ML20151G185
| ML20151G185 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 07/18/1988 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20151G184 | List: |
| References | |
| ISI-P-006, ISI-P-006-R01, ISI-P-6, ISI-P-6-R1, NUDOCS 8807280194 | |
| Download: ML20151G185 (96) | |
Text
. _ _ _ _ .
- VOCTLE ELECTRIC. GENERATING PLANT UNIT 1 INSERVICE INSPECTION PROGRAM ISI-P-006 Revision 1 Summary of Changes Page 1-5 Added the augmented examination requirements addressed in Coorgia Power Company letter GN-1345 dated February 9, 1987, for ASME Code Class 3 portions of the nuclear service cooling water system.
Page 2-7 Delete reference to RR-13.
Page 2-13 Revised Item No. B7.80 "CRD Housings, Bolts, Studs, and Nuts" to reflect as not being applicable to VECP-1. VEGP-1 CRD housings are a welded design instead of bolted derign.
Pages 3-12, 4-2, 4-3, Added relief requests RR-44 through
- . - 4 , 6-3, 6-4, 6-83 RR-51. These relief requests are through 6-93 related to system pressure tests.
Pages 6-1, 6-21, 6-22, 6-23, 6-24, 6-25 Relief Request RR-13 withdrawn.
Pages 6-63, 6-64 Relief Request RR-35 revised.
Page 7-2 Paragraph 2.4 was revised to delete the '
reference to Draft Technical Specification.
Pages 7-3, 7-4, 7-5, 7-6, 7-7, 7-8, 7-36, Added Note 24 to Project Class 212 7-38, 7-49, 7-51, and piping which was optional upgraded to 7-106 ISI Class 1. Optional upgrading requires this piping to be subjected to the system pressure test requirements of IWB in lieu of IWC.
Pages 7-6 Deleted Project Class 313 lines 1-1201-098 and 1-1201-115 from the line list. This piping does not perform a system function described in IWD.
Pages 7-101 and 7-111 Changea the P&ID reference and coordinates on line 1-2420-043 to reflect drawing revision.
l l
8807280194 800718' PDR ADOCK 05000424 o PNV
I 1.10.4 I
Snubbers installed on safety-related systems as well as snubbers )
whose failure of the system on which they are installed would adversely affect a safety-related system shall be examined as required by Section 3/4.7.8 of the Plant Technical t Specifications.
i 1.10.5 Georgia Power Company letter CN-1345 dated February 9, 1987, to the U. S. Nuclear Regulatory Commission requires that a walkdown '
for, visual observation of leakage be performed on accessible ASME Code Class 3 portions of the nuclear service cooling water system. This visual observation is required to be performed with the system at operational pressures during each refueling interval for the first ten years of service. In addition, an ultrasonic examination of two representative welds which are in piping 24 inches in diameter, one in each unit, will be performed every 40 months for the first 10 years of service.
1.11 Relief Requests i
J During the course of the preservice inspection, examination areas were identified where total compliance with the requirements of the ASME Code were not achieved. Relief requests were prepared for cach of these areas. The relief requests address the area of relief, ASME Code examination requirements, Code item no. and category (if applicable), basis for relief, and alternate examination, if any. Each relief request is identified by a unique number and is contained in Section 6 of this document. Relief requests that pertain to a particular category and code item no. are listed opposite the appropriate item no. in the IWB, IWC, IWD, or IWF Table.
General relief requests that do not apply to a unique item No.
are identified below.
Relief Request No. Examination Area '
RR-18 Use of Section XI, Appendix III for j
' austenitic and dissimilar metal piping
- welds
, RR-22 Technique for UT examination of welds in centrifugally cast piping and static- cast elbows i
RR-23 Use of a single calibration block for l examination of three sizes of centrifugally cast piping and three sizes of static-cast elbows RR-31 Use of piping calibration blocks to I
examine thin-wall vessel welds 1-5 006 Rev. 1
Vogtle L iect ric Genera ting Plant Unit No. I Inservice Inspection Isble IWB-2SOO-1 Examination Categories 006 Rev. I B-f, PRESSURE RETAINING DISSIMILAR MEIAL W[LDS Extent and f requsncy of Ebe ElRA1121 Examination Requirements / Examination 1st 2nd, 3rd, 4th Regier lien No. farts [maaland _flSu re M9.___ Meth29' laif fRl' It1LRIH 11' !!a29111 Cooments Enesket_Yn1111 BS.10 Nominal Pipe Size 24 in.
Nozzle-to-Safe IW8-2SOO-8 UI, PI All All End welds a a welds a a gg.gg i
Butt Wolds 85.20 Nominal Pipe Size <4 in.
Nozzle-to-Safe IWB-2500-8 N/A N/A N/A N/A to VLGP.
End Butt Welds 85.30 Nozzle-to-Safe IWB-2$00-8 N/A N/A N/A N/A to VfGP.
[nd Sochet Wolds Ershauflent B5.40 Nominal Pipe Size 24 in. l Nozzle-to-Safe IWB-2500-8 US, PI All All l fnd welds" welds
- RR-12 g l Butt Wolds '
B$.$0 Nominal Pipe Size <4 in.
Nozzle-to-Saru IWB-2$00-8 N/A N/A N/A N/A to VLGP.
End Butt Welds 85.60 Nozzle-to-Safe IWB-2$00-8 N/A N/A N/A N/A to VtCP.
End Socket Weldr
- S tgag_pg!!g ra ggr 85.70 Nominal Pipe Size 24 in.
Nozzle-to-Safe IWB-2$00-8 UI, PI All All End welds
- welds
- Butt Welds 03308 2-1 i
vogtso Electric cener ting ricat unit No. I l tase rv ice inspection table IW8-2500-1 Examination Categories i 006 Rev. 1 8-G-2, PRESSURE NETAIN881G 80LilIIG, 2 IIICHES AND LESS IN DIAMETER Extent and f requency of Examina1[gn Examination Requirements / Examination 1st 2nd, 3rd, 4th Reller lies; No. Farts [mseined* Flaure No. Method Inte rya I intervais IIeeve11 Commentt l Beector Vessel 87.10 Bolts, Studs, Surface N/A N/A N/A and Nuts N/A to VEGP.
fin 1111E11tr 87.20 Bol ts, Studs, and Surface VI-I All bults, same a s fo r Nuts studs, and 1st inter-nuts val stras cenerators 87.30 Bolts, Studs, and Surface VI-1 All bolts, Same a s fo r Nuts .
studs, and 1st inter-nuts val Efft ExcleaD91Il 87.40 Bol t s, Studs, and 5 A rrace N/A N/A N/A Nuts N/A to VEGP.
fjelDs 87.50 Bolts, Studs, and Su rf ace VI-l AIB bolts, Same as for Nuts stuus, and 1st i n te r-seu t s val Pumpt 87.60 Bu t t s, Studs, and Surface VI-I All bolts. Same as for Nuts studs, and 1st in te r-nuts wel Y*1MR1 l
87.70 Bolts, Studs, and Surface VI-s All bolts, Same as for Nuts studs, and 1st inter-nuts val l
GBD HouilDS1 87.80 Bolts, Studs, and Surface N/A N/A N/A N/A to VECP l Nuts l 1
03301 2-13 l
l t . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
i l
l l
Vog t l e E l ec t r ic Gene ra t i ng Pl a n t Uni t No. 1 Inse rvice inspection table IWC-2SOO-1 Examination Categories 006 Rev. 1 C-fl, Att PRISSURE REIAINING COMPONENIS l
Extent and Test' _frecuency of ExeglDRLI9n _ l
[xamina t ion
- Ites No. fini Eweelned' Bigulred _ Method fach Period' Roller I
[Ach Inte rva l
- Reauett Comments '
Presstare Y111n11-CT.lO Pressure Retaining IWC-5221 VI-2 Components Pressure RR-46,47 test
- retalning '
boundary l
C1.20 Pressure Re- lWC-5222 VI-2 tainf99 Coe- test Pressure ponents retalning '
bounda ry
! Eleins l CF.30 Pressure Re- IWC-5221 VI-2 i
t a 8 n i seg Com- Pressure RR-45,46, test' E ponents retaining '
bounda ry 47 g
l CT.40 Pressure Re- IWC-$222 VI-2 talning Coe- test Pressure RR-44,45 g
ponents retaining '
bounda ry hep t CF.50 Presr,ure Re- 8WC-5228 VI-2 taining Coe- Pressura RR-46 test' ponents retaining '
boundary g
Cl.60 Ps esuss e He- 8WC-S222 taening Coe- VI-2 Pressure test ponenLs retaining '
bousada ry Y11Ye1 C1.10 Pressure Re- tuC-5221 teining Com- test
- VI-2 Pressure RR-45,46, ponents retaisIng '
boundary 47 ,
CF.80 Pressure Re- 8WC-$222 VI-2 taining Coe- test Pressure RR-44,45 ponents aetaining
- boundary I
03308 3-12
Vogtle E lectric Generating Plant Unit No. I Inservice inspection Table IWD-2500-1 Examination Categcries D-A, 006 Rev. I SYSitMS $N SUPPORI Of RtACIOR SHuiDOWN fuseCI4001 Extent and Iest And Frecuency or E=ar..{ngtion Emmelnation Examination une 16% fatiLLansined Benialtneanig Method fish forind [ach Intgry11 Roller 833g331 Comments 01.10 Pressesre He- lWA-S000 VI-2 Pressure training Coe- lWD-5221{ RR-47,43, g ponents retalning bounda ry 49,50 5
IWA-SUGO Pressure IWO-5223{ VI-2 RR-49 l retaining
- boundary DI.20 Integ ra l figure VI-3 Attachment- Integral IWO-2500-3 astachments Component Sup-ports and Re-straints a DI.30 Integral figure VT-3 Attacheesst- Integral IWD-2500-1 attachments Mecitanical and ifyd raul ic Snubbers
- DI.40 In teg ra l figure VI-3 Attachment- Integral lWD-2500-1 attachments Spring Supports 1{pe C1.50 Integral figure VI-3 Attachment- Integral lWD-2500-I attachment Constant toad lype Sasppo r t s*
DI.60 In t eg ra l figure VI-3 Attachment- lWD-2500-1 Integ ra t Shock Ab- attachment sorbers a NOTES:
(1) the assystem required bossada ry extends to perfore asp to and inciteding tise safety-related ttee first normally closed valve or valve capable of automatic closure system function.
(2) The system leydrostatic inspection test inspection period of each shall be conducted at or Interval for near the Progree Inspection eeuf of each B. inspection issterval or daaring tise same (J) in the case of easitiple components within a system of siel tar design, function, and seevice, the intergsat a t t acenament or ossly one of the multiple components shall be examined. The lategral attaclements selected for examination sisai t correspond to those component saepperts selected by IWF-2510(b).
- 14) 1here are no emosptions or exclusions from tisese regist rements except as specified in SWA-5254(c).
(5)
A system test hydrostatic (IWD-5221) test emanination.
and VI-2 (IWO-5223) and accompanying VI-2 examination are acceptable in lieu of the system pressure 03301 4-2
vogtle Liect ric Generating Plant Unit No. I Inservsce Inspection Imble IWD-2$00-8 Examissation Categories 006 Rev. I D-8,' SYSilHS IN SUPPOlli Of emf RCfleCY COHC COOLiteC, COMI AlllMEMI llE AT REMOVAL ,
AIMOSrilLRE CLEAleUP, AleD REACIDR RESIDUAL HEAI REMOVAL
[xteest ased lest Assd __Lulauency or ty_gmingdg L fgf1 L1218!IlD2d ixamination Examenation 11ealJlom Ef 91!j fEMBk1 Method Olcit. Perigst RoIie r Lesll _101stDfil 1_8fgung foements D2.30 Psessaare He- lWA-$uun/ VI-2 Ps e ssure HM-47,50, trainissy Com- lWD-5222' E ponees t s retainissy $1 boundary g IWA-$0tMI IWD-$223{ Pressure VI-2 setaining
- boundary D2.20 Integral figuse VI-3 Attaclement- IWD-2SOO-l Integral Coa.possesst Sup- attactament ports and Re-stealssth s D2.30 l as t eg ra l Iignore VI-3 Isstegsal A t t aclamese t- IWD-2500-1 Mecisanica l ased a t tachaess t liyd a ase s ic Sssutsbe r s
- D2.40 Integral l'igure VI-3 In teg ra l Attachment- IWD-2$00-3 Spring I a t tachmesst Supports {pe D2.50 Integrai Iigure VI-3 Attachment- Integral SWD-2SOO-l Constant aLtachment i nee d 1ype Suppotis*
D2.60 I n t eg r.s 1 Iigure VI-3 A t t .s cl.me e s t- Integ ra 1 lWD-2$UU-l Shock Ab- attachment sorbers*
seOl[S:
(l) Ihe system boundary extesids up to and as reqssired tes perform the safety-related systemsincisoding the first snormally closed valve or valve capable or asatomatic closure Tsanc t ion.
