ML17139C764
| ML17139C764 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 07/25/1984 |
| From: | Bean R NUTECH ENGINEERS, INC. |
| To: | |
| Shared Package | |
| ML17139C765 | List: |
| References | |
| ISI-T-106.0, NUDOCS 8412270399 | |
| Download: ML17139C764 (104) | |
Text
IS I-T-106 . 0 Revision 1
( 114. 4001. 0207)
INSERVICE INSPECTION PROGRAM PL'AN FIRST TEN YEAR INSPECTION INTERVAL SUSQUEHANNA STEAM ELECTRIC STATION UNIT 1 AS/SUPPLICROOCUatea RSWSW CATS OORQI
'5%R'V~~~~L~T CATKOORT 2 USE 0 AS SSRR S~'"I~~
INTS HOT 0.
Prepared. for:. CATKOORT 0 CATEOORT A Pennsylvania Power & Light= Compa CCTPTAHCS OPTHIS OOCUMSNT/ORAWIHOOOZS HO AS/SUPPLIS4 PROM PULL COMPLIAHCS WITH CONTRA(
PURCHASE OROSR RKOIRRS MSNTS.
Prepared by: SIO NATURE NUTECH Engineers P.O/CONTRACT N PPSl TWO IL HINTHST,ALLENTOWN,PA ISIOI
. Chicago, Illinois Prepared by: Iss ed R. C Bean Ma in, P E.
Project. Engineer ineer 'Direc,tor Approved. hy:.
' Date: zs r@4 J.~ ~ Clauss, P.E.
~ ~
gineering Manager 8412270399 84f219 PDR ADOCK 05000387 8 PDR
REVISION CONTROL SHEET TITLE: Inservice Inspection Program Plan First Ten Year Inspection Interval Susquehanna Steam Electric Station Unit R C;, Bean, Pro ect En ineer PREPARER' NAME TITLE ZNITI J. M.. Clauss, P. E.
En ineerin Mana er REVIEWER'S NAME TITLE IN IAL.
EFFECTIVE ACCURACY CRITERIA PAGE( S) REVISION . PREPARED CHECK CHECK
- i. to v. 1 1-.1: 1'1
?=1" to.. 3'-4i to"?=3-1.
4-1; to 4'-4: l.
5-lg 5-2. 1 6-1 to 6-18 1 7-1 to 7-39 1 8-1 8-2 g 1 9-1 1 10-1 to 10-8 1 IS I-'Z-106 . 0 Revision, 1
4 TABLE OF CONTENTS Pacae LIST OF'ABLES ~ . . . ~ ~ ~ . ~ ~ ~ ~ . ~ ... .. ~ iv LIST OF FIGURES .....,.....,. ~ . ~ ' ~ ' ~ .. ~: ~
L.-O INTRODUCTION o, ~ ~ <<o. ~ o ~ o. <<o. ~ ~ <<o ~ ~- ~ <<o ~ ~ ~ o o ~ ~ ~ <<o <<<<o ~ oo<<<<<<
?..0 APPKaZCABLE. CODE'ND ADDENDAa ~ ~ ~ ~ .a,e.e.o ~ ~ .<<e.e.o-. ~:e. ~ -ee<<e.
3 ' INSERVZCE INSPECTION CLASS ZF ICATION BOUNDARIES ~ 3-1 4.0 EXEMPTIONS ~ o ~ ~ ~ ~ ~ ~ ~ o o- ~ . ~ ~ ~ ~ ~ ~ . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~. ~ ~ ~ ~ ~ ~ ~ 4-1 5.0 PROGRAM DESCRIPTION ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ 5-1.
6..0 PROGRAM TABLES o. ~ .a e ~ o o ~ o ~ ~ ~ ~ ~ ~ o- ~ ~ ~ ~ ~ ~ ~ ~ o ~ o ~ ~ e ~ ~ ~ ~ ~ ~
7.0 RELIEF REQUESTS ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~. ~ o ~ <<e ~ ~ <<o.o ~ ~ ~ o ~ e ~ ~ ~ ~ 7-L 8.0 AUGMENTED COMMITMENTS e,
~ ~...... ~ ~ .... <<... ~... ~ o' 8-1 9..0 REFERENCES ~ ~ ~ ~ o e ~ oq<<o a o-<<o ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~. ~ ~ ~ o ~ o ~ ~ ~ ~ ~ ~ 9-1
- 10. 0 PPSL 'S CODEi CKEICATIONS . ~ ~ ~ eoo ~ o ~ ~ ~ ~ *<<o o o- e. o ~ o-e o 10-1.
