L-84-341, Forwards Addl Info Re Second 10-yr Inservice Insp Summary Plan,Per 840817 Request
| ML17346A633 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 11/20/1984 |
| From: | Williams J FLORIDA POWER & LIGHT CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| L-84-341, NUDOCS 8411260339 | |
| Download: ML17346A633 (162) | |
Text
REGULATORY ORMATION DISTRIBUTION SY M (RIDS)
ACCESSION NBR'8411260339 DOC DATE! 84/11/20 NOTARI ED:
NO DOCKET FACILt50 250 Turkey Point P'lant'nit 3i Florida Power and Light C
05000250 50 251 Turkey Point Plantz Unit 4g Florida Power "and Light C"
05000251 AUTH,NAME AUTHOR AFFILIATION WILLIAMS<J~ W, Florida Power 8 Light" Co, RECIPeNAME RECIPIENT 'AFFILIATION VARGAiS~Ae'perating Reactors Branch 1
SUBJECT:
For wards -addi info re second 10 yr inservice insp summary pla~rpe 840817 re uest, DISTRIBUTION C DE:
0470 CO S
RECEIVED!L'TR ENCL SIZE:
TITLE>
OR Sub ittal: In ervice Inspection/Testing NOTES<
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FLORIDAPOWER & LIGHTCOMPANY November 20, 1984 L-84-343.
Office of Nuc 1 ear Reactor Regul at ion Attention:
Mr. S.A. Varga, Chief Operating Reactors Branch Pl Division of Operating Reactors U. S. Nuclear Regulatory COIIIIission Washington, D.C.
20555
Dear Mr. Varga:
Re:
Turkey Point Units 3 and 4
Docket Nos. 50-250, 50-251 Inservice Inspection Second 10- ear Summar
'Pro ram Florida Power 5 Light has reviewed the NRC le'tter dated August j.7, 1984 which requested additional information on the Second 10-year Inservice Inspection Summary Plan for Turkey Point Units 3 and 4.
P l
Additional information to assist in the review of the program is attached.
The questions have been addressed in the applicable relief requests.
Should you or your staff have any questions on this information, please contact us.
, Very truly yours, J.
W. Williams, Jr.
Group Vice President Nuclear Energy JWW/PLP/cas cc:
J.
P. O'Rei lly, Region II Harold F. Reis, Esquire PNS-LI-84-369-2
-84ii260339 84i i20-j PDR ADOCK 05000250 8
PDR PEOPLE... SERVING PEOPLE
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TURKEY POINT PLANTS 3/4 FIRST
& SECOND INTERVAL RELIEF REQUESTS INSERVICE INSPECTION FPL letter L-84-87 dated March 30, 1984 submitted a proposed Inservice Inspection (ISI) program for the second 10-year Inspection Interval for Turkey Point Units 3 and 4.
Included in the program, FPL requested relief from certain Examinations where code required volume or surface was not achieved.
During the NRC's
~ Staff review of the program, questions of a generic and specific nature were discussed with the staff and their consultant via telephone conversations and informal receipt of questions.
Accordingly, FPL has addressed these questions and have taken the following corrective action:
1)
Pursuant to the terms of 10CFR50.55a (g)(5)(iv) FPL herewith requests relief from the requirements of the code edition and addenda applicable during the First Inspection Interval not previously submitted.
See index to Additional Relief Request First Interval.
2)
Pursuant to the terms of 10CFR50.55a (g)(5)(iii) FPL herewith requests relief from the requirements of the code edition and addenda applicable to the Second Inspection Interval. In some instances, certain relief requests in the First Inspection Interval are withdrawn based upon the applicable code requirements;
- whereas, others apply or are withdrawn or withheld in the Second Inspection Xnterval, since the applicable code requirements differ. See attachment Index to Relief Requests
( Response to NRC Questions)
Second Inspection Interval.
3)
General questions pertaining to the programmatic aspects will be covered upon completion of the 10 year Inspection Program Plan.
RELIEF REQUEST NUMBER CODE CATEGORY FIRST INSPECTION INTERVAL RELIEF REQUEST INDEX DESCRIPTION 10 5A 13 14 15 B-B/B-C/B-D B-K-1 B-C B-C/B-D REACTOR VESSEL REACTOR COOLANT PUMP INTEGRAL ATTACHMENTS REACTOR COOLANT 6 AUXILIARYCOOLING SYSTEM WELDS REACTOR VESSEL CLOSURE HEAD REACTOR VESSEL
SECOND INSPECTION INTERVAL RELIEF REQUEST INDEX REQUEST NUMBER 6/7 10 12 CODE CATEGORY B-C/B-D B BtB D~B H~B J N/A B-L-1/B-L-2 B-M-2 B-K-1 B-J C-F B-A DESCRIPTION REACTOR VESSEL RPV SAFE ENDS WITHHELD PENDING REVIEW OF ACTUAL CONDITIONS ENCOUNTERED DURING EXAMINATIONS REGENERATIVE HEAT EXCHANGER WITH DRAWN FROM SUBMITTAL RCP FLYWHEEL (RG 1.14)
REACTOR COOLANT PUMP VALVE BODY WITHHELD PENDING REVIEW (SEE RELIEF REQUEST 0
8 ATTACHED)
REACTOR COOLANT PUMP REACTOR COOLANT 6 AUXILIARYCOOLING SYSTEM WELDS CONTAINMENT SPRAY SYSTEM REACTOR VESSEL CLOSURE HEAD
li P
TURKEY POINT UNITS 3
& 4 FIRST INSPECTION INTERVAL INSERVICE INSPECTION RELIEF REQUEST f 5A A.
COMPONENT IDENTIFICATXON:
CLASS 1
REACTOR COOLANT PUMP B. EXAMINATION REQUIREMENTS:
Exam Cat.
Item No.
B-K-1 B5.4 VOLUMETRIC EXAMINATIONS INTEGRALLY-WELDED EXTERNAL SUPPORT ATTACHMENTS INCLUDES THE WELDS TO THE PRESSURE
-RETAINING BOUNDARY AND THE BASE METAL BENEATH THE WELD ZONE AND ALONG THE SUPPORT ATTACHMENT MEMBER FOR A
DXSTANCE OF TWO SUPPORT THICKNESSES C. RELIEF REQUESTED:
t Relief is requested from alternate surface examination of inaccessible weld and adjacent areas of the pump support members not achieved during the Xnspection Interval.
These include the following welds:
Item B5.4 3-RCP-A-Lli2 3
3-RCP-B-Lli2 3
3-RCP-C-L1,2 3
4-RCP-A-Lli 2 3
FIG.
NO.
2 4-RCP-B-L1,2 3
FIG.
NO.
2 4-RCP-C-Lli2 3
FIG.
NO.
2 NOTE:
Relief from Volumetric Examination was granted on Relief Request No.
5 by NRC letter S.A. Varga to R.E. Uhrig dated April 26,1983.
D.
BASXS FOR RELIEF'..
Configuration'f the integrally welded supports as welded to the pump body, and structural interfaces prohibit 100%
ours.'ace examination coverage due to inaccessibility of portions of th weld. Figure no.
1 provides a graphic view of what areas of the lug cannot be examined.
The alternate examinations and tests provide assurance of an acceptable level of quality and safety.
RELIEF REQUEST 4 5A CONTINUED 1)
Perform surface examinations per the ISI schedule.
2)
Upon disassembly of a pump from the pad, conduct a
surface examination on the inaccessible area.
P.
IMPLEMENTATION SCHEDULE FIRST INSPECTION INTERVAL G.
ATTACHMENTS FIGURE NO.
1 RCP INTEGRAL WELDED LUGS EXAMINATION LIMITATIONS.
( Typical all 6 Reactor Coolant Pumps
)
FIGURE NO.
CIS-V-13 REACTOR COOLANT PUMP MAIN FLANGE STUD NUTS AND PUMP SUPPORTS
!1
EKnt'llttIAt'ION f4'ig Il 9 II=
fl n i)i NO FRAN QN UNKRSIOF OF I U& DUE TO A LACK OF AC.C ESS AL i luRKF'l pOINT UNlt ~(q S 30-84 RF.AC.TDP.
Di30LANT PURP IMTfGRAL MELOEQ L065.
