ML20038B626

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Inservice Insp Exam Rept for 801204-810711,in Response to Subsection IWA-6230,Section XI of ASME Boiler & Pressure Vessel Code
ML20038B626
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Site: Maine Yankee
Issue date: 12/01/1981
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Maine Yankee
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NUDOCS 8112080444
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{{#Wiki_filter:f' i d, -o Fils 17.6.3 1 i INSERVI& INSPECTION EXAMINATION f?EPORT MAIfE YAPKEE ATOMIC POWER COMPANY DE&MBER 4,1980 TROLGI JJLY 11, 1981 l 1 i 8112000444 911201 PDR ADOCK 05000309 PDR 0

( ,, g, * ~ l PREFACE. Maine Yankee Atomic Pmer Company completes most of its inservice inspections during refueling outages. A few inspeci.lons are performed during pmer operation and msdieduled shutdowns. This summary report includes all inspections performed since the end of the 1980 outage; up to, and including, those inspections completed during the 1981 refueling outage. A1 enclosed NIS-1 report and abstract provides information on examinations performed, the conditions observed, and corrective actions taken. Examinations were performed primarily by Magnaflux Quality Services of Hartford, Comecticut, with a limited number of inspections performed by Yankee personnel. I e J J

r-TABLE OF (I)NTENTS PAGE NIS-1 OWNER'S DATA REPORT 1 SLM4ARY REPORT

1.0 INTRODUCTION

74 1.1 EXMINATION METFODS 74 1.2 EVALUATION OF DATA 76 .1.3 EXMINATIONS.RESULTS 76 2.0 SLMMARY OF EXMINATIONS 77 2.1 REACTCR VESSEL 77 2.2 PRESSLRIZER 77

2. 3 STEM GENERATP E-1-1 77 2.4 STEM ENERATOR E-1-2 78 2.5 PIPING (SAFETY CLASS 1) 78 2.6 REACTOR COOLANT R.NP (P-1-3) 79 2.7 PIPING (SAFETY CLASS 2) 80 i

2.8 PIPING FRESERVIE EXMINATI0t6 81

3. 0 REACTm COOLANT SYSTEM LEAK TEST 82 4.0 CONC 1.USI0t6 83 l

l 11 l .. - - - -. ~. -. - - )

r I FORM NIS 1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by th? Pr:visi:ns cf th; ASME Code Rules i i

1. Owner MATNE YANKEE ATOMTC POWER CO..

WISCARRET-MATME (Name and Address of Owner) MAINE YANKEE ATOMIC POWER CO., WISCASSET, MAINE p (Name and Address cf Plant) i II ~

3. Plant Unit
4. Owner Certificate of Authorization (if required) 12-29-72.sarjonal Board Number for Unit _ REACTOR VESSEL 2 0 865
5. Commercial Service Date 6
7. Components inspected Manufacturer Ccmponent or Manufacturer or Installer State or National Appurtenance or Installer Serial No.

Province No. Board No. R.P. VESSEL C.E. 67106 NA 20865 R.P. Head C.E. 67206 NA 20865 Pressurizer C.E. 67601 NA 20858 l 20919 Stm. Gen.#1 C.E. 67501 NA Stm. Gen.#2 C.E. 67502 NA 20920 RCP #3 Byron Jackson 681-N-0423 NA NA Piping Stone & Webster NA NA NA ( l l I I I I Note: Supplemental sheets in form of lists sketches. or drawings may be used provided (1) size is SS in. x 11 in.. (2) information in items 1 through 6 on this data report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of thir. form. This form !E00029) rray be obtaitsed from the Creer Cect., ASME, 345 E. 47th St., New Yces, N.Y. 10017 I. -W--.. e. 3 'e==*w-e en g.,.. _ _.bw m -*-Nee-weW M*MwNr '%'IP "6J*F* \\* -'*NWW***M- ='m' -**vw

7, 4 i ? FORM NIS 1 (back)

8. Examination Dates 11-4-80 to 7-11-81
9. Inspection Interval from 12-29-73o 12-29-81
10. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval.
11. Abstract of Conditions Noted
12. Abstract of Correctke Measures Recommended and Taken We certify that the statements made in this report are correct and the examinations and corrective mes-sures taken conform to the rules of the ASME Code, Section XI.

gy [ [. Date, /2 O 19 8! Signed Maine Yankee Owner Certificate of Authorization No.(if applicable) DPR-36 Expiration Date October 21, 2008 CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, ho! ding a valid commission issued by the National Board of Boile[r and Pressure Ve Inspector and/pr tr.c State or Province of M 4 / W' and employed by 8 N S Idf- @ of 84 # # d. have inspected the components described in this owners' Data Report during the period 7 J& l f / P8/ and state that to the best of my knowledge and belief, the Owner / 8 '?f MY l 98/ to has performed examinations and take'n corrective measures described in this Owners' Data Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the inspector nor his emplopt makes any warranty, expressed or implied, concerning the examinations and corrective measures desenbed m this Owners' Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. N#M P 19 I Date fY Commissions MS V ? $

  1. 5 l3 7I Irftpector's S$ature National Board, Scare, Province znd No.