ISZ-T-106 0 Revision
LIST'F TABLES Table Title Pacae 3 0-1 Susquehanna Unit 1 ZSI; Classification Listing ....................'.......
~
Boundary Drawing 3-2 6 ~ 0-1. ISI: P.lan. Summary.-. 6-2.
ISI-T-106 . 0 iv Revision 1.
LIST OF FIGURES
~iciure Title Pace e IRR-F 1 Core Spray and Residual Heat Removal Pump Casing Welds......................... 7-13 IRR-6 1 to Riser Weld,....... '.....<<....>>...,...
Reactor Recirculation Ring Header Sweepolet 7'8 IRR-9 . 1, Snubber, Functional Testing Technical Spec if ication 7-28 10.0-1 Reactor Vessel Bottom Head to CRD Nozzle Weld..... 10-3
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IS I-T.-10 6 0
~
Revision 1'.
1.0 INTRODUCTION
The plan. contained herein outlines the Inservice Inspection ( ISI) Program for Pennsylvania Power and Light,'s (PPaL) Susquehanna Steam Electric Station Unit 1 (SSES Unit fl) for the first ten year (120 month)
~
inspection interval., SSES Unit. fl is an 1100 MW Boiling Water Reactor (BWR). This program complies with the applicable requirement's set forth in 10CFR50 and Section XI of the ASME Boiler and Pressure Vessel Code, Rules for Inservice Inspection of Nuclear Power Plant Components.
As:. stated in 10CFR50 55a(g)( 4), throughout. the service life. oC SSES Unit= 41, components (including supports),
which are classified as. ASME Code Class 1, 2, and 3, shall. meet, the. requirements,. exce t desi n and access subsequertly- become effective and are. incorporated by reference in IOCFR50"55a(b), to the extent: practical within the limitations of design,. geometry~ and materials of" construction af the components.
This ISI Program is subject to change. Changes will be effected via relief requests or miscellaneous document revisions that will be submitted during the interval.
The SSES Unit. 41 ISI. Program shall be updated every ten years,= plus or minus one year, per 10CFR50.55a, or more frequently to reflect: optional Owner upgrades or regulatory commitments This document" does not= include the pump and valve testing ( IWP and IWV) commitments.
IS?-T-106 .0 Revision. L
2' APPLICABLE CODE 2 '.1 Operating License Date 1
During. the initial. ten year (120 month) inspection interval. for which this= program is applicable, inservice examinations: must comply with the requirements'n; the.
latest'. edition and: addenda of. the Code. incorporated'n 10CFR50.55a(b) on the date 12 months. prior to the date or'ssuance of the operating license. The date of issuance of the operating license for SSES Unit 41 is July 17, 1982. The Code in effect 12 months prior to this date is the 1980 Edition, through and including the Winter 1980 Addenda. Use of this Code Edition and Addenda for SSES Unit fl. is subject. to the limitations and. modifications. listed in 10CFR50.55a(b) (2) (ii),. and (iv) A and B as stated," below:
(ii) Pressure-retaining fields. in, ASME, Code Class piping (appX.i'.to Table. IWB-2500 and IWB-2500-1 and." Category B-J:). IE the. facility's, application for a: construction permit., was, docketed prior to July 1,. 1978, the extent of examination for Code Class 1 pipe welds ~ma be determined by the requirements of. Table IWB-2500 and Table IWB-2600 Category B-J of.Section XI of the ASME. Code in the 1974 Edition and addenda through the Summer. 1975 Addenda, or other requirements the Commission may adopt..
( iv"). Pressure-retaining, welds in ASME Code Class 2 piping, (,applies: to Tables IWC-2S20 or / IWC-2520-1, Category: C-F) ..
