ML20091E300
| ML20091E300 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 08/31/1991 |
| From: | Maurice Heath, Stamm M GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20091E282 | List: |
| References | |
| NUDOCS 9111190218 | |
| Download: ML20091E300 (125) | |
Text
{{#Wiki_filter:g ,y m m -t-o e '&-p p BOSTON EDISON COMPANY PILGRIM NUCLEAR GENERATING STATION INVESSEL VISUAL INSPECTION EIGHTH REFUEL OUTAGE l FINAL REPORT GEINSPECTION SERVICES m":na uma, O PDR
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<1 PILGRIM NUCLEAR POWER STATION BOSTON EDISON COMPANY IVI REACTOR INTERNAL COMPONENTS RF0 8 - AUGUST 1991 FINAL REPORT
'l GE NUCLEAR ENERGY 999 WEST VALLEY ROAD WAYNE, PENNSYLVANIA 19087 (215) 975-6000 5
M .t . PREPARED BY: MICHAEL HEATH APPROVED BY: MIDHAEL STARM LEVEL III PROJECT MANAGER INSPECTION SERVICES
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v INDEX FINAL REPORT FOR INVESSEL INSPECTIONS , OF REACTOR INTERNA" COMPONENTS PERFORMED AT PILGRIM NUCLEAR GENERATING STATION BOSTON EDISON ELECTRIC COMPANY SECTION I WORK SCOPE SECTION II SUM'iARY SECTION III DATA SHEETS SECTION IV TRAVELER SELTION V PROCEDURE 1 l l 1 l (O v
I e, cc PILGRIM NUCLEAR POWER STATION INVESSEL VISUAL INSPECTIONS i EIGHTH REFUELING AND INSPECTION OUTAGE SECTION I WORK SCOPE c e l i l l C 9 l l l
PILGRIM NUCLEAR POWER' STATION C.O BO8 TON EDISON COMPANY-IVI REACTOR INTERNAL COMPONENTS RFO 8 - AUGUST 1991 WORK.8 COPE The invessel visual examination performed during RTO 8 included selected portions of the following components: VESSEL CIADDING TOP GUIDE OF CORE-GUIDE RODS AND BRACKETS JET PUMP ASSEMBLY AND BRACES , SHROUD SHELF AND WELDS SURVEILLANCE SAMPLES AND BRACKETS -h --
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CORE SPRAY SPARGERS CORE SPRAY PIPING FEEDWATER.SPARGERS
. CLOSURE HEAD CLADDING AND STEAM DRYER BRACKETS STEAM DRYER SUPPORT-BRACKETS SRM IRM DRY TUBES TOP GUIDE BOLTING FLANGE SEALING SURFACE CRD RETURN NOZZLE--
' CORE PLATE STEAM DRYER.
MOISTURE SEPARATOR The examination'also included. areas that were examined as surveillance'of indications detected during previous outages. ,
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l_.._..__ _: . . _ , . _ . _ _ _ . . - _ . . _ . ---- 6 e PILGRIM HUCLEAR POWER STATION INVESSEL VISUAL INSPECTIONS EIGHTH REFUELING AND INSPECTION OUTAGE SECTION II
SUMMARY
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l PILGRIM NUCLEAR POWER STATION
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BOSTON EDISON COMPANY (J(y / IVI REACTOR INTERNAL COMPONENTS RFO 8 - AUGUST 1991 EIAMINATION BUMMARY During the period of May 28 through June 14, 1991, GE Nuclear Energy personnel performed Invessel Visual Inspections on internal components of the Pilgrim Nuclear Power Station RPV. This section details the techniques used and the results of the inspection. EIAMINATION TECHNIQUES The examinations were performed using Remote CCTV Equipment, underwater lighting, hand held camera mounted lighting, and VHS videotape recording equipment. System resolution was verified using an 18% neutral gray card with both a 1/32" line and a 1 mil wire. Resolution was verified on each videotape recorded. 7_s (L)1 EZAMINATION RESULTS AND RELEVANT INDICATIONS There was no evidence of degradation of the RPV Internal Co:ponents detected during this examination other than the indication noted on the steam dryer. There were two (2) cracks recorded on the dryer leveling screws. The first is located at 35' by the lifting lug and is approximately 2" long. The second is at 215' and is approximately 1 3/4" long, reference Tape PILG-91-15, tape counts 00 through 178. Both leveling screw tack welds were reported cracked in 1987, reference Tape $1. An underwater veld repair was also done in 1987. GE Nuclear located in San Jose, CA has recommended to run as is. Reference GE letter " Evaluation of Steam Dryer Leveling Screw Crackc", June 19, 1991. Reference GE NCR #E-68645-008. Previous data recorded an indication approximately 3" long on B Core Spray Sparger between the "T" box and the B 25 nozzle. No indications were recorded this outage. This area was then wire brushed and videotaped, reference Tape PILG-91-14, tape counts 00 through 1415. Ito indications were detected. An extensive review of the previous data shows the following: No indications were recorded on videotape #1 by ( .' Southwest Research in 1987. {V) 2, ,,cc,
k The 1980, 1981 and 1984 videotapes show linear indications of different lengths, sizes and orientation which could possibly indicate scale or some other phenomena, camera resolution and film quality was excellent in 1987 and 1991. Previous film quality was not as good, and in some cases poor. The following set screws on the shroud side of the jet pumps had a gap. Jet Pump (2 Jet Pump (20 LOOSE PARTS This examination revealed the following loose parts. A "J" hook was located on the shroud ledge between Jet Pump #8 and
#9. This hook was later removed along with a 3/8" s.s. nut.
A small screw on the top guide periphery at 45*. A small screw on the top guide hold down bolt ling at 45*. (y A small washer on the core plate as well as string. NON-RELEVANT INDICATIONS There were many areas that contained indications that were proven to be non-relevant. Both-the O' and 180' guide rods have scratches. There were also scratches noted on the sensing line Jet Pump #16 and the shroud head bolts. Rub and stain marks were also recorded on the steam dryer lifting lugs. Hydrolazing was performed prior to the IVVI Inspection which resulted in excessive debris covering much of the vessel internals. The debris was so thick on the shroud ledge that the man-way covers could not be detected. The man-way covers were brushed off and re-inspected. s.n ,
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PILGRIM NUCLEAR POWER STATION INVESSEL VISUAL INSPECTIONS EIGHTH REFUELING AND INSPECTION OUTAGE SECTION III DATA SHEETS (I
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PROJECT NUMBER: F/ - t/ o +'4 9 ran w. Equipment used During the Examination: CAHERA RESOLUTION TYPE OF VISUAL EXAMINATION g c.w o.s.,..w, . ..... s.,=. emu. 3 v.s 4 c oor to.we we. 3 VT 1 2 vT.: p., 5'n"$ $.'.* ,5f0.N.S O "8CT E "' " " Component Description Tape Number Tape Counts Examination Re sults
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stTC: * - ~ st m en u.. FROJECT NUMBER: 97, y. p y'$ V '**"*' //Ad
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l- - . _ . . . l IN VESSEL VISUAL EXAMINATION DATA S..r.ET PILGRIM NUCLEAR POWER STATION p Visual Exae. nation of Reactor Internals and Components By the Use of Underwater TV Casera Video Tape No.: PILG-91-01 Date: 5/2B/91 II TECHNIQUE PERSONNEL LEVEL EQUIPMENT - CALIBRATION - ' l m-M. HEATH III CAMERA: ETV-1250 RECORDER: PANASONIC AG-6200 N. STAMM III 1 MIL WIRE VISIBLE ON ALL RESOLUTION CHECKS S. MONT1 CONE 11 TECHNIQUE DESCRIPTION: NAND HELD CAMERA, STRAIGHT ON LENS, 90 LENS, TWIN 50's ON CAMERA FOR LIGHT 1HG I Ccaponent(s) and/or Description of Review Tape Area Viewed Recordable Indications Accept Required Counts CAMERA RESOLUTION 1 MIL WIRE RESOLVED YES NO 000000-001:20 1 MIL. WIRE 45' STEAM DRYEP NO APPARENT ABNORMAL YES NO 901:30-007:48 SUPPORT BU.CKET CONDITIONS
/
i 135' STEAM DRYER NO APPARENT ABNORMAL YES NO 007:19-008:4B hI l CUPPORT BRACKET CONDITIONS I 225* STEAM DRYER NO APPARENT ABNORMAL YES NO 006:48-011:03 CONDITIONS
) ll S'JPPORT ERACKET '
ll l ll NO APTARENT ABNORMAL YES NO 011:03-012:17 ll 315' STEAM DRYER ySUPPORTERACKET CONDITIONS 11 a 012:17-019:22 NO APPAEENT ABNORMAL YES No p O' GUIDE ROD AND CONDITIONS
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- IN VESSEL VISUAL EXAMINATION DATA SHEET PILGRIM NUCLEAR POWER STATION Visual Examination of Reactor Internala and Components By the Use of Underwater TV Camera video Tape No.: PILG-91-01 Date: 5/26/91 Component (s) and/or Descriptiori of Review Tape
; Area Viewed Recordable Indications Accept Required Counts 45* TEEDWATER SPARGER NO APPARENT ABNORMAL YES No 044:13-059:48 AND BRACKETS CONDITIONS 135' TEEDWATER NO APPARENT ABNORMAL YES NO 059:48-114:14 SPARGER AND BRACKETS CONDITIONS 1
225" PEEDWATER NO APPARENT ABNORMAL YES NO 314:14-127:00 SPARGER AND BRACKETS CONDITIONS 315' TEEDWATER NO APPARENT ABNORMAL YES NO 127:00-140:25 SPARGER AND BRACXETS CONDITIONS CORE SPRAY PIPING O' NO APPARENT ABNORMAL YES NO 140:25-219:49 (g THROUGH 180 CONDITIONS 1 MIL WIRE 1 MIL WIRE RESOLVED YES NO 219:49-220:21 l l 0 0 l Reviewed by: ///.[, Level y Dates g.gf,y i 2C */ u
IN VESSEL VISUAL EXAMINATION DATA SHEET
- PILGRIM NUCLEAR POWER STATION Visual Exasination of Reactor Internals and Components By the Use of Underwater TV Camera Video Tape No.: P!LG 91-02 Date: 05/28/91 PERSONNEL LEVEL E0VIPMENT -
CALIBRATION - TECHNIQUE M. HEATH 111 CAMERA: ETV-1250 RECORDER: PANISONC AG 6200 l [ M. STAMM 111 1 MIL WIRE VISIBLE ON ALL RESOLUTION CHECKS S. MONTICONE 11 TECHN10VE DESCRIPTION: HAND HELD CAMERA, STRAIGHT ON LENS, 90 LENS. TWIN 50's ON CAMERA POR LIGHTING I Component (s) and/or Description of Review Tape Area Vtaved Recordable Indications Accept Required Counts l -
=mm=a l- )ES NO 0000 0119 l CAMEhA RESOLUTION 1 MIL WIRE RESOLVED l 1 MIL WIRE AND TITLE I
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l 360' N0ZZLES, 'T' BOX l AND BRACKETS I i LOWER COPE SPRAY NO APPARENT ABNORMAL YES NO 4458-4932 1 SPARGER 'A' THROUGH CONDITIONS 180* Reviewed by: y.gr j[ Levels Date eg , ,,, f, REF, IE BULLETIN 80-13, AND GE SIL 289. l 2 ? oc S/
IN VESSEL VISUAL EXAMINA?!0N DATA SHEET PILGRIM NUCLEAR POWER STATION Visual Examination of Reactor Internals and Components By the Use of Underwater TV Casera V2deo Tape No.: P!LG 91-02 Date $/28/91 Component (s) and/or Description of Revaev Tape Recordable Indications Accept Required Counts l Area Viewed . _ _ _ _ . _ .__ - p LOWEP. CORE SPRAY NO APFARENT ABNORMAL YES NO 4932-$B52 SPARGEk 100' THROUGH CONDITIONS 360' 1? Il $B$2-$906 gLOWERCORESPRAY NO APPARENT ABNORMAL iLS NO , 1 SPARCER 0* THROUGH CONDITIONS 180' O 9 l [ D _O Reviewed bys y g g g _ g Levels m Date: og _ oj, y REF. IE BULLETIN 80-13, AND GE SIL 289. E 9'*/ C/
1H VESSEL VISUAL EXAMINATION DATA SHEET P!LCRlH NUCLEAR POWER STATION Visual Examination of Reactor Internals and Components By tht. U*e of Underwater TV Camera Video Tape No.: P!LG 91-03 Dates 6/01/91 PERSONNEL LEVEL EQV!PMENT - CALIBRATION - TECHN!QUE _ a _ _ __ N. HEATH !!! CAMERA: ETV-1250 RECORDER: PANASONIC AG 6200 l H. STAMM !!! 1 MIL WIRE V151BLE ON ALL RESOLUTION CHECKS j S. MONTICONE !! TECHN!QUE DEECRIPTION: HAND HELD CAMERA, STRAIGHT ON l LENS, 90 LENS, TW1H $0's ON CAMERA FOR LIGHTING ll l Componentis) and/or Description of Rev2ew Tape Area Viewed Recordable Indications Accept Required Counts I __ LOWER CORE SPRAY NO APPARENT ABNORMAL YES NO 900:00-015: 00 SPAROER O' THRU 180* CONDITIONS LOWEP CORE SPRAY NO APPARENT ABNORMAL YES NO 015:00 032:20 SPARG2k 200' THRU CONDITIONS 360 " p- UPPER CORE SPRAY NO APPARENT ABNORMAL YES NO 032:20-e51:29 SPARGER O' THRU 180' CONDITIONS UPPER CORE SPRAY NO APPARENT ABHORMAL YES NO 051:29-197126 SPARGER 180 THRU CONDITIONS 360 CAMERA PESOLUTION 1 MIL WIRE RESOLVED YES NO 107:26-108:12 1 NIL WIRE TOP GUIDE HOLD DOWN LOOSE SCREW ON CU1DE NO YES NO 198:12 130:51 BOLTS (360*) OTHER APPARENT ABNORMAL CONDITIONS CAMERA RESOLUTION 1 MIL WIRE RESOLVED YES NO 130:51-131:33 i 1 MIL WIRE i i e Revie*pd by: /7./ y Level Date g . u. ,,, SCREW WAS NOTED ON TOP GUIDE. REF. IE BULLETIN 80-13, AND GE SIL 289. Ef og g/ l l .._..,_ - _.
2- .- . - .:-.. :." ::.:L ::.: . :; Tz^::,. . .._. . ... . . . . . .. - i i IN VESSEL VISUAL EXAMINATION DATA SHEET PILGRIM NUCLEAR POWER STATION Visual Examination of Reactor Internals and Components By the Use of Underwater TV Casara Video Tape No.: PILG-91-03 Date 6/01/91 Component (s) and/or Description of Revied Tape l Required Counts Area Viewed Recordable Indications Accept JET PUMP e 20 NO CONTACT WITH THE YES NO 131:33-145:37 SHROUD SIDE SET SCREW NO APPARENT ABNORMAL YES NO 145:37-159:19 ' l JET PUMP e 19 CONDITIONS JET PUMP $ la NO APPARENT ABNORMAL YES No 159:19-203:07 CONDITIONS CONT. ON TAPE e 04. u e f l 1 l l l l l ! l I ll .m= ., r q l r (( Reviewed by: g g Level: y Date: , NO CONTACT WITil THE SHROUD SIDE SET SCREW OH JET PUMP e 20. REF. GE SIL 420 FOR THE JET PUMP SENSING LINES. yo ,f g REF. GE RICSIL 45 FOR THE JET PUMP RISING BRACES. 1
-. _ _ . . . . _ _ _ : ; _ i . . ; _. . . . . __ _
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IN VESSEL VISUAL TXAMINATION DATA SHEET PILGRIM NUCLEAR POWER STATION Visual Examination of Reactor Internals and Compon6:nts C By the Use of Underwater TV Camera Video Tape No.: PILC-91-04 Date: 5/29/91 LEVEL EQUIPMENT - CALIBRATION - TECHN100E PERSONNEL ETV-1250 RECORDER: PANASONIC AG-6200 ll M. HEATH M. STAMM Ill III CAMERA: 1 MIL WIRE VISIBLE ON ALL RESOLUTION CHECKS l j S. MONTICONE II TECHNIQUE DESCRIPTION: HAND HELD CAMERA, STRAIGHT ON ( LENS, 90 LENS, TWIN Sa's ON CAMERA POR LIGHTING ,. i k Description of Review Tape Component (s) and/or Recordable Indications Accept Required Counts Area Viewed ( YES NO 000:00-016:30 g=JET PUMP e 18 NO APPARENT ABNORMAL CONDITIONS [ II NO APPARENT ABNORMAL YES No 010:30-026:59 l JET PUMP e 17 CONDITIONS l
- NO APPARENT ABNORMAL YES NO 026559-052:17 JET PUMP e 16 CONDITIONS g
~
1 MIL WIRE RESOLVED YES NO 052:17-053:05 j CAMERA RESOLUTION [ 1 MIL VIRE AND TITLE NO APPARENT ABNORMAL YES NO 053:02-112:52 JET PUMP e 15 CONDITIONS NO APPARENT ABNORMAL YE5 NO 112:52-126:50 JET PUMP e 14 CONDITIONS l YES NO 128:50-144:29 JET PUMP e 13 NO APPARENT ABNORMAL CONDITIONS JLT PUMP s 12 NO APPARENT ABNORMAL YES NO 144:29-15B:30 CONDITIONS U YES NO 15B:30-203:04 JET PUMP e 11 NO APPARENT ABNORMAL l CONDITIONS l Level: y Date: q,q, Reviewed by: gg {
- SCRATCHES WERE NOTED ON THE SENSING LINE JET PUMP s 16.
REF. GE SIL 420 TOR THE JET PUMP SENSING LINES. ,7/ **~ 4/ REF. GE RICSIL 45 FOR THE JET PUMP RISER BRACES.
IN VESSEL VISUAL EXAMINATION DATA SHEET PILORIM NUCLEAR POWER STATION Visual Examination of Reactor Internals and Components By the Use of Underwater TV Camera Video Tape No.: PILO-91-05 Date: 5/29/91 ( ICUIPMENT - CALIBRATION - TECHN10VE PERSONNEL LEVEL { c- ETV-1250 RECORDER: PANASONIC AG-6200 M. HEATH III CAMERA: H. STAMM 111 1 MIL VIRE VISIBLE ON ALL RESOLUTION CHECKS S. MONTICONE II TECHNIQUE DESCRIPTION: HAND HELD CAMERA, STRAIGHT ON LENS, 90 LENS, TWIN SO's ON CAMERA FOR LIGHTING Review Tape Component (s) and/or Description of Area Viewed Recordable Indications Accept Required Counts JET PUNP e el NO APPARENT ABHORMAL YES NO 000:00-007:10 CONDITIONS
! CAMERA RESOLUTION 1 MIL WIRE RESOLVED YES No 007:10-007:51 1 MIL WIRE AND TITLE
- JET PUMP e 10 NO APPARENT ABNORMA!, YES No 007:51-019:45 CONDITIONS 160" MANVAY COVER COVERED WITH SEDIMENT YES NO 019:45-022:12 0
0' MANWAY COVER COVERED WITH SEDIMENT YES NO 022:12-025:29 l JET PUMP e el NO APPARENT ABNORMAL YES NO 025:29-040:39 CONDITIONS
- GAP IN SET SCREW YES NO 040:39-054:03 JET FUMP e 02 SHROUD SIDE NO APPARENT ABNORMAL YES No 054:03-105:01 JET PUMP e 03 CONDITIONS NO APPARENT ABNORMAL YES NO 105:01-116:23 JET PUMP e 04 CONDITIONS I
NO APPARENT ABNORMAL YES NO 116:23-125:49 i JET PUMP e 05 CONDITIONS U R gp g g ,g '
\
Reviewed bys j Level: Dates g,
- y
- THERE IS A CAP IN THE SHROUD SIDE SET SCREW JET PUMP e 2 N ## U REF. GE $1L 420 FOR THE JET PUMP SENSING LINES.