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i l 1. Ovner Maine Yankee Atomic Power Company, Wiscasset, Maine 2. Plant Maine Yarkee Atomic Power Company, Wiscasset, Maine 3. Plant tkilt #1 4. Owner Certificate of Authorization DPR-36 5. Commercial Service Date 12-29-72 6. National Board Number for tkilt Reactor Vessel 20865

10. Abstraet of Examinations COMPOENT CATE(X)RY MNBER OF CDMP0fENTS EXAMINED EYJNINATION Reactor Vessel B-C 50% of head-to-flange weld UT B-G-1 27 reactor head studs >

2" UT, LP B-G-1 19 reactor had washers VT B-G-2 16 nuts and bolts i 2" VT Pressurizer B-B 1.5 ft. of longitudinal shell weld UT B-8 2 ft. of circunferential shell weld UT B-D 100% of 3 nozzle-to-ve.ssel welds UT B-F 100% of 2 safe-end welds UT, PT i B-H 1.5 ft. of integral support skirt weld UT B-G-2 20 manway stud and nuts 2" in place VT l t I l1 3-l l 1! e m-. ,,,-,-.-.--,w--,p. v ,--T--- .e w 1-,.r wv r-f- F-

l e i' 1 1. Owner Maine Yankee Atomic Power Company, Wiscasset, Maine 2. Plant Maine Yankee Atomic Power Company, Wiscasset, Nine 3. Plant thit #1 4. Owner Certificate of AJthorizat. ton DPR-36 5. Commercial Service Date 12-29-72 1 6. Mtional Board tunber for thit Reactor Vessel 20865

10. Abstract of Examinations COMP 0ENT CATETRY M.NBER OF CDMPONENTS EXAMINED EXAMINATION i

Steam Generator B-8 1 ft. of 5 longitudinal welds UT MJmber E-1-1 8-8 Partial inspections of 5 circunferential welds UT Steam Generator B-G-2 34 studs & 23 nuts removed from NJmber E-1-2 manways (no ID numbers) VT B-Q 5 tubes - hot leg & bend required by M.Y. Tech. Specs. ET 1 d I - - -. - - - - - - ~

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Owner Maine Yankee Atomic Power Company, Wiscasset, Maine

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)l 2. Plant Maine Yankee Atomic Power Company, Wiscasset, Maine ]f 3. Plant thit #1 4. Ownar Certificate of Authorization DPR-36_ 5. Commercial Service Date 12-29-72 6. National Board ttrter for thit Reactor Vessel 20865

10. Abstract of Examinations COMP 0 TENT CATEGORY NUMBER OF (IMPONENTS EXAMINED EXAMINATION Piping B-F 3 safe end welds UT, PT B.J 100% of 4.9 circumferential butt welds UT B-J 100% of 2 branch comections 6" dia.

UT, MT B-J 100% of 3 branch comections 6" dia. PT B-J 100% of 24 socket welds PT S-K-1 100% of 10 integrally welded supports VT B-K-2 10 intergrally welded supp;rts PT Ptsnp B-G-1 100% of 16 reactor coolant pump studs & nuts > 2 in. dia. UT l l Reactor Coolant B-P All SC-1 components were examined System during the system leak test VT l B l -s-

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i 1. Owner Maine Yankee Atomic Power Company, Wiscasset, Maine l 2. Plant Maine Yankee Atomic Power Company, Wiscasset, Maine 3. Plant Unit #1 4. Owner Certificate of Authorization OPR-36 f 5. Commercial Service Date 12-29 72 6. National Board NJmber for thit Reactor Vessel 20865 il

10. Abstract of Examinations COMP 0ENT CATEG)RY MJMBER OF WMP0 TENTS EXAMINED EXAMINATION Piping C-G 100% of 17 circunferential butt welds UT C-G 100% of 3 circumferential butt welds with reinforcement MT C-F 100% of 40 circunferential and longitudinal welds in pipes and fittings UT C-E-1 100% of 18 integrally welded supports VT i