(2) lhe system hydrostatic test shall issspections period of each inspectson be conducted at or near the end of each inspection interval or during the same (3) isst erva l for Inspectices Peugram 8.
(seonly or theasse caseofoftase mesitiple components mesIt tple componeests wa thin sisalla system of similar desiges be examined. Ilse integral fas sct ions. ased service. the integaal a t t arismeest correspond to those componeest sospports selected by IWi-25tu(b). attacismussts selected for examissa t son sh.sil gas ) lisere are eso exemptions or encisasions Isom Essess
($) A system hydrostatic test sequesements except as speedfied iss SWi *s218e(c).
test ( IWD-$222) and VI-2 examination.(IWD-$223) ased accompassying VI-2 examination ass acceptable iss lieu of time system pressure 03308 s-3 e
1 Vogtle'llectric Cesserating Plant Ussit No. I inservice inspection Imbin 8WD-2500-1 Examination Categories D06 Rev. I {
D-C. SYGIIMS IN SUPPOHI Of RESIDUAL ll[AI MEMOVAL IMOM SPENT (UE L SIORAct POOL 1
Lxtent and I Iest And
. .f fo9tff 0CY Of_Lattinkt iott l Emanination Examination Relier jits_th fff1 L LER!d uid Ef99lffefflLA Metflod Lidt Perhd [e cil 11811 D11 8299111 Costeenti D3.10 Pressure Matraining 8WA-5000 VI-2 Pressure Components
- IWD-$221{ RR-50 g retaissing boundary IWA-SOOO{ Pressesre IWD-5223 VI-2 retaining
- boundary
!s3.20 Integral isgusu VI-3 listeg ra l Attachment IWD-2500-1 . t t a ctimass t Compussene t
%spports assd Restraints
- D3.30 Integaal f igsa s e VI-3 Integral A t t a cismess t- lWD-2$00-3 a t t a chadse t Mecleassica l a sed flyd s a ui s c Susabbe r s
- D3.40 Integral f igsare VI-3 t .. .
Attachmesst- lWD-2$00-1 a t taessment Spring Supports Igpe D3.SO Integaal figure VI-3 instegral At t a chmees t- 8WD-2$00-1 a t tachmess o Constant l uait type Supposts*
D3.60 l est eg s a l l igsare VI-3 las teg ra l At t achmess t- 8WD-2500-3 attacisment Shock Absorbers 8 NOl[S: *
(1) the assystem required busendary sta the to perform tesids up to and asic5sselissg safety-relateo the first normally closed valve or valve capable or mistuas.st ic clossare system fausction.
(2) lhe system laydsostatic test shall be condescted at or near the esus of eacts isespectiose issterval or desrifog Line s.ar ms isespection period of eacle issspect son issterval Inr inspect ion Progs am B.
(3) les the cases os' mie t tiple canspossesit s w a tisies a systess of similar designs. l~sesec t eoss. ased su s v este. Else i ss t s:q s .s e q. t as-s.mose t or osely one of tlac maal t spie composacent s steal l be examissed. Ilse integ ra l at tachmessos selected for examessa t son als.sil cos respused to Linuse compossesst sospports serlected by I WF-2*s lO( b ) .
( 8s ) lisere are seu exemptiosss or enciasseusas t rom (tie se reqssis'emessis except a s spr'c a l'iest iss S WA '22 8 8s ( C ) .
(S) A system Boydsustatic test (SWD-5223) ased accompassyisag VI-2 examissations ase acceptablu ses I sess of Lieu system prussssee test ( IseD .$22 3 ) ased VI-2 cumanisaa t ion.
803Jul as -as u
6.0 RELIEF REQUESTS 6.1 Scope The following relief requests have been prepared from information determined during the preservice inspection of VEGP
'Jnit 1.
- Relief Request No. Examination Area RR-1 Mechanized vessel exam of circumferential welds in reactor RR-2 Mechanized exam of reactor vessel lower shell-to-bottom head weld RR-3 Mechanized exam of reactor vessel lower shell longitudinal welds RR-4 Mechanized exam of reactor vessel meridional welds RR-5 Mechani:ed exam of reactor vessel bottom head circumferential welds RR-6 Volumetric exam of reactor vessel flange ligament areas RR-7 Volumetric exam of reactor vessel closure head welds RR-8 Mechanized exam of elbow-to-reactor vessel safe-end welds RR-9 Class 1 bolting, greater than 2-in. diameter RR-10 Pressurizer integrally welded attachments RR-11 Visual exam of reactor vessel supports RR-12 Volumetric exam of pressurizer welds RR-13 Relief request withdrawn l
RR-14 Volumetric exam of pressurizer surge-nossle-to-vessel weld RR-15 Volumetric exam of pressurizer surge-no::le inner zadius 6-1 006 Rev. 1
.. -__ _ _ _ _ _ _ _ _ _ _ - _ - - _ - _ _ _ _ - - - __ - - __ __ J
Relief Recuent No. Examination Area ,
RR-32 Volumetric exam of RHR heat exchanger no: le inner radius RR-33 Volumetric exam of Class 2 bolting RR-34 Volumetric exam of Class,2 piping welds RR-35 Technique for volumetric exam of thin-wall piping RR-36 Volumetric exam of Class 2 thin-wall piping RR-37 Volumetric exam of small-diameter Class 2 piping RR-38 Subsection IWE i.R-39 Mechanized volumetric examination of pressure-retaining shell and head welds in the reactor vessel outside the beltline region RR-40 Notch length in basic ultrasonic calibration biccks for examination of vassal welds RR-41 Calibration blocks for reactor vessel no::le-to-safe-end welds RR-42 Volumetric examination of no::le inner radius section for steam generator inlet and outlet nos les RR-43 VT-4 visual examination of snubbers RR-44 Class 2 piping hydrostatically tested to Class 1 requirements RR-45 System pressure test of piping which penetrates the containment vessel RR-46 System pressure test on Class 2 components RR-47 System pressure test of air-containing systems RR-48 Class 3 system inservice test on systems used in support of reactor shutdown function 6-3 006 Rev. 1
1 Relief Request No.
Examination Area RR-49 System pressure test on Class 3 .
vertical pit type pumps RR-50 System pressure test.on Class 3 components '
RR-51 Class 3 system functiona5 test on systems subjected to Examination Category D-B requirements 6-4 006 Rev 1
VEGP-1 RR-1 Component or Relief Area Mechanized volumetric examination of pressure-retaining circumferential welds in Reactor Vessel.
Reactor Vessel flange to upper shall circumferential weld examination ID no. 11201-V6-001-WO3 Requirements from which Relief is Recuested l
Item no. Bl.30, category B-A, Table IWB-2500-1 of ASME section l
XI requires a volumetric examination of the Reactor Vessel shell to flange weld. Applicable examination volume is shown in
- figure IWB-2500-4 and includes 100% of the weld length.
Basis for relief Keyways machined into the vessel flange at O', 90', 180', and 270* prevent attaining 100% coverage of the required volume.
Alternate Examination Approximately 98% of the required volume wil_ be examined during ISI.
6-5 006 Rev. 1 J
j VEGP-1 RR-2 Component or Relief Area Mechanized volumetric to bottom head weld. examination of Reactor Vessel lower shell Examination ID no. - 11201-V6-OOl-WO6 Requirement from which Relief is Requested Item no. 31.11, category B-A, table IWB-2500-1 of ASME section XI requires a volumetric examination of pressure-retaining circumferential welds in the reactor vessel. Applicable examination volume is shown in Figure IWB-2500-1 and includes 100% of the weld length.
Basis for Relief Six core support lugs are located on the lower shell adjacent to the bottom head to lower shell circumferential weld. These lugs obstruct sled / transducer movement along the lower shell side (upper scan region) of this weld. Coverage is not possible in the vicinity of these lugs.
Alternate Examination Approximately ISI.
66% of the required volume wil' be examined during 6-6 006 Rev. 1
______________ J
VEOP-1 RR-3 Component or Relief Area Mechanized volumetric examination of pressure-retaining Reactor vessel lower shell longitudinal welds.
Examination ID no. 11201-V6-001-W18' @ 60*
11201-V6-001-W19 @ 180' 11201-V6-OO1-W20 @ 300*
Recuirement from which Relief is Recuested Item No. 31.12, category B-A, Table IWB-2500-1 of ASME section XI requires a volumetric examination of pressure-retaining longitudinal welds in the reactor vessel. Applicable examination volume is shown in figure IWB-2500-2, and includes 100% of the weld length.
Basis for Relief Core support lugs are welded over these longitudinal weld seams I in the lower shell. Examination underneath these lugs is ,
physically impossible. 1 Alternate Examination Approximate percentage of the required volume to be examined during ISI is:
11201-V6-001-W18 - 71%
11201-V6-001-W19 - 71%
11201-V6-001-W20 - 71%
6-7 006 Rev. 1
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - _ _ - - - - - J
VIGP-1 RR-4 Component or Relief Area Mechanized volumetric examination of pressure-retaining, Reactor Vessel meridional welds.
Examination ID no. - 11201-V6-001-W21 @ 0*
11201-V6-001-W22 @ 90' 11201-V6-001-W23 @ 180' 11201-V6-001-W24 @ 270*
Requirement from which Relief is Requested Item No. Bl.22, category B-A, Table IWB-2500-1 of ASME Section XI requires a volumetric examination of pressure-retaining meridional welds in reactor vessel. Applicable examination volume is shown in Figure IWB-2500-3, and includes 100% of the weld length.
Basis for Relief Instrumentation tubes along the bottom ed e and core support lugs at the top edge of these meridional welds 9restrict sled / transducer movement. The required volume cannot be completely examined because of these restrictions.
Alternate Examination Approximate percentage of the required volume to be examined during ISI is:
11201-V6-001-W21 - 89%
11201-V6-001-W22 - 95%
11201-V6-001-W23 - 92%
11201-V6-001-W24 - 98%
)
6-8 006 Rev. 1
VECP-1 RR-5 Component or Relief Area Mechanized volumetric . examination of pressure-retaining Reactor Vessel bottom head circumferential velds.
Examination ID no. Il201-V6-001-WO7' Requirement from which Relief is Requested Item XI No. Bl.21, category B-A, Table IWB-2500-1, of ASME Section requires a volumetric examination of pressure-retaining circumferential welds in reactor vessel head. Applicable examination 100% of the volume is shown in Figure IWB-2500-3 and includes weld length.
Basis for Relief Peripheral instrumentation tubes adjacent to the bottom head torus to along bottom the head required dome weld weld restrict sled / transducer movement volume. A total oftravel.
scan region obstruct the sled / transducer 29 tubes along the Alternate Examination Approximately ISI. 74% of the required volume will be examined during 6-9 006 Rev. 1
1 VEGP-1 RR-6 Comconent or Relief Area volumetric examination of pressure-retaining Reactor. Vessel flange ligament areas.
Examination ID no. - ll2Ol-V6-001-Lol through L54 Requirement from which Relief is Requested Item no. B6.40, category B-G-1, table IWB-2500-1 of ASME Section XI requires volumetric examination of threads in the Reactor F g re WB SbO-(
Basis for Relief A surface discontinuity due to the flange mati.ng surface exists in the flange ligament scan region. A partial volume in the vicinity of the flange mating surface cannot be examined on any of the 54 flange ligaments.
Alternate Exam.d. nation Approximately 92% of the required volume will be examined on each of the 54 flange ligaments.
6-10 006 Rev. 1 I
VEGP-1 RR-7 Comoonent or Relief Area Volumetric examination of pressure-retaining welds in the Reactor Vessel closure head.
Examination ID - 11201-V6-001-WO1 11201-V6-001-WO2 Requirement'from which Relief is Recuested Item No. B1.21, category B-A, Table IWB-2500-1 of ASME Section XI requires a volumetric examination of pressure retaining welds in the reactor vessel closure head. Applicable examination volume is shown in Fig. IWB-2500-3 and includes 100% of weld length for weld 11201-V6-001-WO1. Item No. B1.40, Category B-A, Table IWB-2500-1 requires a volumetric and surf ace examination of the reactor vessel head to flange weld. Applicable examination volume is shown in Fig. IWB-2500-5 and includes 100%
of weld length for weld 11201-VC-001-WO2.
Basis for. Relief The scan volume for weld no. 11201-V6-001-WO1 is limited due to interference of 3 lifting lugs and 5 control rod drive housings. Lifting lugs are 7" x 12" each and CRD housings are 4-inch diameter.
s Weld no. 11201-V6-001-WO2 has a scan limitation dun to the lif ting lugs when scanning from the closure head torus side, and scan limitations due to closure head flange geometry when scanning from the flange side. The geometry of the flange does not permit total coverage due to restricted transducer movement.