REF. GE RICSIL 45 TOR THE JET PUMP RISER BRACKETS.
IN VESSEL VISUAL EXAMINATION DATA SHEET t P!LCRIM NUCLEAR POWER STATION Visual Examination of Reactor Internals and Componente ,
, h( By the Use of Underwater TV Camera i Video Tape No.: PILG-9P 95 Date: 5/29/91 Description of Resview Tape l Component (s) and/or Area Viewed Recordable Indications Accept Required Counts 1
JET PUMP e 06 NO APPARENT ABNORMAL YES NO 125:49-133:19 CONDITIONS JET PUMP e 07 NO APPARENT ABNORMAL YES NO 133:19-143:16 CONDITIONS u JET PUMP e 68 No APPARENT ABNORMAL YES NO 143:16-155:26 CONDITIONS I YES No 155:26-206:11
** NO APPARENT ABNORMAL l JET PUMP e 09 CONDITIONS i l
l JET PUMP e 19 NO APPARENT ABNORMAL YES No 206:11-206:50 ' CONDITIONS CONT. ON TAPE e 06 206:50-207:25 1 MIL WIRE RESOLVED YES NO PllCAMERARESOLUTION l 1 MIL WlRE { U l l l l 1 1 N R l'. a 5
.- O !,.
Levels 777 - bates g , g, g Rev2eved by: g , g t
** '*J' HOOK ~0N SHROUD LEDGE BETWEEN 8 AND 9.
l THIS 'J' HOOK NAS BEEN REMOVED ALONG WITH A 3/8' NUT. yJ ,,- g
- IT4LJB" RDO LINES. _ _ . . _ , . _ _ _ . _ _
IN VESSEL VISUAL EXAM!!iAT10N DATA SHEET PILGRIM NUCLEAR POWER STATION Visual Examination of Reactor Internals and Components By the Use of Underwater TV Camera ( Video Tape No.: PILG-91-06 Date: 5/30/91 PERSONNEL LEVEL EQUIPMENT - CALIBRATION - TECHNIQUE
, _ . . _=
H. HEATH III CAMERA: ETV-1250 RECORDER: PANASONIC AG-6200 H. STAMM III 1 MIL WIRE VISIBLE ON ALL RESOLUTION CHECKS S. MCNTICONE !! TECHNIQUE DESCRIPTION: HAND HELD CAMERA, STRAIGHT ON LENS, 90 LENS, TWIN 30's ON CAMERA FOR LIGHTING Component (s) and/or Description of Review Tape Area Viewed Recordable Indications Accept Required C o'.tn t s
- = -
j BOTTOM SIDE OF THE NO APPARENT ABNORMAL YES NO 9000-0500 TOP GUIDE CONDITIONS CORE PLATE NO APPARENT ABNORMAL YES NO 0508-1949 CONDITIONS
. JET PUMP e le NO APPARENT ABNORMAL YES NO 1049-1390 CONDITIONS (I'
I CAMERA RESOLUTION 1 MIL WIRE RESOLVED YES NO 1390-1450 [ y 1 MIL WIRE 200* SURVEILLANCE NO APPARENT ABNORMAL YES NO 1450-1658 SAMPLE AND BRACKET CONDITIONS 185* SURVEILLANCE NO APPARENT ABNORMAL YES NO 1658-1816 SAMPLE AND BRACKET CONDITIONS I 95* SVRVIILLANCE SAMPLE IS REMOVED YES NO 1816-1347 l j SAMPLE AND BRACKET I D 1 MIL WIRE RESOLVED YES NO 1847-1920 l CAMERA RESOLUTION 1 MIL WIRE
^ .(
Dates Reviewed by: p.g level: g , ,,, p REF. GE SIL 420 FOR THE JET PUMP SENSING LIH1S, REF. GE RICSIL 45 FOR THE JET PUdP RISER BRACKET. J '/ o / 4 /
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b, IN VESSEL VISUAL EXAMINATION DATA SHEET . PILOR!!' NUCLEAR POWER STATION
-- Visual Examination of Reactor. Internals and Components By the Use of Underwater TV Camera Video Tape No.: PILO-91-06 Date: 5/30/91 Component (s) and/or Description of l Review Tape Area Viewed Recordable Indications Accept Required Counts i
TOP CUIDE CENTER NO APPARENT ABNORMAL YES NO 1920-3236 CELLS CONDITIONS g l ll TOP GUIDE PEP.IPHEr.AL SMALL SCREW ON THE TOP YES NO 3236-4418 g 6' THROUGH_180' l GUIDE AT 45 U O 4418-5077 NO APPARENT ABNORMAL YES NO g TOP CUIDE PERIPRERAL
# CONDITIONS l 163 THkOUGH 360' I
\ NO APPARENT ABNORMAL YES No 5077-5166 <
CED N0Z2LE CONDITIONS 1 MIL WIRE RESOLVED YES No 5166-5180 { l CAMERA RESOLUTION 1 MIL WIRE I i i 1
-d H
H H 8-11 . n 1. tj R
-H I
I H I ( Revie"ed byt ))y.} g g Levelt , Dntes og.ef ff 3J' w //
IN VESSEL VISUAL EXAMINATION DATA SHEET PILGRIM NUCLEAR POWER STATION Visual Examination of Reactor Internals anc' Components By the Use of Underwater TV Camera Video Tape No.: PILG-91-07 Date: 30/01 1 q-- LEVEL EOUIPMENT - CALIERATION - TECHN!OttE g PEkSONNEL m- - - = - - % g M. HEATH III CAMERA: ETV-1250 kEC0kDER: PA ASONIC AG-6000 l M. STAMM III 1 MIL WikE VISIBLE ON ALL RESOLUTION CHF'KS l g S. HUNTICONE II TECHNIOUE DESCRIPTION: HAND HELD CAMERA, STRAIGHT ON l l LENS, 90 LEN5, TWIN 50's ON CAMERA FOR LIGHTING l l 0 I _ g Description of , keview Tape g Component (s) and/or Recuared Counts p Area Viewed Re:cerdable Indications Accept i I CAMERA RL!%UTION 1 MIL WIkE RESOLVED YES NO 000:00-001:02 l y 1 MIL WIRE AND TITLE f 001:02-002:34 t 1RM 36-09 NW SIDE NO APPARENT AENORMAL YES NO ONLY CONDITIONS IHM 36-41 NW & SE NO APPARENT ABNORMAL YES NO 002:34-006:47 SIDE ONLY CONDITIONS NO APPARENT ATNORMAL 'i ES NO 006:47-015:41 g SRM 36-33 g CONDITIONS IRM 28-33
- NO APPARENT ABNORMAL YES NO bl5:41-033:20 CONDITIONS IRM 28-25 SE SIDE NO APPARENT AbHORMAL i YES NO 033:20-035:41 lg CHLY CONDITIONS tl 035:41-043:18 NO APPARENT ABNORMAL YES NO g SRM 20-17 SE SW AND NW SIDES ONLY CONDITIONS NO APPARENT ABNORMAL YES NO '043:18-048:13
[1RM20-25 SE AND NW SIDES ONLY CONDITIONS l U IRM 20-33 EE AND NE NO APPARENT ABNORMAL YES NO 048:13-052:34 SIDES ONLY CONDITIONS SRM 20-41 SE AND NW NO APPARENT ABNORMAL YES NO 052:34-056:14 gSIDESONLY CONDITIONS (I_ hl Reviewed by: 7f7 g , Level: Dates og ,o p py l 0 estcarm_mca 8@-39. _ _ _ _ _ y t a 4/
IN VESSEL VISUAL EXAMINATION DATA SHEET i PILGRIM NUCLEAR POWER STATION Visual Examination of Reactor Internals and' Components l By the Use of Underwater TV Caeera
-{
Video Tape No.: PILG-91-07 Date: 5/30/91 l Component (s) and/or Description of Review Tape j-Area Viewed Recordable Indications Accept Required Counts
-IRM 12-41 NW AND SE NO APPARENT ABNORMAL YES NO 056:14-101:11 SIDES ONLY CONDITIONS SRM 12-25 SE AND SW NO APPARENT ABNORMAL YES No 101:11-106:25 SIDES ONLY CONDITIONS IRM 12-09 NW SIDE NO APPARENT ABNORMAL YES NO 106:25-198:28 ONLY CONDITIONS CLAD PATCH AT 0* JNO APPARENT ABNORMAL YES NO 108:28-109:34 CONDITIONS j CLAD PATCH AT 180" NO APPARENT ADNORMAL YES NO 109:34-111:03 CONDITloNS CO.,E PLATE NO APPARENT ABNORMAL YES NO 111:03-121:42 CONDITIONS v CAMERA RESOLUTION 1 MIL WIRE RESOLVED YES NO 121:42-121:58 1 MIL WIRE.
0 11 - 180* MAN'WAY COVER NO APPARENT ABNORMAL YES No 121:58-126:49 CONDITION O'* MANWAY COVER
- NO APPARENT ABNORMAL YES NO 126:49-129:38 CONDITION I
TO R.-e.e.MY n w t. el - .. - : L. a.,, RELOOK OF MANWAY COVERS !.7TER SEDIMENT WAS REMOVED. 3 ? of 4/
- . - -. . - - _= - - - . - - -
~ ~~
IN VESSEL VISUAL EXAMINATION DATA SHEET PILGRIM NUCLEAR POWER STAT 10H Visu61 Examination of Reactor Internals and Coeponents By the Use of Underwater TV Camera VAdeo Tape No.: PILG-91-08 Date 6/04/91 PERSONNEL LEVEL EQUIPMENT - CALIBRATION - TECHNIQUE M. HEATH III CAMERA: ETV-1250 RECORDER: PANASONIC AG-6200 l M. STATIM III 1 MIL WIRE VISIBLE ON ALL RESOLUTION CHECKS S. MONTICONE II TECHNIOUE DESCRIPTION: HAND HELD CAMERA. STRAIGHT ON LENS, 90 LENS, TWIN 50's ON CAMERA FOR LIGHTING l Component (s) and/or Descr2ption of Review Tape Recordable Indications Accept Required l Counts l Area Viewee i l CAMERA RESOLUTION I MIL VIRE RE3OLVED YES NO 0000-0079 l 1 MIL WIRE AND TITLE I N0 VIDEO PICTURE YES NO 0079-0928 lNONE NO APPARENT ABNORMAL NO OP?.8-1390 l STEAM DRYER 45' YES l LIFTING LUG CONDITIONS I g 515' LIFTING LUG NO APPARENT ABNORMAL YES NO 1390-1960 g COMITIONS I l 225' LIFTING LUG NO APPARENT ABNORMAL YES NO 1960-2264 g CONDITIONS 135' LIFTING LUG NO APPARENT ABNORMAL YES NO 2264-2500 g CONDITIONS , I i lWSWSEALTOBANKWELD NO APPARENT ABNORMAL YES NO 2500-2660 g REF. PAR. 6.27.9 CONDITIONS 5 g WNW SEAL TO BANK WELD NO APPARENT ABNORMAL YES NO 2660-2793 g REF. DAR. 6.27.9 CONDITIONS l l WNW - WSW BANK HORZ. NO APPARENT ABNORMAL YES NO 2793-3050 g WELDS REF. PAR.6.27.6 CONDITIONS WSW - WNW SUPPORT NO APPARz.NT !.2.W:RM.iL YES No 3050-3563 g RING TO SEAL WELDS CONDITIONS
. kEF. PAR. 6.27.10 t- si ,
Reviewed by: g . Level: y Date: g o g.. y REF. GE SIL 474 (ATT 40) STEAM DRYER CHANNEL AND SUPPORT RING. ggp y. gf
_ . _ _ - - a . . , _ _ _ . _ _ . _;ra-- z;E. ;;;r_ - .. :- x .- :. ----- -- ---- - IN VESSEL' VISUAL EXAMINATION DATA SHEET PILGRIN NUCLEAR POWER STATION Visual Examination of Reactor Internals and Components By the Use of Underwater TV Camera V2deo Tape No.: PILG-91-08 Date 6/04/91 Component (s) and/or Description of Review Tape Area Vaewed Recordable Indications Accept Required Counts li ' g WSW - WNW SKIRT TO 1 MIL WIRE RESOLVED YES NO 3563-3794 l SKIRT HORZ. WELD REF. 8 PAR. 6.27.15 g NO APPARENT ABNORMAL YES N0 3794-4295 g NW VERTICAL BANK WELD CONDITIONS
-y kEF. PAk. 6.27.3 l l
8 g NW SHELL E0kZ. WELD NO APPARENT ABNORMAL Yi,5 No 4295-4410 g--kEF. PAk.-o.27.4 CONDITIONS _g NW SEAL TO BANK WELDS NO APPARENT ABNORMAL YES NO 4410-4565 CONDITIONS ( EEF. FAR. 6.27.9 (' NO APPARENT ABNORMAL YES NO 4565-4709 j, NW UPPER SUPPORT SEAL y 70 k1NG WELD REF. CONDITIONS y PAR. 6.27.10 I NW SKIRT TO SKIRT NO APPARENT ABNORMAL YES NO 4709 4809 l WELD HokZ. WELD REF. CONDITIONS l j _ PAR. 6.27.13 C=l NO 4809-5018 j'NW SKIRT TO' SKIRT NO APPARENT-ABNORMAL YES CONDITIONS l WELD REF. PAR.6.27.15 BRACKET l U g NW'BELOW LIFTING-LUG NO APPARENT ABNORMAL YES .No 5018-5237_. j CONDITIONS I SW VERTICAL YELDS NO APPARENT ABNORMAL YES NO 5237-5928 l g REF. FAR. 6.27.3 CONDITIONS u I Revs.ewed by [ [ Levelt y Date: ,g, , p,9 O*'''''''""'"^"""c"*""""'""""'"'"- 37 a //
L -... - . 1; _ .... ~ _ _ . -
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IN VFSSEL VISUAL EXAMINATION DATA SHEET PILGRIM NUCLEAR POWER STATION Visual Examination of Reactor Internals and Components By the Use of Underwater TV Camera Video Tape No.: PILG-91-08 Date: 05/28/91 4 i keview Tape l Component (s) and/or Description of Area Viewed Recordable Indications Accept Required Counts l l NO 592B-5972 SW SEAL TO BANM WELD 1 MIL WIRE RESOLVED YES lg REF. PAR. 6.27.9 R NO APPARENT AbN0i; MAL YES NO 5972-6140 y SW Hok2. WELD REF. g PAR. 6.27.4 6 6.27.6 CONDITIONS - l No APPARENT ABNORMAL YES No 6140-6233 l SW HORZ. UPPER RING TO SEAL WELD REF. CONDITIONS l gPAk.6.27.le l NO APPARENT ABNORMAL YES NO 6233-6485 l SW HORZ. UPPER SUPPORT TO SKIRT WELD CONDITIONS
. RET. PAR. 6.27.13 YES No 6485-6718
(( ( lg SW-SSW HORZ. SKIRT NO APPARENT TO ABNORMAL y SKIRT WELD REF. PAR. CONDITICNS l 6.27.15 1 0 R I i
- I q l t
i i I , O 11 Reviewed by: gg, Level: Dates g, o REF. GE SIL 474 ( ATT 40) STEAM DRYER CHANNEL AND SUPPORT RING. Yo a u
a . u b_; m . == - = . : v:=:m==: z.w:_ == ===:=:=- = --- ---- IN VESSEL VISUAL EXAMINATION DATA SHEET , PILGRIM NUCLEAR POWER STATION Visual Examination of Reactor Internals and Components By the Use of Underwater 'lV Camera
-Video Tape No.: PILG-91-09 Dates 6/04/91
~
i PERSONNEL LEVEL EQUIPMENT - CALIBRATION - TECHNIQUE M. HEATH III CAMERA: ETV-1250 RECORDER: PANIS0NIC AG-6200 H. STAMM III 1 MIL VIRE VISIBLE ON ALL RESOLUTION CHECKS
- S. MONTICONE II TECHNIQUE DESCRIPTION: HAND HELD CAMERA, STRAIGHT ON LENS, 90 LENS, TWIN 50's ON CAMERA FOR LIGHTING ll
-Component (s) and/or Description of Review Tape Area Viewed Recordable Indications Accept Required Counts STEAM DRYER CAMERA 1 MIL WIRE RESOLVED YES NO 0000-0065 RESOLUTION 1 MIL WIRE AND TITLE NW VERTICAL BANK WELD NO APPARENT ABNORMAL YES NO 0065-0211 REF. PAR. 6.27.3 CONDITIONS I 0' VERTICAL WELD NO APPARENT ABNORMAL YES NO 0211-0410
' CONDITIONS NE VERTICAL BANK NO APPARENT ABNORMAL YES NO 0410-1016 WELDS 1 THRU 4 CONDITIONS NE.TO NW SUPPORT RING
- SEE BELOW AND TAPE No YES 1016-2668 AND VERTICAL WELD PILG-91-15
.NW TO NE SKIRT TO NO APPARENT ABNORMAL YES NO 2668-2980 SKIRT WELD CONDITIONS NE VERTICAL CHANNEL NO APPARENT ABNORMAL YES NO 2980-3370 L WELD BELOW LIFTING CONDITIONS L LUG g O' GUIDE AND CHANNEL NO APPARENT ABNORMAL YES NO 3370-3560 g WELD CONDITIONS i
SOUTH BANK (5) TO NO APPARENT ABNORMAL YES NO 3560-3980 SEAL HORZ. WELD CONDITIONS SW 70 SE SEAL TO -No APPARENT ABNORMAL YES NO 3980-4180 l l 1 SUPPORT RING WELD CONDITIONS o i V Reviewed by: g ,, g g Level g Date ,
- THERE IS A 2' LONG CRACK ON THE 35 LEVELING SCREW SEE TAPE PILG-91-15 FOR
' DETAILS.
REF. GE' SIL.474 ( ATT 40) STEAM DRYER CHANNEL AND SUPPORT RING. p// ,g _ gj l
- 1. _ _ _ . _ _ _ - _
-.m.-.--- :-. : = : = . _ _ -. .- _ . - . . . _ , .
