techniqaes provides a 45' shear wave exa.imtion from the 2 safe end side obtaining two direedonal coverage of.34 in c7 36.6% of the total ccde volume. g Also, 45* and 60* RL wave examimtions performed from the safe end h side obtairs one directional coverage of the total ccde volume;2 area receivirg one directional coverage only is 63.4% OR.59 D; of the code volume. Paraal Mmtions will ircrease two directioml coverage by 9.7% l hf FIGUPI 18
GRAND GULF NUCLEAR STATON p g ggg pg g gy O INSER/lCE INSPECTION SECTION 4 nesx*:ts. "x TEN YEAR PRIAAM Pnm RD;UEsr; s rs t'" '^' GRA!O GUII 1,"JCIIAR STICION U!Tr 1 FN TTT RD;UEST 10. I-00015 i N9 JEr R11G D;STRA'HEATION lOZZLE TO "SITE DO WELD FLOW NOZZLE SAFE-END INCONEL BUTTER [- \\ 45'RL l Total code volu c at a cross sectioml view is.29 in2 Autmatal techniqaes provides a 45' shear wave exardmtion fror, the safe erd side obtainity two directiomi ccnerage of.10 in2 or 34.5% of the total ocde volure. Also, 45' ard 60' RL wave exardnations performed frun the safe end L side obtains one directiomi coverage of the total coda volu c; area receiving one directional coverage only is.19 inE or 65.5% of the total code volu e. 2g Kvraal eyimtions will increase two directional ccnerage by 27.5% or.08 in. }b FIGURE 19
9 GRAND GULF NUCLEAR STATION IfGFJNICE INSPDCTION RDQUFIB4EtTIS INSERVICE INSPECTION SECTION 4 5l5${;(('d TEN YEAR PROGRAM FELTEF RFWFSP AREA OF LIMITATION7 d AE SEAM TYPICAL FOR VERTICAL SE AMS BM,8N,BP, BR. TOTAL WELD VOLUMN FOR P-SCAN SO.lNCHES 1,256.5 z j l SO. INCHES 52.7, P-SCAN 60* AREA MISSED,4.2 % h B"SEAM SO. INCHES 30.I, P-SCAN 4 5* AR E A MISSED, 2.4 % zo l 160.843" p 4"RING SHELL PLATE LD N VERTICAL SEAM WELD VESSEL FLANGE E 's METAL 'N No 'N 9 -60* Br.1, BN, B P, BR. m 45 x N s N N s \\ '[, s if rs N } ARE A NOT EX AMINED WITH 45* OR 60* SOUND WAVE FROM FLANGE. ARE A NOT EXAMINED WITH 60* SOUND WAVE FROM FLANGE. FIGURE 20 U w
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GRAND GULF NUCLEAR STATON IFSERVlCE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 srstru catm TEN YEAR PROGRAM RELIET REQUESTS REVISION 2 sis an zcs,18. PAGE PANE 1 of 6 GRAh*D GULF NUCLEAR STATION UFIT 1 REQUEST FOR RELIEF NO. I-00004 INSERVICE INSPECTION RPV LOVER HEAD-TO-SHELL VELD A-A I. Component: The lover one-half of Unit I reactor nressure vessel lover head-to-shell veld A-A. II. Code: The Unit I reactor pressure vessel was designed and fabri-cated to AEME Section III, Class 1 recuirenents. Applicable inservice inspections are to be performed in accordance with the ASME Section XI, 1977 Edition with addenda through and including Su==er 1079 Addenda. III. Code rec.uire=ents: The upper portion of this veld is a circumferential shell veld and is required to be volueetrically examined for essentially 100% of the veld length once during the first 10-year inservice inspection interval, in accordance with ATME Section XI, Table IVB-2500-1, Category B-A, Itec Pl.11. The lower portion of this veld is a circumferential head weld and is thus required to be volumetrically exanined for essentially 100% of the veld length, once every 10-year in-service inspection interval, in accordance with ASME Section XI, Table IVB-2500-1, Category B-A, Itec Bl.21. IV. Infer =ation to The A-A veld joins the lowest ring of circumferential shell support the deter-plates on the reactor pressure vessel (RPV) to the RPV bottet eination that the head and is located 80.66 inches above vessel zero. The code requirement bottoe of the core is located at 216.31 inches above vessel is impractical: zero. The veld is approximat.ely 135.65 inches below the bottoe of the core. In addition, the veld is approximate 1v 91.2 inches below the centerlines of the recirculation pump suction nozzles (N1 nozzles) and approximately 98.4 inches below the centerlines of the recirculation pump discharge nozzle (jet pump suction nozzles-N2). The upper portion of the A-A veld is a typical circumferential shell veld. Automated ultrasonic examination procedute and equipeent have been developed which vill permit the required inservice volumetric inspections to be perforced remotely. The lover portion of the A-A veld is a circumferential head veld. Due to the curved geometry of this portion of the veld, auto =ated means for ultrasonic exacination of this portion of the veld have not been developed; thus, this portion of the veld cust be ultrasonically exacined by manual procedure. e 32>' KVPMSP 151 1-00006