ISI-T-106.0 Revision '
P
~ ~
(A) Appropriate Code Class 2 pipe welds in Residual Heat Removal. Systems, Emergency Core Cooling Systems, and Containment Heat Removal Systems, shall be examined. The extent of examination for these systems shall be determined by the requirements of paragraph IWC 1200, Table IWC-2520 Category C-F and.'-G, and paragraph IWC.-2411 in the 1974'dition and Addenda through the Summer 1975 Addenda of Section XI: of the MME, Code.,
(B) For a nuclear power plant whose application for a construction permit is docketed prior to July 1, 1978, the extent of examination for Code Class 2 pipe welds ~ma be determined by the requirements of paragraph IWC-1220, Table IWC-2520 Category C-F and.
C-G and paragraph IWC-2411 in the 1974 Edition and Addenda through the- Summer 1975 Addenda of Section XZ of. the ASME;.Code or other requirements the
-Commission may~=adopt.,
s xe a
Commercial Operation; -Date The commercial operation date and the beginning of the f irst ten year interval for SSES Unit fl is June 8, 1983.
2..0.,3 Program Plan Scope The: SSES, Unit= fL Inservice= Inspection Program'eets the requirements: o* Section XI: oG the ASME Boiler. and Pressure. VesseL Code,, 1980'dition through and'ncluding;
/
the: Winter 1980. Addenda.. This document.,is applicable to Subsect:ions.: IWA,. IWB, IWC',. 'IWD, and: IWE; in this document to Section XZ', the Code-,
All'eferences IS I'-T-106 . 0 Revision 1
Examination Categories, Item Numbers, etc. refer to the 1980 Edition through the Winter 1980 Addenda unless otherwise noted .
2.0.4 Relief Requests Per: 10CPR50..55a(g)(5)( iii)- where the requirements of; the. governing Code Edition or Addenda. are. determined to be. impractical,, within the limitations of design, geometry and. materials of construction of the, components, specific relief is; requested..
Relief requests are included as Section 7.0 of this document.
ISI-T-106.0 .2-3 Rev:is'ion 1,
~
3.0 INSERVICE INSPECTION CLASSIFICATION BOUNDARIES The systems or portions of systems subject to the examination requirements'f the-. ISI'rogram for SSES Unit 51.- and. the associated Class 1, 2, and 3 boundaries are. documented. on; coded piping and. instrument diagrams;
-(PGZDs).. The ISZ'lassification Boundar Drawin s.,
which form m part; of'he. ISZ Program are. listed", in:
,Table 3.0-1,.
The system Inservice. Inspection classifications, developed. specifically to define the extent to which Section XL requirements will be applied, differ somewhat from the ASME. Section ZZZ: design classifications. These dif'ferences occur because. systems, or, portions of systems; have been optionally'pgraded in design and because ISZ classifications, are limited to safety related: systems. which; contain. water, steam, or.
rad'ioactive miterials:.. -NUREG:-0800',. Regulatory Guide
- " ." 1'"26',.;-='and."'10." CFR50 were.'. the documents used; in
-identifying; these boundaries-..
IS I'-T;106 0 Revision 1
TP BLE 3. O-l
+M S Ul SUSQUEHANNA UNIT 1 ISI CLASSIPICATION BOUNDARY DRAWINGS (PaIDs) r I Q
ro wI ISI 0 O Classlf ication System(q) Boupdary I Drawin Title Shown Drawin No.(s) gaiq Steam C-193231 ISI-H-101 process Sampling C-193236-4 ISI-H-123 Sht.4 Process Sampling R((R
,1'PSL C-193236-5 ISI-H-123 Sht.5 Service Water C-193232 ISI-0-109 Service Pater ESQ C-193233 ISI-H-110 pmeggepcy Service '
~-
C-193234-1 ISI-H-111 Sht.l pater System Emergency Service ESg ' C-193234-2 ISI-g-ill Sht.2 patqr System Emergency Service ESQ C-193253 ISI-H-2111 pater System iM I
piese$ Auxiliaries ESg C-193237 ISI-H-134 RHR Seryice Water C-193235 ISI-H-112
-gjstem RHR Service Water RHRSQ C-193254 ISI-H-2112 System HSIV Leakage HSLC C-193238 $ SI-H-139 Control
'PPLE 3.0-1 XM O N SUSQUEHANNA UNIT 1 ISI CLASSIFICATION BOUNDARY DRAWINGS ( P&IDs) (Cont'd)