TYP)CAL ALL3 Pul'1PS (3 LU&S PER PUYle>
R FLIFF R Fg'JF S T NO 5R FI60AE NO. I
RCP (t)
LL gcP-(e) L3 RCP-to I-I C)
RCP-( ~ )-2R RCP-I ~ )-2)
ACP-( v )- 22~
ACP-I ~ >-'
/,i~
~AC)'- I
>- )
/
RCI -I ~ )
~ a RCAC10A COO'N1 nu>
C ACP-I <<>- 2. >>C>> ~ ~ RCP-t ). 20 RCP-I v >- )') RCP-I ~ )- )0. RCP-I i )- ))>> RCP-le> ~ )g -RCP-Ii ~ o RCP-< i )- 1 RCP- < i ) - 0 RCP-(v )- 9 RCP-( ~ )- )0 Pu>IP SUP('OAT I.OCAI Iotr LOOPS A.B,R C RCr-1. >- ).. RCP-I > - ) i~ SUPPOAT OC!4 I L f'RON 4BOyC RCP-I ~ i- ) ) ~ RCP-t <<>- >> nv)<>I>a> So<Ci Sl <( SCn 1 1PC RCP-< ~ >- 12 .ID<Hi! ICAI ION 0+ A(PL CABLI'TUDS AND NUTS r><r>LL BI, t14DL OV It>SCRIING I><C COLLO)r>rr(f UCSIGt<AI IOHS IN nLACC OI <e) ACCCRCNCI 0>IA)r(NG. PLy HAIN ~ )IAI N l14 IN As> I N )14 IN I14 It< hRI >4 >r)N) Ala) COOL ANI COOLAt<1 COOLANT COOLANT COOLANT COOLANT COOLAUY C SAa)Y opsia>'1 Fu><n LOOn PUIIP LOOP AU>1n LOOn >'U><+ LOOn nu>)n LOO>> <)n 100> Pu>RP > oop )>uo)lo Loo& Pump J.OOP A STUDS-l f'SA) 4 NUTS-l I NA) 0 STUDS-(I SBI 0 NUTS-tf HB> C STUDS- <CCS) C NU1S IFNC) A Sup<>OOPS-( g) <3 c,uppoAt S-g) Suf> POI 1$ - C) 'C* I OR)< COOCS I! ! NSPCCT! ONS SCCT ION TURKT: Y PO! NT UN! 1 3/vf caava o> )rlD RCv<SCO RCACTOR COOL.slit! !'ugf> eA! N CLAN@! STuOS ): NuTS ANO pL><14 SuPPORT LgQg no Oall Rl r)$ >on Or <n Cra Rnr no Oa)l al var!Oa Or (>> Cra anr TURKEY POINT UNITS 3 PIRST INSPECTION INTERVAL RELIEF REQUESTS RELIEP REQUEST 4 10 A. COMPONENT IDENTIFICATIONs CLASS 1 Reactor Vessel B. EXAMINATION REQUIREMENTSs Exam Cat. Item No. B-C B-D B1.2 Bl. 4 VOLUMETRIC EXAMINATIONgCIRCUMFERENTIAL SEAM WELDS XN BOTTOM HEAD SHALL INCLUDE WELD METAL AND BASE METAL FOR ONE PLATE THICKNESS BEYOND THE EDGE OF WELD VOLUMETRIC EXAMINATION SHALL CUMULATXVELY COVER 100% OF EACH CXRCUMFERENTIAL WELD. VOLUMETRIC EXAMINATION (INCLUDES NOZZLE TO VESSEL WELD AND ADJACENT AREAS OF NOZZLE AND VESSEL); SHALL COVER 100't OF THE VOLUME TO BE INSPECTED. C. RELIEF REQUESTEDs Relief is requested from Code Volume not achieved during mechanized ultrasonic examination of the following vessel welds. Item B1.2 (Weld 3-WR-9 and Weld 3-WR-31) Item B1.3 (Weld 3-WR-18) ITEM Bl.4 (Weld 3-DO-A, B & C) Fig. No. CXS-V-Ol Fig. No. CIS-V-01 Fig. No. CIS-V-04 D. BASIS OR RELIEF: Configuration and permanent attachments prohibit 100% ultrasonic examination coverage of the required code examination volume. The limitations and justification for each weld from code examination is discussed below including applicable Tables and Figures. S RELIEF REQUEST 4 10 CONTINUED .0 3-WR-18 ( RPV SHELL TO FLANGE WELD) Bl.3, B-C 1.1 The areas receiving NO COVERAGE DURING THE examination performed from the upper shell side are depicted in Figure no. 2. 1.2 1.3 Figure no. 3 depicts those areas that did not receive 0 degree, 45 degree transverse or 60 degree transverse weld coverage due to the geometric configuration of the flange radius, located just above the weld. Percent of coverage limitation is contained in Table l. Examinations performed from the shell side of the weld, essentially provided 100 percent coverage of the weld and 1/2T of base material on the shell side. 2.0 3-WR-9 (LOWER HEAD RING TO DISC WELD) Bl.2, B-B 2.1 Limitations encountered during the examination of the above welds were attributable to physical limitations imposed by the INCORE INSTRUMENTATION TUBES . This condition was most prominent when performing examinations .o detect reflectors oriented parallel to the weld with the search un't positioned on the disc side. Due to the hei. ht restricticns and number of tubes in this area, attempts to perform examinations from the Disc side were abandoned. Figure 4 depicts the coverage on the Disc side during scanning from the ring side. 2.2 Examinations performed for the purpose of detecting reflector oriented parallel to the examination surface were accomplished utilizing a 0 degree search unit applied to the weld and base material for a distance of 1/2 t. As illustrated in figure 5, a portion of the weld and 1/2t of the base material on the disc side was not examined for the reasons detailed in 2.1 above. 0 2.3 Examinations performed for the purpose of detecting reflectors oriented transverse to the weld were restricted in a portion of the base material on the Disc side of the weld due to the INCORE INSTRUMENTATION TUBES. Figure number 6 identifies the areas where search unit module interference was encountered as a result of the tube interference in four locations, around the weld. These limitations were only encountered during scans 8 and 9 of examination no. 2, and scans 7,8, and 9 of examination no. 3, and were limited only to a small portion of the base material on the Disc side. RELIEF REQUEST 4 10 CONTINUED .0 3-WR-31 ( LOWER SHELL COURSE TO LOWER HEAD RING) Bl.2g B-B ~ ~3.1 Examination or the above welds was limited in the areas 'ontaining tNe CORE BARREL ANTI-ROTATION LUGS at azimuth l.ocations of 0, 90,
- 180, and 270 degrees.
These limitations posed physical device limitations when performing examinations from the shell side for the purpose of detecting reflectors oriented parallel to the weld. As depicted in figure no. 7, limitations were encountered on the lower shell course side when performing -45 and 60 degree examinations. Since these limitations were affected by the search unit module
- offsets, examination coverage varies as defined in Table 2.
3.2 Figure 8 represents the coverage received in this area when performing examinations from the lower shell ring side. As noted in this figure, the examination area receives coverage with at least one search unit angle and in some cases, two search unit angles. 4.0 NOZZLE TO SHELL WELD LIMITATIONS ITEM NO. B1.4, B-D (Weld 3-DO-A, B 6 C) Wn~-- oerforming computerized UT examinations of the NOZZLE TO SHELL WELDS from the vessel wall, several areas were described as having limited examination scans. These limitations were restricted to the last several scans of the nozzle to shell examination and were due to the physical limitations imposed by the adjacent nozzles. The limitations all occured in the vicinity of the 90 or 180 degree nozzle azimuth relative to nozzle orientation. Figure no. 9 depicts those areas not examined and Table no. 3 provides the percent of WELD volume not examined. The extent of examination volume achieved ultrasonicaly, and the alternative system pressure tests provide assurance of an acceptable level of quality and safety. E. ALTERNATIVE EXAMINATION 1) Periodic System Leakage tests per category B-P, rabl IWB-2500. Inservice hydrostatic test per category B-P, Kahlca Itqa-2500 RELIEF REQUEST 4 10 CONTINUED F. IMPLEMENTATION SCHEDULE FIRST INSPECTION INTERVAL G. ATT>~%KITS TO RELIEF REQUEST NO. 10 TABLE NO. 1 RPV SHELL TO FLANGE WELD LIMITATIONS TABLE NO. 2 LOWER SHELL COURSE TO LOWER HEAD RING LIMITATIONS TABLE NO. 3 NOZZLE TO SHELL WELD LIMITATIONS FIGURE NO. 1 NOT USED FIGURE NO. 2 RPV SHELL TO FLANGE WELD FIGURE NO. 3 RPV SHELL TO FLANGE WELD FIGURE NO. 4 LOWER HEAD RING TO DISC WELD FIGURE NO. 5 LOWER HEAD RING TO DISC WELD FIGURE NO. 6 LOWER HEAD RING TO DISC WELD FIGURE NO. 7 LOWER SHELL COURSE TO LOWER HEAD RING FIGURE NO. 8 LOWER SHELL COURSE TO LOWER HEAD RING FIGURE NO. 9 OUTLET NOZZLE TO SHELL WELD FIGURE CIS-V-01 RPV CIRCUMFERENTIAL WELD LOCATIONS FIGURE CIS-V-04 RPV NOZZLE ORIENTATION RELIEF REQUEST 4 10 CONTINUED TABLE NO. 1 AREAS OF LIMITED COVERAGE-RPV SHELL TO FLANGE WELD TOTAL WELD COVERAGE LIMITATIONS SEARCH UNIT ANGLE LIMITS OP WELD 0 45 60 45T 60T 60 25 20 60 60 TOTAL WELD LENGTH = 488+5li RELIEF REQUEST 4 10 CONTINUED TABLE NO. 2 AREAS OF LIMITED COVERAGE-RPV LOWER SHELL COURSE TO LOWER HEAD RING EXAMINATION NO. 5 SEARCH UNIT ANGLE 45 45 45 45 60 60 60 60 AZIMUTH LOCATION '76.75-103.25 166.75-193.25 256.75-283.25 346.75-13.25 80.75-107.25 170.75-197.25 260.75-287.25 350.75-17.25 LIMITS DEGREES 26.5 26.5 26.5 26.5 26.5 26.5 26.5 26.5 LIMITS INCHES 35.96 35.96 35.96 35.96 35.96 35.96 35.96 35.96 LIMITS OF WELD 7 4 7 4 7.4 7.4 7.4 7 4 7.4 7.4 TOTAL WELD COVERAGE LIMIT'ATIONS EXAMINATION NO. 5 SEARCH UNIT ANGLE 45 60 OF WELD LENGHT
RELIEF REQUEST 4 10 CONTINUED TABLE NO. 3 RPV NOZZLE TO SHELL WELD LIMITATIONS EXAMINATION AREA EXAMINATION TYPE LIMITS 8 OP WELD CUTLL'T NOZFLE WELDS PARALLEL SCANS OUTLET NOZZLE WELDS TRANSVERSE-SCANS 12 42 a4 '5.Z'I-84 cL. HOE SOIV P40ru 6 P,PV 5H'ELL TO FlRNGC NKLO RELIFF REQUE.ST Nd. l0 J 0 V NKLO ruvxt-1 FOUNT UNlT5 3 S. 2.'I-8'l
- c. t.. ANxasod Nolvf RPV SHELL TO O'I.RhlGF IIELD 3 IdR.I8 RFllFF RFQOE5T NO. lO FIGURE. NO.Z.