IN VESSEL VISUAL EXAMINATION DATA SHEET 2 PILGRIM NUCLEAR POWER STATION Visual Examination of Reactor Internals and Components By the Use of Underwater TV Camera Video Tape No.: PILG-91-09 Date 6/04/91 P Component (s) and/or Description of Review Tape l
- Area Viewed Recordable Indications Accept Required Counts l
SE TO SW SUPPORT RING NO APPARENT ABNORMAL YES NO 4180-4433 TO SKIRT WELD C0hDITIONS SW 70 SE SKIRT TO NO APPARENT ABNORMAL YES NO 4433-4658 SKIRT HOR 12. WELD CONDITIONS 180 VERTICAL BANK NO APPARENT ABNORMAL YES NO 4658-4907 l WELD CONDITIONS SE VERTICAL BANK NO APPARENT ABNORMAL YES NO 4907-5025 [ WELDS e4 AND e5 CONDIT10h5 l 1 5025-5298
- GUIDE kOD CHANNEL AND NO APPARENT ABNORMAL YES NO l
CONDITIONS l VERTICAL BANX WELD 82 i BELOW LUG SW C0kNER NO APPARENT ABNORMAL YES No 5298-5454 l CONDITIONS l i 11 No 5454-5491 NO APPARENT ABNORMAL YES g BDlIND LJG SE CORNER l
, CONDITIONS l
NO APPARENT ABNORMAL YES No 5491-5615 l BELOW LUG SE CORNER a C0hDITIONS NO APPARENT ABNMMAL YES NO 5615-5796 g h0RI2. WELD BANK e5 p CONDITIONS l 1 MIL WIRE RESOLVED YES NO 5615-5796 g CAMERA RESOLUTION l l 1 MIL WIRE O ll 8 - Reviewedby:,fN.[ Level: Dates
&M - h l
l REF. GE SIL 474 ( ATT 40) STEAM DRYER CHANNEL AND SUPPORT RING. l (-{
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I IN VESSEL VISUAL EXAMINATION DATA SHEET
-PILGRIM NULEAR POWER STATION Visual Examination of Reactor Internals and Components
- By the Use of Underwater TV Camera l Video Tape No.
- PILG-91-10 Datet 6/04/91 PERSONNEL LEVEL EQUIPMENT - CALIBRATION -
TECHNIOUE l M. HEATH III CAMEPA: ETV-1250 RECORDER: PANASONIC AG-6200-M. STAMM III 1 MIL WIRE VISIBLE ON ALL RESOLUTION CHECKS *
'S. MONTICONE II TECHNIQUE DESCRIPTION: HAND HELD CAMERA, STRAIGHT ON LENS, 90 LENS, TWIN 50's ON CAMERA TOR LIGHTING i
Componentts) and/or Description of Review Tape Area Viewed Recordable Indications Accept Required Counts i a 0000-0126 hMOISTURESEPERATOR 1 MIL WIRE RESOLVED YES NO 1 MIL WIRE AND TITLE SHROUD HEAD BOLT 848 RUB MARKS AND SCRATCHES YES NO 0126-0547 0547-0740 D SHROUD HEAD BOLT 847 RUB MARKS YES NO , l SHROUD HEAD BOLT 846 NO APPARENT ABNORMAL YES NO 0740-1920 ' CONDITIONS s SHROUD HEAD BOLT 845 NO APPARENT ABNORMAL YES NO 1020-1145 CONDITION 3 l l SHROUD HEAD BOLT 844 NO APPARENT ABNORMAL YES NO 1145-1240 j CONDITIONS
- ! SHROUD-HEAD BOLT #43 NO APPARENT ABNORMAL YES NO 1240-1412 CONDITIONS l l CAMERA-RESOLUTION 1 MIL WIRE RESOLVED YES NO 1412-1458 j j 1 MIL WIRE i
l g SI AND TUBES STARTING NO APPARENT ABNORMAL YES NO 1458-1570 AT O' 11 CONDITIONS STAND TUBE #2 NO APPARENT ABNORMAL YES NO 1570-1620 CONDITIONS STAND TUBE 13 NO APPARENT ABNORMAL YES NO 1620-1740 CONDITIONS (- Reviewed by: ,g [ Levels y Dater g ,y , pf THERE WERE RUB MARKS AND SCRATCHES RECORDED ON THE SHROUD HEAD BOLTS. REF. GE SIL 474 (ATT40) STEAM DRYER AND SUPPORT RING.
IN VESSEL VISUAL EXAMINATION DATA SHEET PILGRIM NUCLEAR POWER STATION Visual Examination of Reactor Internals and Components By the Use of Underwater TV Camera {( Video Tape No.: PILG-91-10 Date 6/04/91 9 l Component (s) and/or Description of Review Tape Recordable Indications Accept Required Counts l Area Viewed
' STAND TUBE e4 NO APPARENT ABNORMAL YES NO 1740-1820 CONDITIONS STAND TUBE 85 NO APPARENT ABNORMAL YES NO 1820-1880 CONDITIONS STAND TUBE 66 NO APPARENT ABNORMAL YES NO 1880-1945 CONDITIONS STAND TUBE #7 NO APPARENT ABNORMAL YES NO 1945-2099 CONDITIONS STAND TUBE #8 NO APPARENT ABNORMAL YES NO 2099-2223 CONDITIONS
, STAND TUBE #9 NO APPARENT ABN2RMAL YES NO 2223-2355 RONDITIONS STAND TUBE ele NO APPARENT ABNORMAL YES NO 2355-2460 l CONDITIONS STAND TUBE eli NO APPARENT ABNORMAL YES NO 2460-2637 CONDITIOFS STAND TUBE 412 NO APPARENT ABNORMAL YES NO 2637-2767 CONDITIONS STAND TUBE s13 NO APPARENT ABNORMAL YES NO 2767-2920 CONDITIONS STAND TUBE c14 NO APPARENT ABNORMAL YES NO 2920-3029 CONDITIONS Dates Reviewed by: ,f7/./ ,g Level: y g, ,g O
( n .- a
IN VESSEL VISUAL EXAMINATION DATA SHEET PILGRIM NUCLEAR POWER STATION
/~N Visual Exasination of Reactor Internals and Components 'd By the Use of Underwater TV Camera Video Tape No.: PILG-91-10 Dates 6/04/91 Corponent(s) and/or Description of Review Tape Area Viewed Recordable Indications Accept Required Counts STAND TUPE 015 NO APPARENT ABNORMAL YES NO 3029-3153 CONDITIONS STAND TUBE 816 NO APPARENT ABNORMAL YES NO 3153-3277 CONDITIONS STAND TUBE c17 NO APPARENT ABNORMAL YES NO 3277-3495 CONDITIONS STAND T'JBE 019 NO APPARENT ABNORMAL YES NO 3495-3660 CONDITIONS STAND TUBE 820 NO APPARENT ABNORMAL YES N0 3660-3860 CONDITIONS STAND TUBE 821 NO APPARENT ABNORMAL YES NO 3060-4183 g > CONDITIONS (k STAND TUBE s22 NO APPARENT ABNORMAL YES NO 4183-4326 CONDITIONS g STAND TUBE 823 NO APPARENT ABNORMAL YES NO 4326-4542 CONDITIONS STAND TUBE 824 NO APPARENT ABNORMAL YES NO 4542-4600 CONDITIONS CAMERA RESOLUTION 1 MIL WIRE RESOLVED YES NO 4680-4700 1 MIL WIRE Reviewed by: jg,g Levela y Dates a _,, , p n
(k) t/s es //
-. . < - . - -. ..=..: . . . -.- - --.
IN VESSEL VISUAL EXAMINATION DATA SHEET PILGRIM NUCLEAR POWER STATION Visual Exasination of Reactor Internals and Components By the Use of Underwater TV Camera Video Tape No.: PILG-91-10 Date: 6/04/91
~
i h l Component (s) and/or Description of Review Tape y Area Viewea Recordable Indleations Accept Required Counts 6 j STEAM DRYER NE NO APPARENT ABNORMAL YES NO 4700-4856 [ VERTICAL VENT e 5 CONDITIONS l SE VERTICAL VENT 8 1 l YES NO 4856-4960 [ EAST SEAL TO BANK NO APPARENT ABNORMAL l WELD CONDITIONS U y SE - NE SEAL TO NO APPARENT ABNORMAL YES NO 4960-5123 y SUPPORT RING WELD CONDITIONS X NO APPARENT ABNORMAL YES NO 5123-5312 ll SE - NE UPPER SUPPORT KING TO SKIRT WELD CONDITIONS p LOWER SEAL TO BANK No APPAEENT ABNORMAL YES NO $312-5430 WELD CONDITIONS J NO APPARENT AbHORMAL YES NO 5430-5736 l SKIRT TO SKIRT NORZ. y WELD l CONDITIONS 0 g CAMERA RESCLUTION 1 MIL WIRE RESOLVED YES NO 5736-5745 g 1 MIL WIRE N 8 I I ll e H H L" __ Reviewed by: 7, Level! - r7 Date: , pp REF. GE SIL 474 (ATT 40) STEAM DRYER CHANNEL AND SUPPORT RING. t'C & Cf
IN VESSEL VISUAL EXAMINATION DATA SHEET IO PILGRIM NUCLEAR POWER STATION
- m. ) Visual Examination of Reactor Internals and Components By the Use of Underwater TV Camera Video Tape No.: PILG-91-11 Date 6/05/91 LEVEL EQUIPMENT - CALIBRATION -
TECHNIOUE f PERSONNEL l l M. HEATH III CAMERA: ETV-1250 RECORDER: PANASONIC AG-6200 M. STAMM III 1 MIL WIRE VISIBLE ON ALL RESOLUTION CHECKS S. MONTICONE II g TECHNIQUE DESCRIPTION: HAND HELD CAMERA. STRAIGHT ON g LENS, 90 LENS. TWIN 50's GN CAMERA FOR LIGHTING if l Component (s) and/or Description of Review Tape y Area Viewoo Recordable Indications Accept Required Counts l' l MOISTUkE SEPERATOR 1 MIL WIRE RESOLVED YES NO 0000-0030 [ CAMERA kESOLUTION
} 1 MIL WIRE AND TITLE 11 NO APPARENT ABNORMAL YES NO 0030-0470 m 11 SHROUD HEAD BOLT #01 g CONDITIONS */**
SHROUD HEAD BOLT #02 NO APPARENT ABNORMAL YES NO 0470-0743 CONDITIONS ** 1, Il ll SHROUD HEAD BOLT 403 NO APPARENT ABNORMAL YES NO 0743-1010 g CONDITIONS ** I l SHkOUD HEAD BOLT e04 NO APPARENT ABNORMAL YES NO 1010-1198 CONDITIONS ** g H g SHkOUD PEAD BOLT 805 NO APPARENT ABNORM.tL YES NO 1198-1373 g CONDITIONS ** N y SHkOUD HEAD BOLT #06 NO APPARENT ABNORMAL YES NO 1373-1488 CONDITIONS ** y SHkOUD READ BOLT ve7 NO APPAREhT ABNORMAL YES NO 1488-1714 CONDITIONS ** l l l SHROUD EEAD BOLT 408 NO APPARENT ABNORMAL YES NO 1714-1874 CONDITIONS ** y l SHROUD HEAD BOLT 809 NO APPARENT ABNORMAL YES NO 1874-2018 CONDITIONS ** (Ol [I (F L Reviewed bys p f , M Level: ,,, Date: g,jj, g
- SCCATCHES y 7 ,,r g ;
++ STAIN MARKS AND PUB /WEAF MARKS
. . . - - . _ . . . . =- - . : -. ...- a .
IN VESSEL VISUAL EXAMINATION DATA SHEET PILGRIM NUCLEAR POWER STATION Visual Examination of Reactor Internals and Components By the Use of Underwater TV Camera Vt;eo impe No.: PILG-91-11 Dates 6/05/91 g l Component (s) and/or Description of Review 'l a n Recordable Indications Accept Required Counts l Area Viewed - SHkOUD HEAD BOLT 819 NO APPARENT ABNORMAL YES NO 2018-2165 CONDITIONS ** I SHROUD HEAD BOLT all NO APPARENT ABNORMAL YES NO 2165-2307 CONDITIONS ** l NO APPARENT ABNORMAL YES NO 2307-2466 l SHkOUD HEAD BOLT c12 ** g CONDITIONS l EHROUD HEAD BOLT s13 NO APPARENT ABNORMAL YES NO 2460-2583 l CONDITI0 tis ** l 11 SHROUD HEAD BOLT 814 NO APPARENT ABNORMAL YES NO 2583-2732 l CONDITIONS **
, J.
SHEOUD HEAD BOLT s15 NO APPARENT ABNORMAL YES NO 2732-2849 (: L CONDITIONS ** g l l YES NO 2849-2943 SHR0"D HEAD BOLT 416 NO APPARENT ABNORMAL l CONDITIONS ** j. I I g SHkOUD HEAD BOLT #17 NO APPARENT ABNORMAL YES NO 2943-3203 CONDITIONS ** g l YES NO 3203-3400 l SHROUD HEAD BOLT #18 NO APPARENT ABNORMAL CONDITIONS ** l I NO 3400-3637 SHROUD HEAD BOLT s19 NO APPARENT ABNORMAL YES CONDITIONS */** l YES NO 3637-3772 l l SHROUD HEAD BOLT 820 NO APPARENT A3 NORMAL
- l CONDITIONS */**
Reviewed by: g , [ Levelt x
---- - Dater g ,g
- SCRATCHES j ** STAIN MARKS AND RUB / WEAR MAPXS l
- f. (~
O
~.. ....-- .- - -.- - . - -.. - - . - - -
~ ~ ~ "
_g_ _ IN VESSEL VISUAL EXAMINATION DATA SHEET PILGRIM NUCLEAR POWER STATION 3 Visual Examination of-Reactor Internals and Components By the Use of Underwater TV Cseera Video Tape No.: PILO-91-11 Dates e/01/91 4 lt Component (sJ and/or Description of Review Tape Area Viewed -Recordable Indications Accept Required Counts l SHROUD HEAD BOLT s21 NO APPARENT ABNORMAL YES N0 3772-4098 CONDITIONS */** I- YES NO 4098-4283 SHROUR HEAD BOLT s22 NO APPARENT ABNORMAL l CONDITIONS ** l I SHkOUD HEAD BOLT 823 NO APPARENT ABNORMAL YES NO 4283-4420 l l CONDITIONS ** 1. SHROUD HEAD BOLT #24 NO APFARENT ABNORMAL YES NO 4420-4606 l l CONDITIONS ** l LIFTING LUG BETWEEN .NO APPARENT ASNORMAL YES NO 4606-4829
- l BOLTS s24 AND s25 CONDITIONS **
t NO APPARENT ABNORMAL YES NO 4829-4965
.}l SHkOUD HEAD LOLT 825
=
l CONDITIONS ** I l, SHROUD HEAD BOLT s26 NO APPAEENT ABNORMAL YES NO 4965-5230 y CONDITIONS **
- 11 )
y SHROUD HEAD BOLT s27 No APPARENT ABNORMAL YES NO 5230-5401 l'. CCNDITIONS ** l l SHROUD HEAD BOLT s28 NO A? PARENT ABNORMAL .. YES NO 5401-5518 l CONDITIONS */** 115' LIFTING LUG NO APPARENT ABNORMAL YES NO 5518-5699 l l CONDITIONS */** 10* LITTING LUG
- NO APPARENT ABNORMAL YES No 5699-5946 CONDITIONS **
-l CAMERA ~ RESOLUTION 1 MIL WIRE 1 MIL WIRE RESOLVED YES NO 5946-5956 Reviewed by: g g, Level: y Dater j, g
- SCRATCHES'
=*-STAINS AND RUB / WEAR HARKS.
O l (t Vf a 4/
^*
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IN VESSEL VISUAL EXAMINAT!0N DATA SHEET PILGRIM NUCLEAR POWER STATION Visual Examination of Reactor Internals and Components (( By the Use of Underwater TV Camera Video Tape No.: PILG-91-12 Date 6/06/91 PERS0hnEL LEVEL EQUIPMENT - CALIBRATION - TECHNIQUE E M. HEATH III CAMERA: ETV-1250 RECORDER: PANASONIC AG-6200 l l M. STAMM III 1 MIL WIRE VISIBLE ON ALL RESOLUTION CHECKS l S. MONTICONE II TECHNICUE DESCRIPTION: HAND HELD CAMERA, STRAIGHT ON l LENS, 90 LENS, TWIN 50's ON CAMERA FOR LIGHTING l l Component (s) and/or Description of Review Tape l Recordable Indications Accept Required Counts ( Area Viewed 0 l hE LOOK OF JET NO APPARENT ABNORMAL YIS NO 0000-0542 PUMP e 10 CONDITIONS l CAMERA RESOLUTION 1 MIL WIRE RESOLVED YES NO 0542-0562
, 1 MIL WIRE NO APPARENT ABNORMAL YES NO 0562-9618 l N0ZZLE B-25 CORE g SPRAY SPARGER CONDITIONS
- l CAMERA RESOLUTION 1 MIL WIRE RESOLVED YES NO 0818-0870 l
l 1 MIL WIRE I NO APPARENT ABNORMAL YES NO 0870-1939 (MOISTURESEPERATOR l SHROUD HEAD BOLT e42 CONDITIONS ** H g SHROUD HEAD BOLT e41 NO APPARENT ABNORMAL YES NO 1039-1188 l CONDITIONS ** l NW LIFTING LUG NO APPARENT ABNORMAL YES NO 1188-1535 CONDITIONS ** 5 NO APPARENT ABNORMAL YES NO 1535-1723 CNDITIONS ** iSHROUDHEADBOLTe40 l YES NO 1723-1881 NO APPARENT ABNORMAL l SHROUD HEAD BOLT 839 CONDITIONS **
! SHROUD HEAD BOLT e38 NO APPARENT ABHORMAL YES No 1881-2042 CONDITIONS **
I YES NO 2042-2244 NO APPARENT ABNORMAL l SHROUD HEAD BOLT 837 I 8 g CONDITIONS ** ( , Reviewed by g . / Level: y Dates g ,g ,g
- RELOOK AT THE B-25 N0ZZLE AREA AND T BOX FOR PREVIOUSLY RECORDED INDICATIONS. NO INDICATIONS WERE FOUND. p ,p gf
-. - . ~ . . . - - - - .. - ..
IN VESSEL VISUAL EXAMINATION DATA SHEET PILGRIM NUCLEAR POWER STATION Visual Examination of Reactor Internals and Components By the Use of Underwater TV Camera Video Tape No.: PILG-91-12 Date 6/66/91 , l' Component (s) and/o:- Description of Review Tape i Area Viewed Recordable Indications Accept Required Counts l SHROUD HEAD BOLT 436 NO APPARENT ABNORMAL YES NO 2244-2375 l CONDITIONS ** g. NO APPAR2N1 ABNORMAL YES tio 2375-2520 lSHROUDHEADBOLT835 g CONDITIONS ** l NO 2520-2616 NO APPARENT ABNORMAL YES l SHROUD NEAD BOLT 434 l CONDITIONS ** lg-SHROUD HEAD' BOLT v33 NO APPARENT ABNORMAL YES NO 2616-2692 ' l CONDITIONS ** I YES NO 2692-2776 g SHROUD NFAD BOLT 832 NO APPARENT ABNORMAL g CONDITIONS ** [J
\/
l
' g SHROUD HEAD BOLT 431 g
NO APPAEENT ABNORMAL CONDITIONS ** YES NO 2776-2934 U-SHROUD HEAD BOLT G30 NO A2 PARENT ABNORMAL YES NO 2934-3038 CONDITIONS ** 0 y SHROUD HEAD BOLT v29 NO APPAkNT ABNORMAL YES No 3038-3164 y CONDITIONS ** I 3164-3545 g STAND TUBE s25 -No APPARENT ABNORML YES NO g CONDITIONS
- I YES N0 3545-3781 g STAND TUBE e26 NO APPARENT ABNORMAL l CONDITIONS X
g STAND TUBE e27 NO APPARENT ABNORMAL YES NO 3781-4014 g CONDITIONS
~ , , , , , .