GRAND GULF NUCLEAR STATCN INSERVICE INSPECTION REQUIREMENTS INSERVICE INSCECTION SECTION 4 8J8/Uj $ TEN YEAR PROGRAM RELIE' REQUESTS REVISION 2 FAGE PAGE 2 of 6 GRAND GULF NUCLEAR STATI0h UNIT 1 REQUEST FOR RELIEF NO. I-00004 (Continued) INSERVICE INSPECTION RPV LOVER HEAD-TO-SHELL VELD A-A IV. Information to The containment design of Grar.d Gulf Nuclear Station Unit I support the deter-is designated Mark III. A feature of this design is that an mination that the annulus space of approximately 30 inches width exists between code requirement the reactor vessel outer circumference and the biological i~s impractical: shield vall inner circueference. The examiners must enter (continued) this annulus space to perfere manual ultrasonic exacination of the A-A veld. Contact radiation levels on, and area radiation 3evels near, the recirculatinn inlet and outlet nozzles, recorded at other BWR plants during the first three to six years of reactor operation have been in the range of 200 cR/hr to 2000 mR/hr. We anticipate the area radiation levels at the A-A veld to be approximately the same as those near the nozzles due to their proximity to each other, the constricted space in annulus, the proxicity to the core, which is treated as an area source, and possible reflection free the metallic insulation on the inner surface of the biological shield vall. For purposes of estinating exposure, we have assured an area radiation level at the A-A veld of 800 mR/hr at the end of the first 40 month inservice inspec-tion period. The level is expected to increase as the plant ages. Due to the large arount of veld area required to be examined and the nature of the radiation sources in the area, shielding is not practical. Such shielding "culd need to shield the entire body, would be heavy and difficult to move and would require significant exposure to erect and move. Based on the results of the examinations performed during the preservice inspections, it la estimated that 16 man-hours vill be required to perform the required manual ultrasonic examinations. This time does not include the time required for personnel to enter and exit the annulus space; however, it does include an allowance for the extra time required by personnel due to wearing protective clothing and for mapping three recordable, but not reportable indications, which were found during preservice inspections. We esticate that the manual ultrasonic examination of the A-A veld vill require approximately 12,800 milliren of personnel exposure. Ertry and exit of the annulus region plus support personnel exposure during the examinations is estimated to require an additional 1,700 nilliter for a total estinated exposure of 14,500 cilliren. '} }, NWFMSP 151 1-00]Q4
GRAND GULF NUCLEAR STATON INSERVICE INSFECTION RFOUIREMENTS INSERVICE INSPECTION SECTION 4 WM TEN YEAR PROGRAY RELIEF REQUESTS REVISION 2 PAGE GRAND CULT NUCLEAR STATION PAGE 3 of 6 trNIT 1 REQUEST FOR RELIEF NO. I-00004 (Continued) INSERVICE INSPECTION RPV LOWER READ-TO-SHELL WELD A-A V. Specific relief Permission is requested th delete all ultrasonic inservice requested: inspections of the lover one-half (Category B-A, Item Bl.21 requirement) of the entire circumference of the A-A veld, except as noted under alternate exa=inations. VI. Reasons why relief Relief fro = the ultrasonic inservice inspections of the A-A 4 should be granted: veld is requested for the following reasons. l. The upper one-half (Category B-A, Ite: Bl.ll) of the A-A reld was examined by remote ultrasonics as a preservice inspection in accordance with ASME Section XI and no re-cordable indications were found. 