Alternate Examination Approximate percentages of the required volume to be examined during ISI are:
11201-V6-001-WO1 - 96%
11201-V6-001-WO2 - 65%
The Code required surface exam will be performed on Weld 11201-V6-001-WO2.
6-11 006 Rev. 1
VECP-1 RR-8 1
Comeonent or Relief Area Mechanized volumetric examination of pressure-retaining elbow to Reactor Vessel safe-end welds (Class 1).
Examination ID No. - 11201-009-9 11201-010-7 11201-011-8 11201-012-0 Requirement from which Relief is Requested Item No. 39.11, Category B-J, Table IWB-2500-1 of ASME Section XI requires a surface and volumetric examination of circumferential piping welds. The required examination volume is shown in Figure IWB-2500-9.
Basis for Relief Physical limitations due to the geometric configuration of the elbows allow approximately 65% coverage from the safe-end side and 0% from the elbow side during the mechanized examination of the Reactor Pressure Vessel.
Alternate Examination The required Code surface examination will be performed. In addition a supplemental manual ultrasonic examination, using a refracted-longitudinal wave calibrated on the centrifugally-cast
' piping calibration block will be performed from the safe-end outside diameter. Weld 11201-009-9 will receive approximately 92% coverage from the safe-end side due to flat spots on the safe-end. The other three lines will receive 100% coverage from the safe-end side. No coverage ekn be obtained from the elbow side due to CD taper. A refracted longitudinal-wave examination will be per'.ormed due to the close proximity of the nozzle to safe-end weld. See Attachment 1.
1 6-12 006 Rev. 1
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VEGP-l RRo A77KHA4EAIT I 6- 13 006 Rev. I
~. _ .-
VECP-1 RR-9 r
Component or Relief $rea
-Pressure-Aetaining Class 1.
Bolling, greater than 2-inch diameter, in Reactor Pressure Vessel Studs ID Nos. 11201-V6-001-B1 through 11201-V6-002-B54 and spare studs DOS-1 and BOS-2.
Require. ment from wl.ich Relief is neeuested Item B6.30, category B-C 1, ASME Code, requires surface and volumetric removed. examinations of Reactor Pressure Veasel studs when Paragraph IWA 2232 (c) requires that the ultrasonic examination meet the requirements of Article 5,Section V.
, Basis for Relief A more sensitive examination, wherein a shear-wave trarsducer is lowered into the heater hole in the center of the stud, has been developed.
The calibration block contains 3 notches which were electrical discharge machined into the thread area with the following approximate dimensions:
Notch No. Length Width Depth 1 0.942" 0.089" 0.060" 2 0.487" 0.089" 0.126" 3 0.387" O.089" 0.148" This calibratier, technique will be used in lieu of the required bottom hole technique.
Alternate Examination The more senuitive shear-wave examination, as described above, will be used. The Code required surface examination will be performed if thu studs are removed, 6-14 006 Rev. 1
VECP-1 RR-10 Comeonent or Relief Area Surface examination of Pressurizer integrally welded attachments (Class 1).
Pressurizer support skirt weld I.D.'No. Il201-V6-002-W35.
Requirement from which Relief is Recuested Item No. B8.20, Category B-H, Table IWB-2500-1 of ASME Section XI, requires a surface examination on areas A-B and C-D as shown on Fig. IWB-2500-13 for the Pressuriser integrally welded attachments.
Basis for Relief The pressurizar heater penetrations restrict personnel's access to Area C-D shown on Fig. IWB-2500-13 on the pressuriser skirt weld.
Alternate Examination Area A-B shown on Fig. IWB-2500-13 will recei/o a surface examination as required by the Code.
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VECP-1 RR-11 Comeonent or Relief Area Visun.' VT-3 examination of inaccessible component supports for the Reactor Pressure Vessel.
Requirement from which Relief is Recuested Item No. F2.30, Category F-9, Table IWF-2500-1, of ASME Section-XI requires a visual Vr-3 examination of component suppocts. The support examination boundaries are defined in IWF-1300. Relief is requested from the visual VT-3 examination of the Reactor Pressure Vessel supports located underneath'the nozzlea.
11201-V6-001-RS1 11201-V6-001-RS2 11201-V6-001-RS3 11201-V6-001-RS4 Basis for Relief The Reactor Pressure Vessel supports are encased in concrete which method.
renders them inaccessible for examination by the visual The Reactor vessel nozzles render them inaccessible from the top side.
impractical. Removal of the examination barriers is See Attachment 1 for a sketch of the Reactor Prossure vessel supports.
Alternate Examination None.
6-16 006 Rev. 1
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VEGP-1 RR-12 Component or Relief Area Volumetric examination of pressure-retaining welds in . pressurizer (Class 1).
Requirement fron_which Relief is Reduested Item No. B2.ll, category B-8, requir-a a volumetric examination of the weld volume shown in Fig. IWB-2300-1. Item No. 33.110, Category B-D, requires a volumetric examination of the weld volume shown in Fig. IWB- 2500 ~(b). Item No. 35.40, Category B-F, requires a volumetric and surface examination if the volume and area shown in Fig. IWB-2500-8. Each examinatior. requires 100% of weld length be covered. (See RR-13 for disctssion of calibration block).
Basis for Relief Geometric configuration presents physical limitations which prevent complete coverage of welds by ultrasenic examination.
The welds on which a complete Code examination cannot be accomplished are listed in Attachment 1.
Alternate Examination The required Code surface examination will be performed on the nozzle to safe-end welds. An ultrasonic examination will be performed on the affected welds to the extent shown in Attachment
- 1. In addition, a surface examination will be performed on the head-to-nozzle welds to supplement the ultrasonic examinations.
6-18 006 Rev. 1
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VECP-1 RR-13 Relief Request Withdrawn .
6-21 006 Rev. 1 l
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VEGP-1 RR-14 Comoonent or Relief Area Volumetric examination of pressure-retaining surge noz-le to vessel weld in the pressurizer.
Examination I.D. no. - 11201-V6-002-W16 Recuirement from which Relief is Recuested Item No. B3.110, Cat 3 gory B-D, Table IWB-2500-1 of ASME Section XI requires the volumetric examination of pressurizer nozzle-to-vessel welds. The applicable examination volumes are shown in Figure IWB-2500-7(b). Relief from the volumetric examination requirement for the pressurizer surge nozzle-to-vessel weld is requested.
Basis for Relief The electrical heater well couplings and associated cables surround the pressurizer surge nozzle on the bottom head. These heater couplings restrict coverage of the required examination volume of the surge nozzle-to-vessel weld. The extent of coverage obtainable on this ultrasonic examination is:
Nozzle side of weld - 0%
Head side of weld - 20 to 30%
Alternate Examination In addition to the limited volumetric examination as outlined above, a surface examination covering 85% of the pressurizer surge nozzle-to-vessel weld will be performed during ISI.
6-26 006 Rev. 1
l VEGP-1 RR-15 Comoonent or Relief Area Volumetric examination of inner radius section of the pressurizer surge nozzle Examination I.D. no. - 11201-V6-002-IR 06 Requirement from which Relief is Requested Item No. 83.120, Category B-D, Table IWB-2500-1 of ASME Section XI requires a volumetric examination of pressurizer nozzle inside radius section. The applicable examination volumes are shown in Fig. IWB-2500-7(b). Relief from this examination is requested.
Basis for Relief The geometry of the nozzle barrel prohibits an ultrasonic scan from the nozzle side, and the heater well couplings prohibit the scan from the vesse.1 head side. An inner radius section.
examination of this nozzle will, therefore, not be possible.
Alternate Examination None.
l t
6-27 006 Rev. 1
VEGP-1 RR-16 Comconent or Relief Area surface examination brackets) on pressuricer of integrally welded attachments (support Examination ID no. - ll201-V6-002-W23 through W30 Requirement from which Relief is Requested Item No. B8.20, category B-H, XI requires a surface examination tableof IWB-2500-1 of ASME 5ection integrally-welded attachments on the pressurizer. Applicable examination area is shown in Figure IWB-2500-15.
Basis for Relief The support rack assembly which holds the spray and relief piping of the pressurizer, rests above the integrally welded attachments the welds. (support brackets) and, thereby, restricts access to Removal of the rack assembly to perform the necessary examination is not feasible. Relief is, therefore, requested.
Alternate Examination None.
6-28 006 Rev. 1
D-- '
VEGP-1 RR-17 l
Comoonent or Relief Area l Volumetric examination of pressure-retaining nozzle to, elbow welds in Steam Generator (Class 1). See J.ttachment 1 for examination identification numbers.
Requirement from which Relief is Requested Item B9.11, Category B-J, ASME Code, requires surface and volumetric examinations of circumferential piping welds. The required examination volume is shown in Fig. IWB-2500-8. Relief from total coverage of the required volume is requested as indicated in Attachment 1. (See RR-22 and RR-23 for information about cast elbow examination and calibration block). 4 Basis for Relief All welds will be ultrasonically examined 100% from the elbow side using the centrifugally-cast piping technique as discussed in RR-22.
Due to the geometric configuration of the nozzles, a meaningful ultrasonic examination cannot be performed from the nozzle side. Scanning for reflectors parallel to the weld coverage will be accomplished using a 1/2-node refracted longitudinal wave from one beam direction only. In addition, transverse scans will be performed on the weld and the elbow side.
Alternate Examination The Code required surface examination will be performed. An ultrasonic examination will be performed from the elbow side as discussed above.
6-29 006 Rev. 1
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VEGP-1 RR-18 Component or' Relief Area ASME Code,Section XI, Appendix III for austenitic and ,
dissimilar metal piping welds.
Requirement from which Relief is Requested Section XI, IWA-2232(c), requires the use of Article 5 of Section V for the ultrasonic examination of non-ferritic piping. Relief is requested from this requirement.
Basis for Relief Supplement 7, Appendix III, pr ides more appropriate guidance for ultrasonic examination of stenitic and dissimilar metal piping welds.
Alternate Examination Ultrasonic examination of austenitic and dissimilar metal piping welds will be performed using the requirements of Appendix III,Section XI, ASME Code.
6-31 006 Rev. 1
VECP-1 RR-19 Component or Relief Area Volumetric sheet weld.examination of steam generator channel head.-to-tube Weld Numbers: ll201-86-001-WO8 11201-86-002-WO8 11201-B6-003-WO8 11201-B6-004-WO8 Requirement from which Relief is Requested ASME Code Item No. B2.40, Category B-B, requires volumetric examination of the tubesheet-to-head weld on the primary side of steam generators.
Figure IWB-2500-6 shows the applicable examination volume and includes essentially 100 percent weld volume. Relief is requested from examining 100% ofof the the volume of these welds.
Basis for Relief Four vesse'l supports and an identification tag prevent access to 100% of the weld length by the transducer. The tube sheet interferes with transducer placement for the upstream scans and the curvature of the channel head interferes with the downstream scans.
Alternate Examination Ultrasonic examinations will be performed on the percentage of weld volume indicated in Attachment 1.
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l 6-32 006 Rev. 1
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Component or Relief Area Volumetric examination of pressure-retaining welds in Class 1 piping excluding areas covered in RR-21, RR-24, RR-25, and RR-26.
Requirement from which Relief is Reduested Item no. B9.11, category B-J, Table IWB-2500-1 of ASME Section XI requires a volumetric and surface examination of welds in Class 1 piping of nominal pipe size 4-inches and greater. The applicable examination volumes are shown in Figure IWB-2500-8. Relief is requested for those examinations where the total examination volume coverage is less than the required volume. The examination numbers and their extent of volume coverage are listed in attachment 1.
Basis for Relief Physical limitations due to geometric configuration of the welded areas, support obstructions, etc., do not permit a complete coverage of the welds as required by ASME Section XI.
Alternate Examination The ultrasonic examination, to the extent possible, and the Code required surface examination will be performed.
6-34 006 Rev. 1
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l VECP-1 RR-21 Component or Relief Area Volumetric examination of pressure retaining branch pipe connection welds for nominal pipe size 4-inches and greater in Class 1 systems. Affected welds are listed in Attachment 1.
Requirement from which Relief is Requested Item No. 89.31, Category B-J, Table INB-2500-1 of ASME Section XI requires a surface and volumetric examination to be done on branch pipe connection welds. The examination areas are shown in Figures IWB-2500-9, -10 and -11.
I Basis for Relief Due to the geometric configuration, a meaningful ultrasonic examination can not be performed from the branch connection side for any welds. All welds except 11201-009-4 and 11201-012-4 can be ultrasonically examined 100% from the pipe side using the centrifugally - cast piping technique discussed in RR-22.