C-E.1 11 integrally welded supports MT C-E-1 6 integrally welded supports PT C-E-2 18 integrally welded supports VT-Status of work required for the current interval: By the and of 1982, H11ne Yankee will have completed all the examination requirements for the first inspection interval. i l i ~6" } l _ 1 I

n 1. Owner W ine Yankee Atomic Power Company, Wiscasset, m ine 2. Plant Maine Yankee Atomic Power Company, Wiscasset, Maine 3. Plant thit #1 4. Chener Certificate of Authorization DPR-36 1 5. Commercial Service Date 12-29-72 e l 6. Stional Board Number for thit Reactor Vessel 20865 1

10. Abstract of Examinations (Preservice)

COMPONENT CATEGORY MJMBER OF CDMPONENTS EXAMINED EXAMINATION Piping Presure B-J 100% of 6 butt welds - baseline Boundary examinations of 3 check valve installationc EDCR 81-16 RT, UT, VT B-J 100% of 4 socket welds - baseline examinations - E EDCR 79-54 Visual, liquid penetrant or magietic cartical examinations were performed for the following desigi changes. These changes were mach to safety class 1, 2 and 3 components that are exempt from further inservice inspections, other than periodic leak testing. They are listed here for information only: EDCR 79-54 Reactor Vessel Vent EDCR 80-37 Hot Leg Injection EDCR 80-44 Pest Loca Hydrogen Control System EDCR 80-45 SCC & PCC Piping Modifications EDCR 80-51 Primary Component Cooling Isolation EDCR 81-3 HPSI Header Recirc. Lines EDCR 81-10 Pressure Taps & Root Valves for Primary Inventory Trend System EDCR 79-18 SCC Trip Valves l PDCR 5-81 CS Pump Casing Header Drain and test Connections PDCR 11-81 PCC-M-43, SCC-N-165, Bypass Modification l i l 1 e l

1. Ovner Wine Yankee Atomic Power Company, Wiscasset, Wine 2. Plant Maine Ywkee Atomic Power Company, Wiscasset, Maine l 3. Plant tk11t #1 4. Ovner Certificate of Authorization DFR-36 5. Commercial Service Date 12-29-72 l 6. %tional Ebard MJRDer for thit Nactor Vessel 20865

11. Abstract of Ccriditions Noted WELD / COMP 0 TENT EXAMINATION METFDD INDICATION Safe-end per (SE-2)

H, UT Linear surface indications But weld 10"- 01-1 (19) H, UT Linear earface irregularity Support 10"-CH-2 (CH-A 7) F_PT thdercutting on support t 6 l l I i l' I O V ! o '1-------,- .-_, _.. _...-. - _,....,. ~. - . n --

j t j i l 1. Ovner Maine Yankee Atomic Power Company, Wiscasset, Maine i i 2. Plant Maine Yarkee Atomic Pcwer Company, Wiscasset, Maine I t 3. Plant thit #1 4. Ovner Certificate of Authorization DPR-36 3 i I 5. Commercial Service Date 12-29-72 i f 6. National Board MJmber for thit Nactor Vessel 20865 I

12. Abstract of Corrective Actions Recommenchd and Taken f

WELD /COMPOENT (I)RRECTIE ACTIONS TAKEN Safe-end per (SE-2) Removed indication by filing. Butt weld 10"-01-1 (19) Removed indication by 11 git grinding. SJpport lO"-CH-2 (CH-A-7) Evaluated by engineering and approved for service. l 1 1 we -g<y-- <m-- p-w.- r-- e 4 e

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I wiscAssET, MAINE 04570 OR TURB\\ME

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VALVE IlOUSE see rir.. is SEE ' " " I srE rio. :: SIIIEl o WA L L <->c -~ ~~~ ~ ~*~~ 'S i E. f! n. i Es ~ g ( )k2 ()C5 r=- " E,. ( ll 20 / \\,, /s 2 3 y t'I e pg 4.% 'I 2f n 'It i E D-50t TE D / t v \\ /y F R0fn 5#ifl 0 W Ang to 5 88-2 A# 5 88 ' 3 1 i 6 ' I I \\ r.f TO A10 ion OrtAAf rD sn.: j F 50t AiroN FALVf' l ff t, /Ik g M g 31 Wrp p-4-001 20 / ,30 f It" WEPo-o-GOD

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7 i i MAlNE YANKEE ATOMIC POWER CuinPANY l _l'O : STEAM GElF.roli E l-3 l / R R #2, BOX 3270 WISCASSET, MAINE 04578' FROM: FW-F - 30 I ('NE. AR l g,p. PEM. OR TURB\\NE IIALL)- C-2 p O~~-~~~~.fe is 'l 9 A' 7:,Tr4.e, 8 / c.c o. r i n yt. - - - ~, 6 7 E 3 4 p' 5, Wa t t.