^
Reviewed by: Level: y Date:
./ g g, g,
- STAIN MARKS
-** WEAR / RUB MARKS AND STAIN MARKS v
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i
IN VESSEL VISL'AL IXAMINATION DATA SHEET PILGRIM NUCLEAR POWER STATION Visual Examination of Reactor Internals and Components ( By the Use of Underwater TV Camera V1Geo Tape No.: PILG-91-12 Date 6/06/91 Review Tape fComponent(s) and/or Description of Recordable Indications Accept Required Counts g Area Viewed STAND TUBE #28 NO APPARENT ABNORMAL YES 11 0 4014-4227 CONDITIONS
- I NO APPARENT 1.BNOR.tAL YES N0 4227-4422 lSTANDTUBE#29 CONDITIONDS l
NO APPARENT ABNORMAL YES NO 4422-4542 CONDITIONS
- ISTANDTUBEe30 gSTANDTUBE#31 NO APPARENT ABNORMAL YES NO 4542-4b59 CONDITIONS
- STAND TUBE 432 No APPARENT ABNORMAL YES N0 4659-4808 CONDITIONS
- I NO APPARENT ABNORMAL YES NO 4808-4B98 ISTANDTUBEe3JCONDITIONd i NO APPARENT ABNORMAL YES NO 4898-5011 '
I, STAND TUBE #34 CONDITIONS
- NO APPARENT AENORMAL YES NO 5011-5076 STAND TUSE #35 I CONDITIONS -
NO APPARENT ABNORMAL YES NO 5076-5183 STAND TUBE 836 CONDITIONS I NO APPARENT ABNORMAL YES NO 5183-5295 CONDITIONS
- ISTANDTUBE#37 NO APPARENT ABNORMAL YES NO 5295-5386 ISTANDTUBE438CONDITIONS
- Level Date Reviewed by p,g y
- STAIN HARKS c e 72 */ C/
IN VESSEL VISUAL EXAMINATION DATA SHEET .
- PILGRIM NUCLEAR POWER STATION Visual Examination of Reactor Internals and Components By the Use of Underwater TV Camera Video Tape No.: PILG-91-12 Dates 6/06/91 4 1 l
Component (ss and/or- Description.of Review Tapa Area ~-Viewed Recordable Indications Accept Required Counts STAND TUBE #39 NO APPARENT ABNORMAL. YES No. 53B6-5440 I , CONDITIONS N g STAND TUBE e40 No APPARENT ABNORMAL YES NO 5440-5522 [ CONDITIONS STAND TUBE e41 NO APPARENT ABNORMAL YES NO 5522-5590 l CONDITIONS l i STAND TUSE e43 NO APPARENT ABNCRMAL YES No 5590-5715 CONDITIONS CAMERA RESOLUTION 1 MIL WIRE RESOLVED YES No- 5715-5726 1 MIL WIRE-
.\j '
1 U I i Il
- Il 11 11 H
U IL - - - Reviewed by: Level: Dates
./ y g,q,7
. STAIN MARKS
\
SJ */ til 1
IN VESSEL VISUAL EXAMINATION DATA SHEET PILGRIM NUCLEAR POWER STATION Visual E.anination of Reactor Internula and Components , By the Use of Undersater TV Camera 'h Video Tape No. : PILG 91-13 Dater 6/06/92 LEVEL EQUIPMENT - CALIBRATION - TECHNIOUE PERSONNEL 7 CAMERA: ETV- 1250 RECORDER PANASONIC AG-6200 III M. STAMM III 1 MIL WIRE VISIBLE ON ALL RESOLUTION CHECKS
- IM. HEATH S. MONTICONE II TECHNIQUE DESCRIPTION: HAND HELD CAMERA, STRAIG,HT ON LENS, 90 LENS, TWIN 50'S ON CAMERA FOR LIGHTING Review Tape component (s) and/or ' Description of Recordable Indications Accept Retvired Counts
{ Area Viewed a=w.a 1 MIL VIRE RESOLVED YES No 9000 0052 j CAMERA RE'iOLUTION j1MILWIREANDTITLE I NO APPARENT ABNORMAL YES NO 9052-0755 l STEAM DRYER BANK s3 0* CONDITIONS l
'l BANX s2 AND e3 TIE NO APPARENT ABHORMAL YES NO 0755-1984 l
Ci. [ BAR WELD 180* TO O' CONDITIONS I I 1884-1136 NO APPARENT ABNORMAL YES NO l BANK s3'AND MANWAY g COVER CONDITIOt.5 NO APPARENT ABNORMAL YES NO 1136-1175 BANK #3 CONDITIONS l YES NO 117S-1291 BANK s2 TIF BAR WELD NO APPARENT ABNORMAL 0' TO 180' CONDITIONS I NO APPAREUT ABNORMAL YES NO 1291-1402 l BANK s2 BANK TO VERTICAL WELD 180* CONDITIONS NO APPARENT ABNORMAL YES NO 140?-1468 l BANK s2 TIE BAR WELD CONDITIONS l 180* TO O' I NO APPARENT ABNORMAL YES NO 1468-1543 l BANK s2 AND el TIE CONDITIONS IBARWELD0*TO180" BANK el TIE BAR VELD g 180' TO O' NO APPARENT ABNORMAL CONDITIONS YES NO 1543-1615 I NO APPARENT ABNORMAL YES NO 1615-1693 l BANK s1 BANK TO *
- 0" CONDITIONS lVERTICALWELD Dates Reviewed by: y')/, [ g g Level --
.f7f- g,q, REF. GE SIL 474 ( ATT 40) STEAM DRYER CHANNEL AND SUPPORT RING. .f f & / /
t IN VESSEL VISUAL EXAMINATION DATA SHEET I PlLGRIM NUCLIAR POWER STATION
- t. Visual Exteination of Reactor Internals and Components j ,
By the Use of Underwater TV Camera Video Tape No.: PILG-91-13 Date 6/06/91 L Tape Component (s) and/or Description of Review l Required Counts Area Viewed Recordable Irdications Accept CAMEkA RESOLUTION 1 MIL WIRE RESOLVED YES I NO 1693-1700
] 1 MIL WIRE l YES NO 1700 1953 NO APPARENT ABNORMAL l BANK 82 CORNER WELD -
g EAST SIDE 0* TO 180' CONDITIONS 1 NO APPARENT ABNORMAL YES NO 1953-2231 l BANK s2 CORNER WELD WEST SIDE 0' TO 180" CONDITIONS l ~ l NO APPARENT ABNORMAL YES NO 2231-2446 g BANK e3 BANK TO CONDITIONS . l VERTICAL PLATE WELD g e' BANK #1 CORNER WELD NO APPARENT ABNORMAL YES NO 2446-3440 g 180* TO 0 CONDITIONS l BANK e4 IIANWAY EAST NO APPARENT ABNORMAL YES NO 3448-3504 lg.31DE CONDITIONS ll 11 ll - 11 t i I I I; D I U q ,l Reviewed by: Levelt y Dater g p, REF. GE SIL 474 (ATT 40) STEAM DRYER CHANNEL AND SUPPORT RING. Q, t 1
\
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fi w // l ___--____-____________--_______---__________.__2__--_-_-__.-_ . . _ _ - . _ _ _ _ _ _ _ .
IN VESSEL VISUAL EXAMINA?ICH DATA SHEET PILGRIM NUCLEAR POWER STATION Visual Examination of Reactor Internals and Componente ((, By the Use of Underwater TV Camera Video Tape No. : PILG-91-14 Date 6/06/91 i PERSONNEL LEVEL EQUIPMENT - CALIBRATION - TECHNIQUE l M. HEATH III CAMERA: ETV-1250 RECORDER: PANASONIC 70-6200 . M. STAMM III 1 MIL WIRE VIS)BLE ON ALL RESOLUTION CHECKS S. MONTICONE II TECHNIQUE DESCRIPTION: HAND HELD CAMERA, STRAIGHT ON LENS, 90 LLNS, TWIN 50's' ON CAMERA FOR LIGHTING f Ir l Component (s) and/or Description of Review . Tape l Area Viewed . Recordable Indicaticas Accept Required Counts p _ - B' CORE SPkAY 'T' NO APPARENT ABNORMAL YES No 0000-1415 g ' BOX 34I CONDITIONS
~
l l 1 MIL WIRE hESOLVED YES NO 1415-1484 l CAMERA RESOLUT10N l 1 MIL WIRE
.' I I
I W 4 l! W 5 H R I X R X l 1 1 R I 1 e 4 feviewed by: g g Levelt y Dater d-&-f/ THE *B' CORE SPRAY SPARGER, 'T" BOX, BETWEEN 'T' BOX AND THE B25 N0ZZEL WERE WIRED, BRUSHED AND VIDEO TAPED WITH CLOSE HIGH RESOLUTION AND SENSITIVITY TO VERITY corutrutet v orcoRnin DATA. NO ~NDICATIONS WERE OBSERVED. fg ,p g/
4 IN VESSEL VISUAL EXAMINATION DATA SHEET PILGRIM NUCLEAR = POWER STATION Visual Examination of Reactor Internals and Components
- . By the Use of Underwater TV Camera Video Tape No.: PILG-91-15 Dates 6/14/91 FERSONNEL LEVEL EQUIPMENT - CALIBRATION -
TECHN10VE M. HEATH III CAMERA: ETV-1250 hECORDER: PANASONIC AG-6200 M. STAMM III I MIL WIRE VISIBLE ON ALL RESOLUTION CHECKS S. MONTICONE II l TECHNIOVE DESCRIPTION: HAND HELD. CAMERA, STRAIGHT ON
-l LENS, 90 LENS, TWIN 50's ON CAMERA FOR LIGHTING l
i g Component (s) and/or Description of Review Tape y Area Viewed Recordable Indications Accept Required Counts l CAMERA RESOLUTION 1 MIL WIRE, RESOLVED YES NO 9000-8024 l 1 MIL WIRE AND TITLE I l LEVELING SCREW BY THE 9 2' LONG CRACK YES YES. 0024-0135 l 35 LIFIIN.G LUG
, ,_I ..r- g LEVELING SCkEW'BY THE 913/4" LONG CRACK YES TES. 0135-0178 y 215 LIFTING LUG W
q LEVELING SCREW BY THE NO APPARENT AbHORMAL YES NO 0178-0203 g 155 LIFTING LUG CONDITIONS U l LEVELING SCREW BY THE NO APPARENT ABNORMAL YES NO 0203-0232 l 335 LIFTING LUG CONDITIONS I I I I I l
- l-H I
I l 0 l R { -
. 0 .r l 1
Reviewed by: g g Level y Date g. y.gf REF. GE NCR-E-68645-008' REF. GE LETTER :(EVALUATION OF STEAM DRYER LEVELING SCREW CRACKS 19 JUNE 91), RECOMMINDS TO RUN AS IS. gy ,p g/
~. GE Nuclest Energy
~
Q,,, ' ~ ~ ~ ~ ~ ~ - [. tncas.c u se5.u m u nta 19 June 1991 H. E. Shepherd Site Services Manager Pilgrin Station SUB.7ECT: Evaluation of Steam Dryer Leveling screw Cracks
REFERENCES:
- 1. DRT B13- 01538-19
- 2. FDDR MKl-0505 Rev 3 Pilgrin Dryer Repair
- 3. EAS 97-0887 August 1987, Pilgrim Nuclear Power, Station Steam Dryer Evaluation GE Nuclear Energy has reviewed and evaluated video tapes of the visual inspection of the steam dryer at the Pilgrin Station.
f The purpose af this letter is to report the results of that avaluation. The verification for this letter is contained in
~ Reference 1.
BACKGROUND: In the 1987 refueling outage cracks were observed adjacent to the tack welds for two of the four steam dryer leveling screws. The IcVeling screws with -cracked tack welds were located at 35 and 215 degrees. The cracxs extended for the full length of the tack welds. There was no evidence that the leveling screws had rotated due to the cracked welds. The cracked tack welds had performed like a mechanical locking device. These cracks were repaired per Reference 2 and evaluated in Reference 3. The repair consisted of adding'two new tack welds to each of the two leveling screws with cracked tack welds. The welding was performed underwater. . The original construction tack weld design was one 0.25 inch fillet. weld 0.50 inch long for each leveling screw. The repair , tact weld design was two 0.375 inch fillet welds 1.0 inch long , for each leveling screw. The cracked original construction tack welds were not removed. f 8 *F C/
=- - - - _ _ ,
[ , , , . DISCUSS 10N: During the 1991 refueling outage cracks were observed adjacent Since the original cracks to the same two leveling screws. were not removed, this by itself was to be expected. However, the current cracks are longer than those in 1987. The cracks have propagated into the new tack welds.' The current length of the cracks 'is difficult to accurately determine as no measurement device was lowered and included in the video. The design size of welds per AWs is a mininum. Thus the actual tack walds could be larger than the drawing specified valus. It is judged that all three tack The welds are tack welds significantly larger than the design length. are the only visible feature that can be used to estimate the length.of the cracks. It is judged that the crack adjacent the 35 degree leveling screw is approximately 150 to 180 degrees around the circumference of the screw. One and of the crack can be clearly seen. It is judged that the crack adjacent the 215 degree leveling screw extends the full length ofItthe is $cdged inspection, Neither end of the crack is visible.
- that the crack length is greater than 180 degr.aes. The ends of the tack welds behind the leveling cerews are not visible.
/T Thus the total length of tha 'eelds can not be quantified. For both the 35 and the 215 degree leveling screws, the cracks are
(#) open a small amount adjacent to the original tack welds and are much tighter adjacent to the repair tack weldr. The cracks are primari1.y located in the dryer support ring at the toe of the tack welds. Since the repair tack welds are larger than the original tack weld, the cracks do not follow a circular path. Instead the cracks follow the irregular contour of the tack welds. e v.- JFf . - t/
- ._m_._ _ _ . . . _ --- __ ___ __ _ --__ _ _ _ __ - - - - - - - _ _ _ _ k_ - The cause of the cracks was stated in Reference 3 to be fatigae. The current judgenent is that the cause of the cracks is intergranular stress corrosion cracking (IGSCC). The bases for the revised judgement are as follows. (1) A fatigue crack would follow a smooth well defined path along the region of maximum alternating stress. These cracks do not follow a smooth path. These cracks are not located in the region of highest alternating stress, which for a fillet veld 1s-through the throat of the veld. Thase cracks instead follow the ' irregular path of lower stress at the toe of the fillet veld. (2) Many BWR's have reported IGSCC cracks in the steam dryer support ri.4g. All of theso cracks have been located within approximately one inch of a we.id. These cracks have'been shown to be IGscc through the use of nota 11ographic examination of crack samples. The support ring is fabricated by cold rolling a piece of flat plate. Then many pieces are welded to the support ring without any heat treatment. Thus the support ring is sensitized due to both cold work and welding. The ..upport ring also has significant residual stress due to both rolling and welding. The leveling screws are used to tranonit the weight of the steam dryer to the four reactor pressure vessel (RPV)' brackets. At initial reactor assembly the feur invaling screws Vere installed to be in contact with their respective RFV bracket (g and then. tack welded to lock them in position. The only purpose of the tack welds is to prevent turning of the leveling screws. The leveling screws are loaded in compression. Thus the highest loaded threads are at the bottom of the scrsw (the and opposite the tack welds) . The steam dryer is classified as not safety related and is not under the jurisdiction of the ASME code. 4 9 m W
- a. ., -
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$ RECODIENDATION:
GE recommends that the cracks be dispositioned as accept as is. GE also recommends that the cracks be visually insp4cted during the next refueling outage to determine if there had been'any leveling screw rotation or significant crack extension. The bases for these reconnendations are as follown. (1) There currently is adequate uncracked weld on the 35 degree leveling screws. (2) The growth rate of the cracks since 1987 nas been
- slow enough such that sufficient tack weld should remain on the 35 degree leveling screw at least until the next refueling _
outage to perform the locking function. (3) It is not known-if
- the crack adjacent to tha 215 degree leveling screw extends the full length of the tack welds because the ends of the crack and the ends of the tack weld are not visible. Since the crack j
adjacent to the repair tack welds is tight, it is judged that
.the crack has not propagated through the full thickness of the tack welds. (4) Even if the crack should propagate completely through the weld thickness and all the way around the leveling screw, the weld will perform its function because the crack contour will not: allow.th6 screw to turn. In essence the completely cracked tack weld would become a mechanical locking device. This was denonstrated by the lack of leveling screw
. rotation that was observed in 1987. (5) Even if it is postulated tnat the leveling screws torn sufficiently to take r~s '
I them out of contact with the RPV brackets, there will be no
\ efftcu on dryer perforrance and there will be no safety consequences. of course, in this extreme casa the repair necessary during the next refueling optage may be more extensive.
Prepared by Verified by [ e d O. 3
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J. E. Charnley M. O. Lenz Principal Engineer Engineer Reactor Design Engineering Reactor Components Design 4 4 4 ,
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6 PILGRIM NUCLEAR POWER STATION INVESSEL VISUAL INSPECTIONS EIGl!Til REFUELING AND INSPECTION OUTAGE SECTION V PROCEDURE O e - o V (?
{( BOSTON EDISON , PILGR!H NUCLEAR POWER STATION Temporary Procedure No. TP91-080 INVESSEl. VISUAL INSPECTION (IVVI) PROCEDURE FOR BWR-3 REACTOR PRESSURE VESSEL INTERNALS
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G GE Nuclear Energy PROCEDURE NO.: GE-VT-204 TITLE aEvision No.: , INVESSELVISUALINSFECTION(IVVI)PROCEDUREFOR (' BWR-3 REACTOR PRESSURE VESSEL INTERNALS mreu s ee. uvato ev: . m o n o r m a t er:
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NO. GE-YT-204 REY. 9 PAGE I OT 24 p
@- GE Nuc/ car Energy TITLE INVESSEL VISUAL INSPECTION (IVVI)
PROCED'JRE FOR BWR 3 RPV INTERNALS
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C TABLE OF CONTENTS SECTION DESCRIPTION , MQI
- 1. 0 SCOPE 2
- 2. 0 REFERENCES 2
- 3. 0 PERSONNEL . 3
- 4. 0 EQUIPMENT 3
- 5. 0 CALIBRATION 5
" 6. 0 EXAMINATION 5
- 7. 0 RECORDING IB
- 8. 0 EVALUATIDH 19
- 9. 0 REPORTS 20 EXHIBIT I 21 b EXHIBIT II EXHIBIT III 23 Figure 1 24 e e TP91-080 Rev. O Page 3 of 26
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m_ f k0. CE VT+N4 REh 4 PAUL 2 0F 24 TITLEt !!!YtaSEL VISUAL 'fHEPECTION (1YVI) GE Nuclear Energy rRo:EDURE FOR BWi *> KPV INTERNALS 1.. rm 1.1 This procedure defines the method and requirenehts for YT-1 and YT 3, Invessel Visual Inspection (IVV!) of the Reactor Pressure Vessel (RPV), General Electric Boilir.g Water Reacter (BVR), type 7HREE (3) internals which are made accessible during scheduled refueiing Ans afintenance outages. This procedure seets the requiresents GT the An'e rictn Sc;19ty of Mechanical Engineers (ASME) Boiler and Pressurt Ct,de, Tabl* IVB 2500, Exteinstion Categories B N 1 and B N 2. Augmented inspection requirements are also defined in this procedure. 1.2 This procedure can be utilized in its entirety or pettiens thereef, as
" directed by the Insers.*ce Inspection (151) Prograe er the specified outage workacope. The inspections can be conducted in any order so as to allow for increase in production or to support other operations during refueling and usintenance outages.