Due to the small pipe size and taper no meaningful ultrasonic examination can be performed on welds 11201-009-4 and 11201-012-4 from either side of the weld. See Attachment 2 for configuration.
Alternate Examination i The Code required surf ace examination will be performed. An
- ultrasonic examination will be performed from che pipe side i except on welds 11201-009-4 and 11201-012-4.
i i
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6-36 006 Rev. 1
EHN} s AL LIEl!M(1L._1 Code Jduntification 11% G8 Lus9a UsutGripli 'l Pe rcesit ago L".L* = iflud Esitristin!!
11201-001-2 B-J 12" Brancia Connectioss 50% llu:% fxam from pipe side 01 Exam (som 11201-002-2 brancia side B-J 6" Branch Connectiosa 50% 100% 1 xam f rom ge s po sede 0% Exam (som brancia side 11201-003-2 B-J 6" Branch Connection $0% 100% 1 xam from pipe side 01 Exam from 11201-004s-2 branch side B-J 16" Branch Connection $0% 100% Exam from pipo side 0% Enam room 11201-004-3 brancia side B-J 12" Brancia Cossaiect iosa 50% 100% l'xam rsom pipo side U$ Exam reom 18201-009-s brassch side B-J 4" oranch Connectiosa o% u% Exam rs oam ui ttsur side 18201-009-6 B-J 10" Branch Connectiosi SO% 1001 Exam from pipe side 0% Exam f rom brancia side IIEGI-Olo-4 B-J 10" Branch Connection $0% 100% lxam from pipe sede 0% Exam from branch side 11201-u81-$ B-J 14 " us.esa.la consiectioss $0% 100% 1x.am from popo sido 0% Exam from brancia side 19201-012-as B-J as " Branch CosisaccLiosa 0% 0% [xam reum citiser side 18201-012-6 8-J 10" Brancia Connectiosa 50% 100 Exam (som pipo side 0% Exams room brassch side 03218 6-37 006 Hav. I
i i
t i CONTOUR / PROFILE
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6- 38 006 Rev. 1
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VEGP-1 RR-22 l Component or Relief Area Volumetric examination of pressure-retaining welds in centrifuga11y-cast stainless steel piping and static cast stainless steel elbows made of SA 351-CF8A material in the Reactor Coolant System.
Requirement from which Relief is Requested i ASME Code Section XI, Article III - 4420 requires that the examination shall be performed using sufficiently long examination beam path to provide coverage of the required examination volume in two beam-path directions. The examination shall be performed from two sides of the weld, where practicable or from one side of the weld as a minimum. Article III - 4430 requires that the angle beam examination for reflectors transverse to the weld shall be performed on the weld crown on a single scan path to examine the weld root by one-half V-path in two directions along the weld. Article III-2430 requires that manual scanning shall be done at twice (+6dB) the primary reference level as a minimum. A meaningful ultrasonic examination cannot be eccomplished on the cast stainless steel using conventional shear-wave techniques. S:nce a 1/2-node examination using a refracted 45' longitudinal wave was found to r be the superior technique, relief is requested from the above requirements.
Basis for Relief The cast SA-351, CF8A material contains a banded microstructure that consists of a duplex grain size ranging from extremely coarse to very fine. This irregular grain structure causes significant attenuation and some angular variations during a typical shear-wave ultrasonic examination. A better technique was developed wheroic a 1.0 inch dual-element focused transducer, utilizing a 45' refracted longitudinal wave with a frequency of 1.0 Mhz was used. During calibration, the primary reference level is set using side-drilled holes. Calibrations using side-drilled holes are more sensitive than those usinq notches and cause the primary reference level to be set higher.
Scanning is possible only at the primary reference level due to excessive noise associated with the higher gain levels and the metallurgical structure of the Imaterd.al. A demonstration using l this technique was performed for Region II of the NRC and was determined to be a conservative method of detecting ID reflectors. (Reference NRC report numbers 50-425/85-24 and 50-425/85-25).
l i
I 6-39 006 Rev. 1 i
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VEG_Pd Alternate Examination A refracted-longitudinal wave ultrasonic examination, which is a 1/2 node examination, will be performed. Scanning will be done at the primary reference level. The Code required surface examination will be performed on all wsids.
6-40 006 Rev. 1
VEGP-1 RR-23 Comeonent or Relief Area Use ut a single calibration block made from centrifugally-cast 29-inch inside diameter (ID) and 2.45-inch nominal walr piping to examine piping of 27-1/2 inch ID with 2.32-inch nominal wall and 31-inc.4 ID with 2.60-inch nominal wall as well as static-cact elbows of 27 1/2, 29 and 31-inch ID with nominal wall thickness of 2.15, 2.48, and 2.62-inches respectively.
kequirement from which Relief is Requested Subparagraph TII-3410, Appendix III of ASME Section XI requires that basic car'bration blocks shall be made from material of the same nominal c4ameter and nominal wtl.1 thickness or pipe schedule as t:'e pipe to be examined. Relief is reauested from this requirement for main loop piping in thn primary reactor coolant syste.i.
Basis for Relief Paragraph IMA-2232(c) of ASME Section XI allows the use of Article 5 of Section V for the ultrasonic examination of piping made of other than ferritic materials. l'aragraph T-540 of Article L of Section V delineates the ultrasonic examination requirements of wolds in wrought and cast ma erials.
Paragraph T-543.3.1 allows for use of a block of essentially the same curvature, or alternately a flec block for examinations where the examination surface dixmeter is greater than 20-inch.
Also, figure T-546.1 allows a calibration block thickness vf 3 inches 'co be urad for thicknesses between 2 inches and 4 incht.s . Using this analysis, a singla calibration block of 29-inch ID (2.45" nominal thick) will be appropriate to examine 27 1/2-inch ID (2.32" nominal thick) and 31-inch ID (2.6" nam, thick) piping welds also.
Alternate Examination The craibratior bl' sk f abricated from the hot leg piping (29" I.D. & 2. 45" nomir.: n'zl thickness) will be used to examine the cold leg (27 1/2"
- 4.32" .eminal wall) and the crossover leg (31" I.D. & 2 . .$ " -ss nal vo'. ciping welds. This calibration block v 3Lse be
- i to examine the 27 1/2, 29, and 31-inch ID mlbs . ,;
and 2.62-inches wall thickness respect 1> J, 6-41 006 Rev. 1
yEGP-1 RR-24 Cgmeon.ent or Relief Area Volumetric examination of pressure-retaining Reactor Coolant Pump Inlet nozzle to elbow welds and cutlet nozzle to' pipe welds. (Class 1) See Attachment 1 for examination identification numbers.
Recuirement from which Reliof is Recuested Item B9.11, Category B-J, ASME Code, requires surface and volumetric examinations or circumferential piping welds that are 4-irches or larger in diameter. The required examination volume is snown in Fig. IWB-2500-8. Relief from total coverage of the required volume is requested.
Basis f_or Relief All welds will be ultrasonically examined 100% from the elbow or pipe side using the centrifugally-cast piping technique as discussed in LR-22 and RR-23.
Partial examination is possible from both no::le sides near the weld since the surfaces are parallel to each other. However, full-coverago is not possible because of increasing taper with increasing distance from the weld.
Due to this geometric configuration of the nc::les, an ultrasonic examination can only be accomplished on 30% of the required volume from the pump inlet-no::le side and 50% of the required volume from the pump outlet no::le side.
Alternate Examination The Ccde required surface examination will be performed. Also,
'an ultrasonic examination will be perforned to the extent indicated in Attachment 1.
l 6-42 006 Rev. 1 l
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ALLDEI*mfnL_I Cudas MERLiliElL12H_Mou ElLf99Df Yescentage Efftgrigt{2g
[ xas e t!eJl gatitgis t 19.13 11201-005-8 B-J 31" Elbow to Reactor Coolant Pump Nozzle 90% 100% fxam from elbow sade 80% Luca Croa nozzle side 18201->O6-8 B-J 3 3" t ibow to Heactor Coolasit Pump N92zle 90% 100% Exam f rua elbow side 80% Lxas (roe nozzle side 11/u1 001-8 B-J 3 3" t ibow to Reactor Coolant Pump Nozzle 90% 100% Exam from elbow side 801 Exam from nozzle side 18201-008-8 B-J 31" Elbcw to Reactor Coolant Pump Nozzle 90% 100% Exam from elbow side 80% Exam from s'azzle side' 11201-009-1 B-J 27.5" Reactor CoJIant Pump Nozzle to Pipe 75% 100% fxas from pipe side 50% Exam from nozzle s i dst 13201-010-1 D-J 21.5" heactor Coolant Passp Nozzle to Pipe 75% ' lou % Exam from pipe side 50% Exam from nozzle sido 11201-018-1 D-J 21.5" Heactor Coolaset raemp Nozzse to Pipe IS% 100% txam reum pipe side 50% Exam from nozzle side 18205-012-1 B-J 21.$" Reactor Coolant Psamp Nozzle to Pipe 7$1 100% f xam from pipe side 50% [xam from siuzzle side 03278 6-43 006 Rev. I
~ _
VECP-1 RR-25 Component or Relief Area Calibration block for volumetric examination of .
pressure-retaining reactor coolant pump outlet nozzle to pipe welds. (Class 1).
Examination ID Nos. - 11201-009-1 11201-010-1 11201-011-1 11201-012-1 Requirement from which Relief is Recuested ASME Code,Section XI, III-3411 states that calibration blocks shall be fabricated from one of the materials specified for the piping being joined by the weld and if material of the same specification is not available, material of similar chemical analysis, tensile properties, and metallurgical structure may be used.
Basis for Relief Due to the nozzle taper, a 50% ultrasonic examination can be performed from the nozzle side as discussed in RR-24. The 27.5" piping is significantly thinner than the Reactor Coolant Pump discharge nozzles. Weld metal was deposited en the pipe to increase the thickness of the pipe to that of tne nozzle so that a full perstration weld could be made. This overlay material extends approximately six inches on the pipe side of the weld.
See Attachment 1. The refracted longitudinal wave examination which had previously been demonstrated to be the superior technique for examining cast material (see RR-22), was completed during PSI using high scanning levels. ID pipe geometry was observed; thus, the longitudinal wave did penetrate the overlayed pipe. As a result, defects could be observed, if presant, regardless of the calibration technique used. The ultrasonic calibration block used was the cast piping block (see RR-23) and had not been overlayed with weld material. See Attachment 1.
Altarnate Examination The Code required surface examination will be performed and an ultrasonic examination will be performed from the pipe side through the overlay material.
6 44 006 Rev. 1 i
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VEGP-1 RR-26 Component or Relief Area Volumetric examination of pressure-retaining circumfe,rential welds in Class 1 piping equal to or greater than 4-inch diameter made of SA-376 grade material. Affected welds are listed in Attachment 1.
Requirements from which Relief Requested Iten No. 39.11, Category B-J, Table IWB-2500-1 nd Item No.
C5.21, Category C-F, Table IWC-2500-1 of ASME Section XI require a surface and volumetric examination of circumferential piping welds. The required examination volume is shown in Figure IWB-2500-8. Article III-4420 requires that the examinations shall be performed using a sufficiantly long examination beam path to provide coverage of the required examination volume in two beam-path dirletions. The examination shall bc cerformed from two sides of the weld, where practicable, or from one side of the weld as a minimum. Article III-4430 requires that the angle beam examination for reflectors transverse to the weld shall be performed on the weld crown on a single scan path to examine the weld root by one-half V-path in two directions along the weld. Article III-2430 requires that manual scanning shall be done at twice (+6dB) the primary reference at a minimum. A meaningful ultrasonic examination could not be accomplished on the SA-376 materiki using conventional shear-wave techniques.
Since a 1/2 node examination using a refracted 45' longitudinal wave was found to be the superior technique, relief is requested from the above requirements. (See RR-18).
Basis for Relief Physical limitations exist due to ths geometric configuration of valves and tees. Additionally, the SA-376 material exhibits severe angular variations and significant attenuation problems during a typical shear-wave ultrasonic examination. This was determined to be caused by a severely banded microstructure.
However, a refracted-longitudinal wave, which is a 1/2-node examination technique, was found to be possible during PSI.
DurAng calibration for the refracted L-wave examination, the primary reference level will be set using side-drilled holes.
Calibrations using side-drilled holss are more sensitive ' L~
those uaing notches and cau is the primary reference lev. 'o be set higher. Scanning is possible only at the primary ret.cance level due to the excessive noise associated with the higher gain levels and the metallurgical structure of the material. On pipe to valve configurations, the weld will be examined on the pipa side using the half-node technique. Scanning from the valve side is not possible due to valve geometry, on pipe to tce 6-46 006 Rev. 1
VEGP-1 configurations, the weld'will be examined on the pipe side using the half-node technique. Only partial scanning from the tee is possible due to geometry.