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. _. _ _ _ _ - _.(..--.,.--.-_--.-__ MAINE YANKEE ATOMIC POWER CuanPANY -< ~i 1 R R #2{ BOX 3270 TO : STE AIA GEb)ERATOR l-2 WISCASSET, MAINE 04578' N ~

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e d (A r' N g \\. 4" Sill-l0 LOCATION; PRIPA Ally AUX. BLDG. p t / / 6*X-ECC.HED f-3 i M l L kL'd ' R i c. - - -{ 3" SlH-37 c3,g _3.u m J 1131-4 4 4 i I !.i b (a T _ ff SlH-26 !~ l l t/2" saH2 i T I I 'j i SlH-H-97 1 - d 4" Sill-3 MAINE YANKEE ATOMIC POWLfl Pvmesti. j R R #2, BOX 3270 WISCASSET, MAINE 04578 d 1 i i ex 4"RE D UNE. l7P / ( siH-17 1 / 2 HANGERS 1 f "stW4 4

l U o0 ..~ ..) ( MAINE YANKEE ATOMIC POWEll COMPANY W R #2, DOX 3270 WISCASSET, MAINE 04578 - - ~ r ~ 7 1 nc.-Sil-502.\\ .3 H Rc HSS-6DI 82 s ou nc-HSS-60 P_ j g oi s 82 c s ac-io ) Rt -s-28 4 ,, c 6-FAC-Sil-501 ^ NPN ' Noo o g e. 2. i 82 D b \\ es a es c Y \\ / ] 1 i l l 8 1 I 8' ' 89 C I I ai s s2 I - es s I i i y_ __ _ _. _ _ _ s i s I h N 32 nC 29 I 33 st2 ac.7 g i l W i r FIGURE B-12. RC !I J IN. REACTOR COOLANT LINE I 1 e + i 3 e . ~l

m - E + 4 g </-N k~ '. Q / e / I, : :;t-o i + L*) ut O. (. / V i-j g i E e E = n s a o '.R e e e a s a e a 55 5 lC 39m E o M D4 d_E / Q 'e 0$E E E 3 3N N $ s 'c N

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/ = 9 -. c. s..- ec e = v l w-y h l ( = il ca ( ~ E i i -~> T-t -Y l 3 I f p/ , =. - = , ~- 2 =I E h ~ _ v e = s -c N, 5 $5 s 2 c ~ ~; } v 4 = ~ -v s e -M E-- = c ( N l'* E i D, d =" 9 v e O 5 5 h b, , f1 O a O e g ,ii [ l ~ Q 85 i l. M' /*;-..=. 7 l> i v i j f . - - _.. -....--...~ -, - ~~~- - l I

1 MAINE YANKEE ATOMIC POWEfl COMPANY R R #2, BOX 3270 wiscASSET,1.1AiWE 04578 1 i 4 ] i T ~ s /,8**RC-g$ i l RC-5-38 s 2 RC-SH-sos s2 is .l i l l Rc-37 73 / rs 3 \\, 1 ^ )7 R'- s \\ l i w W s4d' SS j l R( - jg.gg, 4 77 8 iN S3 j 72 A u 33-1/2" RC 12 1 FIGURE D 15. RC 16 3-IN. REACTOR COOL. ANT LINE 9 l 1 i j 1 o } I

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) N) MAINE YANKEE ATOMIC POWER 90 ANh R R #2, BOX _3273. j WISCASSET, MAINE 04578 l, 1 I j l i i RC-R-22(Vd S9 S8 i 39 40 t 1 S7 .Rb~b-b RC-R-20 RC-R-M M y 28 8 T RC-6%-2\\ o V PK-8 j 4, Sw. i3 4s 4 i SSG 4s SW-i2 j l 4s sy Q Sw.io 38- ^ ) [ HTo ne.is j 6 s4A I;,, 2. m 45-c PR -A -L 'N: ) 4 ss Kc-5 -21 (W) nier oc o 8: i PR. el-i- e 1 r ecuni n 36. _Rc.i7 3 N.REAcTon coot ANT tlNE ? ? l