2.0 PEPEREli.CII fm 2* Aeerican Society cf Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section V a,d XI.
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2.2 General Electric Procedure, TCP-03, ' Procedure iw Qualification and Certification cf Wondestructive Examination Personnel, which meets the requireeents of the 'Aterican Society of Ncndestructive Testing (ASNT), Recconended Practice No. SNT-TC-1A, 1975 and 1980 Edition.
- 2. 3 A>erican National Standard Institute (ANSI), " Qualification of Personnel,' ANSI N45.2.6, 1978 Edition.
- 2. 4 United States Nuclear Reguistory Cornission (USHRC), 1.E. Bulletin Nueber 80 13, dated May 12, 1960.
- 2. 5 USNRC NUREG-0619, 'BWR Feedvater Hozzle and CRD Return Line Nozzle Cracking.'
- 2. 6 USHRC Regulatory Guide 1.147. ' Inservice Inspection Code Case Acceptability, ASKE Section XI, Division 1.'
2.7 GE Service Information Letter (SIL) Number 289, Core Spray Sparger Visual Inspection, dated February, 1979.
- 2. 8 GE SIL Number 409, Incore Dry Tube Cracks dated July, 1986.
- 2. 9 GE SIL Nuaber 422, Inspection of Jet Pump Sensing Line, dated March, 1985.
2.10 GE SIL Number 465, Jet Punp Mixer Unurual Surface CSeervation, dated May, 1988. 1P91-0B0 Rev. O Page 4 of 26
. . . - . . _ _ _ . . _ - 21. Z. Z.~ " " -' _ ._
f , NO. UE Y1 204 REY. S PAGE 3 0F 24 TITLE: INYFSSEL V3EUAL INSPECT!0W (!VV1) GE Nuclear Energy pro:CouRE ron svn 3 RPv xxTEnxAt.S g b 2.11 GE SIL Number 474, Steam Dryer Channel Cracking, dated October, 198B. 2.12 GE E!L Number 515, Reactor Pressure Vessel Head Linear Indications, dated May 3, 1990. 2.13 DE RICS!L Number 250, Reactor Pressure ,'esetl Head Clad Cracking, dated April 12, 1990. 2.14 DE RICSIL Wueber 854, Core Support Shroud Crack Indications, dated November, 1990. 2.15 ASME Code Case N-424, ' Qualification of visual exaeinstion personnel, Section XI, Division 1.' 2.16 ASME Code Case 1730, 'Exatination - Acceptance standards for surface indications in cladding, Section XI.' 3.0 PERS0WNEL 3.1 All personnel performing YT 1 visusi exatinations shall be trained, qualified and certified to at least a VT-1 Level 11 in accordance with fi the GE Procedure TGP 03 or equivalent. ( l 3. 2 All personnel performing YT-3 visual examinations shall be trained, I qualified and certified to at least a VT-3 Level II in accordance with l the GE Procedure TCP-t3 or equivalent. 3.3 The visual exaniners are required to cowplete the appropriate data sheets for the exatinations that are performed and record the examination results of those exatinations.
- 3. 4 Personnel periorsing the visual exarination shall additionally be knowledgeable regarding the couponent being exarined and be able to identify celeterious indications relative to that component.
3.5 Personnel shall be knowledgeable in the underwater reacte visual exavination process and equiptent. The underwater casera techniciana l shall be knowledgeable and have experience with the underwater camera equipment. The technicians may be required to demonstrate their proficiency of the underwater camera handling capabilities to the lead visual examiner prior to performing 3Ay,r.9,IL over the Reactor Cavity. 3.6 All personnel performing exaeinstions per this procedure shall be trained in the handling of Radioactive seterials and special precautions necessary when verking in a radiation or a radioactively contatination area. e - 4.0 00VIPMENT ROTE: Certain equiptent is reqrited to pterfort particular IVV! exatinations. The following checklist provides a list of equiptent that any be used during particular IVVI examinations: . - - TP91-080
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TITLE: SE-VT-264 REV. 8 PAGE 4 DF to INVESSEL VISUAL INSDECT10N (IVVI) enoEEount ron swa 3 RpV ,1NTEnsats b l 4.1 ' Refueling bridge er service platfors. i 1 4.2 underwater closed circuit Television Castra Systes. ! a) Two (2) Underwater Caseras b) Two (2) Underwater Castra Control Units, b6ckup boards and tubes. c) Two (2) 125 foot cable harness. d) Lighted straight view tens attacheent. e). Lighted right angle sirror attachsent. f) Two (2) High resolution TV sonitors (regular sonitors if required)..
- 4. 3 An IVV1 resolution fixture, holding the 9.901 inch disseter wird and/or a 18% neutral grey card (GE visual cosparator card) with a 1/32 inch black line.
- 4. 4 Character generator with power supply.
4.5 Connecting cables. 4.6 Two (2) Microphones. 4.7 Video tapes (super o.' regular VHS) as required.
- 4. 8 Float bon for a viewing aid.
4.9 Work table for electronics. 4.19 Two (2) High resolution (super or regular) video tape recorders as required. 4.11 General area light (s) (required for resolution). I I 4.!! Local area light (s) (required for resolution). l ! 4.13 Ny!?1 rope (250 feet). 4.14 Seall handling poles (ISO feet). 4.15 Saall set of air pliers. l 4.16 Inspection fluture (optional): al Core spray sparger inspection feature. b) Casera holding fluture (general use). c) Dry tube inspection fixture. TP91 0B0 Rev. O Page.6 of 26
- . -. . = -. :.- --.. -.:... = :-- ... - .-.
NO. GE-VT-104 REV. e PAGE 5 DF C4 TITLE: INVES!!L VISU4L INSPECT!DN (!VVII GE Nuclear Energy PROCEDURE FOR BWR 3 REV INTERNALS d)Steas dryer inspection fluture, e) Resote operated vehicles. 5.8 EALIPRATION 5.1 When perforsing the IVV! of the core spray pipinD internal brackets, core spray internal piping, core spray spargers and core spray sparger brackets, the IVV! resolution requiresents shall be considered adequate and Qualified when the cosbined 11thting, access and angle of vision is suf ficient to resolve a 0.001 inch disseter wire. This resolution wtre
.say be located in an IVV1 resolution fisture.
- 5. 2 When perforsing the IVV1 of the ressining components that are listed in this procedure, the IVV! resolution shall be considered adequate and quallfled when the combined lighting, access and angle of vision is sufficient to resolve a 1/32 inch black line on a 18% neutral gray card. This resolution standard say be located in an IVV1 resolution flature.
- 5. 3 There are no specific VT-3 resolution requirements; however, when perforsing esaminations in accordance with this procedure, the resolution requirements of the VT-3 esasinattens shall be at least equal tt that of a VT-1 resolution as identified in paragraph 5.2.
- 5. 4 The IVV1 casera resolution shall be performed only once on each sajor cosponent or every twelve (12) hours or when changes are made to the eQunpsent. The castra to cosponent distance should remain as constant as possible during the esasination after the resolution has been verified.
NOTE: !VV! video castra resolution is rtQuired on both the live video 1 sages as well as the recorded vidte tape image. 6.0 ETAMINDTION 6.1 Procedure General Requirements 6.1.1 Reactor shut down and renovable (Reactor Vesstl fr'ternals) itess i renoved for normal refueling.
. 6.1. 2 Reactor cavity water level at the norsal full level for IVV! ; ,
perforsed free the refuel bridge, or just below the RPV Flangt i when perf orsing the IVV! free the service plat fors. !
, 6.1.3 Reactor water tesperatures should be saintained at less than 90 ;
degrees Fahrenheit and water clarity shall be suf ficient for the ( esasiners to view the castra position and to establish tt.e i necessary resolution with castra syntes. ' TP91-080 Rev. O Page 7 of 26
._ . : - .,7- - ._. 2 .r m * - -.. . . -
l j ND. SE-VT-284 REY. 8 PAGE 6 DF 24 l TITLE 1NVESSEL V!$UAL 1NSPECT!DN (IVV1) i GE Nuclear Energy PRDOEDURE FOR SWR 3 RPu !NTERN4LS ] l l NOTE: The water tesperature of 90 degrees Fahrenheit er less is l recessended for a higher quality esasination. Water tesperature affects the esasination in several wayst
- a) Temperatures above 148 degrees Fahrenheit and 122 degrees Fahrenheit say adversely affect'the B/W (Westinghouse Model ETV-1250) and color casera (Westinghouse Model ETV-1256) heads respectively.
b) Theraal distortion (heat waves) of the visual emasination begin around 100 degrees Fahrenheit and progressively worsen, at which time the IVV1 enasination say be impossible to perfors. c1 Husidity on the refuel flaer generally increases with an increase in the water tesperature. The Westinghouse ETV-1250 ans ETV-1256 Castra Control Units operate with relative busidity in the range fres 8 to 95% (non-condensing). ' 6.1. 4 Assure the required equipment is available, set up, operationally tested and ready for une during the exasination. 6.1. 5 Reactor water clarity shall be established and judged satisfactory ( U r,the emasination by the lead GE Level !! or Level !!! eussiner. 6.1. 6 Access for perforsing visual emasination of the dry tubes and control cell components requires the appropriate fuel assesblies to be removed. 6.1.7 Access for perforsing IVV1 below the top guide and the core plate requires the appropriate control cells to be disassembled. (ie, renoval of the 4 fuel assemblies, control rod drive (CRD), CRD thersal sleTve, placesent of a valve flange over the CRD housing flange, fuel support casting, control red blade and guide tube. 6.1. 8 All work shall be perforsed in accordance with the owner's Health Physics Procedures and industrial safety requirements. 6.1. 9 Ensure that proper health physics coverage is provided during the renoval or installation of any itess free the RPV. 6.1.18 All tools, equipment and saterials used in a designated tool control area shall be Icoged into and out of the area. Tools and associated equipment to be used over the reactor cavity or RPV shall be tied of f to prevent anything dropping into the RPV. Specific requirements for such control are beyond the scope of
-, this procedure, but sust be consistent with owner's requirements and/or procedures.
6.1.11 Prior to emasination, all parts of the invessel casera or sanipulator(s) (nut s, bolt s, etc. ) shall be' captured or properly retsined to prevent lost in the Reactor Vessel. Page 8 of 26
N3. r,E-VT-204 REV. O PAGE 7 0F 24 f t, ) TITLE: INVESSEL VISUAL IN$pECTj0N (tyyg) pao:EounE ron nun 3 nov iwTrw.ss GE Nuclear Energy , t 6.1.12 The emasination shall be recorded on video tape with voice recording and character generator, unless otherwise 10dicated by own t r. 6.1.13 Where required, particular attention shall be given to each welded joint and the heat affected gone (KAZ) associated with each welded joint. . 6.1.14 When using optical aids to isprove the angle of vision and/or resolution, care sust be taken to ensure that the eQuipsent does not shadow the area of interest or otherwise mask the emasination area. 6.3.15 The video tape recorded during the emasination should be reviewed by an independent Level 11 or Level Ill IVV1 Visual Emasiner. Tisely review of those tapes could resolve any questions prior to IVVI eQuiptent being disassembled or resoved from the area of emasination. 6.1.16 All are-s and components emasined by the resote underwater television syntes shall have the systes cualif ted by verifying the IVVI resolution requiresents appropriate to the amasination being perforsed, per paragraph 5.2. (i 6.2 Resete Televisten Technieves - TVV1 6.2.1 When a video recorder is used during the emanination, do not run the recorder constantly. Achieve the best resolution and focus postible. When the emasiner is satisfied with the picture, begin the recording. Record still 1: ages for about 20 seconds. During scans, continue to record at the end of the scan for about 20 seconds. At the end of an isage recording, press the pause button on the recorder. This will provide for a smooth transition from one 1 sage to another without loss of any previously taped images. Additionally, it will elisinate emeessive reviewing and editin3 time. 6.2.2 Perfora a visurl scan of cosponents by soving the television casera slowly across the cosponent surface, pausing at each weld so that the emaniner can verify whether or not flaw indications are present.
- 6. 3 Evas tner's Duties 6.3.1 Emasiners shall sign of f the invessel visual emasination data sheet (s) as required (See Exhibit 11 and III).
6.3.2 Review the video tape 45 each cosponent is emasined and check the (g tape for quality, cospleteness and accuracy. Fill in the appropriate inforsation on the invessel visual emaninetion data sheet (s). (See Exhibit !! and III). TP91-0B0 Rev. O Page 9 of 26
I f No. SE-VT-204 REV. t PAGE 8 or 24 TITLE: INVESSEt. VISUE INSPECT!DN (IVV!)
# pao:Eount Fon un 3 nov,1wTERNst.s GENuclear Energy Y
6.3.3 Using the underwater television systes and adequate lighting, emasine those areas as outifned in the procedure for canditions listed on each component. An) abnormalities should be docusented with video recording and appropriate supplesental docusentation shall be attached to the data package. (See Exhibit !! and !!!).
- 6. 4 ASME Code Recuiresents - TVVI 6.4.1 ASME Section XI Code, Subsection IWA-2211 Visual Emasination VT-1:
a) The VT-1 visual emasination shall be conducted to detersine the condition of the part, cosponent, or surf ace emasined. including such conditions as cracks, wear, corrosion, erosion or physical dasage on the surface of the part or component. b) Dietet H sual emasination say be conducted when access is sufficient to place the eye within 24 inches (61 es) of the surface to be emasined and at an angle not 1965 than 30 degrees to th9 surface. Mirrors say be used to improve the angle of vision and aids such as a sagnifying lens say be used to assist emasinations. The specific part, component, or section thereof, under insediate emasination, shall be 111usinated, as necessary, with a flashlight or other CO auxiliary lighting, to attain a sinisus of 15 foot candles (fe) for general emasination and a sinisus of 50 fc for the detection or Study of small indications. In addition, illusination of the area to be emasineo pay be required at right or oblique angles to eupose cracks or evidence of corrosion or erosion. Resolution shall be considered adequate and qualified when the combined lighting, access and angle of vision is sufficient to resolve a 1/32 inch black line on a 18% neutral gray (GE visual comparator). card. c) Resett visual emanination say be perforsed where conditions exist that prevent direct visual emasination. Resote visual emasination say include visual aids such as telescopes. l periscopes, binoculars, fiber optics, televisten cameras and sonitornng systest or other suitable instruments. Resote l techniques shall desonstrate the ability to provide a resolution at least equivalent to that obtained by direct t visual emasination. Mirrors, noveable lights rotating optics I or any cosbination thereof say be utilized to display cracks, surface scratches, or evidence of corrosion, erosion, l sisalignsent or sovement. In the event remote visual
- emasination is required utilizing remote equipsent, l evaluations shall be perforstd by personnel with experience in i the sethod selected.
wb t TP91-080 Rev. O i Page 10 of 26 l ... _ _
9 GE Nuclear Energy ND. TITLE: GE-VT-204 REV. 8 PA3E 9 0F 24 INVESSEL VISUAL INSPECfloN (IVVI: pro: Count roR SWR 3 RPV ,1NTERNALS 6.4.2 ASME Section XI Code, Subsection IW4-2213 Visual Emasination VT-3: a) The visual emasination shall be conducted to detersine the general sechanical and structural condition of cosponents and their supperts, such as the presence of loose parts, debris, or abncesal corrosion products, wear, erosion, corrosion and the loss of integrity at bolted or welded connections. b) The VT-3 visual emasination say require, as applicable to determine structural integrity, the seasuresent of clearances, detection of physical displacesent, structural adequacy of supporting elesents, connection between load carrying structural sesbers and tightness of bolting. 6.4.3 For component supports and cosponent interiors, the visual emasinations say be performed resotely with or without optical aids to verify the structural integrity of the component.
- 6. 5 E=asinatten A.eas r.eneral 6.5.1 The following cosponents, when required to be emastned using this procedure, shall be emasined per the sethods indicated and the
( results of the IVV1 emasination noted on the data sheets. 6.5.2 Visual emasinations are required to be performed on the accessible areas which are defined as the space above and below the Reactor Core that is sade accessible for emasinations by renoval of components during norsal refueling outages. 6.6 Above f*;,r Plate Esasinatten (A*DE) Genees)
- 6. 6.1 The steam dryer hold down lugs and the top head emasinations should be performed by the direct visual sethod.
6.6.2 The shroud, shroud support welds, jet pump diffuser welds, jet pusp sensing line brackets and the access cover welds should be inspected during the jet pusp assembly emanination. It will be difficult to view any large areas within the shroud and vessel wall due to 11 sited accessibility. 6.6.3 The emasination of the steas dryer and separator are performed while in the flonded equipment storage pool. This will require lose fors of access for the casera holders from above, such as the refueling bridge. l 6.6.4 The following components shall be emasined in accordance with the ISI Progras er outage workscope and the following conditions recorded as a sinisus on the applicable data sheets (( ' 6.7 G,.laddine Dstches - ACPE tif required) l I l 6. 7.1 Condition of cladding patches. i 1P91-080 Rev. O i Page 11 of 26
)
(
- NO. GE-VT.264 REV. 9 PAGE le DF 24 J
V TITLE: INVESSEL VISUAL INSPECT 104 (1VV1) GE Nuclear Energy paa:EDUP.E FOR SWR 3 RPV INTERNALS 6.7.2 Note general cendition of cladding observed.
- 6. 8 Guide Red - ACDE *
- 6. 8.1 Condition of bracket to vessel wall weld.
6.8.2 General condition of upper guide rod bracket.
- 6. 4. 3 Condition of plug weld.
- 6. 8. 4 General condition of guide rod including the lower plug and bracket attachment to the throud.
- 6. 8. 5 Record the guide rod arisuth emasined.