%a i<%. I h >i') 4;1.l'6 I I ] er 4 ~ ~r I Si45'mi Vn 6915 fbi VKK a ae'~15 1. VKK,15%,eO'-<A, .ed'URKEY POiNT UM1T5 3 5 7-9-8 l p.. /vDER$D/o HoQF LQldFR HEAD RlhlG TO DISC UJCLO R F LlFF REQUl= &T NO. )O Hogg LQU3FR HEAQ RING TO DI5t'IMNI0 RFLIFF RFGULST N6 IO & 0 I I I PI ~blbQF~ QtfAL4dt ~'~~'l)f~~ %- , I ,'. Q:Ill fCAN NflO $ I 4 >qt Iiet Iter I 5848 r TUMi 10iNt UNGAG 3* PR 8~ Ec N fRSOIO IVOl06 L04)FR HERO RlM6 TO Oi5C tdELO 3-MR-9 RELll'F REQUEST NO. l 0 FIQlRE NO 6 L(IG >o .s LQKKSjLL 8bfFS'~ f)HdiQf go CO 'P<' iaaf%~ Sal'unes tain iZnS > E I RN hl NOIVg LOU)FR Sl)ELL COUR5F TO LONFR HFAO RlN& >'4lR3'I RfLlFF REGOEgT NO lO l'IGURF NO 7 e I WELO ~ o ~~\\ ~ ~ 00~&toO ~ rusher= I l'Owr ue<s z 5-29 8~ E' A~OKRSci~ 'lO+E LONI;R SHF.LL COOR5r= TO iOldB HERD R)NG RELlFF REGUF5l'O. IQ fl&ORF NO. 8 I/2t TYP(CAL OUTLET ZZLE AREA NOT EXAhllNE 0 [jj] 60 FROM SHEIL N022LE AZINIUTH 350 TO IO g 45 T 8, 60 i FROM SHELL 458 60FROM SHELL 458 60 FROM SHELL I/2t TANGENTIAL SURFACE WAVE XUR,)<F5 PD/N5 UNVi,5 3 5-2-'I-8 0 NO&C DIIAWKIY F.L. RNDERSOIV hEVI DV Day: QULLl. T NOLl,LF TO SHl'LL h)LLD REI II=F ALGQI=57 NO. I 0 DhAWIK HUM% 0 I!AT I NG SURf AC!.'S FOR FLANGI' s GAtlCNI 4RI."4 SCC I'IG. t>0. C I5-UC5-I>) OUI LCl NOZZI C UPRCR SHCLL COUR5C Ql ltR 10 Its' I tt0 g I ~.'." NOZZi I .)4 ILNIRl I ON 4 iOCI)1t!stCAxtOtsf ~ ..>Ll S l.: S>3. I I>i ufS> t>i Vl" SL >S>' 'Oii I Vli s>>'At.. I Oit li.Irstt '> Sat I'IG. t>J Cl'5 US S-OL QZ tttICRHCUsAIC SHCI l COUASC fss! Cs NLSS iSs>> s lN C's ROO ING tSs> MIN. ClAOOING v!ts. Cl AUUING I.OvCR SHCIL 'OURSL L UAf Sut'I'OR 1 Gu s 0!. C1Z3 LOVCR slC40 Rilwc ) 1R-10 )- ssa-) j <ie4 leaf s>sst i ~ >s>>V ~ S i~ ~ ~ a ~ ss iy tiUILS I, i > IC ~.O. 10 Cl ROUI tiG FOR
- l. lil!IAI.:OiiS SCL Rf:I il.l'COUCS1 NO.
u1 crA>ts IAv RCculAIGRr Gv,UC i.is0 iis itRI4> S+scs '%i Siss t stt siO Os st ~ ~ s s s ~i ~ Os) 1 fU>t H'iU OISC ~ ~ s I i i ~ ~ ~ ~ i ~ ~ ~ s ~ Ps ~ ~ s ~ ~ s ~ s ~ ~ ~ ~ s s s l SO i st>51Ruttft>IRI IOts ttUZZl LS i-t>s>'.0. SCC FIG. tio. cis-ucs-00 t n < s.p i,i'i >eG s> siss >soe RCf'CRCNCf ORAV INGS s?Cv. 1CSI ING>SOUSC t l 1st EAC i> COOCS I? INSI"LCIIptt Sf:Cl !PN !URIC Y AP I ft I Uh! I f.l..lS!0 f?I'AC It'll I'AL"OUI>L VI >~l I C I ACUtff I Af Nl I'l ivsL t!'I. OCAl l OIIS I ft~>1 ttt,tf,'ft 1 *fI pft NpZZI I., i Itis, IIUI1!>f,ii: JF QA V I lt~l~+IL C: 'C ll ')
- i. >>stsss" C I'5 V 0 I
NOTES'. f'R INNER ft40IUS IX4IIS 400 I IRSI 10 NOZZL C IOCN1 If IC41 ION.Cx4IIoLC J-OO-S-S. 2. FOR VESSEL SUPPROT IOEN'Ilf'IC41ION 400 [S I 10 NOZZLE IO. Cx4II>LC J-OO-B-S. 0'i LOOP 8 OUTLCT NOZZL C WRteo T(CII CAQNATOR SLP" EIIG QlEr'wsOR IIAGER Iail M E Ot ~ ii Pl~! < 4 QePfvav t OOP 8 INLET NOZZL E J-00-8 J-Ol -8 J204 2ZO4 J-00-C 200" eo" QIJO'-Ol-4 904 I 00~ 4 INLCT NOZZL C VLSSl:L SUPPORT MCLOCD P40 DET4lL nal [ Rial 9>[C ~ 9! II 5[a I YI'[ Loo> C OUTLCT NOZZt C I 00 4 OUILt I NGZZI C J-0 I-C LOO> C INLCT NOZZI C J-00-4 IICf'CRL'NCC OR4'NING RCV IICST INGHOUSC I I le14C 9 CODES 8 INSPECTIONS SEC'llON TURKEY POINT UNlT 3 It[YI Claw eoa CH CGa ava ao ITal[ a[ vl9IOlv IY Cv [Ca[ C a>t'aOYCO dv ~ OaavN IY vTO Gal[ aCYISCO R U V L NOZZLE OR1ENTAT lON 8 NOZZLE'O SHELL IIELD LOCAT lONS ~ NOZZLE INNER RAOTUS RELIEF REQUEST f 13 TURKEY POINT UNITS 4 FIRST INSPECTION INTERVAL INSERVICE INSPECTION ' COMPONENT IDENTIFICATION: CLASS 1 REACTOR COOLANT AND AUXILIARYCOOLING SYSTEM WELDS B. EXAMINATIONREQUIREMENTS: Exam Cat. Item No. 1) B-J 2) B-J B4.5 B4.6 VOLUMETRIC EXAMINATION, SHALL INCLUDE THE WELD METAL, THE BASE METAL FOR ONE WALL THICKNESS BEYOUND THE EDGE OF THE WELD. VOLUMETRIC EXAMINATION; BRANCH CONNECTIONS THE WELD METAL, THE BASE METAL FOR ONE PIPE WALL THICKNESS BEYOUND THE EDGE OF THE
- WELD, ON THE MAIN PIPE
- RUN, AND AT LEAST 2" OF THE BASE METAL ALONG THE BRANCH RUN.