- r. M ISI to H
- r. I Clqssification o I 0 O poundary SySt:erat s) PP&L V ~
C)
Drawin Ti tie Shown Drawin No.(s)
Nqclear Boiler QBlg$ C-193239 ISI-H-141 FP NPP$
CS nuclear Boiler NBP$ C-193240 ISg-g-142
/easel Instru- SBLC mentation Reaptor Recirculation PR
"<<'~~ C-193241 IP$ -H-143 Peactor pater ANCE C-193242 IS)-H-1)4 C)ean Up Control Rod Drive CPP g-1932/3 IS(-g-147 System Part B Standby Liquid SBf C C-193244 Isr-H-148 pont.rol System Reactor Core RClg C-193245 IS(-g-1)9 "Iyolation Cooling RCIC Turbine-Pump RCIC C-193246 gg f.-H-150 piyisiop I Resjdua) C-193247-1 $ S$ -P-151 Sht.l Heat Removal System Division II Residual RHR C-193247-2 fS$ -H-151 Sht.2 Peat Re@oval System J fi ~
0-TABLE 3. 0-1 NM 0 N H SUSQUEHANNA UNIT 1 ISI CLASSIFICATION BOUNDARY DRAWINGS (P6 IDs) (Cont> d) t I
~
8 Q ISI v I 0 I 9 O Classification
~
rQ ~
Drawin Title Sysgerq f s)
Shown Drawin PP&L No.(s)
Boundary Core Spray System Cg C-193248 ISI-g-152 fuel Pool Cooling FPCC C-193249 IS)-N-153 and Cleanup pig> Pressure HPCI C-193250 ISI-H-155 Coolant Ip)ection PPCI Turb)ne-Pump HPC$ C-193251 ISI-8-156
'(r".tgul ~
Control Structure CSCg '., C-193252 ISI-g-186 Cpilleg pater
4.0 EXEMPTIONS Certain components (or parts of components) may be exempted from the inservice examination requirements of ASME Section XI per provisions contained in the Code.
This section lists the "Code Allowed Exemptions" as app1icable* to the.- SSES, Unit. Il. ZSZ. Program These exemptions are further detailed'n the Inservice-Inspection Classification Boundary Drawings 4.0.1 ZSZ Class 3.". Exemptions The following Class 1 components are exempt from volumetric: and surface examination requirements of ZMS-2500: e IWB-L220(a) Components that are connected to'he reactor coolant. system and part of the
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reactor coolant-. pressure; boundary and that.'are of such size. and. shape so that,
=='pon= postulated rupture the resulting flow of; coolant" from the reactor coolant system under normal plant operating conditions is within the capacity of makeup systems which are operable from on-site emergency power.
The maximum size line break that can be made up by the reactor coolant. system has been calculated, to be 1.41. inches (inside diameter) for." liquid. carrying. lines and:
/
Z 82 inches'inside .diameter) for steam:
carrying lines.
I%3-1220(b) (1.) Piping of l. in. nominal. pipe. size and smaller, and ZSI-T-3.06 ' 4-1 Rev.is ion
( 2) components and the ir connection in piping of 1 inch nominal pipe size and smaller.
IWB-1220(c) - Reactor, vessel head connections and.
associated piping, 2 in. nominal. pipe size" and.. smaller, made inaccessible; by.
control. rod; drive. penetrations.-
Table- IWB-. 2500-1., Examination*., Category B-H,, Footnote No.
1 integraL welded attachments with a base material design thickness less than 5/8 in. and weld buildup on nozzles that serve as. supports.
Table IWB-2500-1, Examination Category B-K-l, Footnote No.- 3, integral. welded-'ttachment with, a base material.
design thickness. less than 5/8 inch.
4..0. ? ISI Class': Exemptions;
- ~
r e f
-'" The- faXlowing"Class;?+ components're-. exempt. from the volumetric: and. surface.'- examinations requirements of.
IWC-2500:
IWC-1220(b) -- Components of systems or portions of systems, other than residual. heat removal systems. and emergency, core. cooling systems, that." are not required to operate above a; pressure of..275'sig or above a temperature of. 200 F.'SZ-T-106
~0 4-2 Rev'is ion
IWC-1220(c) Component connections (including nozzles in vessels and pumps), piping and associated valves, and vessels and the ir attachments that: are 4 .in. nominal pipe size and smaller.