6.9 St ese Dever Succe*t Bracket - ACDE 6.9.1 Condition of bracket to vessel wall wald. 6.9.2 Condition of dryer stating surface for wear. 6.9.3 Record the steam dryer support brackets emastned. V 6.10 Steas Devee Hold Down Prathet - ACDE 6.10.1 Condition of dryer hold down bracket s. 6.10.2 Condition of the seating surface. 6.18.3 Condition of the attachment weld to the RPV head. 6.10.4' Record the stese dryer hold down bracket a21suth emasined. NOTCt This inspection is performed using direct visual techniques while the RPV head is on its storage pedestals. 6.11 Resetor Dressure Vessel Head - ACDE 6.11.1 General Condition of the inside surface adjacent to the top head vertical and herfrontal pressure vessel welds (clad or unciacded). 6.11.2 Record the location of the head weld emasined. NOTE: This inspection is performed using direct visual techniques while the RPV Head is on its storage pedestals. 6.12 Fe edwat er Scareer End Bracket - DCDE l l t 6.12.1 Condition of bracket to vessel wall weld. C. 6.12.2 General condition of bracket. 6.12.3 Record the feedwater sparger and bracket azieuth emaninec TP91-0B0 Rev. O Page 12 of 26
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O N3. GE-VT-204 REV. O PAGE 11 OF 24 TITLE: INVESSEL VISUE INSPECTION (Ivv!) GE Nuclear Energy Pao:EDURE FOR BWR 3 RpV INTERggs l ( m._ l l 6.13 f e edwat er les*et* - 4CDE 6.13.1 General condition of feedwater sparger. l 6.13.2 Condition of sparger welds. 6.13.3 Condition of nogale welds er flow holes as applicable. 6.13.4 Condition of end bracket pins and tack welds. 6.13.5 Condition cf end bracket welds l 6.13.6 Record the Fredwater Sparger 421suth enastnec. l 6.14 Feed =ater Nerrie - AC E l 6.14.1 Condition of the nortle inner radius accessible areas. 6.14.2 Condition of nozzle bore accessible areas. 6.14.3 Record the Feed =ater Norrle atinuth emasined. 6.15 te-e Serav tya r nal pietne uall Bracket - ArcE_ O 6.15.1 Condition of bracket to vessel wall welds. 6.15.2 Condition of the bolt head taek welds. 6.15.3 General condation of the bracket. 6.15.4. Record the core spray internal piping wall brackets emasined. ! ! 6.16 per Seeav Int ernal DieLn.c - ACDE 6.16.1 General condition of core spray header piping. ! 6.16.2 Condition of core spray header welds. 6.16.3 General condition of core spray downeeser piping. 6.16.4 Conditten of core spray downtoner welds. i
- f. . .. $ Condition of elbow welds.
l
- l In16.6 Condition of junction (teel box welds with particular attention to the heat affected rone of the flow divider welds.
6.16.7 condition of junction (teel box to thereal sleeve area.
<( 6.16.8 Record the arisuth or loop emasined.
TP91-0B0 Rev. 0
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ND. BE-VT-284 REV. 8 PAGE la DF 24 TITLE: sNVESSEL VISUAL INSPECTION (!VV1) GE Nuclear Energy PRD:EDURE FOR BWR 3 RP 1NTERNALS Q . l 6.1? Cere Serav Searere - Arpt 6.17.1 Esas ue the four core spray spargers in at least four*casera passes for the followings a) One pass concentrating on the upper sparger tack welds and nortle conditions. b) 03e pass concentrating on the lower sparger tack welds and nortle conditions. c) Two passes of different angles covering as such of the sparger
, pipe surface as possible including the tee welds.
d) Tne esasination should concentrate for cracks in the welds and the weld heat affected acnes. Cracks have also been found in the sparger piping. el Condition of the sparger supported brackets to sparger and top guide. 6.17.2 Record tn, ; ;&. esatined. fi 6.18 J e t pu s e e s t e s b1 v - ACDE 6.18.1 Condition of bras bolt keroer and taek welds. 6.18.2 Condition of lock plate, flat head screws and tack welds, b.18. 3 Alignment and condition of hold down bean. 6.18.4' Condition of beas retainer. 6.18.5 Stating of ras head, nogales and condition of inlet suction area. 6.18.6 Condition of riser brace and attachsent weld to vessel wall 6.18.7 Condition of riser brace to riser meld. 6.18.8 C:ndition of wedge assembly. 6.18.9 Condition of the restrainer bracket, set screws and tack welds. 6.18.18 Condition of slip joint. 6.18.11 Condition of dif fuser to adapter weld. O 6.18.12 Condition of diffuser weld to shroud plate. ( 6.18.13 Record the jet pump assembly esasined. TP91-080 Rev. O Page 14 of 26
. _ - _~ ..- _ .._ _ .._. ._. _ _ . _ . _ . . _ . _ . _ j NO. GE-VT-204 REV. O PAGE 13 Or 24 l TITLE: INVESSEL VISUAL INSPECTION (lvyl)
- GE Nuclear Energy pro:tounE ron swn 3 Rev ,teT:a,m;.s d
6.19 LtL.Duse Sensine Line - ptDE 6.19.1 Condition of sensing line attachsent welds to brackets. 6.19.2 Condition of bracket weld to diffuser. 6.19.3 Condition of the sensing line coupling welds. . 6.19.4 Record the jet pump sensing line emasined. ! i 6.20 Shroud Suecert plate Weld - AODT. 6.20.1 Condition of accessible throud support plate wtld to reactor vessel wall. 6.20.2 Condition of accessible shroud support plate weld to shroud, 6.20.3 Condition of accessi31e shroud stiffer welds (if applicable). 6.20.4 Record the section of shroud support plate weld emasined. 6.21 Ehecud - A00E (- 6.21.1 General condition of the shroud /stparator flange sating surface. 6.21.2 Record the section of the throud/ separator flange sating surface e m a s t ne d. 6.21.3 Condition of the inside surface accessible portion of the circusferential weld in the mann cylinder section of the shroud. This weld is located between the core plate and the top guide (see Figure 1). 6.21.4 If indications are identified during the emasination as required in paragraph 6.21.3. emastne the outside area of the shroud weld that contains the suspect indications. 6.21.5 Record the secticn of the throud circusferential weld emasined. 6.21.6 Condition of the inside surface accessible portion of the two vertical welds in the sain cylinder section, upper portion of the shroud (see Figure 1). 6.21.7 Condition of the inside surf ace accessible portion of the two wertical welds in the sain cylinder section, lower portion of the shroud (see Figure 11. 6.21.8 If indiestions are identified during the emasination as required (( in paragraph 6.21.5 and 6.21.6 emasine the outside area of the shroud weld that contains the suspect indications. 6.21.9 Record the section of the shroud vertical welds emasinet TP91-080 Rev. O Page 15 of 26
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9 GE Nuclea7 Energy N3. TITLE: GE-VT-284 REV. 8 PAGE 14 DF 24 INVEBSEL VISUAL INSPECT 10N !!VV1) PROCEDURE FOR SWR 3 RPV INTERNAS 6 6.21.9 If during the emasinations of paragraphs 6. 21. 3, 6. 21. 6 or 6. 21. 7 indications are identified, other shroud welds say be required to be emasined by the owner. Record these additional shroud welds j omasined. i
'6.22 S5eoud Suceert Areets Cover - ACDE l 1
6.22.1 Condition of the shrt,ud access cover weld to shroud support plate. . I 6.22.2 General condition of the access cover. 6.22.3 Record the arisuth of the access cover emasined. 6.23'Instrueent Dev Tube - ACDE 6.23.1 Condition of the upper two (2) feet of the dry tube. 6.23.2 Check for cracks in the spring housing. 6.23.3 Record the X-Y coordinates of the dry tubes eussined. h NOTE: The four (4) fuel assesblies surrounding the dry tube should be resowed to allow casera access. Be careful not to busp the dry tube. (.[ Inspect dry tubes from all four (4) directions (if accessible). 6.24 Surveillance Satele Holder - ACDE 6.24.1 Condition of the upper sounting bracket and weld. 6.24.2 Ccndition of the lower sountinD bracket and weld. 6.24.3' 6entral condition of the sample holder. 6.24.4 Record the sasple holder enastntd. 6.25 Conteel Red Drive Nerrie - ACDE 6.25.1 Condition of the nozzle inner radius area. 6.25.2 Record the atinuth of the CRD nettle emasined. 6.26 Top Guide Held Downs - AEDI 6.26.1 Contlition of bolt, keeper, wedge and taek wesos. 6.26.2 Esasine one pass around peripheral top guide and 2 center fuel cells and all 4 corners of each cell. 6.26.3 Record the location of the area esasined. (' 6.27 Stese Dever - ACDE TP91-080 Rev. 0 6.27.1 General condition of the lif ting eye asseablies. D
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' N1 GE-VT-2Bo REW e PA3E 15 0F 24 TITLE: INVESSEL VISUAL INSDECT!DN (IVV!)
- GE Nuclear Energy PanouRE r0R ILWR 3 RPV INTERNALS h
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h 6.27.2 Condition of the attachsent welds to the lif ting eye and the dryer wall. , 6.27.3 Condition of the bank vertical welds. 6.27.4 Condition of the small heritental welds between the vertical welds near the bottes of the vertical welds and top of the upper support ring. 6.27.5 Condition of the upper and lower plugs in the bank area between the bank vertical welds (if required). 6.27.6 Condition of the bank horigental welds. 6.27.7 Condition of the bank tie bar welds. 6.27.8 Condition of the aanway cover weld. 6.27.9 Condition of the seal to bank weld. 6.27.10 Condition of the upper support ring to the seal weld. 6.27.11 Condition of the support lugs adjacent on the supper support (. ring.. 6.27.12 Condition of the upper support ring consternating on the upper 2* looking for horizontal indictions. 6.27.13 Condition of the upper support ring to the skirt weld. 6.27.14. Condition of the drain channel welds consternating on the bottos 2" of the vertical welds. {' I 6.27.15 Condition of the skirt to skirt horizontal weld. 6.27.16 Condition of the lower support ring to skirt weld. 6.27.17 Condition of the upper and lower guides and welds. 6.27.18 Record the arisuth or location of the dryer that was erastned. 6.28 St eas Seearat er - ACDE 6.28.1 General condition of separator. 6.28.2 Conditten of lifting eye assemblies. l 6.28.3 Condition of outer peripheral (top and bottos) standpipes and ' (g welds. ! 6. EB. 4 Record the area exastned. TP91-0B0 Rev. O Papa 17 of 26
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Q) t V b j ND. TITLEI GE-VT-284 REV. O PAGE 16 0F 24 INVESSEL. VISUAL INSDECTION (IVV!) GE Nuclear Energy pre:EDuRE ron swr 3 apv INTERS.t.s q J k 6.29 Stras SeDa* ster Bhroud_ Head Belt - AODE 6.29. 1 Condition of the snroud hesi bolt.
- 6.29.2 Condition of the locking ecllar assembly for wear.
- 6. 29. 3 Record the number of bolts emasined.
6.38 Below Core Plate E=asination (BCDE) - BENERpLt 6.38.1 The IVV1 emasination is required when the components are made accessible during the norsal refueling outage activities. Access for perforsing IVV1 below the core plate requires the appropriate control cells to be disassesbled, tie, renoval of the 4 fuel assemblies, support ca. sting, control rod guide tube, CRD. unlatching of the CRD thersal sleeve and the placesent of a valved fla %e over the CRD housing flange.).
$.31 Fuel Suceert Castine - BCDE 6.31.1 Condition of the tack welds securing the flow ortf aces.
6.31.2 General condition of the casting. 6.31.3 Check for proper stating in the guide tube. 6.31.4 Check the alignsent pin in the core plate for emeessive bending. 6.31.5 Condition of lower tie plate stating area in fuel support casting. 6.31.6, Record the location of the castings emasined. 6.32 Centeel Rod Guide Tube - BODE 6.32.1 General condition of guide tubes. 6.32.2 Check for debris inside the guide tube. 6.32.3 Condition of the spud fingers and pin located at the top of the CRD housing, inside of the control red guide tube. 6.32.4 Check for proper seating cf the guide tube. 6.32.5 Condition of guide tube seating surface when it contacts core plate. 6.32.6 Record the location of the guide tube emasined. O g 6.33 Control Red Drive Housine - BCDE 6.33.1 Condition of the weld between the CRD stub tube and the ves*el bottos head. TP91-080 Rev. 0 l Page 18 of 26
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f ND. GE-VT-204 REV. e PA3E 17 DF 24 TITLE: INVESSEL Visu% INSPECTION (IVVII GE Nuclear Energy pro:EDURE FOR BWR 3 RPV INTER (.( 6.33.2 Condition of the weld between the CRD housing and the stub tube. 6.33.3 General condition of the CRD housinD.
- 6.33.4 Check for debris around the CRD housing.
6.33.5 Record the X-Y coordinates of the CRD's emasined. 6.34 In-Core Guide Tube - PCE 6.34.1 Condition of the weld between the in-core and the vessel bottos head. 6.34.2 Check the weld joining the in-core guide tube tc the in-core housing. 6.34.3 General condition of the in-core guide tube. 6.34.4 Condition of the stabilizers. 6.34.5 Check for debris around the in-core guide tubes. 6.34.6 Record the X-Y coordinate of the in-core guide tube. C 6.35 Stanebv (leute Centeel pt eine and ROV Dif f erential Dressure lestrueent Eneine - FCPE 6.35.1 Condition of the weld between the pipe and the vessel wall. 6.35.2 Condition of the SLC support bracket welds. 6.35.3' General condition of the SLC piping. 6.35.4 Condition of the DDI support bracket weles. 6.35.5 General condition of the DPI piping. 6.35.6 Record the SLC or DPI piping emasined. 6.36 Bett es Pead Drain - BCDE - 6.36.1 General condition of the drain line openings. 6.36.2 Check for debris around drain line opening. 0 6.36.3 Record the bottos head drain emasined. 6.37 Core plate Suev. t - BCDE 6.37.1 Condition of the ft!!et welds between the core plate and th* support beans. 6.37.2 Record the section of core plate supports that are emasine
N3. GE-VT-204 REV. O PAGE 18 Or 24 TITLE: INVESSEL VISUAL INSDECTION ?!VV!) pro:EDURE FOR BWR 3 Rpq INTERNALS
- GE Nuclear Energy
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( 6.3B f.h,*oud Sueeert pillars - BCDE (if applicable) 6.38.1 Condition of support ptilar to lo er vessel head welds 6.38.2 Condition of support pillar te shroud teeld. 6.38.3 Check for debris and pillar erosion. 6.38.4 Record the shroud suppor. pillars examined.
- 6. 39 Ce s el vt i on o f E w a s i nt41]Ln, g
6.39.1 Remove all inspection equipment from the reactor preseurs vessel and ;1ean up the area. 6.39.2 View and edit exasination video tapes. 6.39.3 Cosplete all of the exasination data sheets. 6.39.4 Verify no lost parts from the inventory list. b 7.0 RECORDING 7.1 The visual exastner shall be responsible for recording of exastnation
**sults that provide a to.is f or evaluation and f acilitate cosparison eith the results of subsequent exasinations.
- 7. 2 The following relevant conditions sust be reported as a sinisus to the Owner as unere ' table.
7.2.1 Struc+ vrai , ,tortion or displacesent of parts to the extent the
.cekpon ?,t iunction say be ispaired.
7.2.2 Loose, sissing, cracked, or fractured parts, bolting or fasteners. TP91-0B0 Rev. O Page 20 of 26
5 N3. GE-VT-Reo REV. 8 PA3E 19 DF 24 TITLE: INVESSEL VISUAL INSDECTION (IVV1) GE Nuclear Energy pao:EDURE FOR SWR 3 RPV INTERNALS a (
- 7. 2. 3 Foreign saterials or accumulation of corrosion productt that could interfer with control rod notion or could result in blockage of coolant flow through the fuel.
7.2.4 Corrosion or erosion that reduces the nosinal section thickness by more than 5%.
- 7. id. d Wear of sating surfaces that say lead to loss of funct' ion.
7.2.6 Structural degradation of interior attachments such that the original cross sectional area as reduced sore than 5%. 7.2.7 The components previous VT emasination results shall be reviewed to verify that indications have tot changed. If indications have changed, the visual smasiner shall insure that the change is identified on the Emasination Sussary Sheet (Exhibit 1).
- 7. 3 Abnorsalit.ies detected shall be docusented with sketches, photographs j , or other forms which will aio in the evaluation process.
\ i g 8.0 EVALUAT10N k E.1 Co ?conents where emasination either reveals andications that are in eus -s of the Danet's specification (s) or previously recorded indications that are significant larger than recorded shall be unacceptable for service. If Dwner's specif scation is not p?cvided, Peragraph 7.2 shall apply. B. 2 Visual emasinations that detect surface flaws where practical, should be supplesented by either surface or valueetric emasinations to
- detersine the character of the flaw (size, shape and orientation).
- 8. 3 The Lead Visual Emaniner shall evaluatw emasination results to the inspection criteria specified in the Evaluation Section. The video tapes and recorded emasination results shall be reviewed and evaluated by at least a Level !! independent reviewer other than the emasiners that perforsed the emasination. This evaluation shall be docusented on the Emasination Sussary Sheet (See Exhibit 13.
If TP91-0B0 Rev. O Page 21 of 26 1 < m _
G. GENuclear Energy NO. TITLE: GE-VT-284 REV. 8 PAGE 20 DF R& INVESSEL VISUAL INSPECTION (1VV1) PRDOEDURE FOR SWR 3 RDV NTERNALS g V
- 4. 4 The lead visual IVV! emasiner shall notify the Dwner's representative of any defects that will require additional engineering evaluation or any abnorsalities that are unacceptable within 1 hour after the cospletion of 45e evaluation procens..
9.8 REPORTS 9.1 The emasination results shat! be recorded on the Invessel Visual Emasination Data Sheets (Ear Exhibit 11 and 111). Alternative data sheets say be used if the sinious inforsation is recorded in accordance with the procedure requirements. After the IVVI emasination is completed, the Emasination Sussary Sheet (Enhibit 1) shall'be filled
'out sussaritirg the emasination that was performed.
- 9. 2 The Invessel Visual Emssination Data Snetts shall be prepared for all cosponents emanined. The forsat of the data sheet exhibits are subject to change as say be required. The Visual Esasination Data Sheet shall include the following inforsation as a sinious:
a) Visual Esasiner(s) signature (s) and level (s) b) Date of Emasination () c) Procedure Nusber, Revision Nus)?r; Field Revision Request Nusber d) Type of visual examination (direct / remote) e) 111usination used, if any f) Direct Visual Aids Used, if any g) Remote Visual Equipment used, if any
.h Identification of Cosponents Emasined
- 1) Emasination Results j) Location and Size cf any indications
- 9. 3 Should Owner request a report in addition to the Emasination Sussary Sheet and the Invessel Visual Emanination Data Sheets, the report should be prepared and subsitted to the Owner as specified by the contract.
L U l C TP91-080 Rev. O Tage 22 of 26 l
i s .. BOSTON EDISON
-(i PILGRIM NUCLEAR POWER STATION Temporary Procedure No. TP91-080 INVESSEL VISUAL INSPECTION (IVVI) PROCEDURE FOR BWR-3 REACTOR PRESSURE VESSEL INTERNALS utnmnh!ryconrsu,_
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NOT REQUIRED Date ORC REVIEW REQUIRE"J _. D.f~t. , 6-i3-9i NOT REQUIRED Pknntna d Outace Manaaer Date ( Effective Date: E N-9f Expiration Date: //- # ~ M TP91-080 Rev.-0 Page 1 of 26
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PROCEDURE NO.: GE-VT-204 TITL.E nEvisios No.: , ( INVESSEL VISUAL INSPECTION (IVVI) PROCEDURE FOR
' BWR-3 REACTOR PRESSURE VESSEL INTERNALS PREP r Br. REYlEWED Bf. . APS*t34D FOR USE BY
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..jq NO.