Alternate Examination The Code required surface examination will be performed. A refracted longitudinal wave examination will be performed to the extant practical as listed in Attachment 1.
6-47 C06 Rev. 1
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BMr26 eLgast!qvitj (Coat as) code re rcent age Ignatiricetion No. Cateenry Desc riet ion [aamind Bes t e a cL120 11204-127-7 8-J 10" Pipe to Valve 50% Coosetry or valve 11204-127-8 B-J 10" Valve to Pipe 50% Geow t ry of Va lve 11204-127-19 B-J 10" Pipe to Vaive So% coometry or Vaave 11204-121-20 B-J 10" Valve to ripe $0% Geometry of Valve e
0 03218 6-49 006 Mtv. I
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VEGP-1 RR-27 l
Component or Relief Area Visual VT-3, examination of internal surfaces of Class 1 pump 1 casings size.
and Class 1 valve bodies exceeding 4-inch nominal pipe l
, Requirement from which Relief is Requested.
Item No. B12.20, Category B-L-2 and Item No. 312.50, Category B-M-2, Table IWB-2500-1 of ASME Section XI requires a visual, VT-3 examination of the internal surface of Class 1 pumps and valve bodies that exceed 4-inch nominal pipe size, respectively. Examinations are limited to one pump or valve j within a group of pumps or valves which are of the same i
constructional design; manufacturing method; and that perform '
similar functions. Relief from this tsquirement is requested.
Basis for Relief Disassembly of these pumps and valves for the visual examination, during the inspection interval in the absence of required maintenance, represents an unnecessary exposure to radiation and contamination and is counter to the ALARA guidelines to keep the occupational does rates as low as reasonably achievable. In view of the cost in man-rem and in view of the minimal benefits obtained, we conclude that this code requirement does not l provide sufficient benefits to justify the radiation exposure.
Alternate Examination Class 1 pumps and valvez exceeding 4 inches nominal pipe size are subject to visual examination of the internal surfaces when disassembl'ed for maintenance. The coverage provided by
, examinations during routine maintenance coupled with the system i
leakage and hydrostatic tests will provide adequate assurance of the structural integrity of the class 1 pumps and valves, while keeping exposure to radiation and contamination as lou as reasonably achievable.
6-50 006 Rev. 1
VEGP-1 RR-28 Component or Relief Area Volumetric examination of the nozzle inside ractius section of the steam outlet norzle on the Steam Generators. .
Examination Identification No, ll201-B6-001-IRO3 Requirement from which Relief is Requested Item No. C2.22, Category C-8, Table IWC-2500-1, of ASME Section XI requires a volumetric examination of the nozzle inside radius section for nozzles in pressure-retaining vessels. The required examination volume is shown in Figure IWC-2500-4. Relief from this requirement is requested.
Basis for Relief The configuration of this nozzle is such that the nozzle does not have an inner radius. The nozzle is manufactured from a forging '
that is a solid block of steel. Seven (7) holes, each 8 1/2-inch diameter, have been drilled through this forging to provide an outlet for the steam. Thus, this nozzle does not have a conventional inner radius.
Alternate Examination None.
l l
6-51 006 Rev. 1
VEGP-1 RR-29 Component or Relief Area Volumetric examination of pressure retaining welds in Steam Generators Secondary Side (Class 2).
Attachment 1. Affected welds a're shown in Requirement from which Relief is Recuested Items C1.10 and C1.30, Category C-A, Table IWC-2500-1. ASME Code Section XI require volumetric examination welds. of pressure vessel Examination IWC-2500-2 volumes are shown in Figures IWC-2500-1 and respectively. Item C2.21, Category C-B, require surface welds. and volumetric Examination areasexaminations and volumes ofare nozzle-to-shell shown in (or head)
Figure IWC-2500-4. Relief from total coverage of the required volume requested. is Basis for Relief Geometric configuration presents physical limitations that prevent complete coverage during ultrasonic examination, Alternate Examination The required Code surface examination will be performed on the nozzles.
An ultrasonic examination will be erformed to the extent shown in Attachment 1.
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6-52 006 Rev. 1
MN2 A_It asheent_1 Code Percentage 1d981111E111180JLh Et1190E Lht1EEif L I#ft _ fnasanog Begir_{ELi2D 11208-86-001-Wie C-8 32" Steam Outlet peozzle to Head Wold $01 Examsnation not possible frees nozzle side ll2Ol-86-002-Wl9 C-B 16" Ma sse f eedwa ter Muzzle to Slearll Wald $01 8 xasaisnation s6ut possilste (som nozzle side ll203-86-003-Wo$ C-A l ower Cosie (pd Ste b Bas ~re s to l ower 901 Observatiosi port restricts access to Stee l l Barres "B" Weld part of weld il2DI-86-004-Wol C-A Lowe r $ lie l l Barret "A" to lube Plate Wold 941 leelse plate geometry restricts access to past of weld 18208-86-Ou4-W26 C-u 6" Aux, f eedwa ter alozzle to Sleer t l Wald 46*, t m.asignat ion not possible f rom seuzz s o side. 931 coverage from steelt side due to geoemestric limi ta tloses.
43271 6-$3 006 84uv. I
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VEGP-1 RR-30 Comoonent or Relief Area Volumetric and/or surface examination of pressure-retaining welds in Class 2 vessels (or componants). Specific examination identifications are shown in Attachment 1.
Recuirement from which Relief is Requested !
Item Nos. C1.lO, C1,20, and C1.30, Category C-A, Table IWC-2500-1 of ASME Section XI require volumetric examination of pressure-retaining welds in Class 2 pressure vessels.
Applicabla examination volumes are shown in Fig. IWC-2500-1 and
-2 and includes 100% of the weld length. Item No. C2.21, category C-B, requires volumetric and surface examination of pressure-retaining nozzle welds in Class 2 vessels. Applicable examination volume and area are shown in Fig. IWC-2500-4 and includes 100% of the weld length. Item No. C6.lo, Category C-G, requires surface examination of pressure-retaining welds in Class 2 pumps. The examination area is shown in Fig. IWC-2500-8 and includes 100% of the weld length. Actual examinations and their extent of coverage are listed in Attachment 1. (See RR-31).
Basis for Relief Access limitations are due to geometric configuration of the welded areas. Flanges and supports restrict coverage of required examination volume and areas. The actual restriction
! for each weld is shown in Attachment 1.
Alternate Examination The maximum percentage possible of the required ultrasonic examination will be performed. The Code required surface examination will be performed on the Boron Injection Tank.
Also, the Code required surface examination will be performed to l
i the extent possible on the Safety Injection Pump.
l 6-54 006 Rev. 1 l.
FB-30 Att4 Clement I ,
Code item re rcentage usatirin ijun_f m Eilinory _Muu antscript ion [s sines pestricting (flegenerative lleat [xchanger)
!!208-16-001-WOI C-A Cl.30 llead to Iube Shees Weld 94% 94% Code emae done from
^
ficad side of welet - weldolet II208-16-001-Wu2 C-A Cl.30 lobe Shee t
- o She l l Wo ld 931 93", Code exam done from stee l t side or weld -
weldolet il208-[6-001-WO9 C-A Cl,30 Iube Sheet to Shell Weld 93% 93% Codo exam deste from shell side or weld -
weldalet Il208-[6-001-Wlo C-A Cl.30 lube Sleest to llead Weld 941 94% Code exas done from head side of weld - weldotet
([xcess tetdown lleat [xchanger)
Il208-[6-002-WOI C-A Cl.20 Unit flange to Channel elead Wald 45% 45% Code exam doste from (tetdown lleat [xcleanger) chan:ie l head s.ide or weld 4 ins t rismeseta t ion l ine s i site r f e re.
lit 06-16-Oo3-Wu3 C-A C1.20 Vessel llead to llead flan 9e 29% 29% Code exam dosse (sue fietdown ficheat lieat Excleange r) head side - flange botting interferes.
192J8-[6-001-WO3 C-A Cl.10 Vessel fear.ge to Vessel Steel l 84% 84% Codo exam stone (s oam head (Discharge Pulsa tioss Dampesser) sido - welded idass t i rica t ion plate II208-Vs-002-WOI e C-A Cl.10 llemi-Ilead to lleei-tiead Weld 891 1 . in t e r fe resace (Boson l esj ec t ion tank) ll204-V6-001-Wol C-Bl C2.28 160tz te to llead Wold 50% 1 04:1 Exam f rom locad side -
0% from nozzle sidas .
l 63288 6-$5 006 kov. 1
EM")Q i M t arl=enL.1 1 Cont!41 Code item Percentage 149!!LifiEttion leo. Gt1H9Of _bo m Descrsotion [Eas11ted itesa dGL120 ll204-V6-001-WO2 C-A Cl.20 stead to Shell Weld 381 761 exas fross head side disc to supports - 01 from shele side due to taper 11204-V6-001-Wu3 C-A Cl.20 ssead to Shell Weld $01 100% exasa from head side -
01 from shell side due to taper ll204-V6-005-Wu4 C-8 c2.25 sconto to stead Wold So1 3001 emas rrue head side -
1 01 fram nozzle side l Sa fe ty laajection Pump) 11208a- P6-003-WO2 C-C C6.10 fissap Casiseg to Suction 66% Pamp saspport s p revuss t access j -
leozzle Weld to required area l
l 03258 6->6 006 Huv. I
I VEGP-1 RR-31 Component or Relief Area lUse of piping calibration blocks to perform ultrasonic examination of austenitic welds in thin-walled vessels (nominal wall thickness 2 inches and less). The following vessels are affected:
RER heat exchanger 11205-ES-002 Letdown heat exchanger 11208-E6-003 Letdown reheat haat exchanger ll208-E6-007 Excess letdown heat exchanger ll208-E6-002 Regenerative heat exchanger 11208-E6-001 Suction dampener 11208-V4-001 Requirement from which Relief is Requested Paragraph IWA-2232, ASME Section XI allows the use of the applicable requirements of Article 5 of Section V for the ultrasonic examination of Class 1 and 2 vessel welds in material other than ferritic steel. However, Article 5 does not provide specific guidance on how to perform these examinations. Relief is requested for modification of these requirements to allow the use of Section XI, Appendix III. (See RR-30).
Basis for Relief Article 5 of Section V does not give complete guidance for performing ultrasonic examination of austenitic welds. However, paragraph T-548 does give permission to modify or supplement the
! provisions of this article. Therefore, the ultrasonic l examination of austenitic vessel welds was performed in accordance with Appendix III of ASME 3ection XI, and the calibration blocks were designed in accordance with Fig. T.547.1 (provision for 10%T notch depth) and Eig. T-546.1 (provision for side-drilled holes).
Alternate Examination l Calibration standards, designed in accordance with figures
- T-547.1 and T-546.1 of ASME Section V and containing 10% T notch depths and side-drilled holes, will be utill:ed to perform ultraronic examinations on the above listed thin-wall vessels.
l The calibration blocks were fabricated from the same diameter and wall thickness piping as the heat ixchangers.
l l
l 6-57 006 Rev. 1
VEGP-1 RR-32 Comconent or Relief Area Volumetric examination of the inner radius of inlet and outlet nozzles of the Residual Heat Removal heat exchanger. (Class 2)
Examination I.D. no. - 1205-E6-002-IR01, 1205-E6-002-IR02 Requirement from which Relief is Requested Item No. C2.22, category C-B, Tabis IWC-2500-1 of ASME Section XI requires a volumetric examination of the inner radius section of pressure retaining nozzles (12-inch and greater nominal pipe size) in vessels having greater than 1/2-inch nominal wall thickness.
requirement.
Relief is requested from this volumetric examination Basis for Relief Examination requirement / Figure no. IWC-2500-4 of ASME Section XI does not illustrate the nozzle design of the Vogtle Unit 1 RER Heat exchanger. The nozzles in question have a sharp inner corner instead of the usual smooth, round configuration. Also, there is a reinforcing metal plate welded behind the inner corners. (See Attachment 1). It is, theref:re, not practical to perform an inner radius ultrasonic examination on these nozzles. -
Alternate Examination None.
6 58 006 Rev. 1
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RR-33 Commonent or Relief Area Volumetric examination of pressure-retaining bolting in Safety Injection Pump Housing. (Class 2)
- Safety Injection Pump casing studs I.D. Nos. - ll204-P6-003-Bol through B32 Regairement from which Relief is Requested Item No. C4.30, Category C-D, Table IWC-2500-1 of ASME Section XI, requires a volumetric examination of pressure-retaining bolts and studs that are greater than 2 inches in diameter. The examination is limited to the bolting in one pump from a group ,
' of pumps which are similar in design, size, function, and service. Relief is requested'from the volumetric examination of pump-casing studs if the pumps are not disassembled for maintenance.