2. The lover one-half (Category B-A, Itee Bl.21) of the A-A veld was examined by manual ultrasonics as a preservice inspection in accordance with ASME Section XI and a total of three recordable, but not reportable, indications were ' found. The examination report shovi that the indications are outside the heat affected zont of the veld. 3. The entire reactor pressure vessel was subjected to r hydroctatic Pressure test in accordance with ASKE Section III. 4 The upper one-half of the A-A veld vill be examined by recote ultrasonics during the first inservice inspection interval in accordance with the requireeents of ASKE Section XI. 5. The entire reactor pressure vessel vill be subjected to a syste= icakage test at each refueling outage and to a system hydrostatic test each inservice inspection interval in accordance with the requirements of ASME ( Section XI. VII. Alternate Testing: Instead of examining the entire lover one-half of the A-A veld, we propose to perform manual ultrasonic exacinations only of the section of the veld in which the three recordable indications were found (approximately a 12 inch by 12 inch surf ace ag, oncep inservice inspec_ tion interval.f % manual exa=' nations v11 M erforced to the extent possible in consideration with the discussed limitations. With the vessel support skirt being located 6 inches below the A-A seat, the uaxirnim obtainable "V" A. "31 NVPMSP 151 I-00aD-
I GRA'O 0015 NUCLEAR STAici INSERVICE INSPECTION REQUIREMENTS INSERVi2 INSoECTION SECTION 4 U3'&P,ff: TEN YEAR PROGRAM RELIEF RE00ESTS REVISION 2 PAGF GRAND GULF NUCLEA. STATION PAGE 4 of 6 D UNIT I REQUEST FOR RELIEF 60. I 00004 (Continued) INSERVICE INSPECTION RPV LOVER HEAD-TO-SHELL WELD A-A dirtncion is niso 6 inche', this prevents both the 60' s VII. Alternate Testing: (Continued) and 45' T-Scans from examining the total veld volume (see figure 2). The three recordable indications were record et in_ che base __ material of _the head utfifzing thg, O' se n,.,)'We vill monitor the size of the indications and, i any of the indications appears to be increasing in size, we vill evaluate the indications and take appropriate actions, which ray include ultrasonic examinations of other sections of the veld. The anticipated exposure for perforring the alternative examination would be less than 500 nillirem. l 1 9f NVPMSP ISI 1-00004 1 )
i GRA*C GULF NUCLEAR STATON INSERVICE INSPECTION RE0VIRD!ENTS INSERVICE INSPECTION SECTION 4 8l8,M"$ TEN YEAR PROGRAM RELIEF REOUESTS REVISIO" 2 pAGE l GRAND Gl'LF Nt' CLEAR STATION PACE 4A of 6 l' NIT I RE0lTST FOR RELIEF NO. I-00004 (Continued) INSERVICE INSPECTION RPV LOVER HEAD-TO-SHELL VELD A-A VIII. NRC Discussion The following stateeents, conclusions, recom=endations, Statements etc. have been adopte('by the NRC and are to be considered part of this request-for-relief's approval: Since a 12" by 12" patch of the A-A veld can be examined with manual volumetric methods without excessive radiation exposure and since monitoring an additional 12" by 12" patch where no flavs had occurred prior to PSI would give a ceasure of the condition of the retainder of the veld, we recommend that an additional 12" by 12" patch of the A-A veld be volumetrically examined. The second or reference patch should be at least 90* from the patch containing the flaws. Therefore, relief is reco= mended as requested provided: (0) The upper portion of the A-A veld is volumetrically examined over 100% of the veld length, (b) The ennual volueetric exaninatione, over a 12" by 12" area, of the reportable defects and a reference patch in the lover nortion of *.he A-A veld are performed and evaluated, and (c) the Code-required eymte: orecaure tests are performed. ] The rt. quested relief has been reco== ended baced on the iepracticality of conducting manual ultrasonic examinations in radiation fields estimated to exist in the examinations area. If actual radiation fields are lover, for exaeple if the core were removed, teore extensive examinations should be conducted. j It is further recot=nended that inprovements in automated ) ultrasonic inspection technology be conitored and that the entire length of the lover portion of the A-A veld be examined if techniques become available during the 10-year inte n*al. 3f in n;u na 1-u m- -l
~ l GRAND GULF NUCLEAR STATc4 INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 $3/"//,f,$ TEN YEAR pry) GRAM RELIEF FEOUESTS REVISION 2 PAGE PAGE 5 07 6 GRAND GULF UNIT ONE BOTTOu HE AD TO RING er i i l
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.a s -m/"" RiNo a i to I BOTT0fd HE AD qq ("' Bottou HLA0 S ktRY an / Percentage of Code Required ',31ume (CRV) that will be examined being planned ) volumetric methods for Seam Mr l Upper Pertion: 100 UT by remote ultrasonics. 1.over Portion: 1.43% UT Sy Manual ultrar.onics due to perservice of three (3) Recordable Indicatior.s, fb 1 PT TP.SF ISI 1-00004 I
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