TITLE: INVESSEL VISUAL INSPECTION (IVVI)
* (g' GE Nuclear Energy PRD;EDURE FOR BWR 3 RPV INTERNALS TABLE OF CONTENTS SECTION DESCRIPTIM MQE, 1.9 SCOPE 2
- 2. 0 REFERENCES 2 3.9 PERSONNEL 3
- 4. 9 EQUIPMENT 3
- 5. 0 CALIBRATION 5
- 6. 8 EXAMINATION 5
- 7. 8 RECORDING 18
- 8. 8 EVALUATION 19
- 9. 8 REPORTS 20
( EXHIBIT I 21 EXHIBIT II 22 EXHIBIT III 23 Figure 1 24 l p1J ( TP91-080 Rev. O
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t . NO. GE-VT-204 REV. 8 PAGE 2 0F 24
.* - TITLE INVESSEL VISUAL INSPECTION (IVVI)
( GE Nuclear Energy PROCEDURE FOR BWR 3 RPV INTERNALS . 1.9 EQP[, 1.1 This procedure defines the method and requirements for YT-1 and VT-3, Invessel Visual Inspection (IYVI) of the Reactor Pressure Vessel (RPV), General Electric Boiling Water Reactor (BWR), type THREE (3) internals which are made accessible during scheduled refueling and maintenance outages. This procedure meets the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Code, Table IWB-2500. Examination Categories B-N-1 and B-N-2. Augmented inspection requirements are also defined in this procedure.
- 1. 2 This procedure can be utilized in its entirety or portions thereof, as directed by the Inservice Inspection (ISI) Program or the specified outage workscope. The inspections can be conducted in any order so as to allow for increase in production or to supnort other operations during refueling and maintenance outages.
2.8 FIIIRINEE 2.1 American Society of Mechanical Engineers (ASME) Boiler and Pressure ( Vessel Code, Section V and XI.
- 2. 2 General Electric Procedure, FQP-03, ' Procedure for Qualification and Certification of Nondestructive Examination Personnel, which meets the requirements of the 'American Society of Hondestructive Testing (ASNT),
Recoreended Practice No. SNT-TC-1A, 1975 and 1980 Edition.
- 2. 3 American National Standard Institute (ANSI), 'Oualification of Personnel,' ANSI H45.2.6, 1978 Edition. ,
- 2. 4 Ur.ited States Nuclear Regulatory Cortission (USNRC), I.E. Bulletin Nueber 80-13, cated May 12, 1980.
- 2. 5 USNRC NUREG-0&i9, 'BWR Feedvater Nozzle and CRD Return Line Nozzle Cracking.'
- 2. 6 USNRC Regulatory Guide 1.147, ' Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1.'
2.7 GE Service Information Letter (SIL) Number 289, Csre Spray Sparger Visual Inspection, dated February, 1979.
- 2. 8 GE SIL Number 409, Incore Dry Tube Cracks, dated July, 1986.
- 2. 9 GE SIL Number 420, Inspection of Jet Pump Sensing Line, dated March, f 1985.
2.10 GE SIL Number 465, Jet Pump Mixer Unusual Surface Observation, dated May, 1988. TP91-080 Rev. 0
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... j NO. GE-VT-204 REY. 8 PAGE 3 0F 24 TITLE: INVESSEL VISUAL INSPECTION (IVVI) - GE Nuclear Energy PRO:EoVRE r0R BWR 3 RPV JHTERNALS 2.11 GE SIL Number 474, Stena Dryer Channel Cracking, dated October, 1968. 2.12 GE SIL Number 515, Reactor Pressure Yessel Head Linear Indications, dated May 3, 1990. 2.13 GE RICSIL Number 250, Reactor Pressure Yessel Head Clad Cracking, dated April 12, 1990. 2.14 GE RICSIL Number 054, Core Support Ehroud Crack Indications, dated November, 1990. 2.15 ASME Code Case N-424, ' Qualification of visual exaninstion personnel, Se= tion XI Division 1.' 2.16 ASME Code Case 1738, ' Examination - Acceptance standards for surisce indications in cladding, Section XI.' 3.0 PERSOWNEL 3.1 All personnel performing VT-1 visual examinations shall be trained, qualified and certified to at least a VT-1 Level II in accordance with the GE Procedure TCP-03 or equivalent. 3.2 All personnel performing VT-3 visual exarinations shall be trained, qualified and certified to at least a VT-3 Level II in accordance with the GE Procedure rCP-03 or equivalent. 3.3 The visual examiners are required to complete the appropriate data sheete for the examinations that are performed and record the examination results of those examinations. . 3.4 Personnel performing the visual examination shall additionally be knowledgeable regarding the cosponent being exarined and be able to identify deleterious indications relative to that component.
- 3. 5 Personnel shall be knowledgeable in the underwater reacte visual examination process and equiptent. The underwater camera technicians shall be knowledgeable and have experience with the underwater camera equipment. The technicians any be required to demonstrate their proficiency of the underwater camera handling capabilities to the lead visual exasiner prior to performing any verk over the Reactor Cavity.
3.6 All personnel performing examinations per this procedure shall be trained in the handling of Radioactive asterials and special precautions necessary when working in a radiation or a radioactively
) contamination eres.
4.0 EQUIP Q , NOTE: Certain equipment is required to perfore particular IVVI examinations. The following checklist provides a list of equipment that any be used during particular IVVI examinations: TP91-080 Rev.
NO. GE-VT-204 REV. 9 PAGE 4 DF 24
.- TITLE: INVESSEL VISU4L INSPECTION (IVVI)
GE Nuclear Energy pro:EDURE FOR BWR 3 RPV INTERNAL; i 1 (- 4.1 Refueling bridge or service platfors. 4.2 underwater closed circuit Television Casera Systes, a) Two (2) Underwater Caseras b) Two (2) Underwater Camera Control Units, backup boards and tubes. c) Two (2) 125 foot cable harness. l l d) Lighted straight view lens attachment. l l e) Lighted right angle sirror attachment, j f) Two (El High resolution TV sonitors (regular sonitors if required).. 4.3 Rn IVV1 resolution fixture, holding the 0.001 inch disseter wire and/or a 18% neutral grey card (GE visual comparator card) with a 1/32 inch black line. 4.4 Character generator with power supply. ( 4. 5 Connecting cables. l 4.6 Te.o (2) Microphones.
- 4. 7 L' ideo tapes (super or regular VHS) as required.
- 4. 8 Float box for a viewing aid.
4.9 Work table for electronics. . 4.1t Two (2) High resolution (super or regular) video tape recorders as required. 4.11 General area 1:.5tts) (required for resolution). 4.12 Local area light (s) (required for resolution). 4.13 Nylon rope (250 feet). 4.14 Ssall handling poles (100 feet). 4.15 Small set of air pliers. . 4.16 Inspection fixture (optional): ! , a) Core spray sparger inspection fintere. b) Camera holding fixture (general use). c) Dry tube inspection fixture. TP91-080 Rev. O Page 6 of 26
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f NO. GE-VT-244 REVS O PAGE 5 DF e4
.- / TITLE: INVESSEL V1994L INSPECT!ON (1VV1)
O GE Nuclear Energy pro:EDU F r0R BWR 5 RPV INTERNALS Y
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d)Pteas dryer inspection fixture, e) Remote operated vehicles. 5.0 CAL)BRATIDN 4 5.1 When perforaing the IVVI of the core spray piping internal crackets, core spray internal piping, core spray spargers 6nd core spray sparger brackets, the IVVI resolution requirements shall be considered adequats and qualified when the combined lighting; access ahd angit of vision is sufficient to rescave a 9.001 inch diaseter wi*a. This ras'lution e wire say be located in an IVV! resolution fixtues.
- 5. 2 When performing th'e IVVI of the ressining cosponents that ace listed in this r .wedure, the IVV! resolution shall be considered acequate and qualified when the contined lighting, acerss and angle of vision is sufficient to resolve a 1/32 inch black line on a 18% neutral gray card. This resolution standard say be located in an IVVI resolution fixture.
/T 5.3 There are no specific VT-3 resolution requirements; however, when
{s l perforsing exasinations in accordance with this procedure, the resolution requireeents of the VT-3 examinations shall be at least equal to that of a VT-1 resolution as identified in paragraph 5.2.
- 5. 4 The IVV! casera resolution shall be perforsed only once on each major coiponent or every twelve (12) hours or when changes are made to the equipment. The casera to component distance should ressin as constant as possible during the exasination after the resolution has been verified.
NOTE: IVVI video castra resolution is required on both the live video images as well as the recorded video tape image. 6.8 ErAMINATION 6.1 Procedure General Requirements 6.1.1 Reactor shut down and resovable (Reactor Vessel internals) items removed for norsel refueling. 6.1.2 Reactor cavity water level at the norsal full level for IVVI perforsed from the refuel bridge, or just below the RPV Flange when perforsing the IVV1 from the service platfora. 6.1.3 Reactor water temperatures should be saintained at less than 90 degrees Fahrenheit and water clarity shall be suf ficient for the
, emasiners to view the casera position and to establish the necessary resolution with camera systes.
TP91-080 Rev. O Page 7 of 26
.e NO. GE-VT-204 REV. 8 PAGE 6 OF 24 O'- GE Nuclear Energy TITLE: INVESSEL VISUAL INSPECTION (IVVil PROCEDURE FOR BWR 3 RPV INTERNALS ( NOTE: The water tesperature of 90 degrees Fahrenheit or'less is recessended for a higher quality emanination. Water 4esperature affects the emasination in several ways: a) Temperatures above 140 degrees Fahrenheit and 122 degrees Fahrenheit say adversely affect the B/W (Westinghouse Model ETV-1250) and color casera (Westinghouse Model ETV-1256) heads respectively. b) Thersal distortion (heat waves) of the visual emasination begin around 100 degrees Fahrenheit and progressively worten. at which tise the IVV1 examination say be ispossible to perfora. c) Husidity on the refuel floor generally increases with an increase in the water tesperature. The Westinghouse ETV-1250 and ETV-1256 Casera Control Units operate with relative busidity in the range fros 0 to 95% (non-condensing). 6.1.4 Assure the required equipsent it available, set up, o,?erationally tested and ready for use during the exasination. 6.1.5 Reactor water clarity shall be established and judged satisfactory for the exasination by the lead GE Level 11 or Level 111 exasiner. 6.1. 6 Access for perforsing visual exasination of the dry tubes and control cell components requires the appropriate fucl assemblies to be resoved. 6.1. 7 Access for perforsing IVV1 below the top guide and the core plate requires the appropriate control cells to be disassembled. (ie, resoval of the 4 fuel assesblies, control rod drive (CRD), CRD thereal sleeve, placement of a valve flange over the CRD housing flange, fuel support casting, control rod blade and guide tube. 6.1. 8 All work shall be performed in accordance with the owner's Health Physics Procedures and industrial safety requirements. 6.1.9 Ensure that proper health physics coverage is provided during the resoval or installation of any itess fi ca the RPV. 6.1.10 All tools, equipment and saterials used in a designated tool control area sha :1 be legged into and out of the area. Tools and associated equ'.psent to be used over the reactor cavity or RPV shall be tied of f to prevent anything dropping into the RPV. Specific requirements for such control are beyond the scope of { this procedure, but sust be consistent with owner's requirements and/or procedures. 6.1.11 Pr ior to examination, all parts of the invessel casera or aanipulator(s) (nut s, bolt s, etc. ) shall be' captured or properly retained to prevent loss in the Reactor Vessel. TP91-080 Rev. O _ _ __ P_aRe 8 of 26
GE-VT-204 REV. 8 PAGE 7 DF 24 O GENuclear Energy NO.
.. TITLE: INVESSEL VISUAL INSDECTION (!VVI) " PROCEDURE FOR BWR 3 RpV INTERNALS 6.1.12 The examination shall be recorded on video tape with voice recording and charactea generator, unless otherwise indicated by owner. '
6.1.13 Where required, parti:ular attention shall be given to each welded joint and the heat affected zone (HAZ) associated with each welded joint. 6.1.14 When usir.g optical aids to improve the angle of vision' and/or resolution, care sust be taksn to ensure that the equipment does not shadow the area of interest or otherwise sask the exasination area. 6.1.15 The video tape recorded during the exasination should be reviewed by an independent Level !! or Level III IVVI Visual Examiner. Timely review of those tapes could resolve any questions prior to IVVI equipment being disassembled or removed free the area of exasination. 6.1.16- All-areas and cosponents exasined by the remote underwater television systes shall have the systes qualified by verifying the ' IVV! resolution requiresents appropriate to the examination being Ig performed, per paragraph 5.8. 4 6.2 Resote Television Technicues - TVV1 6.2.1 When a video recorder is used during the exasination, do not run ' the recorder constantly. Achieve the best resolution and focus possible. When the examiner is satisfied with the picture, begin the recording. Record still isages for about 20 seconds. During scans, continue to record at the end of the scan for about 20 seconds. At the end of an image recording, press the pause button on'the recorder. This will provide for a soooth transition from one image to another without' loss of any previously taped images. , Additionally, it will elisinate excessive reviewing and editing tier. 6.2.2 Perfore a visual scan of components by soving the television casera i slowly across the component surface, pausing at each weld so that the examiner can verify whether or not flaw indications are
- present.
6.3 Exasiner's Duties 6.3.1 Exasiners shall sign off the invessel visual exasination data sheetts) as required (See Exhibit 11 and !!!). g 6.3.2 Review the video tape as each component is exasined and check the f tape for quality, cospleteness and accuracy. Fill in the appropriate inforsation on the invessel visual exasination data sheet (s). (See Exhibit II and III). TP91-080 Rev. 0 , Page 9 of 26
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' TITLE: INVESSEL VISUAL INSPECTION (1991) k GE Nuclear Energy PROCEDURE FOR ILWR 3 RPV INTERNALS 6.3.3 Using the underwater television systes and adequate lighting, examine those areas as outlined in the procedure for conditions listed on each cosponent. Any abnorsalities should be documented with video recording and appropriate supplemental documentation shall be attached to the data package. (See Exhibit !!,and Ill).
6.4 ASME Code Reevicesents - IVV1 6.4.1 ASKE Section XI Code, Subsection !WA-2211 Visual Exasingtion VT-1: a) The VT-1 visual examination shall be conducted to detersine the condition of the part, cosponent, or surface e'n'asined, including such conditions as cracks, wear, corrosion, erosion or physical damage on the surface of the part or cosponent. b) Direet visual exasination say be conducted when access is sufficient to place the eye within 24 inches (61 es) of the surface to be examined and at an angle not less than 30 degrees to the surface. Mirrors say be used to isprove the
, angle of vision and aids such as a sagnifying lens say be used to assist examinations. The specific part, component, or
( section thereof, under insediate examination, shall be illusinated, as necessary, with a flashlight or other auxiliary lighting, to attain a sinisus of 15 foot candles (fe) for general exasination and a sinisus of 50 fc for the detection or study of small indications. In addition, illusination of the area to be exasined say be required at right or oblique angles to expose cracks or evidence of corrosion 3r erosion. Resolution shall be considered adequate and qualt .ed when the combined lighting, access and angle of vision is sufficient to resolve a 1/32 inch black line on a 18% neutral gray (GE visual cosparator) card. c) Resete visual exasination say be performed where conditions exist that prevent direct visual exasination. Resote visual exasination say include visual aids such as telescopes, periscopes, binoculars, fiber optics, television cameras and sonitoring systess er other suitable instruments. Resote techniques shall demonstrate the ability to provide a resolution at least equivalent to that obtained by direct visual exasination. Mirrors, soveable lights, rotating optics or any cosbination thereof say be utilized to display cracks, surface scratches, or evidence of corrosion, erosion, sisalignment or sovement. In the event resote visual exasination is required utilizing reacte equipment, evaluations shall be perforsed by personnel with experience in ( the sethod selected. l l TP91-080 Rev. O anam na ao es i i
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; N3. GE-VT-204 REV. O PAGE 9 DF 24 TITLE: INVESSEL VISUAL INSPECTION (IVVI)
,'(x,/ GE Nuclear Energy PRC;EDURE FOR BWR 3 RPV INTERNALS 6.4.2 ASME Section XI Code, Subsection IW4-2213 Visual Exasination VT-3:
a) The visual exasination shall be conducted to determine the general sechanical and structural condition of components and their supports, such as the presence of loose parts, debris, or abnormal corrosion products, orar, erosion, corrosion and the loss of integrity at bolted or welded connections, b) The VT-3 visual exasination say require, as applicable to detersine structural integrite, the seasuresent of clearances, detection of physical displacesent, structural adequacy of supporting elements, connection between load carryinD structural sesbers and tightness of bolting. 6.4.3 For component supports and compv'ent interiors, the visual exasinations say be perforsea reactely with or without optical aids to verify the structural integriny cf the cosponent.
,s 6. 5 E=asinatten Areas - General i
6.5.1 The followinD components, when required to be exasined using this k -- rectedure, shall be emanined.per the sethods indicated and the results of the IVVI examination noted on the data sheets. 6.5.2 Visual examinations are required to be performed on the accessible avers which are defined as the space above and below the Reactor Core that is made accessible for examinations by resoval of components during normal refueling cutages. 6.6 Above Cere Plate E=asination (ACDE) General
- 6. 6.1 The steas dryer hold down lugs and the top head exasinations should be performed by the direct visual sethod.
6.6.2 The shroud, shroud support melds, jet pump diffuser welds, jet pump sensing line brackets and the access cover welds should be inspected during the jet pusp assembly emasination. It will be difficult to view any large areas within the throud and vessel wall due to limited accessibility. 6.6.3 The exasination of the steas dryer and separator are perforsed while in the flooded equipsent storage pool. This will require some fors of access for the camera holders free above, such as the i refueling bridge. 6.6.4 The following components shall be exasined in accordance with the
! ISI progras or outage workscope and the following conditions recorded as a sinisus on the applicable data sheet:
6.7 Claddino Patches - ACPE (if required)
- 6. 7.1 Condition of cladding patches.
NO. GE-VT-204 RE V. 9 PAGE le DF 24 TITLE: INVESSEL VIGUAL INSPECTION (IVV1) pADOEDURE FOR BWR 3 RPV INTERNALS _ GENuclear Energy 6.7.2 Note General condition of cladding observed.
- 6. 8 Suide Rod - ACPE
- 6. 8.1 Condition of bracket to vessel wall weld.
- 6. 8. 2 General condition of upper guide rod bracket.