C RELIEF REQUESTEDt Relief is requested from Code Volume not achieved during manual Ultrasonic Examinations of the following welds Item B4.5 (12"-RC-3) 6" of circumferential weld FIG. NO. 1 Item B4.5 (14"-AC-4) 5" of circumferential weld FIG. NO. 2 Item B4.6 (12"/10"-RC) An area 4" x 3" of circ. weld FIG. NO. 3 D. BASIS FOR RELIEF! Configuration, permanent attachments and/or structural interferences prohibit 100% ultrasonic examination coverage of the code required examination volume. The limitations and justification for each weld is depicted in the attached figures. Fig. no. 1 Limitation due to welded plate at 180 degrees Fig. no. 2 Limitation due to proximity of adjacent pipe run at 270 degrees. RELIEF REQUEST 4 13 CONTINUED Fig. no. 3 Limitation due to the location of thermocouple at 100 degrees. The extent of examination volume achieved ultrasonicaly, and the alternative system pressure tests provide assurance of an acceptable level of quality and safety. B. ALTERNATIVE EXAMINATION 1) Periodic System Leakage tests per category B-P, Table IWB-2500. 2) Inservice hydrostatic test per category B-P, Table IWB-2500. F IMPLEMENTATION SCHEDULE FIRST INSPECTION INTERVAL G ATTACHMENTS FIGURE NO. 1 120 REACTOR COOLANT LINE LIMITATION FIGURE NO. 2 14" AUXILIARYCOOLANT LINE LIMITATION FIGURE NO. 3 10" REACTOR COOLANT BRANCH CONNECTION LIMITATION. C, FLOQJ %OP 08FIO CS.rute n 2)o so ialsusATioru td 61Pgg Pc.erg TOP bff40 C 6IU7EQ 9o' 8O~ tabac.0KO PLA7E 6n Cdogs 0 NoT GE, gqa~ivEO PuE Td ~fiOEO pLATE gT l80o '-so-en
- g. g
~ A ~OEPS N4Qf RFfKTOR C aOLAhlr 5'ISrFN tuFM lZ'Rc RFL)FF RFBUI.ST No l3 fidNE ND. I UQIT Nb, g ~ I INIlyRTIDlV r II'-Rc-I EL8D N 270 I 80'd BARM yuE'O OSSrWUC1IOH ~" PIPF ar 2 PRZ.. RB.lfF week FULL SCALE PLOT RRDI NOT EXRNlhlFD TOREI POIN! UNt s' 9 < WOrv F- ~ L ~ RiuOERSOrv FluNILIIIRj CODI.AI07 5'ISTEM llJI.LD IW'-AC-f, RCLlFf'F'GUEST NO I 3 jeune np.2. r e l 80 THERMO COUPLE R $ "al" ARM CRN NOT BE SCANAlED DUE TO THERMO COUPLE. TLlRKl."l l'OlNT UNlT '-30.84 Ai 'oe)E g L. Ah)DFRS~ RKACTOR COOLAMT 5'ISTEM IltrELD IZ/IO"-RC 10 BRPiNCH C.OAINr='cTIOlV CLIFF RFGllEST MO. Ig FIGNE'd. 3 TURKEY POINT UNITS 3/4 PIRST INSPECTION INTERVAL INSERVICE INSPECTION RELIEF REQUEST NO. 14 A COMPONENT IDENTIFICATION CLASS 1 REACTOR VESSEL CLOSURE HEAD B. EXAMINATION REQUIREMENTS Exam Cat. Item No. B-C B1.3 VOLUMETRIC EXAMINATION OF HEAD FLANGE WELD SHALL CUMULATIVELYCOVER 100% OF EACH CIRCUMFERENTIAL WELD. C. RELIEF REQUESTED Relief is requested from Code Volume not achieved during the manual Ultrasonic examination of the Vessel head -to-flange welds. Item Bl.3 (Weld 3-WH-12) 16" of circumferential weld. FIG. NO. 1 (HEAD WELD) No examination from the flange surface. Item Bl.3 (Weld 4-WH-12) 16" of circumferential weld. FIG. NO. 1 (HEAD WELD) No examination from the flange surface. D. BASIS POR RELIEP Configuration and permanent attachments prohibit 100% Ultrasonic examination coverage of the required code examination volume. The lj.mitations and justification for each weld is depicted in the attached figures. Figure No. 1 Limitations due to welded arrow located above stud hole No. 1. The arrow limits 7" of circumferential scanning of the closure head weld. No examination achieved from the flange surface due to configuration. Figure No. 2 Limitations due to 3 welded lugs located 120 degrees
- apart, between stud holes 10/ll, 29/30 and 48/49.
Each lug limits 3" of circumferential scanning of the closure head. 'l t RELIEF REQUEST 4 14 CONTINUED Therefore, the combined length (limitation) due to the arrow (7") plus the lugs (3"x3") totals 16" of weld not examined. The extent of examination volume achieved ultrasonicaly and the alternative system pressure tests provide assurance of an acceptable level of quality and safety. E ALTERNATIVE EXAMINATIONS
- 1) Periodic System Leakage tests per category B-P, Table IWB-2500.
- 2) Inservice Hydrostatic test per category B-P, Table IWB-2500.
F. IMPLEMENTATION SCHEDULE FIRST INSPECTION INTERVAL ATTACHMENTS FIGURE NO ~ 1 RPV CLOSURE HEAD CUT A%AY VIEW, DENOTING MEASUREMENTS OF LIMITATIONS. " FIGURE NO 2 RPV CLOSURE HEAD LIMITATIONLOCATIONS t'~ Cy I]I li p I ~ I <<<<a <<1 I ~ I~ yti OETAIL Pi" NELQKO AKRON y Ot i++ ldELOEQ ARROijJ LOeTi=O ABOUE STUD H6LE NO. I l QlH 1Li R-La)H IL~ CLOSURE HEAD TC FLFINGE 4JM I I I I I I I I I GETAIL 5~ hlELDt:0 LlfTlNt; Lut; T'1PlCAl 3 PLACE5 TljRl(l'.Y P0INT UNlT 3/1 SCAI. S'-30-84 0IIAWN Y 6 L. FIR)OCRSbN VI OV OIV: RPV CLOSURF HEAD ( CLlTANRY U(EMI) riRLfj'5 Ti)AT UtPJ NOT BE F/AN)NL'0 DUE TO LINlJRT)ON5 aF.LiF.l-REaur.ST NO if FIGURE ND. I ~' 0 ro 4>> LENGTH QF WELD 48I'ROWN WIDTH ~ T HICKNESS 7 2 HE,AD 'ual 270' ~e'10 g hlD EX'uE tO I. u)flap aging 1%tt
- 2. Qf)KO LES S~~i gO
~O O ~ VESSE l44y l~ gl L o'O r+ ~o~ lfN&tll4fgpss ltsi>> Ilail NI1 jQQfg IKIBSS TllRKES P0INT UNlt 3/ "I
- S'-30-9 I
AL I ~ogf + g ~MOKQ5oM RPV CL05llRE III:.AD ME'LOED A'HACIINF'ldT LOCH TIONQ RFLIEF REQUEST AIO I + FIGURE ND. 2 I' TURKEY POINT UNIT 4 PIRST INSPECTIOH INTERVAL RELIEF REQUESTS RELIEF REQUEST 4 15 A. COMPONENT IDENTIPICATION: CLASS 1 Reactor Vessel B. EXAMINATION REQUIREMENTSs Exam Cat. Item No. B-D Bl.3 Bl.4 VOLUMETRIC EXAMINATION SHALL CUMULATIVELY COVER 100% OF EACH CIRCUMFERENTIAL WELD. VOLUMETRIC EXAMINATION ( INCLUDES NOZZLE TO VESSEL WELD AND ADJACENT AREAS OF NOZZLE AND VESSEL); SHALL COVER 100% OF THE VOLUME TO BE INSPECTED. C RELIEF REQUESTED: Relief is requested from the code volume not achieved in the performance of mechanized ultrasonic examination of the following vessel outlet nozzle and flange to shell welds. ITEM B1.3 (WELD 4-WR-18) ITEM Bl;4 (Weld 4-DO-A, B S C) D. BASIS FOR RELIEP: FIG. NO. CIS-V-01 FIG. NO. CIS-V-04 k Confi'guration prohibit 100% ultrasonic examination coverage of the required code examination volume. The limitations and justification for each weld from code examination is di cussed below including applicable Tables and Figures. 1.0 NOZZLE TO SHELL WELD LIMITATIONS B1.4, (Weld 4-DO-A; B & C) When performing computerized UT examinations of the NOZZLE TO SHELL WELDS from the vessel wall, several areas were described as having limited examination scans. These limitations were restricted to the last several scans of the nozzle to shell examination and were due to the physical limitations imposed by the adjacent nozzles. The limitations all occured in the vicinity of the 90 or 180 degree nozzle azimuth relative to nozzle orientation. Figure no. 1 depicts those areas not examined and Table no. 1 provides the percent of weld volume not examined. RELIEF REQUEST 4 15 CONTINUED 2.0 4-WR-18 ( RPV SHELL TO FLANGE WELD ) B1.3 2.1 The areas receiving no coverage during the examination, performed from the upper shell side are depicted in Figure No. 2. , 2.2 Figure No. 3 depicts those areas that did not receive 0 degree, 45 degree transverse or 60 degree transverse weld coverage due to the geometric configuration of the flange radius located just above the weld. Percent of coverage limitation is contained in Table l. 2.3 Examinations performed from the shell side of the weld, essentially provided 100 percent coverage of the weld and 1/2T of base material on the shell ,side. The extent of examination volume achieved ultrasonicaly and the alternative system pressure
- tests, provide assurance of an acceptable level of quality and safety.