Basis for Relief The pressure retaining studs of safety injection pumps are i inaccessible for volumetric examination while '.n place under tension. An ultrasonic examination on the ;u.mp studs would require removal of the cap nuts. Removsl of the cap nuts to strictly perform an examination is unwarranted due to the extensive detensioning and retorqueing that would be required on the cap nuts and studs.
l Alternate Examination i
The studs will be examined when the pumps are disassembled for maintenance.
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6-60 006 Rev. 1 r
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RR-34 j compenent or Relief Area Volumetric examination of pressure-retaining piping welds in Class 2 systems except those listed in RR-36 and RR-37'.
Requirement from which Relief is Requested Item No. C5.21, Category C-F, Table IWC-2500-1 of ASME Section XI requires surface and volumetric examination of pressure-retaining welds in Class 2 piping. Applicable examination volumes are chown in Fig. IWC-2500-7 and includes 100% of the weld length. The examination areas and the extent of volumetric coverage are listed in Attachment 1.
Basis for Relief Physical limitations due to gecmetric configuration of the welded areas restrict coverage ef examination volume as required by figs. IWC-2500-7.
Alternate Examination The Code required ultrasonic examination will be performed to the extent possible. Also, the Code required surface 1
examination will be performed.
6-61 006 Rev. 1 Y
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03281 6-63 (sss6 8(ev. I
VEGP-1 RR-35 Component or Relief' Area Volumetric examination of pressure retaining welds in ,
thin-walled (less than 0.5 inch wall thickness) piping and small-diameter (down to 2-inch diameter) piping. In the 1983 ASME Code through S'83 Addenda, these lines are exempt due to size or pressure and temperature. However, Georgia Power Company has agreed to accomplish volumetric examinations on these welds.
Requirement from which Relief is Requested ASME Code Section XI, Article III - 4420 requires that the examination shall be performed using a sufficiently long examination beam path to provide coverage of the required examination volume in two beam-path directions. The examinations shall be performed from twc sides of the weld, where practicable, or from one sida-of the weld as a minimum.
Article III - 4430 requires that the angle beam examination for reflectors transverse to the weld shall be performed on the weld crown on a single scan path to examine the weld root by one-half V-path in two directions along the weld.
Basis for Relief The thin wall piping welds at VEGP have extremely wide weld crowns on both circumferential and longitudinal welds. Because of this, the scans parallel to the welds will not be performed since the cound beam cannot be made to hit the root aret of the weld. The weld crowns cannot be ground flush because of minimum wall thickness violations due to weld shrinkage at the root. ,
Alternate Examination An axial ultrasonic scan, using a 1/4-in, diameter 60 degree shear wave transducer will be performed on the required welds.
i This transducer will use a modified wedge to reduce the front l
wedge to index point distance.
[
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6-64 006 Rev. 1 i
]
VEGP-1 RR-44 Comeonent or Relief Area /
System hydrostatic test on Class 2 components which cannot be isolated from Class 1 components. -
Requirement From Which Relief is Recuested Item numbers C7.40 and C7.80, Examination Category C-R, Table IWC-2500-1 of ASME Section XI requires a system hydrostatic test on Class 2 components with a test pressure specified in IWC-5222.
Basis for Relief The test pressures required by IWC-5222 (Class 2) are higher than those required by IWB-5222 (Class 1). IWC-5222 requires a test pressure of 1.25 times Psv or Pd. IWB-5222 requires a test prescure of 1.02 to 1.10 tines Po depending on the temperature.
Portions of Class 2 piping are isolated from Class 1 piping by utilizing check valves which open with flow to Class 1. To pressurize the upstream side of the check valves to Class 2 requirements would result in exceeding the Class 1 hydrostatic test pressure requirements. Relief is requested from the Class 2 hydrostatic test pressure requirements for portions of piping and valves between the bounuary valves and first shutoff valves. Attachment i lists the applicable lines and corresponding is requested.
check valves and shutoff valves for which relief Alternate Examination In lieu of pressurizing those portions of piping to Class 2 requirements, they will be pressurized to Class 1 requirements.
6-63 006 Rev. 1
RR-44 '
Attachment 1 Line No. Check Valve (s) Shutoff Valves ?&ID 1208-023 1208-U4-006 1208-U4-005 1208-042 1X4DB114 1208-U4-359 1208-U4-356 1X4DB114 1208-044 1208-U4-360 1208-U4-357
- 1208-046 1X4DB114 1208-U4-361 1208-U4-358 1X4DB114 1208-488 1208-U6-037 HV-8147 1208-008 1X4DB114 1208-U6-035 HV-8146 & 1X4DB114 1208-U4-498 1204-063 1204-U6-013 HV-8801A&B 1204-082 1X4DB119 1204-U6-013 HV-8843 1X4DB119 1204-058 1204-U6-013 1204-U4-007 1204-016 1X4DB119 1204-U4-120 HV-8802A & HV-8881 1X4DB121 1204-197 1204-U4-121 HV-8802A & HV-8881 1204-020 1X4DB121 1204-UC-128 HV-8840 & HV-8825 1X4DB121 1204-201 1204-U6-129 HV-8840 & HV-8825 1X4DB121 1204-017 1204-U4-123 HV-88028 & HV-8824 1X4DB121 1204-199 1204-U4-122 HV-88023 & HV-8824 1X4DB121 1204-029 1204-U4-146 HV-8835 & HV-8823 1X4DB121 1204-030 1204-U4-145 HV-8835 & HV-8823 1X4DB121 1204-031 1204-U4-144 HV-8835 & HV-8823 1X4DB121 1204-032 1204-U4-143 HV-8835 & HV-8823 1X4DB121 1204-039 1204-U6-147 HV-8809A 1X4DB121 1204-U6-148 HV-8890A 1204-041 1204-U6-149 HV-88093 1X4DB121 1204-U6-150 HV-88903 6-84 006 Rev. 1
VEGP-1 RR-45 Comeonent or Relief Area System hydrostatic test and system pressure test during system functional and system inservice test on Class 2 piping systems of containment penetrations which are not required for cperation to support engineered safety featuren systems.
Requirement From Which Relief Is Requested Item Numbers C7.30, C7.40, C7.70, and C7.80, Examination Category C-H, Table IWC-2500-1 of ASME Section XI requires a system hydrostatic test and a system pressure test during system functional and system inservice testing on Class 2 piping and valves.
Basis for Relief IWA-1320(d) states, "The portion of piping that penetrates a containment vessel, which is required by Section III to be constructed to Class 1 and 2 rules for piping and which may differ from the classification of the balance of the piping system, need not affect the overall system classification that determines the applicable rules of this Division." Relief 1s requested from the system pressure tests requirements of Examination Category C-H on the class 2 portions of piping which penetrate the containment vessel on the piping systems described above. The safety-related function of these piping penetrations is to minimize the release of radioactivity to the outside atmosphere following a "Loss of Coolant Accident." Appendix J of 10 CFR Part 50 requires adequate testing of containment penetrations to provide assurance of structural integrity and, as such, further testing by Section XI is not necessary.
Alternate Examination Piping systems which penetrate the containment vessel will be tested as required by Appendix J of 10 CFR 50.
6-85 006 Rev. 1 l
VEGP-1 RR-46 Component or Relief Area System pressure test on Class 2 pressure retaining components during system functional or system insarvice test.
- Requirement From Which Relief is Requested Item Numbers C7.10, C7.30, C7.50, and C7.70, Examination Category C-H, Table IWC-2500-1 of ASME Section XI requires a VT-2 visual examination during a system functional or a system inservice test per IWC-5221. Relief is requested to allow VT-2 visual examination of pressure retaining components during conditions other than system functional or system inservice testing.
Basis for Relief Portions of some systems are normally pressurized or can be pressurized to their normal operating pressures without the system being pressurized during a system functional tert or a system inservice test. A typical example of the above is the '
portion of a system from an atmospheric storage tank to the suction side of a pump. Relief is requested to allow VT-2 visuni examination of pressure retaining conponents at any time as long as the portion of the system being examined is subjected i to pressures which meet or exceed the requirements of IWC-5221.
Alternate Examination A VT-2 visual examination will be performed on pressure re~aining components at pressures which meet or exceed the requirements of IWC-5221. l l
6-86 006 Rev. I 1
VECP-1 RR-47 Comeonent or Relief Area System pressure test on Class 2 and 3 pressure retaining components during system functional or system inservide test.
The containment hydrogen monitor system and the radiation monitor system are affected by this relief request.
Recuirement From Which Relief is Recuested Item Numbers C7.lO, C7.30,. and C7.70, Examination Category C *4, Table IWC-2500-1 of ASME Section XI requires a VT-2 visual examination during a system functional or system inservice test per IWC-5221. Item Numbers D1.10 and D2.10, Examination Categories D-A and D-B, Table IWD-2500-1 of ASME Section XI requires a VT-2 visual examination during a system functional test (IWD-5222) or n system inservice testing (IND-5221).
Relief is requested from performing a VT-2 visual examination during s*fstem functional or system inservice testing on systems which contain air during system operation.
Basis for Relief The containment hydrogen monitor system and the radiation monitor system contain air during system operation. VT-2 visual examinations are conducted to locate evidence of leakage from pressure retaining components. Since these systems are air-containing systems, a VT-2 visual examination will not locate evidence of leakage and, as such, a VT-2 visual examination is unnecessary.
Alternate Examination The system hydrostatic tests required once per interval are boundary. to ensure the integrity oi' the pressure-retaining sufficient 1
l i
6-87 006 Rev. 1 1
I VEGP-1 RR-48 Comeonent or Relief Area Class 3 syrtem inservice test on systems used in support of reactor shutdown function (Examination Category D-A) .
- Requirement Frem Which Relief is Requested s
Item No. D1.10, Examination Category D-A, Table IWD-2500-1 of ASME Section XI requires VT-2 visual examination of pressure-retaining components during "System Inservice Test (IND-5221)."
Relief is requested from this requirement on those portions of systems listed in Attachment 1.
Basis for Relief IWA-5213(c) requires that systems be in operation for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to the start of VT-2 visual examination during system inservice test. Those portions of systems listed in Attachment 1 are not normally in operation for durations of at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Relief is requested to perform VT-2 visual examination during the performance of system functional test (IWD-5222) as similarly required by Examination Category D-B pressure retaining components.
Alternate Examination A VT-2 visual examination will be performed during system functional testing in lieu of system inservice testing.
l l
6-88 006 Rev. 1 l
VEGP-1 RR-48 Attachment 1 Line 1208-242 from 1208-P6-006 to 1208-F6-003 .
Line 1208-243 from 1208-P6-007 to line 1208-242 Line 1208-213 from line 1208-242 to 1208-T4-003 and valve 273 Line 1208-131 from 1208-F6-003 to valve HV-8104 and line 1208-134 Line 1208-134 valve HV-8439 from line 1208-131 to valve 188, line 1208-118 and Line 1208-118 from line 1208-134 to valve 174 Line 1208-116 from line 1208-134 to valves TV-01118 and TV-0110B Line 1208-127 from line 1208-116 to valve 171 Line 1208-450 from line 1208-131 to line 1208-213 6-89 006 Rev. 1
l VECP-1 RR-49 Coreonent or Relief Request System hydrostatic test and VT-2 examination during system inservice test on Class 3 vertical pit-type pumps. .The following nuclear service cooling water (NSCW) pumps and transfer pumps are affected by this relief request.
1-1202-P4-001 1-1202-P4-005 1-1202-P4-002 1-1202-P4-006 1-1202-P4-003 1-1202-P4-007 1-1202-P4-004 1-1202-P4-008 Requirements From Which Relief is Requested Item number D1.10, Examination Category D-A, Table IWD-2500-1 of ASME Section XI requires a system hydrostatic test (IWD-5223) and a VT-2 examination during system inservice tes: ting (IWD-5221) on Class 3 components.
Basis for Relief The NSCW pumps and transfer pumps are vertical pit-type pumps which take suction from the NSCW tower basins. Since these pumps are vertical pit-type pumps, there are no isolation valves un the cuction side of the pumps to facilitate hydrostatic testing. Therefore, the performance of a hydrostatic test on ihe pumps and the piping to the first discharge shutoff valve is impractical. In addition, the performance of a VT-2 examination during system inservice testing is also impractical on the suction side portion of these pumps because they are submerged in the NSCW tower basins.
Alternate Examinations These pumps are periodically tested as required by Subrection IWP. These tests verify operability of these pumps and by doing so would detect significant leakages through the pressure-retaining boundary. A VT-2 examination will be performed each inspection period during system inservice testing on portions of the pumps which are not surmerged in the N3CW tower basin.
6-90 006 Rev. 1
VECP-1 RR-50 comeonent or Relief Area System pressure test on Class 3 pressure-retaining components during system functional or system inservice test. -
Recuirement From Which Relief is Recuested Item Number D1. lO of Examination Category D-A ar.d Item Number D3.10 of Examination Category D-C, Table IWD-2500-1 of ASME Section inserviceXItest requires a VT-2 visual examination during a system per IND-5221.