ZWC-5222(d) For.- open ended portions- of discharge.
lines beyond the lasC. shutoff valve in nonclosed systems, demonstration of an open flow path test shall. be- performed in lieu of the system hydrostatic test.
Table IWC-2500-1, Examination Category C-C., Footnote No.
1 - integral. welded attachment with a base material design thickness less than 3/4 inch.
403 ISI Class 3, Exemptions The'. followingClass 3'- components are exempt from the examination; requirements of: IWD-2600.:,
ZWD-Z220 1 Integral. attachments of supports and restraints to components that, are 4 in nominal pipe size and smaller'within the system boundaries of examination categories D-A, D-B, and D-C of Table IWD-2500-L shall be exempt fran the visua1 examination VT-3'.
IWD-1220 .? Integral. attachments of. supports to components exceedingand'estraints-
- 4. in.
nominal, pipe. size= may be. /
exempted from the visual. examination. VT-3 of Table IWD-2500-1. provided:
ISI-T-106 . 0 4-3 Revision 1.
a) The components are located in systems (or portions of systems) whose function is not required in support of reactor residual. heat removal, containment heat.
removal, and emergency core cooling..
b) The components operate .at.,a:- pressure: of:
275 psig or. less and a-: temperature-. oG .
'200 F or less..
IWD-5223(d) For open ended'ortions of discharge lines beyond the last shutoff valve in nonclosed systems (e.g , service water systems), confirmation. of'dequate flow during" system opera'tion shall be acceptable; in l.ieu. of. system hydrostatic.
test.,
,".IWD-5223(e) Open: ended'. vent: and'rain lines., from
,e.,';"components:".extending: beyond'. the. last shutoff; valve. and; open, ended. saf'ety or, relief valve discharge"lines shall be exempt from hydrostatic. test..
ZSI'-'T;3.0 6 0 4-4 Rev.ision l
5.0 PROGRAM DESCRIPTION The Inservice Inspection Plan Summary Table is included as Section 6.0 of this document. The following describes the information presented in the table:
A. Cate o and Cate or Descri tion The Section. XZ. Examination Category and its description as defined in Tables, IWB-2500-1, IWC'-2500-1., IWD-2500-L, and IWF-2500-2 for Class 1, 2,. and 3 components and their supports are listed .
B Item Number and Item Number Descri tion The Item. Number; and. its description as defined in Tables IWB-2500-1., IWC-2500-1, IWD-2500-1, and IWE-2500-2. are listed.. All Item Numbers and applicable 'Item Number. Descriptions are listed for." each. Category
~ CA r
Section. XZ"Exam Re uired The- examination.
method, or methods required; as defined. in Tables IWB-2500-1, IWC-2500-1, IWD-2500-1 and IWF-2500-2 are listed. The abbreviations used are as follows;
~ SNUB Snubber inservice test. per IWF-5000 SURF Surface examination per ZWA-2220 VOL Volumetric. examination per IWA-2230 VT-1. -- Visual. examination per IWA-2211 VT-?' Visual. examination. per'WA-2Z12.
VT-3isual. examination per'WA-2213 VT-4' Visual.'xamination per ZWA-2214.
ISI-T-106 .0 5-L Revision 1
D. Relief Re uests Relief 'request numbers (IRR-XXX) reference a specific relief request.
.contained in Section 7.0.
E. Alternate Exam The examination method(s) that will be performed in lieu of the required Section XI, method(s), when rel.ief has~ been requested, are included. Refer. to. the. re1ief, request. for the. specific components: affected.
F~ Remarks General clarification remarks have been included where appropriate.
Notes wnich clarify PP5:L' understanding of Section. XI requirements can be found in Section 10;.0 oK this; document.
ISI'-T-106 .8 Revision 1
0 SECTION 6 . 0 INSERVICE INSPECTION. PLAN
SUMMARY
TABLE'OR SUSQUEHANNA STEAM ELECTRIC" STATION UNIT-L IS?-T-L06'0 Revisjon
TABLE 6.0-1 PENNSf LVAHIA ONER 4
}.IONA CO%'AHT
'UQ}UBIANNA STEAH ELECIR}C QM STATIOH - UH}T I M ISI PIAH SSNARf H
v I tn H I TIKI EXAH RELIEF ALTERNATE 0 >" CATEOORf NHBER DESCR I PT ION REgUIRBIENT RBBUEsT 6INI g O t'J ~
ID PESQSE }IETAI}lltSOLDS IH REACTSI VEST.