A ~. l l MAlHE YANKEE ATOMIC POWER COMPANY R R #2, DOX 3270 t WISCASSET M/LINE 04578' S9 ~ 45 A o ^s E2 Pressurizer f i / as s es s t / p' l, 44 's, / i 'sj# $g r-un RC-R-5( / S5 88 s c tr 34 f f "RC-ust-t ot a/ 2" RC 19 g j s e s i, (84^ \\ 44 A 53 S3A f S i t 4 4 7 44 8 44 C 51 S2 M 'hkussille 8 s 'vsi\\ nc.is 3 4 { IlGURI D 18. RC 19 4 IN. RI ACTOR COOL ANT t INE (Siwei l of 2) i ) e

j i, i - i liJ ) w ( Y NAP n U.C REW 9 O 1 P 8 C H 7 C 5 4' 4 n I M 0 e A T A 2, O f 0E t T 7 N A 2I N E 3A E M i X K n. O A N T B E A n AY ,S I r 5 i. e 2S s. m E#A i me N C N e n I RS A I i MRW m i, A L o %E i 0 ^ n ii w i l n. w 4 7 n. . (,, A += 9 n i 4 2 r j,i liiL n e u '0 r i s 7. 7 1 n ,i i n n i a'n i m e e eo ) ( i !>I! ii l! iI:1Ii: 1 4 I 4 e

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) N ( MAINE YANKEE ATOMIC POWER 40 A H h

  • i R R #2, BOX. 3270.

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( ~'y i 1 i MAINE YANKEE ATOMIC POWER C0.nPANY R R #2, BOX 32"/0 WISCASSET, MAINE 04578 %A To 4"* l.C 19 h N 'Al A fel A hiA %, 19 A km l N # ^ i.w I 1 4 1110 f. fe l A i sq l- } (g, ~ i n,, /,l i2ii j i I <t.

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l .i '. MAINE YANKEE ATOMIC P_OWER COMPANY j

  • R R #2, BOX 3270
j wiscAssET MAINE 04578 i
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MAINE YANKEli: STOMIC POWER COMPANY g n,n o c.e R R #2, BOX 3270 WISCASSET, MAINE 04578 Lot V1 J.0 Sitt S 2. S ts s ia 5 $ gg.g,y D 5 87 s k { s i3<.c .$9-l.-t S 15 %s s3 4 W.$ f I s se stri-su-so

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r / 'j MAINE YANKEE ATOMIC POWEkCOMPANY h R R #2, BOX 3270 Q WISCASSET, MAINE 04578 } STEAM e-f GEN. i E-l-l A I 4 '.l i s Y.'FPDSit 329 OR WF PD-SS-32 9 f WF I'D L SS-202 K FPD-SH-19] PENET. i e' CRANE WAIL 53 L _- ,,'N ,f g WFPD-Sil-2 ) 1 ( - WF PD-Sil-32n CONTAINMEN T W F PD-Sil-2 8 WFPD-Sil-22 W F PD-SS-23 ANCllOil FW-100 p I 53 ' EDUCER WFPD Sll24-FW-F 107 (EDUCE R F W-M-lO 4 j _g m .-c+ ( 14** WFPD-4 SC-2 l-I SHOCK SUPPRESSOR 7 SPRING HANGERS 3 HANGER i

~ ~ - =- ~ __ ~ ~ -. .I - - -. _ _ _. ~. _ r\\ ,3 [9 .l 4 I N MAINE YANKEE ATOMIC POWER CO ePANY R R 1/2, BOX 3270 J WISCASSET, MAINE O'4'578' WAPD-ll-309-pWAPD-il-307 f ^ l WAPD-H-311 -WApo-it-30g ' WAfD-Il-310 N 'WAPD-A-30S j WAPDil-304 i s ANCHOR WAPD-if-302-WAPD-H-303 L WAPD-A-312 WAPD-li-369A ) h i 1 I J l T> - WAN-H-3OO l (WAPD-Sil-3G73 'N b Y i'. WAPD-H-314 t WAPD-SH-3GS 5 / l j fl'ELEV PEN 75 '. 4 e CONT. WALL ) CONT. \\ ,L l f l. e,s j ma,e-as s. f PAGE 2 OF 3 j ; 6"WAPD-23-60lR3 I la 0 !j 2 SPRING HANGERS ITEY 1 l 14 HANGERS h

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k1AINE YANKEE ATOMIC POWER COwiPANY nin #2, sox 3273 .i WiScASSET, MAINN. 0457d OU BON ' M1 '2-k i TO: Cll ARGlklG PUMP SUCTiot t HEADE R C. ll-6 FROM: VALVE \\\\S\\- 53 l I / i fd% 6' RED / 6'01-3-152-El }_._['zI ~ja .a rs h i e D. f .1 i O (' .en-n =,5 A 3-LI' '0,fs e r IO*- Gi-l - ISZ-R2 y s,! CHARGING.UNE W-ces -l ggg gi 24 WCLb5 ,J I ANC a*.o M )( A.-i FIG. 2.30 j: ~ 1 .i: ) I 1 1