E ALTERNATIVE EXAMINATION Periodic System Leakage tests per category B-P, Table IWB-2500. ~ .) Xnservice hydrostatic test per category B-P, Table IWB-2500. F IMPLEMENTATION SCHEDULE FIRST INSPECTION INTERVAL G ATTACHMENTS TO RELIEF REQUEST NO. 15 TABLE NO. 1 NOZZLE TO SHELL WELD LIMITATIONS TABLE NO. 2 RPV SHELL TO FLANGE WELD LIMXTATXONS FIGURE NO. 1 OUTLET NOZZLE TO SHELL WELD FIGURE NO. 2 RPV SHELL TO FLANGE WELD FIGURE NO. 3 RPV SHELL TO FLANGE WELD FIGURE CIS-V-01 RPV CXRCUMFERENTIAL WELD LOCATIONS FIGURE CIS-V-04 RPV NOZZLE ORIENTATION RELIEF REQUEST 4 15 CONTINUED 'ABLE NO. 1 RPV NOZZLE TO SHELL WELD LIMITATIONS EXAMINATION AREA EXAMINATION TYPE LIMITS 8 OP WELD OUTLET NOZZLE WELDS PARALLEL SCANS OUTLET NOZZLE WELDS TRANSVERSE SCANS 12 42 RELIEF REQUEST 4 15 CONTINUED TABLE NO ~ 2 AREAS OF LIMITED COVERAGE RPV SHELL TO FLANGE WELD TOTAL WELD COVERAGE 'LIMITATIONS SEARCH UNIT ANGLE 0 45 60 45T 60T OF WELD AND REQUIRED VOLUME 60 25 20 60 60 TOTAL WELD LENGTH ~ 488.51~ I/2t TYPlCAL OUTLE ZZ AF.'fA NQT EXAMINf0 gj] 60 FROM SHELL NOZZLE AZIMUTH $5Q TQ IQ. g 45i 8 60i FROM SHELL 46 6 60 FR& M SHELL 458 60 FROM SHELL I/2t TAN 6 fN 7 I A L 5 0 RFAC E'AYf ~OAI.'-g.R-g< OIIAWN SY E.L. R NDERSOId IIEVI IIOVIOOY: Gull I'T NOLLt I-. TO 5HI:LL h)ELD Rl=l.<I=F AEQLII-ST NO l 5 OIIAWINONUMI WfLO TURKI='l POlNT ONlT5 4 5 - 2.'I-81 e.r.. RwoEesoa hlOIVF RPV SHELL TO t LRNGF ldt:LD R. uJR-l8 RF.LII.:F RFQLlE5T NO. l5 F'IGURE. NO. 2. v I l i~'i'i4,"f.Y I o F I)AT I NG SUR!"ACI'S FOR f'LANG! L i04tlCNI 4R<'4 SCC F IG. NO. CIS-UCS-o.) OUI L <".1 t<olli L = ~ UPPCR 5HL<LL COURS<. Qt ~~~ ~ ~ -- ~ - - ~~ ~am.: 0 } in.l ):<JZ: 1 Vl'L '><<<"<<J<<<<) ru'l"I 4 L.;.,i. i t>J. Cl<<J-<< '> 04 $-vR-5S J v<<.' ~ <<ll l t 3 QILQ PC Pf LI OI)i)$ 0 M ~g)CL<
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TURKEY POINT UNIT 3/4 SECOND INSPECTION INTERVAL RELIEF REQUESTS RELIEF REQUEST 4
1 A
COMPONENT IDENTIFICATION:
CLASS 1
Reactor Vessel B
EXAMINATIONREQUIREMENTS<
Exam Cat.
Item No.
B-C B-D B1.30 B3.90 VOLUMETRIC EXAMINATION SHELL TO FLANGE WELD, INCLUDES ESSENTIALLY 100%
OF WELD LENGTH.
VOLUMETRIC EXAMINATION (INCLUDES NOZZLE TO VESSEL WELD AND ADJACENT AREAS OF NOZZLE AND VESSEL)
C RELIEP REQUESTED:
Relief is requested from the code volume not achievable in the performance of mechanized ultrasonic examination of the following vessel outlet nozzle and flange to shell welds.
ITEM B1.30 (WELD 3-WR-18
& 4-WR-18)
DWG. CIS-V-01 ITEM B3.90 (Weld 3-DO-A, B
& C)
DWG. CIS-V-04 (WELD 4-DO-A, B
& C)
DWG. CIS-V-04 D. BASIS FOR RELIEP:
Configuration prohibit 100% ultrasonic examination coverage of the required code examination volume.
The limitations and justification for each weld from code examination is discussed below including applicable Tables and Figures.
1.0 NOZZLE TO SHELL WELD LIMITATIONS B3.90,-
When performing computerized UT examinations of the NOZZLE TO SHELL WELDS from the vessel wall, several areas were described as having limited examination scans.
These limitations were restricted to the last several scans of the nozzle to shell examination and were due to the physical limitations imposed by the adjacent nozzles.
The limitations all occured in the vicinity of the 90 or 180 degree nozzle azimuth relative to nozzle orientation.
Figure no.
1 depicts those areas not examined and Table no.
1 provides the percent of weld volume not examined.
ELIEP REQUEST 4 1 CONTINUED 2.0 RPV SHEIL TO FLANGE WELD B1.30 2.1 The areas receiving no coverage during the examination performed from the upper shell side are depicted in Figure No. 2.
2.2 Figure No.
3 depicts those areas that did not receive 0 degree, 45 degree transverse or 60 degree transverse weld coverage due to the geometric configuration of the flange radius located just above the weld.
Percent of coverage limitation is contained in Table l.
2.3 Examinations performed from the shell side of the weld, essentially provided 100 percent coverage of the weld and 1/2T of base material on the shell side.
The extent.of examination volume achieved ultrasonicaly and the alternative system pressure tests provide assurance of an acceptable level of quality and safety.
E.
ALTERNATIVE EXAMINATXON 1
1)
Periodic System Leakage tests per category B-P, Table IWB-2500-1.
2)
Inservice hydrostatic test per category B-P, Table IWB-2500-1.
F.
IMPLEMENTATION SCHEDULE TWO NOZZLE EXAMINATIONS (EXAM CAT. B-D)
(PROGRAM B)
AND 50%
OF THE SHELL TO FLANGE WELDS SHALL BE EXAMINED BY THE END OF THE FIRST INSPECTXON PERXOD G.
ATTACHMENTS TO RELIEF REQUEST RO.
1 TABLE NO.
1 TABLE NO.
2 FIGURE NO.
1 FXGURE NO.
2 FIGURE NO.
3 FXGURE CIS-V-01 FXGURE CIS-V-04 NOZZLE TO SHELL WELD LIMITATIONS RPV SHELL TO FLANGE WELD LIMITATIONS OUTLET NOZZLE TO SHELL WELD RPV SHELL TO FLANGE WELD RPV SHELL TO FLANGE WELD RPV CXRCUMFERENTIAL WELD LOCATXONS RPV NOZZLE ORIENTATION
RELIEF REQUEST f 1 CONTINUED TABLE NO 1
RPV NOZZLE TO SHELL WELD LIMITATIONS
&GO4INATION AREA EXAMINATION TYPE LIMITS \\ OF MELD OUTLET NOZZLE WELDS PARALLEL SCANS OUTLET NOZZLE WELDS TRANSVERSE SCANS 12 42
RELIEP REQUEST 4
1 CONTINUED TABLE NO.
2 AREAS OF LIMITED COVERAGE RPV SHELL TO PLANGE WELD TOTAL WELD COVERAGE LIMITATIONS SEARCH UNIT ANGLE LIMITS 4 OP WELD 0
45 60 45T 60T 60 25 20 60 60 TOTAL WELD LENGTH ~ 488.51"
l/2f TYPICAL OUTLET ZZL
~
AP,EA NOT EXAMINED g
60 FROM SHELL N022LE AZIMUTH MO TO io.
g 45i 5 60i FROM SHELL 46 6 60 FR 0 M SHELL 45K 60 FROM SHELL I/2t TANG EN T[AL SURFACE'AV E
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CODES 8
INSPECT IONS SECTION TURKEY POINT UN I T 3/g SCail'aavN OY IITO OalS aCv SCO TIER U
V L
NOZZLE ORIENTAT ION 8 NOZZLE'O SHELL MELO LOCAT IONS
~ NOZZLE INNER RROIUS p1wp~L I
I:ICD oh~sea C I S-V-0 I aC1IS Oa sl COa Oall RS VISION Ce COa
TURKEY POINT UNITS 3
6 4
SECOND INSPECTION INTERVAL INSERVICE INSPECTION RELIEF REQUEST 4
3 A
COMPONENT IDENTIFICATIONt CLASS 1
REGENERATIVE HEAT EXCHANGER BE EXAMINATIONREQUIREMENTSt Exam Cat.
Item No.
1)
B-B 2)
B-D B2.61 VOLUMETRIC EXAMINATIONS TO INCLUDE 100%
OF THE LENGTH OF CIRCUMFERENTIAL TUBE SHEET TO SHELL WELD.
B3. 150 VOLUMETRIC EXAMINATION TO INCLUDE 100%
OF B3.160 EACH NOZZLE TO VESSEL WELD AND NOZZLE INSIDE RADIUS AREA 3)
B-H 4)
B-J B8.40 VOLUMETRIC OR SURFACE EXAMINATION TO INCLUDE 1008 OF EACH INTEGRALLY WELDED SUPPORT OF ONE'XCHANGER.