}I},}0 +el } }lelds Bl z} } Clrcueferentlal VOL 8'} t}2 Longltudlnal VOL 81,2$ Head Holds ACCESSIBLE LEHOTN OF 8} >2} C}rcumterentlal 1/OL ALL TELOS 8} .22 Her Idl onal QOL
- 6
- }i I.';.
BI.3I} She} }-to-flange Held Bl,]0 Head-to-flange Held $ 0L ANO SISf 8},50 Repair Hs}ds
}I} 5} Belt} lne Reg}on yOL HO REPAIR TELOS AS OF PgE OF OOQHENT PREPARATIOH B-B PKSQSE REl'AII}ltGKISS IH VESSELS OTIC THAN REACTOR VESSELS NO CNPONENTS IBlRI PILL PENETRATION NELOS 0}'GLZLES }I} SSES UNIT I IS ON INSPECTION VESSELS IRPECTIOH P}IOGRHI 8 PROGRAN 8
}Ieaclor Vessel
}I3.90 }Iozzl e-to-1/essel olds VOL IRR-7 83.}pQ Nozzle Inside Radius Section VOL
TABLE 6.0-i PEHHSYLVAHIh P})KEI} SUSQUEHANNA
}.IQIT CO%'AN/ STEAN ELEClRIC 5 H STATION - UNIT }
(D Ul fa t9
}TP EXA)l RF LIEF ALTERHATE 0 H CATTBORf N)IBER DESCRIPT ION EELEIEEEEIIE ~BBEEEE EEIEI EI O H ~
O Qpsslf' zef )}0 CCHPONENTS (BKR) 83~} }I} Pzz} e-to-Vessel olds 83 ~ '}20ozz}q }aside Radius SectIoq St~ Genelotors (PrlEEary Side} IlO CCHPONENTS (BWR) 83 f130 }}ozzie-to-Vessel Kelds 83 ~ })0 pzz}q Inside Radius Section
~}'xchanE)ers (PrlEEary Side) NO (XMPONENTS (BKR)
B3 ~ }50 }}ozz}e-to-1fessel Kelds 83 '60 Pzzle }nslde Radius Section lqli~-I I ~ z QESRSE RETAINIIQ PARTIAL PEHETRATIOI} IKlDS IH VESSELS
}0 fort)el }'enetrat}on Kelds EXTERNAL SlNFACES 8(,}} Vesse} Nozzles gT-2 255 NOZZLES h)NNG 8} l2 Conti ol Rod Ol Ivo Nozzles P-2 EACII GRON'F Instrua>>ntatlon Nozzles VT-2 FENETRATIONS OF CHPARABLE SIZE ANO FU)CTI OH
~Posse'}zer }IO (XNPONENTS (BKR) 84,20 })eater Penetrotlon Kelds QESQNE RETAIHIN) 0}SSHI(AR HETAL %}OS Reactor Vessel 85~}0 )}DEalnal Pipe Size > 4 ln. P}.L lfELOS Nozzle-to-Safe End htt Holds VOL ANO SNf
TABLE 6.0-I PEHNST LVA)II A lPOfElg A SUSQUE)IANNA LIBIT CQ%'~ . STEHI ELECTRIC STATIOH - UNIT I ISI PUUI meART
}TH EX A)I RELIEF ALTERNATE CATBiSV HUlBER DESCRIPT ION ~UIRBIEIIT RACIEST 6IAN 85t}I }kxslpa} Pipe Size < 4 In.- AL}. MELOS Ifozz}e-to-Safe End Rtf )folds SIRF 85t}2 }}ozzie-to-Safq End Socket Molds IIO NOZZLE TO SAFE EHD SOCKET %LOS press+.lzer HO COU'ONENTS (B)8) 85)2g }}on)na} p}pe Size > 4 In, f}ozzie-to-Safe End Buf f Me}ds
}}on)pa} I'Ipe Size < 4 In.