I'liiMMW AUKILIARY Bu\\LDi'\\G ..EVEL,7 MAltlE YAf4KEE ATOMIC POWER Co.aPAIJY / R R #2, BOX 3270 TO: Cl\\ARGlh1G FUMP SUCTION WISCASSET, MAINE 0'4578 HE.ADER C\\\\-6 .FROM : VALNE l1S\\- 52 l s' cn-r-ssz-se a__, ~ 10 a b* Rtb. z 2 Aa nsion A,-z? I Wcn-s.-sSt.gz se ,I e l jt no" cn-t-tsi-xi 1 m lo' C 64 - Z-152-af 2 i ,3 Omstatais LsAst of .,a M la/t t D S e '# ~' Se,pg u".. ~ i FIG, 23l j! j 5 i 4 3 l i i I ~

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1.0 INTRODUCTION

This report describes the inservice inspection performed during the 1981 refueling outage at the Maine Yarkee Atomic Power Station, Wiscasset, Maine. The non-destructive l examination procedures used for inservice inspection were in accordance with the 1974 edition of the ASME Boiler and Pressure Vessel Code, Section XI, " Rules for Inservice Inspection of Maclear Power Plant Components", up to and including the Summer 1975 Addenda; except that piping examinations and acceptance criteria for piping examinations were in ac:ordance with the Summer 1976 Addenda. Additional examinations were as delinestd by Plant Technical Specifications. Inspections were conducted to the extent allowed by system chsign and the non-destructive testing technology employed. This report sunmarizes the areas examined, the type of examinations, test data results, evaluations, and repirs. Manual ultrasonic testing techniques were employed in conjmetion with visual, liquid penetrant, and radiogragt11e examinations. 1.1 Examination Methods All non-destructive examinations were performed in accordance with Yankee Atomic Electric Company procedures fomd in Engineering Guidelines Book III, " Inservice Inspection POE Procedures". The examination procedures were reviewed and approved by-persomel qualified to SNT-TC-1A, Level III; and conform to the requirements of ASME Seetion XI (S' 75 & S' 76) and applicable portions of ASME Seetion V (S' 75). The inservice inspection examinations were performed and evaluated by persomel qualified to the 1975 edition of SNT-TC-1A. t 4 ' j L- -- -. l

i l The following Tocedures ~were utilized for the examinations: j Procedure A Number Revision Title YA-ISI-l 6 Inservice Inspection Program Requirement YA-G-1 0 Preparation of Welds for Ultrasonic YA-VT-1 4 Visual Examination Procedure YA-MP-1 1 Magletic Pa.tical Examinetion YA-PE-2 2 Liquid Penetrant Examination YA-RT-1 1 Radiogra;211c Examination YA-UT-1 1 Ultrasonic Examination - General Requirements YA-UT-2 1 UT of Vessels - Circumferential Longitudinal, Meriodional, and Flange Welds YA-UT-4 1 UT - Nozzle to Vessel Welds YA-UT-5 1 UT of Integral Support Attadiment Welds YA-UT-7 1 UT of Bolting YA-UT-9 1 UT of Ferritic Piping Welds YA-UT-10 2 UT of Austenitic Piping Welds YA-UT-ll 1 UT of Piping Dissimilar Wtal Welds YA-Ul-13 1 UT of Vessel - Nozzle Inner Radius YA-UT-15 1 UT of Piping - Straicfit Eham ,e 3 a e g e -.. i ! I J

~ n-,_ l F' i 1.2 Evaluation of Data f i The examination results were reviewed oy personnel qualified to SNT-TC-1A Levels II i and III. Indications were evaluated to the acceptance standards in the 1974 edition of the ASME Boiler and Pressure Vessel Code Section XI, up to and including the Summer 1975 Adchnda, except that the acceptance standards for piping examinations are in accordance with 'he Summer 1976 Addenda. 1.3 Examination Results Summaries of all examinations that were performed are contained in Section 2.0 of this report. All detailed examination data, calibration records, material and equipment cerifications, personnel qualifications, and procedures are maintained at the Plant site 1 as part of the permanent Plant records. Details of reportable indications and corrective measures can be found in the applicable parts of Section 2.0. ] i l l l l '9 1 i ,s )

1 o I 2.0 SIM4ARY OF EXAMINATIONS This section sunenarizes the inservice examination. data for the 1981 refueling i outage at Maine Yarkee. The results are stsnmarized in accordance with ASME Section XI examination categories. 2.1 Reactor Vessel B-C Reactor Head-to-Flange Weld j Half of this weld, from 1800 to 3600, was examined ultrasonically. There were no sig11ficant indications. B-G-1 Pressure Retaining Bolting Greater than 2 Indies Twenty-seven reactor head closure studs; numbers IS thru 13S,15S thru 27S and 30 were examined ultrasonically, and by liquid penetrant. There were no significant indications. Nineteen reactor head closure stud washers; nutters 1, 4, 6, 10, 12, 14, 15, 16, 18, 20, 22, 24, 25, 26, 28, 30, 32, 34, and 35 were examined visually. There were no sicpificant indications.