B9.21 SURFACE EXAMINATION TO INCLUDE 100%
OF WELD SURFACE ON APPROXIMATELY 258 OF THE TOTAL INTERCONNECTING PIPING JOINTS C. RELIEF REQUESTED Relief is requested from code volume and surface area not achievable in performance of ultrasonic and surface examination on the Regenerative heat exchanger or vessel, interconnecting piping and support welds.
Item B3.150 B3.160 Item B8.40 NOZZLE TO SHELL WELDED SUPPORT Item B9.21 INTERSTAGE PIPING Item,B2.61 SHELL TO TUBESHEET PTP-3 PTP-4 PTP-3 PTP-4 PTP-3 PTP-4 PTP-3 PTP-4 3
WELDS 3 WELDS 6
WELDS 6
WELDS 1
WELD 1 WELD 6 WELDS 6
WELDS TABLE 1 TABLE 1
'ABLE 1 TABLE 1 TABLE 1 TABLE 1 TABLE 1 TABLE 1 D. BASIS FOR RELIEFt Configuration, limited accessibility, high radiation levels, and supports prohibit 100% ultrasonic and surface examination coverage of the required code examination volume and surface area.
The limitations and justification for each weld from code examination is discussed below including applicable Tables
RELIEF REQUEST 4 3'ONTINUED and Figures.
The amount of associated effort and supporting work to comply with the code requirements is not justified for following reasons:
1)
To perform these examinations, large expenditures of manhours and man-rem are required with essentially no compensating increase in plant safety, coupled by the increase in radiation (see figure nos.3 and 4 for comparison in radiation levels from 11-2-82 to 10-9-83 exposure.
Additional areas contributing to the justification are as follows:( surveys were taken on Turkey Point 3, verification was made against Turkey point 4, and determined that the surveys in this relief were identical to unit 4.)
Florida Power
& Light Company performed examinations on both Units 3
4 heat exchangers during the first and second inspection periods.
The coverage and/or the examination limitations are depicted in figure no. 1.(The RGX examination coverage and/or examination limitations.)
The regenerative heat exchanger component design arrangement and accessibility are not normally conducive to meaningful examination.(
see fig.
no.
2 for design configuration
)
Additional temporary shielding must be installed for any examination, except for the visual method.
As a consequence, this would reduce the access to the component for examination due to existing space conditions.
The component has to be uninsulated for examination.
Typically, surfaces also have to be conditioned resulting in additional manrem and creating significant cleanliness problems.
Table nq.
1 defines the identification of all Regenerative heat exchanger welds.
The alternate examinations and, system pressure tests provides assurance of an acceptable level of quality and safety.
E.
ALTERNATIVE EXAMINATION In lieu of volumetric and surface examinationn perform visual (VT-2 6 VT-3) examinations during system pressure tests.
RBLIBF RBQOBST 4
3 CONTINUED F.
IMPLBMBHTATIOH SCHEDULB
- 1) During each refueling outage the following will be performed:
- a. Perform a visual examination (VT-3) at the beginning of the refueling outage for leakage and boric acid cumulation.
~
- b. Prior to return to operation a visual examination (VT-2) will be performed during the system leakage test.
- 2) Perform a visual examination (VT-2) during the system hydrostatic pressure test at or near the end of the inspection interval.
G ATTACHMENTS FIGURE NO.
1 EXAMINATION LIMITATIONS FIGURE NO.
2 DESIGN CONFIGURATION OF REGENERATIVE HEAT EXCHANGER FIGURE NO.
3 RADIATION SURVEY 1982 FIGURE NO.
4 RADIATION SURVEY 1983 FIGURE CIS V 11 REGENERATIVE HEAT EXCHANGER SHELL IgIIgIII TABLE NO.
1 LIST OF AFFECTED WELDS 3
REGENERATIVE HEAT EXCHANGER WELD IDENTIFICATION RELIEF REQUEST NO 3
TABLE NO.
1 HEAD TO SHELL SHELL TO TUBE SHEET-PRIMARY TUBE SHEET TO SHELL-SECONDARY CHANNEL HEAD WELD SECONDARY RGX-(I)-1 RGX-(II)-1 RGX-(III)-1
- RGX- (I)-2
- RGX- (II)-2
- RGX-(III)-2 RGX-(I)-3 RGX-(II)-3 RGX-(III)-3 RGX- (I)-4 RGX- (II) -4 RGX- (III)-4 SHELL I NOZZLE WELDS
- RGX-(I)-9 RGX-(I)-10
- 'RGX-(I)-11 RGX- (I)-12 SHELL II RGX-(II)-9 RGX-(II)-10 RGX-(II)-ll RGX-(II)-12 SHELL III
- RGX-(III)-9 RGX-(III)-10
- RGX-(III)-ll RGX-(III)-12 NOZZLE TO PIPE INTERSTAGE PIPING SHELL I SHELL II SHELL III INTEGRALLY WELDED SUPPORTS
- RGX-(I)-7 RGX-(I)-8
- RGX-(I)-9 RGX-(I)-5
- RGX-(II)-5 RGX-(II)-6
- RGX-(II)-7 RGX-(II)-8
- RGX-(III)-7
- RGX-(III)-5 RGX-(III)-6 RGX-(III)-8
- RGX-(I)-LUG
- RGX-(II)-LUG
- RGX-(III)-LUG NOTE
- = DENOTES EXAMINATIONS REQUIRED BY CODE 4,
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4
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KR SHELL Z HR 3/gs SHELL II 8/.
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TURKEY POINT UNITS 3/4 SECOND IHSPBCTIOH INTERVAL IHSERVICB IHSPBCTION RELIEP REQOBST 0 6/7 A
COMPONENT CLASSIPICATIOHs CLASS 1
REACTOR COOLANT PUMP B. EXAMINATIONREQOIREMENTSs Exam Cat.
Item No.
B-L-2 B12.10 VOLUMETRIC EXAMINATIONS TO INCLUDE 100%
OF PRESSURE RETAINING WELDS, OR A SUPPLEMENTARY SURFACE EXAMINATION ON ONE PUMP IN EACH GROUP OF PUMPS PERFORMING SIMILAR FUNCTIONS IN THE
, SYSTEM.
B-L-2 B12.20 VISUAL EXAMINATION OF THE INTERNAL PRESSURE BOUNDARY SURFACES ON ONE PUMP IN EACH OP THE GROUP OF PUMPS PERFORMING SIMILAR FUNCTIONS IN THE SYSTEM.
CD RELIEF REQUBSTEDs Relief is requested from code volumetric or supplementary surface) and visual examinations of the Reactor Coolant Pump Casing welds and internals during the Inspection Interval.
These include the following pumps
( including 3 applicable:
casing welds per pump):
Item No. B12.10/B12.20 3-RCP-A 3-RCP-B 3-RCP-C 4-RCP-A FIG.
NO.
6 4-RCP-B FIG.
NO.
6 4-RCP-C FIG.
NO.
6 D. BASIS FOR RELIBPs Volumetric (ultrasonic) examination is not feasible due to the material construction of the pump casing.
Configuration of the pump design requires disassembly of the pump (including internal parts) to perform radiographic examination.
Supplementary surface examination is not practical due to the porous nature of the natural construction based on examination conducted on one pump (PTP-3), during the first interval. Visual examination is not practical since it requires total disassembly of the pump.
The limitations and justification for code relief is dicussed below including applicable figures.
1)
STATE-OP-THE-ART ULTRASONIC TECHHIQUBS have not been developed to meet the code requirements.
In the event that, an ultrasonic examination technique is developed that meets the code requirements, the intent of the code will be followed.
RELIEF REQUEST 4 6/7 CONTINUED 2)
Florida Power
& Light Company has representation on the ASMF Code committees, and keeps abreast of State-of-the-Art developments in all aspects of nondestructive examination methods in the industry.
Radiographic examination is not possible without the complete disassembly of the pump (see figure 1).
To perform this examination, large expenditures of manhours and man-rem are required with essentially no compensating increase in plant safety.
Based on actual data compiled from the radiographic examination of the Turkey Point Unit No.
3 reactor coolant pump casing welds and visual examination of the internal boundary surface on one pump, in excess of 5900 manhours and 46 man-rem exposure was expended in the disassembly, examinations and reassembly of the pump.
These examinations are conducted under somewhat adverse conditions which have far reaching effects as depicted in Figures 2 thru Figure 5.
- 3) There is a very low probability, based upon industry experience, to disassembly pump(s) for maintenance purposes.
There is no requirement by the pump manufacture (Westinghouse) to disassemble the pump(s) as part of normal maintenance or inspection.
Accordingly, Florida Power
& Light Company's procedures do not require disassembly of the pump(s) for maintenance or inspection purposes.
There are no reported failures within the pump casings with these model pump(s). It's note worthy to mention that removal of the pump impeller does not provide access to the casing internal surfaces which would still prohibit the inspection (visual and volumetric) of the pump to code requirements.
See Figure 1 for items to be removed for code ISI examination compliance.
4) 5)
Florida Power
& Light Company feels that adequate safety margins are inherent in the basic pump design.
The structural integrity afforded by the existing pump casing material will not significantly degrade over its lifetime. The reactor coolant pump casing material, cast stainless steel (ASTM A351-CFSM), is widely used in the nuclear industry and has performed extremely well.