Category D-B, Item Number D2.10, Examination Table IWD-2500-1 of ASME Section XI requires a VT-2 visual examination during a system functional test per IWD-5222. Relief is requested to allow VT-2 visual examination of pressure-retaining components during conditions other than system functional or system inservice testing.
Basis for Rejeief Portions of some systems are normally pressurited or can be pressurized to their normal operating pressures without the system being pressurized during a system functional test or a system inservice test. A typical example of the above is the portion of a system from an atmospheric storage tank to the suction side of a pump. Relief is requested to allow VT-2 visual as examination of pressure-retaining components at any time long as the portion.of the system being examined is subjected to pressures which meet or exceed the requirements of IWD-5221 or IWD-5222.
Alternate Examination A VT-2 visual examination will be performed on pressure-retaining components at pressures which meet or exceed the requirements of IWD-5221 or IW-5222.
l 6-91 006 Rev. 1 Y
vzor-1 RR-51 Comoonent or Relief Area Class 3 system functional test on systems subjected to Examination Category D-B requirements.
- Requirements From Which Relief is Requested Item Number D2-10, Examination Category D-B, Table IWD-2500-1 of ASME Section XI requires VT-2 examination of pressure retaining components during "System Functional Test (IND-5222)." Relief is requested from this requirement on those portions of systems listed in Attachment 1.
Basis for Relief The portions of systems listed in Attachment 1 are pressurized during normal systen operation and, as such, it is requested that the VT-2 visual examination be allowed to be performed during a system inservice test.
Alternate Examination A VT-2 visual examination will be performed during system inservice testing in lieu of system functional test.
6 02 006 Rev. 1 j
RR-51 A t t a c h.?.e nt 1 Line 1217-267 from valva 084 to line 1217-071 Line 1217-268 from valve 085 to line 1217-072 Line 1217-266 from valve 086 to line 1217-073 .
Line 1217-265 fron valve 087 to line 1217-150 Line 1217-073 from line 1217-266 to line 1217-150 Line 1217-071 from line 1217-267 to line 1217-150 Line 1217-072 from line 1217-268 to line 1217-150 Line 1217-150 from valve HV-2041 to lines 1217-071, 1217:022, 1217-073, and 1217-265 i
0421I 6-93 006 Rev. 1
Containment Building Normal Preaccess 1505 Purge Supply
' Containment Building Normal Preaccess 1506 Purge Exhaust Containment Building Post-LOCA Purge Exhaust 1508 Containment CRDM Cavity and Reactor Support '
1511 Cooling Containment Building E:'.ec Hydrogen Recombiner 1513 containment Eeat Removal 1515 Safety-Related (ESF) Chillers 1592 Radiation Monitor 1609 Waste Processing 3ystem-Liquid 1901 Fire Protection Water 2301 Service Air 2401 Auxiliary Gas 2402 Instrument Air 2420 Post Accident Sampling 2702 7.3 Containment Penetrations A. list of containment penetrations and their examination requirements follows the Line Designation List.
7.4 Safety-Related snubbers outside the Scoce of ASME Code,Section XI Technical Specification 3/4.7.8 requires the examination of I snubbers on safety-related systems and on nonsafety-related systems where a snubber failure could have an adverse affect on a safety-related system. Safety-related lines which contain snubbers requiring Section XI exams are included in the Line Designation List. Non safety-related lines which contain snubbers designed as safety related by the List architect / engineer are listed in a Supplemental Line filed behind the list of containment Penetrations.
0425I 7-2 006 REV 1
VEGF est No.1 006 Nov. I Line Designation List 1 6 Geactor Coolasit - System No. 1201 SIN
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3 zGE e L 1 z?E ot ot$ "*' ' k C 25 o 1 1201 068 0.750 1 212 IGO 0.219 120 3 N/A N/A VI-2 J, L 2F D6'
~f3l f2ff f aIIT TWofe-~24-1 1201 Oil 1.000 2 242 til 0.133 120 3 N/A N/A VI-2 J, ll2 G3 1 1201 Gil 3.000 2 212 ELI 0.216 120 3 N/A N/A VI-2 J. L 112 F2 See Note II 1 3203 084 U.750 1 232 fC0 0.249 653 2235 N/A N/A VI-2 8 21 BS 332 86 See Note 24 1 1201 091 0.F50 1 232 ICO 0.289 653 2235 N/A N/A VI-2 8 21 Cl 112 01 Suo Noto 24 1 1201 Il6 3.000 I lil IGO 0.438 617 2233 N/A PI VI-2 21 68 6 Il6 113 G4
, 1 1201 117 3.000 I Ill fGO 0.438 611 2233 N/A PI VI-2 21 IIS Ill 113 G4
{
1 1201 IIS 3.000 I Ill IGO 0.438 617 2233 N/A PI VI-2 21 11 5 118 113 G4 1 3208 119 3.000 1 lil ICO 0.438 617 2233 N/A PI VI-2 21 isS 119 183 G4 1 1201 120 0.750 1 232 ICO 0.219 $56 2301 N/A N/A VI-2 B 21 Cl 113 E7 See Note 24 5 1208 123 0.750 1 212 TCO 0.249 S$6 2308 N/A N/A VI-2 B 21 Cl 133 El See Note 24 5 1201 117 0.lSO I 282 000 0.219 $$6 2305 N/A N/A VI-2 B 21 CF 133 [F See Note 24 -
I l 1 2203 123 0.150 1 232 800 0.289 556 2301 N/A N/A VI-2 B 21 GT 133 El See Nogo 24 1 1208 124 0.750 1 212 fGO O.289 $56 2308 N/A N/A VI-2 8 21 fl 183 [$ See Hoge 24 I 1201 125 0.150 212 800 0.289 $$6 N/A 1 2Jul N/A VI-2 8 21 Il 113 ($ See Note 24 1 3203 126 0.150 1 212 IGO 0.219 S$6 2301 N/A N/A VI-2 B 27 fl ll? [$ See Note 24 1 1201 121 0.150 1 212 IGO 0.239 556 2301 N/A N/A VI-2 8 21 I6 113 [S See Note 24 1 1201 128 0.l50 212 ICO 0.219 631 2233 N/A N/A 0 1
VI-2 27 IS 183 14 See Note 24 5 1201 129 0.750 1 212 iCo 0.289 617 2233 N/A N/A VI-2 5 21 IS 113 f4 Sec Note 24 5 1201 130 0.150 1 212 fC0 0.219 687 2233 N/A N/A VI-2 8 21 IS 333 14 See Not6 24 '
1 1208 131 0.lSo 1 232 fCO 0.219 681 2231 N/A N/A VI-2 8 21 IS 333 f4 Soo Note 24 1 1203 132 0.lSO I 212 500 0.289 617 2233 N/A N/A VI-2 8 21 C4 II) [2 Sco Note 24 1 3201 133 0.150 1 232 ICO O.219 617 2233 N/A B 21 N/A VI-2 C4 13J E2 See Note 24 04 'S I 1-6 hS F s
VEGI ait NO.1 Line Designation List 006 Rev. I gpg Neactor coolant - systee No. I201 5 6 Slicet of a
i me taundies " = .E Refescene Deawing E maman etion Mentiod 4 ,I [ ., F c ISI Class 850-pg,go 352 j u ; ;g_ [ [. -
og IF
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2 System fio .
Z d C.
g S
h --
at 2 f
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I 1201 134 232 33 y, X, d 0.75a 1 500 0.289 617 2233 N/A ~ h/A ' VI-2 8 27 W - W W 7~eldte74 -
1 1201 135 0.150 212 IGO 0.219 617 2233 1
N/A N/A VI-2 8 21 G4 !13 [2 See Note 24 1 1201 150 0.750 1 212 IGO 0.219 $$6 3 N/A N/A VI-2 B 26 81 A7 Ill See Note 24 1 1 2831 Ils 3.000 2 212 LLI 0.133 120 3 N/A N/A VI-2 J. L 112 C2 3 See Note 11 1 3201 119 2.000 lil U.se 65 556 2301 I FCQ N/A PI VI-2 21 II 179 113 f6 I 1201 ISO 2.000 lit TCO 0.465 556 2301 1
N/A PI VI-2 21 f1 ISO 113 f6 I I?ol 183 2.000 I lil FCG 0.465 556 2308 N/A PI VI-2 21 Il 181 til C6 I 1208 182 2.000 I Ill ICO 0.465 $$6 2308 N/A Pt VI-2 21 Il 182 113 E6 3 1201 183 2.000 I lil 500 0.465 637 2233 N/A PI VI-2 21 f4 IST 113 L3 1 1201 184 2.000 1 Ill IGO 0.465 611 2233 PI N/A VI-2 21 I4 184 133 f3 I 1204 185 2.000 I lil ICO 0.465 687 2233 N/A PI VI-2 21 I4 185 133 03 1 1201 186 2.000 1 Ill FCO 0.465 617 2233 PI N/A VI-2 21 I4 IS6 113 [3 1 1201 188 0.750 3 313 18 ! 0.113 70 3 N/A N/A VI-2 112 til i 1205 188 1.000 3 313 LLI O.333 70 3 N/A N/A VI-2 112 til 1 1201 191 2. t H M3 I Ill ICO 0.344 556 21HI N/A PI VI-2 27 f6 191 183 f5 3 1208 192 2.000 1 lit ICO 0.344 556 2308 PT 88/A VI-2 27 16 192 113 f5 1 3201 193 2.000 1 153 ICO 0.344 556 2301 st/A PI VI-2 21 f6 193 113 55 3 1201 194 2.000 t Ill ICO 0.344 556 2303 N/A PI VI-2 21 f6 194 133 f5 1 1201 191 0.315 1 212 ICO 0.065 556 2203 N/A N/A VI-2 J. ( 26 D6 III of See Notes 18, 28 1 1203 191 0.500 1 232 fGo 0.188 556 2201 .1/A N/A VI-2 J, s 26 D6 Ill DJ See Note 24 1 1208 198 0.375 1 282 IGO 0.065 $$6 2201 N/A N/A VI-2 J, s 26 I6 Ill fl See Notes 18,2 1 1201 198 0.500 282 FC0 0.188 $$6 2203 1
N/A N/A VI-2 J. ( 26 f6 Ill fl See Note 24 1 1201 199 0.375 1 252 ICO 0.065 556 2208 N/A 80/A VI-2 J. < 26 f3 lit f2 See Notes 38,2 Osa >S i F-7 6SSs a
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VEGP at No.1 Line Deign 8 tion List 006 Hev. I 2
safety injection - system No. 1204 4 8 Sp,,
Sheel of _
a t - Numbe' - = .E fl*88888K* D'* wins
., E w ein hon u.thod j [ $ 854 Class M-y5 "r r c pago l pI
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$5 0 ,E 5aa Zd.-E. E i 1204 044 6.000 1 lil FC0 0.719 AMS 2485 UI FI VI-2 46 T e g Gle4 121 TF 1
! 1204 045 6.000 1 Ill IGO 0.739 AMS 248$ UI FI VI-2 46 SF 045 123 A7 0
1 1204 047 0.750 1 212 (Co 0.239 AM8 248$ N/A st/A VI-2 8 46 IS 125 f7 See Note 24 1 1204 048 0.7$0 1 212 , TCO 0.239 AM8 248$ N/A N/A VI-2 a 46 I8 128 T7 See Note 24 I 3204 049 0.i>0 1 282 IGO 0.239 AMS 248$ M/A ss/A VI-2 8 46 123
[8 0F See Note 24 1 3204 0 *>0 0.750 1 212 (C0 0.219 AMS 2485 N/A N/A VI-2 8 46 G8 123 C7 See Note 24 f I 12W 056 0. l*>0 1 232 (C0 0.249 163 2735 N/A N/A VI-2 8 44 Cl 119 C6 See Note 24 I 1204 0$7 0.750 2 232 100 0.219 130 2$00 N/A N/A VI-2 E, ; 44 S$ 119 C4 5 1204 U$l 1.000 2 212 TCO 0.230 130 2$00 N/A N/A VI-2 E, ; 44 C4 119 C3 i 6
1 1204 037 3.000 2 282 100 0.438 130 23$0 ui PI vi-2 34 85 0$7 116 CS
- 1204 0$7 4.000 2 I i 232 800 0.*> 3 3 130 23$0 UI PI VI-2 44 83 O$7 316 2 07 3 1204 OS7 6.000 2 232 iC0 0.719 130 23$0 UI FI VI-2 44 CS OSF 139 C4 1 1204 USS 0.730 2 232 (GU U.289 18$ 273$ st/A st/A VI-2 f, a 44 03 189 82 See Note 18 1 31*04 0*> 8 1.000 2 282 8G0 0.2Lo IIS 2135 N/A se/A VI-2 44 84
- f. Il9 83 1 8204 063 0.130 2 fl2 f t.o u . .* I s l l *, *
. t 13 re/A N/A V8-2 E, 189 t *>
bea Note 18 1 1204 063 3.u00 2 282 800 U.438 IIS 213*> UI PI VI-2 44 f6 063 119 t$
I 1204 063 4.000 2 282 ICO U.$31 Il$ 2735 UI PI VT-2 44 [G 063 119 f4 I 1204 063 6.000 2 212 ICO 0.719 11$ 273$ UI PT VI-2 44 D$ 063 14 11% Sco Note 18 1204 06T 1.000 2 232 100 I i 0.2$0 11$ 2735 st/A N/A VI-2 E, 3 44 D3 339 D3 e 1 1204 069 1.u00 2 212 500 0.250 11$ 273$ N/A st/A VI-2 E. ; 44 IS 839 84 1 1204 076 3.$00 I ill ico 0.281 18$ 273$ N/A PI VI-2 44 fl tal6 119 C6 8 1204 076 3.000 I til 500 0.438 Il$ 273$ as/A PI VI-2 44 [7 0 16 189 16 Oa. 3 y.36 l
VEGP -, nit No.1 Line Designation List '006 Nev. I System: Saiety Issjectloss - System No. 1204 6 a n
Stieel of _
I sne Numties .