2. 2 Pressurizer B4 Longitudinal and Circumferential Shell Welds Ole aid a half foot of weld nuncer P-VL2 and two feet of weld P-C2 were examined ultrasonically. There were no sicfificant indications.

B-F Nozzle-to-Safe Ehd Welds i 100% of safe end welds SE-1 and SE-2 were examined by ultrasonics and liquid penetrant. A 4/10 in. linear indication was discovered in the transition area of weld SE-2. This indication was removed with a file, and the surrounding area was i blended to a slight taper. The weld was re-examined and no indications were found. B-H Integral Support S<irt Weld One and a half feet of the attadiment weld, at 2250 was examined ultrasonically. There were no sig11ficant indications. l B-G-2 Pressure Retaining Bolting 2 indi diameter Twenty manway studs and nuts were visually examined while installed in the manway. No recordable indications were observed. l

2. 3 Steam Generator E-1-1 8-8 Longitudinal 91 ell Welds One foot of each of 5 welds; l-M1,1-M2,1-M3,1-M4 and 1-M5 were examined ultrasonically. There were no sig11ficant indications.

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I t e B-8 Circumferential 91 ell Welds The follcwing welds were examined ultrasonically and no significant indications ~! were observed: 27 in. of weld 1-C2 12 in, of weld 1-C3 l 4 in. of weld 1-CA 4 in. of weld 1-C5 4 in. of weld 1-C6 2.4 Steam Generator E-1-2 B-G-2 Pressure Retaining Bolting 2 in. diameter Thirty-fnter manway studs and twenty-three manway nuts were examined visually while they were removed. te recordable indications were observed. B-Q St.pg enerator Tites Five htndred and sixteen tubes were examined for defects, in accordance with Maine Yarkee Tech. Specs. Eddy current examinations were performed on the hot leg and U-bend of each tube, and no recordable indications were observed. 2.5 Piping B-F Pressure Retaining Dissimilar Metal Welds Weld RC-14-S (SE-2) was 100% examined by ultrasanics and liquid penetrant. Welds RC-14-S (SE-1) and RC-9-S (SE-8) were examined by ultrasonics from the carbon side only. Examination from the cast stainless steel side was not possible because of the materials large grain structure. The weld and adjacent material was 100% examined by the liquid penetrant method. There were no recordable indications - observed during the ultrasonic or liquid penetrant examinations. B-J Circumferential Ploe Welds The following butt welds were 100% examined ultrasonically. There were no sig11ficant indications. Line tomber Weld tombers RC-19 45, S-10, 45-A, S-8, S-7, S-9, 45-8 RC-ll 91-A, 90-C, 90A RC-17 41-A, SW-12, 43, SW-13 RC-16 S-1, 71-B, S-2 RC-26 S-37, 56, 54, S-29, S-30, 55, 35-A, S-31 CH-51 1260-A, S-4 SIH-31 60, 60-A, 60-8, 60-E, 61-A, S-17A SIH-42 19, S-1-A, S-1, S-2, S-4, 17 SIH-20 S-6, S-5, S-4, 74 SIH-41 26, S-3, S 4, 27, 30, S-16 l t il !l 1-lln

e l' B-J Brandi Connection Welds Greater than 6 Inches i Nozzle-to-pipe welds Li Jnd N-2, on line RC-14, were examined ultrasonically and j by mag 1 etic partical. re sig11ficant indications wre found. B-J Branch Comection Welds 6 Indies or Less l Three branch welds; numbers 15,16, and 17 on line RC-15 were examined by liquid penetrant. There were no indications. B-J Sodet Welds The following so&et welds were examined by liquid penetrant. There were no recordable indications. Line Wmber Weld Wnters RC-19 46-A, 47, 48-A ORH-1 20, 6, 19, 18, 17, 21 DRH-2 57, 58, 60 CRH-5 128, 129 CH-58 1471, 1472, 1473, 1474, 1478 CH-127 1513, 1514 CH-128 1496, 1497, 1498 B-K-1 & B-K-2 Integrally Wel&d Supports and Components Ten integrally welded supports were examined visually and by liquid penetrant. The liquid penetrant examination was limited to welds on the pressure boundarys. There were no sig11ficant indications. the following supports were examined: Line Wmber Support Wmbers CH-126 H-6, H-17 CH-270 CH-A-140, 01-A-144 SIH-30 SIH-A-140 SIH-42 SIH-A-44 SIH-41 SIH-A-119, SIH-A-129 l WH-1 DRH-1-3, N H-1-4 2.6 Reactor Coolant Pump #3 B-G-1 Pressure Retaining Bolting Greater Than 2 Indies l Sixteen studs and nuts were 100% examined ultrasalically aid partially examined visually while in place. There were no recordable indications. i i i _. _ =. - -