The presence of some delta, ferrite (typically 5% or more) substantially increases resistance to interga'nular corrosion and stress corros'i'on cracking.
The delta ferrite also results in improved resistance to pitting corrosion.
Florida Power
& Light Company feels that the satisfactory inspection results achieved in Feburary 1982 (see D.2),coupled with the same inspections conducted by three (3) other utility, company's and employing the same manufactures model pumps, provides additional assurance as to the pump's casing integrity.
RBLIEF REQUEST 0 6/7 CONTINUED E.
ALTERNATE BXAMINATIONS:
I
- 1) Manufacture s shop radiographs, ASME Section III
- 2) Hydrostatic Tests, ASME Section XI 3) 100% visual examination of the external surfaces only of one pump casing welds to the extent and frequency of examination category B-L-1 4)
The alternate examination and tests provide assurance of an acceptable level of quality and safety.
F.
IMPLEMENTATION SCHEDULB At or near the end of the Inspection Interval G
ATTACHMENTS TO RELIEF REQUEST NO ~ 6/7 FIGURE NO.
1 FIGURE NO.
2 FIGURE NO ~
3 FIGURE NO.
4 FIGURB NO.
5 FIGURE NO.
6 REACTOR COOLANT PUMP GENERAL SURVEY OF RCP AREA PRIOR TO RT (MINAC)
AND DURING THE (MINAC) EXAMINATION 14'L.
GENERAL SURVEY OF RCP AREA PRIOR TO RT (MINAC)
AND DURING THE (MINAC) EXAMINATION 30'6~
EL.
GENERAL SURVEY OF RCP AREA PRIOR TO RT (MINAC)
AND DURING THE (MINAC) EXAMINATION 58'L'ADIATION SURVBY READINGS REACTOR COOLANT PUMP WELD IDENTIFICATION fi LOCATION
gaarr4 I'l4lg s lid I
Eo t
Ul a-v 7 IS)
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ONAWN E. L. AQOERSd~
D OY:
RCALTOR f:L30LADJT
~UNP Rl;Llj.F Rt..OUI=& t No. 6/7 OhANI HEI SNh 1-4;URE NO.
I TLIRI(h'I P0INT UNI1 3/1
Qn AD gn SCAN S-30-8 0 ONAWN 0 5 i ~ R MI7ERSOhJ OV DOY:
GENFRAL 5UI<9E'I OF MP ARL'8 PRIOR TO R'T (NINAC)
AND DllALNG THE (MiHn(.) FXflM)NA'tIOM IQ'I.EVQTIQg FIGURE NO.
2.
PELIFF AEMESf INO. (oI 7
0
lq p vl>
nnD
+ Cll cpP 0
bn D,
Q TURl<L'0 PINED uNt 3/
I
" -30-84 cAca'ORQ ORAWN ~
EL ANDERSON' havIS EO SY:
GENERAL SURUE'I OI'CP AREA PROR TO Rl(PllNA( l RNO DUPING THE (NIMAC) EXRNINATION 30'-6" ELEURT10N RELLF.F REOUBT NO. (of7 FIMIRE NO. 3
BENERFIL SURVE'I OF R(P AREA PRIOR, TO RT(PlINAC )
AND DtlRLN6 lBE(PllhlHC 1 FNNINA'tlOA 58'LEVATE'10M Nl RJ,"LILF RMLILST NO. 6/7 FI6URE ND. 6
RELIEF REQUEST NO. 6/7 FIGURE NO.
5 RADIATION SURVEY READINGS ITEM NO.
14'RIOR DURING ELEVATIONS 30 I 6 II PRIOR DURING 58'RIOR DURING A
B C
D E
p G
HI J
K L
M N
0 P
Q R
S T
U V
W X
Y ZZl Z2 Z3 Z4 Z5 Yl NOTES:
100 100 80 90 70 70 100 5
150 75
.3 5
25 2
5 2.5 50 5
2.5 4
~ 4 2
.4 14
.6
.5
.6 7
45.8 2
3.5
.8
~ 4
.4
.7 10 10 10 10
~ 4
.5 1.5 10 5
6 5
10 4
3 4
.8
.5 1
400 400 400 400
.5 1.5 7
5 15 5
4 15 15 15 15 600
- 1. ALL DOSE RATES ARE IN MREM/HOUR 2.
READINGS FOR DURING WERE TAKEN DURING 360 DEGREE ROTATIONAL SHOT AT 100%
POWER.
44.0
~a )-acP.(.)-a
/869
/Z.6Z ~YE I
I I
I 4/.50 7 YP.
F </0 678/
I I
I I
74
~ ~r0 Tyf.'yyp
(+>). RCP-Pi)-(.
TLlR.YiE.'I POlN t LlNiH 3/0 u~OT
+%
= ADD TIIE LINT MO. 3 I 0
- IlDO THE RCP NO.
A.BsC oA1f; /g /~ 8 gy Pagspll OT:
S<Mf g~y~f
'+fllCKO'tntXOe COOLWZ VuI~V WEXO XOENTlFlCAtlON E LOCATION RJPl P RELIEF REGucer VD 6(1 FIGURC Nu.
TURKEY POINT UNITS 3
k 4
SECOND INSPECTION INTERVAL INSERVICE INSPECTION RELIEF REQUEST 4
8 A
COMPONENT IDENTIFICATION:
CLASS 1
VALVE BODIES B.
EXAMINATION REQUIREMENTS:
Exam Cat.
Item No.
B-M-2 B12.50 VISUAL EXAMINATION (VT-3)
OF INTERNAL SURFACES VALVES NRC QUESTION NO.
5 OF SECOND REQUEST FOR ADDITIONAL INFORMATION Please indicate whether the entries under Item B12.50 of Appendix A in your May 4, 1984, submittal mean that you have identified a total of 13 valve groups in the Turkey Point Plant that fit footnote 3 for Item B12.50.
For how many of these groups have you examined one or more valves
? What were the results of these examinations
? If this information has been previously submitted to NRC, you may refer to specific pages in previously submitted documents.
t
RESPONSE
The 13 valves identified in the Program represents the total number of valves, not groups, to code requirements (note 3).
The records under review show that eight (8) different valves have been examined during the repair or maintenance of the valves.
Some of these more than once.
Since these records do not always report the manufacture, we do not know how many groups they represent.
We will transmit this information upon completion of our review. Accordingly, we will revise the relief request, and update the program to reflect this information.
NOTE:
There were no reported findings of the valve body internal surfaces.
TURKEY POINT UNITS 3
& 4 SECOND INSPECTION INTERVAL INSERVICE INSPECTION RELIEF REQUEST 4
9 A
COMPONENT IDENTIFICATION:
CLASS 1
REACTOR COOLANT PUMP B. EXAMINATION REQUIREMENTS:
Exam Cat.
Item No.
B10.20 VOLUMETRIC OR SURFACE EXAMINATION, INTEGRALLY-WELDED EXTERNAL SUPPORT ATTACHMENTS INCLUDES THE WELDS TO THE PRESSURE
-RETAINING BOUNDARY AND THE BASE METAL BENEATH THE WELD ZONE AND ALONG THE SUPPORT ATTACHMENT MEMBER FOR A DISTANCE OF TWO SUPPORT THICKNESSES C. RELIEF REQUESTED:
Relief is requested from code volumetric orsurface examination of inaccessible weld and adjacent areas of the pump support members not achievable during the Inspection Interval.
These include the following welds:
Item B5.4 3-RCP-A-L1,2 3
3-RCP-B-L1,2 3
3-RCP-C-L1,2 3
4-RCP-A-Lli 2 3
FIGURE NO.
1 4-RCP-B-Ll, 2 3
FIGURE NO.
1 4-RCP-C-L1,2 3
FIGURE NO.
1 D. BASIS FOR RELIEF:
Configuration of the integrally welded supports as welded to the pump body and structural interfaces prohibit meaningful nor conclusive ultrasonic or radiographic code examination.
Further 100%
surface examination coverage is not achievable due to 'the inaccessibility of"'portions of the weld.. Figure no.
1 provides a
graphic view of what areas of the lug cannot be examined.
The alternate examinations and tests provide assurance of an acceptable level of quality and safety.
E.
ALTERNATIVE EXAMINATION 1)
Perform surface examinations per the ISI schedule.
2)
Perform VT-3 examination to the extent practical on areas inaccessible for surface examination per surface ISI schedule.
1
RELIEF REQUEST f 9
CONTINUED 3')
Upon disassembly of a pump from the pad, conduct a
surface examination on the inaccessible area.
F.
IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL G.
ATTACHMENTS FIGURE NO.
1 RCP INTEGRAL WELDED LUGS EXAMINATION LIMITATIONS. ( Typical all 6 Reactor Coolant Pumps
)
FIGURE NO.
CIS-V-13 REACTOR COOLANT PUMP MAIN FLANGE STUD NUTS AND PUMP SUPPORTS
SCP-E+) L~
RCP-I ~ ) - 2re RCP I ~ )- 25 RCP t ~ I
~ I
/
RCP-I r r ~
'l.I'- I s e -
5 0
RCACIOA COO'N1 Pu>IP a)
RCP tr I 22~
ACP-I RCP la I 20 ACP-t ~ I- >0
,/
lp
~
Q.,
I '(j'RCP-I
~ I eeCI e
e
~
e RLs -I ~ e-r, L0045 4.8.i C
r e
acr.ce)ce
!JeeJ!.