6.8.3 Condition of plug weld. 6.8.4 Gen ral condition of guide rod including the lower plug and bracket attachment to the shroud. l 6. 8. 5 Record the guide rod arisuth emasined. 6.9 St eas Drver Suceert Bracket - A00E 6.9.1 Condition of bracket te vesse' wall weld. 6.9.2 Condition of dryer seating surface for wear. 6.9.3 Record the steam dryer support brackets exasined. 6.,10 Steas Dever
- eld Down Pracket - ACDE 6.10.! Condition of dryer hold down brackets.
6.10.P. Condition of the seating surface. ( 6.10.3 Condition of the attachment weld to the RPV head. f 6.10.4 Record the steas dryer hold down bracket arisuth'exastned. NOTE: This inspection is perforsed using direct visual techniques while the RPV head is on its storage pedestals. 6.11 Reactor Dressure Vessel Head - ACDE 6.11.1 General Condition of the inside surface adjacent to the top head vertical and horizontal pressure vessel welds (clad or uncladded). 6.11.2 Record the location of the head weld emasined. NOTE: This inspection is perforsed using direct visual techniques while the RPV head is on its storage pedestals. 6.12 Feedwater Searcer End Bracket - A0DE l 6.12.1 Condition of bracket to vessel wall weld. 6.12.2 General condition of bracket. 6.12.3 Record the feedwater sparger end bracket azieuth emasinec TP91-080 Rev. r Page 12 of 26
s 1 , e NO. GE-VT-204 REV. 8 PAGE 11 DF 24 TITLE: INVESSEL VISU4L INSPECTION (IvV1) f GE Nuclear Energy PROCEDURE FOR SWR 3 RPV INTIRNALS l 6.13 Feedwater Soareer - ACDE l 6.13.1 General condition of feedwater sparger. ; 1 6.13.2 Condition of sparger welds. 6.13.3 Condition of norale welds or flow holes as appiicable. 6.13.4 Condition of end bracket pins and tack welds. ! 6.13.5 Condition of end bracket welds 6.13.6 Record the Feedwater Sparger arisuth exasined. 6.14 Feedwater Norrie - ACDE 6.14.1 Condition of the nor:1e inner radius accessible areas. 6.14.2 Condition of norrle bore accessible areas. g's 6.14.3 Record the Feedwater Nozzle arisuth exasined. 6.15 Core Serav Internal Dienne Wall Braeket - ACDE 6.15.1 Condition of bracket to vessel wall welds. 6.15.2 Condition of the bolt head tack welds. 6.15.3 General condition of the bracket. 6.15.4 Record the core spray internal piping wall brackrts exasined. 6.16 Core Serav Internal Pf eine - ACDE 6.16.1 General condition of core spray header piping. 6.16.2 Condition of core spray header welds. 6.16.3 General condition of core spray downconer piping, 6.16.4 Condition of core spray downeoser welds. 6.16.5 Condition of elbow welds.
- 6.16.6 Condition of junction (teel box welds with particular attention to the heat affected zone of the flow divider welds.
6.16.7 condition of junction (teel box to thereal sleeve area. 6.16.8 Record the azieuth or loop examined. TP91-080 Rev. O Page 13 of 26
N3. GE-VT-204 REV. O PAGE 12 0F 24 TITLE: INVESSEL VISUAL INSDECTION (IVVI) GE Nuclear Energy PROCEDURE FOR BWR 3 RPV INTERNALS ( -- 6.17 Etri..Serav Seeroer - ACDE 6.17.1 Exasine the four core spray spargers in st least four casera passes for the followings a) One pass concentrating on the upper sparger tack welds and nozzle conditions. b) One pass concentrating on the lower sparger tack welds and nozzle conditions. c) Two passes of different angles covering as such of the sparger pipe surface as poasible including the tee welds, d) The exasination should concentrate for cracks in the welds and the weld heat affected zones. Cracks have also been found in the sparger piping. e) Condition of the sparger supported brackets to sparger and top guide. 6.17.2 Record the areas exasined. 6.18 Jet Dueo Assesb1v - ACDE 6.18.1 Condition of beas bolt keeper and tack welds. 6.18.2 Condition of lock plate, flat head screws and tack welds. 6.18.3 Alignsent and condition of hold down beas.
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6.18.4 Condition of bras retainer. 6.18.5 Seating of ras head, nozzles and condition of inlet suction area. 6.18.6 Condition of riser brace and attachment weld to vessel wall 6.18.7 Condition of riser brace to riser weld. 6.18.8 Cendition of wedge assembly. 6.18.9 Condition of the restrainer bracket, set screws and tack welds. 6.18.1e Condition of slip Jcint. 6.18.11 Condition of diffuser to adapter weld. l 1 6.18.12 Condition of diffuser weld to shroud plate. l 6.18.13 Record the jet pump assesbly exaained. 1 I TP91-050 Rev. 0 Page 14 of 26
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G 4 B NO. GE-VT-204 REV. 8 PAGE 13 DF 24 TITLE: INVESSEL VISUAL INSPECTION (IVVI)
"O GE Nuclear Energy PROCEDURE FOR BWR 3 RPV INTERNALS QJ 6.19 Jet Puso Sensino Line - ACDE 6.19.1 Condition of sensing line attachment melds to brackets.
6.19.2 Condition of bracket weld to diffuser. 6.19.3 Condition of the sensing line coupling welds. 6.19.4 Record the jet pusp sensing line examined. 6.20 Shroud Support Plate Welo - ACDE 6.20.1 Condition of accessible shroud support plate weld to reactor vessel wall. 6.20.2 Condition of accessible shroud support plate weld to shroud. 6.20.3 Condition of accessible shroud stiffer welds (if applicable). 6.20.4 Record the section of shroud support plate weld examined.
/ ~h 6.21 Sneeud - ACDE N) 6.21.1 General condition of the shrcud/ separator flange sating surface.
6.21.2 Record the section of the shroud / separator flange sating surface exasined. 6.21.3 Condition of the inside surface accessible portion of the circunferential weld in the sain cylinder section of the shroud. This weld is located between the core plate and the top guide (see Figure 1). 6.21.4 If indications are identified during the exasination as required in paragraph 6.21.3, exasine the outside area of the shroud weld that contains the suspect indications. 6.21.5 Record the section of the shroud circunferential weld exasined. 6.21.6 Condition of the inside surface accessible portion of the two vertical welds in the main cylinder section, upper portion of the shroud (see Figure 1). 6.21.7 Condition of the inside surface accessible portion of the two vertical welds in the sain cylinder section, lower portion of the 4 shroud (see Figure 1).
, 6.21.8 If indications are identified during the exasination as required j in paragraph 6.21.5 and 6.21.6, exasine the outside area of the shroud weld that cantains the suspect indications.
6.21.9 Record the section of the shroud vertical welds exasinet Rev. O TP91-0B0 Page 15 of 26 f_
\ i l ND. GE-VT-204 REV. 9 PAGE 14 DF 24 TITLE: INVESSEL VISUAL INSPECTION (IVVI)
^ GE Nuclear Energy PROCEDURE FOR BWR 3 RPV INTERNALS l
l l 6.21.9 If during the examinations of paragraphs 6.21.3. 6.21.6 or 6.21.7 indications are identified, other shroud welds say be required to be exasined by the owner. Record these additional shroud welds l exasined.
'6.22 Shroud Sucoert Access cover - ACDE 6.22.1 Condition of the shroud access cover weld to shroud support plate.
6.22.2 General condition of the access cover. l 6.22.3 Record the arisuth of the access cover exasined. l 6.23 Insteusent Dev Tvi ce - ACDE 6.23.1 Condition of the upper two (2) feet of the dry tube. 6.23.2 Check for cracks in the spring housing. ! 6.23.3 Reeced the ~~Y coordinates of the dry tubes exasined. NOTE: The four (4) fuel assemblies surrounding the dry tube should be ( resoved to allow casera access. Be careful not to busp the dry tube. Inspect dry tubes from all four (4) directions (if accessible). 6.24 Surveillance Sasole Holder - ACDE i 6.24.1 Condition of the upper sounting bracket and weld. 6.24.2 Condition of the lower sounting bracket and weld. 6.24.3 General condition of the sample holder. 6.24.4 Record the sample holder exasined. 6.25 Control Rod Drive Norrle - ACDE 6.25.1 Condition of the nozzle inner radius area. l 6.25.2 Record the arisuth of the CRD nozzle exasined. 6.26 Too Guide Hold Downs - ACDE 6.26.1 Condition of bolt, keeper, wedge and tack welds. 6.26.2 Exasine one pass around peripheral top guide and 2 center fuel cells and all 4 corners of each cell. ( 6.26.3 Record the location of the area exasined. 6.27 Stras Dever - ACDE TP91-080 Rev. O I 6.27.1 General condition of the lifting eye assesblies. age 16 of 26 l
f NO. GE-VT-204 REV. O PAGE 15 0F 24 1 - TITLE: INVESSEL VISUAL INSPECTION (IVVI)
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GE Nuclear Energy PROCEDURE FOR BWR 3 RPV INTERN.tB (. 6.27.2 Condition of the attachsent welds to the lif ting eye and the dryer wall. 6.27.3 Condition of the bank vertical welds. 6.27.4 Condition of the small horizontal welds between the vertical welds near the bottos of the vertical welds and top of the upper support ring. 6.27.5 Condition of the upper and lower plugs in the bank area between the bank vertical welds (if required). 6.27.6 Condition cf the bank horizontal welds. 6.27.7 Condition of the bank tie bar welds. 6.27.6 Condition of the aanway cover weld. 6.27.9 Condition of the seal to bank weld. 6.27.10 Condition of the upper support ring to the seal weld. ( 6.27.11 Condition of the support lugs adjacent on the supper support ring.. 6.27.12 Condition of the upper support ring consternating on the upper 2" looking for horizontal indictions. 6.27.13 Condition of the upper support ring to the skirt weld. 6.27.14 Condition of the drain channel welds consternatir.g on the bottes 2" of the vertical welds. 6.27.aS Condition of the skirt to skirt horizontal weld. 6.27.16 Condition of the lower support ring to skirt weld. 6.27.17 Condition of the upper and lowse guides and welds. 6.27.18 Record the arisuth or location of the dryer that was exasined. 6.28 St eas Seearat or - ACDE 6.28.1 General condition of' separator. 6.28.2 Condition of lifting eye assesblies.
! 6.28,3 Condition of outer peripheral (top and bottes) stanepipes and welds.
6.28.4 Record the area enasined. TP91-080 Rev. O Page 17 of 26
GE-VT-204 REV. 8 PAGE 16 0F 24 S'- GE Nuclear Energy ND. TITLE: INVESSEL VISUAL INSPECTION (IVVI) PRDCEDURE FOR BWR 3 RPV INTERNALS 6.29 Steas Seoarater Shroud Head Belt - ACDE 6.29.1 Condition of the shroud head bolt. 6.29.2 Condition of the locking collar assembly for wear. 6.29.3 Record the nusber of bolts examined. 6.38 Below Core plat e Eveninatien (BCDE) - GENER4Lt 6.32.1 The IVVI evasination is required when the cosponents are made accessible during the norsal refueling outage activities. Access for perforsing IVVI below the core plate requires the appropriate control cells to be disassemblec, (ie, removal of the 4 fuel assesblies, support casting, control rod guide tube, CRD, unlatching of the CRD thersal sleeve and the placement of a valved flange over the CRD housing flange.). b.31 Fuel Suceert Castine - BCDE l 6.31.1 Condition of the taek welds securing the flow orifices.
< 6.31.2 General condition of the casting. G 6.31.3 Check for proper seating in the guide tube.
l 6.31.4 Check the alignsent pin in the core plate for excessive bending. l 6.31.5 Condition of lower tie plate seating area in fuel support casting. 6.31.6 Record the location of the castings emasined. , 6.32 Lontrol Red Guide Tube - BCDE l l 6.32.1 General condition of guide tubes. 6.32.2 Check for debris inside the guide tube. 6.32.3 Condition of the spud fingers and pin located at the top of the CRD housing, inside of the control rod guide tube. 6.32.4 Check for proper seating of the guide tube. 6.32.5 Conditicn of guide tube seating surface when it contacts core plate.
, 6.32.6 Record the location of the guide tube examined.
( 6.33 Control Red Drive Housine - BCDE 6.33.1 Condition of the weld between the CRD stub tube and the vessel bottos head. TP91-080 Rev. O Page 18 of 26
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3, 7 ;r5m------------- ------------- l i i d, NO. GE-VT-204 REV. O PAGE 17 DF 24
. TITLE: INVESSEL VISUAL INSPECTION (IVV1) 'g/~'gy GE Nuclear Energy PROCEDURE FOR BWR 3 RpV INTERNALS 6.33.2 Condition of the weld between the CRD housing and the stub tube.
6.33.3 6eneral condition of the CRD housing. 6.33.4 Check for debris around the CRD housing. 6.33.5 Record the X-Y coordinates of the CRD's emasined. 6.34 In-Core Guide Tube - BCDE 6.34.1 Condition of the weld between the in-core at# lhe vessel bottos head. 6.34.2 Check the weld joining the in-core guide tubs to the in-core housing. 6.34.3 General condition of the in-core guide tube. 6.34.4 Condition of the stabilizers. 6.34.5 Check for debris around the in-core guide tubes. (~4
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6.34.6 Record the X-Y coordinate of the in-core guide tube. 6.35 Stanedv Lieute Centeel Pietne and RDV D L f ferential Pressure Instrument Etoine - BCDE 6.35.1 Condition of the weld between the pipe and the vessel wall. 6.35.2 Condition of the SLC support bracket welds.
- 6. 3b. 3 General condition of the SLC piping.
6.35.4 Condition of the DPI support bracket welds. 6.35.5 General condition of the DPl piping. 6.35.6 Record the SLC or DPl piping exasined. 6.36 Bottes Head Drain - BCDE - 6.36.1 General condition of the drain line openings. 6.36.2 Check for debris around drain line opening. 6.36.3 Record the bottos head drain exasined.
,O 6.37 Core Plate Succert - BCDE 6.37.1 Condition of the fillet welds between the core plate and the support beans.
6.37.2 Record the section of core plate supports that are exasine TP91-080 Rev Page 19 of 26
NO. GE-VT-204 REV. 8 PAGE 18 OF 24 TITLE: INVESSEL VISUAL INSPECTION (IVVI)
,,.' GE Nuclear Energy PROCEDURE FOR BWR 3 RPV INTERNALS ;
s. j l 6.38 Shroud Support Pf11ses - BCDE fif applicable) -
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6.38.1 Condition of support pillar to lower vessel head we'1d. 6.38.2 Condition of support pi!!ar to shroud we1d. 6.38.3 Check for debris and pillar erosion. 6.38.4 Reeced the shroud support pillars emasindd. 6.39 Cesele:1en of Ewasination 6.39.1 Remove all inspection equipsent from the reactor pressure vessel and clean up the area. 6.39.2 View and edit emasination video tapes. ! 6.39.3 Cosplete all of the exasination data sheets. 6.39.4 Verify no lost parts from the inventory list. f ? 7.0 RECORDING 7.1 The visual exasiner shall be responsible for recordin2 of examination results that provide a basis for evaluation and facilitate cosparison with the results of subsequent emasinations.
- 7. 2 The following relevant conditions sust be reported as a sinisus to the Owner as unacceptable.
l 7.2.1 Structural distortion ce displacesent of parts to The extent the cosponent function say be ispaired. 7.2.2 Loose, sissing, cracked, or fractured parts, bolting or fasteners, l l t G TP91-080 Rev. O Page 20 of 26
NO. -. SE-VT-344 REV. 8 PAGE 19 OF 24 6 TITLE: INVESSEL-VISUAL INSPECTION (IVV!) s GENuclear Enemy: . PROCEDURE FOR BWR 3 RPV INTERNALS 17.2.3 Foreign saterials or accueulation of corrosion products that could interfere with control rod notion or could result in blocka0' of coolant flow through the fuel. 7.2.4 Corrosion or erosion that reduces the nominal section thickness by more than 55 7.2.5 . Wear of sating surfaces that say lead to loss of function.
- 7. 2. 6 Structural degradation of interior attachments such-that the original cross sectional area is reduced more than 55.-
- 7. 2. 7 The components previous VT exasination results shall be reviewed'to verify that indications have not changed. If indications have changed, the visual exasiner shall insure that the change is ;
identified on the Exasination Sussary Sheet- (Exhibit 1).
- 7. 3 Abnormalities detected shall be-documented with sketches, photographs or other fores which will aid in the evaluation process.
=4.8 EVALUQTION 8.1 Components where exasination either reveals' indications-that are'in excess of the Owner's specification (s)-or previously recorded indications.that are significant larger than recorded _shall be unacceptable for service. If Owner's specification is not provided, par.sgraph 7.2 shall apply.
- 8. 2 Visual exasinations that detect surface flaws where pr,actical,_should be supplemented by either surface or_volusetric examinations to determine the character-of the flaw-(size, shape and-orientation).
8.3 The Lead Visual Exasiner shalll evaluate exasination results to the inspection criteria speelfied in the Evaluation Section. The video _ at' pes and recorded exasination results shall'be reviewed and evaluated by at least.a Level II independent reviewer other than the exasiners that performed the exasination. This evaluation shall be docusented on the Examination Sussary Sheet (See Exhibit II.
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TP91-0BO_ Rev. O Page 21 of 26 - n ._ _
NO. GE-VT-204 REV. 9 PA3E 20 0F 24 TITLE: INVESSEL VISUAL INSPECTION (IVVI) GE Nuclear Energy PROCEDURE FOR BER 3 RPV INTERNALS (.
- 8. 4 The lead visual IVV! emasiner shall notify the Owner'- representative of any defects that will require additional enginee.1 j evaluation or any abnorsalities that are unacceptable with . I hour after the completion of the evaluation process.
9.0 REPORTS 9.1 The examination results shall be recorded on the Invessel Visual Ewasination Data Sheets (See Exhibit II and III). Plternative data sheets say be used if the sinisus inforsation is recorded in accordance with the procedure requiresents. After the IVV! exasination is cospleted, the Exaeination Sussary Sheet (Exhibit I) shall be filled out sussarizing the exasination that was perforsed.
- 9. 2 The Invessel Visual Exasination Data Sheets shall be prepared for all co1ponents examined. The forsat of the data sheet exhibits are subject to change as say be required. The Visual Exasination Data Sheet shall include the following inforsation as a sinisus a) Visual Examiner (s) signature (s) and level (s) b) Date of Exasination c) Procedure Nusber, Revision Nusber, Field Revision Request Number I d) Type of visual exasination (direct / remote) e) Illumination Used, if any f) Direct Visual Aids Used, if any g) Resote Visual Equipment used, if any h Identification of Components Exasined i) Exasination Results j) Location and Size of any indications 9.3 Should Owner request a report in addition to the Exasination Sussary Sheet and the Invessel Visual Exasination Data Sheets, the report should be prcpared and submitted to the Owner as specified by the contract.
I TP91-080 Rev. O Page 22 of 26 l
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NO. GE-VT-204 REV. 8 PAGE 23 Dr 34 g TITLE: INVESSEL VISUAL INSPECTION (1991) GENuclear Energy eG A PROCEDURE FOR SWR 3 RPV INTERNALS IWYESSEL VISUAL EXAMINATION DATA SHEET GENyckor Ewry , tCOWTINUAT60N) arrr.: w m._ .arve.=
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