}Iozzle-to-Safe End Butt Molds
})5,22 Qzzt e-to-Safe End Socket Molds '
0
$ g<$ I%~sg<$
< ~ ui
.i~
Sf'enerator HO CSPONEHTS (BMR) 85,30 Qelnal Pipe Size > 4 In. Hozzl e-fo-Safe End Butt )folds 85 3} )}oelqa} Pipe Size < 4 ln. Nozz}e-fo-Safe End Butt 'ifo}ds 85,32 Nozzle-fo-Safe End Socket Molds Hoot Exchangers )}O CSIPONENTS (BWR) 85,4f) I}oe)nal Pipe Size > 4 In. HoZzle-to-Safe End Butf Maids 85 $ ( }}onIna} Pipe Size < 4 In, Nozt}e-fo-Safe End Butf Maids 85 42 }t>zzje-to-Sa fe End Socket Molds I'Ipfng 85,50 Pxalpa) PIpe Size > 4 ln. /L}. +LOS Diss)el fag Hotel Butt Molds VOL AND StRF
}5,5} f}as}nal Pipe Size < 4 ln. )LL MELDS Dlsslellar Hotel Butt Molds SIRF
0 e
T E 6,0>>} PEHNSYLYAN)A PQfE}} 4 SUSQUEIUIHHA L I GIIT GH'ANY STEAN ELECIRIC gH STATION - UNIT I O M ISI PUN St%NARY C4 &
- t. ~
I al H IT@ EXAN RELIEF ALTERHATE 0 t CATTBIXIY NHBER OESCR IPTI ON REgUIRENEIK REQUEST EXAH 9 O ri C) 85t52 P}ssle}lar Natal Socke}'etds llO Ol SS IHI LAR HEfAL SOCKET KELOS f}IESSNIE RETAI HIM BOLTI NI, GREAPR THAN 2 ln IH OIIOKTER Peactor Yessel ALL BOLTS, STUDS, HUTS 86t IO C}osure Ifjtad Ntts SlSF SJS}IINGS, THREADS IN 86,20 C}osure Studs, }n place VOL fLAHGE STUD HOLES 86 30 Plosts e Studs, when neoved Slllf AHO YOL 86,$ 0 Threads }n f}ange VOL EXAHINED ONLY MIEN 86,50 C}osure }Ias}ters, Bushings ; lclfI,4',,') 'r ' t p CONNECTIONS ARE D I S-i~ ASSEHELEO t Passu'/zep I}O CCHPONENTS I BttR) 86,60 Bo}fs and Studs 86,70 f}an~e Surface, when connection d}sossetb}ed B6,80 +tst Bushings ~ and Kashers Strum 6onerators NO CCHPOHEHTS I BKR) 86,90 Bolts and Studs p6 l00 f}ange Surface, when connect'ion d)sasseabled p6,}}0 gluts, Bushings, and Kashers
}lent Exchangers }lO QHPOHENTS IBKR) 86 ~ }20 Pits and Studs 86,}30 f}ange Surface, when connection d I sassoab I ed p6 ~ )40 fluts, Bushings, and Kashers
T 6.0-1 ~ ~ PEHHSf LVAI}lt}(OK}I l SOSl) UEI WINA LIBII3'O%'hHT STEAH ELECIRIC QM STATIOH - UHIT } O UI ISI PLAN SUIIARf rQ tn I EXAH RELIEF ALTER)}ATE 0 o CATBIORf NNBER DESCRIPT IDH EE}lllRBlENT EB}EEET EENl RBIAA(S rE ~ O 3'}p}pg 86l350 points orftd Studs BOL/SE STUDS, NUTS, ETC 6IEATE}I THAN 2 IICHES, 86 '60 }'}ange Surface, }Then connection dl sossonb I ed r 86 ~ }}utsE Bush}ngs, and Itashers f 3)0'6,}SO Ptofps i, Bo}fs and Studs ftOL IRR-5 i P6 t190 3'lant}e Sfs face, }Then connection d}sassoabled YT-3 fSE 86,200 Bu5hlngs E and Ihshers
~
r i~ l