- = E
. Refeseeue Deawing E Examinaleors Melhod 8 $, 8' c 15t Class ISI-
[ System ijT i S E iI Y I Ig a fi .
b g,pago y . Notn 3
No.
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C Old I5 **I #
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$5 zS d- O ~
T 1204 123 2.000 2 212 0 jj yX 0 IBGO 0.1$4 120 700 N/A N/A 75-2 Ig Taf L> ~ 72D - E5-8 1204 125 10.000 2 ?I2 ilGO 120 0.365 700 UI PI VI-2 45 E$ 121 120 [5 1 120ta 122 2.000 2 232 Wo 0.1$8s 120 700 N/A N/A VI-2 H 4$ DS 120 C$
1 1204 122 10.000 2 212 ilCO 0.365 123 700 f2T PI VT-2 45 C5 122 120 C5 1 1204 123 2.000 2 232 liC0 0.154 120 700 N/A N/A VI-2 45 B5 il 120 A$
I 1204 323 10.000 2 282 isCo 0.365 120 700 UI PI VI-2 ass B5 123 120 A5 I I?O4 1 24: 10.000 I Ill FC0 1.000 AMa 2485 ui Pt VI-2 45 C6 124 120 C6 3 1204 125 10.000 I Ill 500 1.00c AMS 28sSS UI PI VI-2 45 16 12$ 120 05 1 1204 126 IP.OOO 1 ill 100 1.000 AM8 2483 UI PI VI-2 45 C6 126 120 C6 3 1204 121 10. 0J-* I lit 100 1.000 AMtl 248$ UI PI VI-2 8s) 521 120 11 6 A6 1 1204 128 0.150 2 282 tti 0.113 120 65 N/A N/A VI-2 E, a 46 (4 121 L3 1 1204 129 0.750 2 212 til O.113 120 65 N/A N/A VI-2 E, ; 46 84 121 [3 3 1204 130 0.750 2 212 tt1 0.133 120 65 f4/A N/A VI-2 E, . is6 D4 12I 03 1 1204 131 0.150 2 212 iLI 0.II3 120 6S N/A N/A VI-2 f, 8s6 04 '
123 03 I 1204 13/ o./$U 232 ILu l
u.249 AHu f43's N/A N/A VI-2 8 45 C6 820 C6 See Note 24 I 1204 138 0.150 212 IGO 1 0.219 AM8 2485 N/A N/A VI-2 8 8s5 f6 120 16 See Note 24 5 1204 139 O.150 1 232 iCO O.219 AMD 2481 N/A N/A VI-2 g a> D6 120 s
C6 See Note 24
-1 1204 14G O.150 232 500 1 U.219 AM3 248$ N/A N/A VT-2 8 45 06 120 D6 See Note 24 1 1204 141 U. ISO I 212 5G0 0.239 AMD 248$ N/A N/A VI-2 e a> GT 820 s
G8 See Note 24 1 1204 142 U.150 212 500 1 0.239 AMS 248$ N/A N/A VI-2 8 4> LI 120 t as See Note 24 1 1204 143 0.l$0 1 212 IGO U.219 AMS 28s8$ N/A N/A VI-2 8 a$
s D1 120 CS See Note 24 5 1204 144 0.150 1 212 160 0.289 AM8 2485 N/A N/A VI-2 8 % D1 120 US See Note 2ta 1 1204 148 0.750 2 232 f60 6.289 206' 2660 N/A N/A VI-2 f.- . 321 115 e
08e-$1 1-38 j
VEGP w.it No.1 Line Desegnation List 006 nov. I System: Climalca l ased volume Constrol - System No. 1208 2 Il Stacet el _
.. e ,. . . a*- %
. = s <.a m , _ I m F
u d E. c ist Class 858-psigj s!- 3 3p_ r r ;o ip-. , ,,,,
E System g h 3 N 3
tio. ! p Seeface V6sual .h ZE- '2 K 2 E $ N. O? Osb "'** 'k
$0 E5 0 f jf b 1 1208 020 0.750 2 212 LLI 0.113 150 35 N/A N/A VI-2 J. ( 28 T ~~ 7% N I 1208 020 2.000 2 212 LLI 0.154 ISO 35 N/A N/A VI-2 J, ( 28 E6 lik DF See Note il 1 1208 020 3.000 2 212 LLI 0.236 150 35 N/A N/A VI-2 J. ( 33 C4 148 C8 I 1208 022 1.000 2 212 RCO 0.133 130 2350 N/A N/A VI-2 J. ( 33 C7 148 C7 1 3208 022 2.000 2 232 FC0 0.344 130 2350 ui PI VI-2 30 C7 022 136 8 86 1 1208 022 3.000 2 252 FCG 0.438 130 2350 ut FI VI-2 30 CT 022 116 3 86 1 1208 023 0.150 2 232 FC0 U.249 130 2340 N/A g N/A VI-2 E, 28 A6 134 86 See Note 18 1 1208 023 1.000 2 232 TCO 0.250 130 2340 N/A N/A VI-2 E, 3 28 B5 l l8e AS I 1208 U23 8.500 2 212 fC0 0.285 130 2340 N/A N/A VI-2 E, i 28 81 Ilse Al see Note 31 1 1208 023 2.000 2 212 IGO 0.344 130 2340 UI FI VI-2 28 83 023 116 i Al 1 1208 024 1.500 1 III ICD 0.288 130 2340 N/A PI VI-2 28 87 024 134 B7 1 1208 025 0.750 212 ICO 0.219 130 2340 N/A l
1 N/A VI-2 8 28 C7 314 88 See Isote 24 1 3208 026 3.000 2 212 kCO 0.236 115 350 N/A N/A VI-2 J, K 33 D3 148 D6 1 1208 027 3.000 2 232 kCO 0.236 185 3'20 N/A N/A VI-2 J. K 33 04 148 87 I I?OS 028 1.000 2 212 Iss.sa ss.333 335 r,e s N/A N/A VI-2 J, K 33 03 348 0; I 1208 028 2.000 2 232 ECO O.154 135 350 N/A N/A VI-2 J. A 33 D3 the DE I 1208 030 3.000 2 232 kGO O.236 150 350 N/A N/A VI-2 J, K 33 G3 148 D6 I 1208 031 3.000 2 232 kGO 0.216 150 350 N/A N/A VI-2 . X 33 14 148 81 '
i 1208 032 3. COO 2 232 kGO D.133 ISO 350 N/A N/A VI-2 J, K 33 C3 1431 D1 1 1208 0J2 2.000 2 212 kCO 0.154 150 350 N/A N/A VI-2 J, K 33 C3 148 DE A 1208 034 3.000 3 313 ELI 0.236 75 AIM N/A N/A VI-2 32 D4 Ils D4 08e os /-41 ests a
VEGP .t No.1 Line Desegnation List 006 nov. i g,,. m .i .I ... v.t C...L,.. -
,,.L.. . 12o8 .
4 1I Stieel .I _
l .. . .
8 f
=
i 8-
< , _ , _ a--
ISI-a?- g
s a3- T T- 33 c 158 Class 1"- pago
{ Syslem g U .! . e4oi..
too. b E C h
) $d5 5 E 5 $N5 O* OK- # Suefms Visual **
.h * --
I h,"a $5 0 1208 044 1.000 2 212 fCO 0.250 130 2340 N/A h jf 88/A ~VF-2~ 'C .75~ - A8s- ~~~ 114 ~N 1 1208 044 1.500 2 212 lCO 0.281 130 2340 N/A N/A VI-2 E, a 28 SF 114 A7 1 1208 044 2.000 2 212 IGO 0.344 130 2340 UI PT VI-2 28 A3 044 114 AS 1 1208 045 1.500 1 Ill FC0 0.281 130 2340 88/A PI VI-2 28 87 045 114 ST 1 I?O8 046 0.750 2 212 IGO 0.219 13C 2340 N/A N/A VT-2 E, ; 28 - A6 114 B6 See 860ta 18 1 1208 046 1.000 2 212 fC0 0.250 130 2340 88/A N/A VI-2 E. ; 28 85 114 A6 1 3208 046 1.530 2 232 FCO 0.281 130 2340 N/A N/A VI-2 E. ; 28 87 114 Al I 1208 046 2.000 2 282 (CD 0.344 130 2340 UT PI VI-2 28 A3 046 114 A5 3 1208 041 3.$00 1 !!! TCO 0.281 130 23s,0 al/A PI VI-2 28 81 047 114 87 1 1208 08s8 0.150 282 1 l Al 0.219 130 2340 N/A N/A VT-2 8 28 Cl 114 88 See 960te 24 5 1208 049 0.750 212 ICO 1
0.239 130 2340 N/A N/A VI-2 8 28 C7 114 US 1 1208 0$0 0.750 212 See Note 24 1 (C9 0.219 130 2340 N/A N/A VI-2 8 28 C7 114, 88 3 1208 053 2.000 2 212 fGO See Note 24 0.344 130 2340 N/A UT PI 33 C6 OSI 148 06 1 1208 052 3.000 2 212; IGO 0.438 130 2340 Ut PI VI-2 33 E7 052 148 Si i 1208 053 1. *st N) 2 212 iqs, 18.285
- 830 .14u N/A al/A VI-2 J, ( 33 C6 laga Of I 1208 0$3 2.000 2 282 f00 0.344 130 2340 UI PI VI-2 33 C6 053 148 Of 1 1208 0$$ 0.150 2 212 180 0 0.333 293 390 N/A N/A VI-2 J, s 28 31 3 114 882 See Note 18 I 1208 0$*> 2.000 2 212 IIGO 0.IS4 293 390 N/A N/A VI-2 J. ( 154 1 1208 055 3.000 2 866 See Note 18 212 14G0 0.236 293 390 N/A N/A VI-2 J, K 28 813 114 ,
til See Note il ons'Sl l-ba J
um
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- 7. Deleted
- 8. This line haa 2 segments. The segment inside the containment connecting spray nozzle headers is exempt per H.
- 9. Deleted
- 10. Deleted -
- 11. This line penetrates the containment wall.
- 12. This line has guard pipe around it.
- 13. This line does not require aurface or volumetric examination, due to pipe wall thickness criteria.
- 14. The pressure retaining boundary includes only those portions of the system required to operate or support the safety system function up to and including the first normally closed valve (including a safety or relief valve) or esive capable of automtic closure when the safety functica is required.
- 15. Safety-related boundary ends at valve EV-2627B
- 16. Safety-related boundari ends at valve EV-2629B
- 17. For spools 21208241SO4 uhrough S06 only.
- 18. This line is not included in Line Designation Report 1X4DROO4, Revision 18.
- 19. This line includes 31" ID x 29" ID x 50' reducing elbow to steam generator inlet nozzle.
- 20. This line exemot past HV8111B,
- 21. This line exempt past HV8111A.
- 22. This line exeApt past 11208U6124.
- 23. Welds in the 1501 and 1515 systems have been included in the count for the 1202 system. Volumetric examinations will be accomplished on a sufficient number of welds in the 1202 system to neat the 7.5 percent requirement of the welds in the 1501, 1515, and 1202 systems. Surface examinations will be accomplished on all welds that are examined volumetrically.
- 24. Project Class 212 piping optional upgraded to Class 1 as allowed by IWA-1320(c). Optional upgrading requires this piping to be subjected to the system pressure test requirements of IWB in lieu of IWC.
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