PUHP 5UPI'ORI I.OCAIION LOOPS 4 ~ B.a C
RCP-I i I- >0 RCP-I i >r I)>>
RCP-I ~ >>.
c RCP-I ~ I-I.
RCP-I a I. Ia~
RCP-I ~ >- ]
RCP-I ~ ) - I)
RCP-I i >- O RCP-I ~ I-so Q
SUPPOAI OC14 I L rROII 4BOYC RCP I ~ I
>5 e
RCP I+)
I I
~eeelterrae Se'>see ee I II SOee I rs'I RCP I ~ )
)2 IUl'HI!IICAI!OW Ul APPLICAOLL 51uOS ANO HUIS SIIVLL OL IIAOL Of IHSCRIIHG
)SIC.rOLLOVI>lf OCSIrrHAI IONS tN PLaCC Orl RCI CRLHCl ORAv IHG.
RCv Coot.AHI COOLANI COOLAH1 COOLAH'I COOLANT COOLAN1 COOLRQT Pul)4 PUIIP uun4 sru>sf 4UI1P Pulse'I>is p sst)ilP Pl> >SIP IIAIH rlAIH
~14 I H He) IN H4 IN
>14 IN Ps III >e>
eeO gall AW C
LANT A I >e)
OLISh) T L 004
Ool'.OOP I.OOP LOOP Rl r ISI Ver A 51UDS-I I'54 )
A HUIS I rNA )
0 STUDS-I I SO I 0 NU15-I I'HB I C 51UDS-I I'CS)
C Hu'15-I FNC I Ies 5>lpyOR'tS-( g l r) Cul)POA>>-
Q)
C SIIIIPter15 C) 7ee Cla 4++
~eV vali
> I
!'UH>
rteA I N rl ANDRI STUQS
)l NUTS ANO PUr)+
SUPPORT LUCIS p~p~g MT
>.vasta C I S-v- I S gr I ee OI ee a>a
f
TURKEY POINT UNITS 4
SECOND INSPECTION INTERVAL RELIEF REQUEST RELIEF REQUEST 4 10 A
COMPONENT IDENTIFICATION:
CLASS 1
REACTOR COOLANT and AUXILIARYCOOLING SYSTEM WELDS BE EXAMINATION REQUIREMENTS:
Exam Cat.
Item No.
1)
B-J B9. 11
- VOLUMETRIC AND SURFACE EXAMINATION OF CIRCUMFERENTIAL WELDS EQUAL TO OR GREATER THAN 4 INCH NOMINAL PIPE SIZE.
2)
B-J B9.31 VOLUMETRIC AND SURFACE EXAMINATION OF BRANCH CONNECTIONS WELDS EQUAL TO OR GREATER THAN 4 INCH NOMINAL'IPE SIZE.
C RELIEF REQUESTED Relief is requested from code volume and area not achievable by ultrasonic and surface examination of the following welds:
Item B4.5 (12"-RC-3) 6" OF CIRCUMFERENTIAL WELD FIG.
1 (UT
& PT)
Item B4.5 (14"-AC-4) 5" OF CIRCUMFERENTIAL WELD FIG.
2 (UT ONLY)
Item B4.6 (12"/10"-RC)
AN AREA 4" x 3" OF CIRC.
WELD FIG.
3 (UT
& PT)
C.
BASIS FOR RELIEF:
Configuration,permanent attachments and/or structural interferences prohibit 100% ultrasonic and surface (as applicable) examination coverage of the required code examination volume and surface.
The limitations and justification for each weld is depicted in the attached Figures.
Fig. no.
Fig. no.
Fig. no.
1 Limitation due to welded plate at 180 degrees 2 Limitation due to proximity of adjacent pipe run at 270 degrees.
3 Limitation due to location of thermocouple at 100 degrees
RELIEF REQUEST 4 10'ONTINUED The extent of examination volume and area achieved and the alternative tests, provide assurance of an acceptable level of quality and safety.
E.
ALTERNATIVE EXAMINATION 1)
Periodic System Leakage tests per category B-P, Table IWB-2500-1; 2)
Inservice hydrostatic test per category B-P, Table IWB-2500-1;
/
E.
IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL F.
ATTACHMENTS FIGURE NO.
1 FIGURE NO.
2 FIGURE NO.
3 12" REACTOR COOLANT LINE LIMITATION 14" AUXILIARXCOOLANT LINE LIMITATION 10" REACTOR COOLANT BRANCH CONNECTION LIMITATION.
8pP t g5ULATl6/v u) Et.OKO PS.AT+
~os no~a C KlvTgQ 270 qoo i 80~
Mfa.OKO.
- ISLAM, 6<<Coul 0 MOT 66 Ewh~wEO Ouf TO mE'I.OEO pLATE, i8oo P. g. A~ OE'PS~
No ur'FACTOP.
C.DDLRMT 5')$ )FN NFLD IZ"-RC-3 RF.L)FF RFBUFST NO.
i0 fldNE ND. I
EL80~
I 80 F ULL SCALE PLOT RRFR NOT EXRN)RED
~0 EARh1 yuE m aesrR'ucnam
+iPIPE )%7 g70o PRZ.
Re'ue'F Tank TUggt 5 POINT UN)
'-30-84 8 c puofaso~
RllNILIAR>l I ODI.ANT 5'ISTEM IIJI LD I4'-AC-'f, RI.LIF;F RFQLIEST NO.
i0 riess pro.2.
0
UNIT too, awe.it DO' 80 THERMO COOL.g R P"x'f" FIRFR CW IDIOT Ot SCANNED DOE, TO THERNO COUPLF l2. IO'-Rc AL I TURKn PO!NT UNIT 5'.30 -8 f
~.g. peoE'ps~
RK'ACTOR COOLAAlT 515TEM MELD l2/IO"-RC l 0" BRANCH C.ONN ECTIOM REUFF RFGIlEST ND l0 FIGURE hfO. 9
0
TURKEY POINT UNITS 3/4 SECOND INSPECTION INTERVAL INSERVICE INSPECTION RELIEF REQUEST NO.
12 A.
COMPONENT IDENTIFICATION CLASS 1
REACTOR VESSEL CLOSURE HEAD B. EXAMINATION REQUIREMENTS Exam Cat.
Item No.
B-A Bl.40 VOLUMETRIC AND SURFACE EXAMINATION OF HEAD TO FLANGE WELD INCLUDES 100%
OF THE CIRCUMFERENTIAL WELD LENGTH.
C. RELIEF REQUESTED Relief is requested from code volume not achievable by ultrasonic examination of the vessel closure head -to-flange weld.
- 1) Item B1.40 (WELD 3-WH-12) 16" OF CIRCUMFERENTIAL FIG.
NO. 1/2 WELD
(
HEAD SIDE
)
No examination from the flange surface.
l
- 2) Item B1.40 (WELD 4-WH-12) 16" OF CIRCUMFERENTIAL FIG.
NO. 1/2 WELD
(
HEAD SIDE
)
No examination from the flange surface.
D. BASIS FOR RELIEF Configuration and permanent attachments prohibit 100%
Ultrasonic examination coverage of the required examination volume.
FIGURE NO.
1 Limitations due to welded arrow located above stud hole No. 1.
The arrow limits 7" of circumferential scanning of the closure head weld.
No examination achieved from the flange surface due to configuration.
FIGURE NO.
2 Limitations due to 3 welded lugs located 120 degrees
- apart, between stud holes 10/11, 29/30 and 48/49.
Each lug limits 3" of circumferential scanning of the closure head.
Therefore, the combined length (limitation) due to the arrow (7") plus the lugs (3"x3") totals 16" of weld not examined.
1
RELIEF REQUEST 4 12 CONTINUED The extent of examination volume and area achieved and the alternative tests provide assurance of an acceptable level of quality and safety.
E.
ALTERNATIVE EXAMINATIONS
- 1) Periodic System Leakage tests per category B-P,
- table IWB-2500-1;
- 2) Inservice Hydrostatic test per category B-P, table IWB-2500-l~
F.
IMPLEMENTATION SCHEDULE SECOND INSPECTION INTERVAL G.
ATTACHMENTS FIGURE NO.
1 RPV CLOSURE HEAD CUT AWAY VIEWi DENOTING MEASUREMENTS OF LIMITATIONS.'IGURE NO.
2
RPV CLOSURE HEAD LIMITATIONLOCATIONS
1
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CL05URE HEAD TC FLANGE IdELD I
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RPV CLOSURF HLAD ( COTFINRY U(EM/)
ggEP'S TltAT C.Rbl NOT BF FXANlNIDUE TO Llh9lTATlON5 RF.L1F.I= REGUFST NO PlGLIRE NO. I
I8 LENGTH QF'ELD 48I'Q3WN WIDTH
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MEAD 4
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VESSEL IRf65" TIlEKEl P0IIjT ilwlt 3/'I
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RPV CI.OsllRE.!~I-:nO tdELAEO AVACHNrNT LOC~ TIOVS REUEF REIMEST HO.
) P FIGURE ND.'L