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~= ~ ~ ~ ~ ~ " ,T ~~ e (e l 2.7 Piping l C-F Circumferential and Longitudinal EhJtt Welds The following full penetration welds, in pipes and fittings, were examined ultrasonically. There were no recordable indications. Line Msnber Weld Numbers t l SIH-22 10 i SIH-31 S-10 SIH-42 S-10, 15 RH-12 S-37 RH-26 S-26, 53 RH-28 C-16 RH-ll S-44, S-49 RH-25 34 RH-27 S-26 RH-20 S-41 RH-13 S-22 RH-30 48A, S-26 RH-33 S-33 CS-6 S-32, S-33, S-27, 50 CS-4 S-14, S-16 CS-21 S-32 CS-23 11, S-39, S-41 CS-22 S-14, S-15 CS-8 S-45, S-46 CH-3 2 CH-4 1 CH-5 11 CH-1 18, 19 CH-2 17, 19, 21, 22 C-G Circumferential EkJtt Welds in Ploes The following full penetration welds were examined ultrasmically. There were no recordable indications: Line Rrnber Weld Rsbers WFPD-4 15 WFPD-8 16, 9, 17 WFPD-10 19 WAPD-21 24 WAPD-23 10 WAPD-25 17 SDHV-1 S-9 SaiV-2 7 SDHV-3 S-4 SHP-1 4, 4-L, 6 SHP-2 9, 23 SHP-3 S-42 I The reinforcement-saddle welds; SFP-1-S-3, SHP-2-S-22 and SHP-3-S-40, were examined by agnetic particles. No recordable indications were fomd. 4 _

= 4 t i& C-E-1 and C-E-2 Integrally Welded Supports Visual and liquid penetrant (or mapetic partical) examinations were. performed on the following welds. Liquid penetrant and mapetic partical examinations were performed on pressure bomdary welds only. Support CH-2-CH-A-7 had mdercutting on I}r the support side of the pressure baundary weld. This undercutting was evaluated and found to be insipificant. tb other indications were fomd. Line NJmber Support PO t ers }' WFPD-8 WFPD-SH-1, WFPD-SH-40 WFPD-lO WFPD-A-13, WFPD-H-14, WFPD-LSS-213 WFm-LSS-214, WFPD-SH-30 CH-2 CH-A-7 SIH-17 SIH-A-11 SDHV-4 SDHV-SH-46 RH-2D RHS-4 RH-27 RH-R-17 CS-22 CS-A-56 WAPD-23 WAPD-SH-367 WAPD-2$ WAF0-SH-368 CS-2 CS-A-42 CS-4 CS-R-62 WFPD-4 WFPD-SH-19 2.8 Piping Preservice Examinations B-J Circumferential Pipe Welds Three 1D-indi check valves were installed in the hic) pressure safety injection sys tem. Each butt weld was examined by ultrasonics and radiography. There were no simificant indications. Line tunter Valve tOmber Weld tonbers SIH-22 HSI-61 575, 576 SIH-31 HSI-62 577, 578 SIH-42 H5I-63 579, 580 i I l i r i ! Il

4 i ,1..- I 3.0 SYSTEM PRESSWE LEAK TESTS j The reactor coolant system was given a system pressure leak test at the system nominal operating pressure. Visual examinations were performed afte,r the system had been tn&r pressure for four hours, in order to fulfill requirements for examination categories B-E and B-P sid a system leakage test prior to startup. Wmerous leakages were detected at pa&ing glands and gasketed closures while increasing the system pressure to the leakage test pressure. All suth leakages were corrected prior to cc:mencing the final system leakage test. m leakages (other than normal controlled leakages) were etected on the final system leak test. 1 E 1 ' I i , l ! y-. m. . ~, ._m,-

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4.0 CONCLUSION

S i l' These examinations were performed to fulfill Maine Yankee's requirements for inservice inspections for the third period of our first inspection interval. We will complete our first interval examinations during our refueling outage in 1982. ._f l l l l l i I, i' t --}}

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