)o}~s 86,230 Bolts and Studs NO BOLTS E STISS, HUTS, ETC, 86,220 }:}ange Sw'face, uhen connection QIEATER THAN 2 I)CHES, dlsasseabled 86 )23$ Nuts, Bushings,.and Noshers 8-G-2 fSESRRE RETAIHIIQ BOLTIIQ, BOLQIlg IIAY BE EXAHINEO 2 }n. AM) LESS }H OIAHETKR o) II} PLACE UNDER TENSION b) lSEH CONNECTION IS P } SASSBI BLED c) IIHEN THE BOLTINO IS IIEHOVEO fleoctor Vessel pl,}9 Bo}fs, Studs, ond }Ifts 3}0 BOLTS, STISS ANO NUTS
< 2 ItCHES gessfs Izer 3}0 CNPONENTS } BIIR)
P,ZI3 Bolfs, Studst and Nuts
TABLE 6 0-} PENNSf LVAHIA POWER 4 SOS'E) UNNA LI HIT CSPAIN STEHI ELECTRIC 5H STATION - UNIT } O Ul ISI PIAH SNOIARf
- r. MI tn Q EXA)l REL}EF ALTERNATE 0 l CATIBQIy IINBER DESCRIPTION REglllRBIENT 6IAN O REQUEST gO o St~ Benerators }IO COIPONEN/S l BMR) 8$ e3I} Bolfs; Studs, and Nuts
}}enf Exchangers }IO CNPOHENTS (BMR) 8$ ,$ 0 }bits< Studs, ond Nots
}'}p}w ALL BOLTS/ STUDS, AHD NUTS 8$ ,50 Bo}fs, Studs, and Puts V}'-}
ps ALL BOLTS'T,UOS, ANO NUTS I,I
$ 7,60 Bolts, Studs, and Nuts a, ~ l~
lfo}ves ALL BOLTSQ STUDS, ANO NUTS 87,7g Bolts, Studs, ond Nuts ~
~
CRO Pwslngs 87,80 Bo}fs, Studs, and Hots VT-I }AlfN OISASSENBLED
}N}E6RAL ATTACIHEHTS FOR VESSELS Reactor Jesse} IDOL OF THE LENGTH OF THE BB }g In)agro} ly Welded Attachaents VOL OR SURF MELO PressN'}~r I}0 COU'ONENTS I BMR) 88,2I} }ntegral ly Welded Attachnents Steca Generator f}0 CCHPONENTS l BMR)
Ban Integral ly Welded Attachments
})eat /@changers }}0 OPPONENTS IBMR) ps, jo }qtegral}y Molded Attachments
TABLE 6.0-} PEINSf LVAN}/f%WER $ SUSQ UEIUINNA L I GIIT COFAlff STEAH ELECI}II C STATION UNIT I ISI PIAH QWIARf EX AH RELIEF ALTERNATE OESCR IPl'ON UEgUIRBlEIIT RBUUEEE EEEII P}}fSSINf }IETAIHIHGOLDS IH PIPING IRR-6 IRR-IO 89<}l} Holt}na} Pipe Size>> $ ln,
~
}}
Qrcumferentlal Welds SINP AN) VOL 255 PP THE CIRC WELOS 89.}2 Longltudlna} Hsl ds SIIIF ANO ljOL )ACI} LONG %LD INTERSECTING
$ SELECTEO C}RC WELD 89.20 }}om}na} Pipe S}ze < g ln, 891)} CIFceaferentlal Kelds SINF 255 OF TNE CIRC WELDS 89t2$ Longltudlna'} Welds SNF }.ONG }COLDS INTERSECTING CIRC WELOS REQUIRED TO BE ZEIE}'Ef~f< )" E EZ EXANINED
~ E, E CU 89,3I} }t anch P}pe O>>nnectlon Welds 255 OF BRANCH CONNECTION 89t3}'famine} p}pe Size>> 4 ln. SINF ANO 'ltOL WELOS 89.32 Nomina} pipe Size < 4 ln, SNF 89 40 Sod(et We}ds SINF 255 OF SOIXET WELDS
}I}TKRALhTTACIIIEHTS FOR PIPIHGU PIMPS AIO VALVES
~lying 1005 OF THE WELD LENGTH
}IIQ IQ }ntegrally Welded Attachments VOL OR SINF
/
~
pups
$ 10,20 }nfegra} }y }folded Attacteents VOL OR SINF ga}ves 8}0,30 Integrally Ifelded Attachments VOL OR SURF
T 6.0-$ PEHNSf LVANIA PNER f SUSQUEHANNA L)SIT CORAL STEAN ELECIRIC STATION - UHIT I ISI PLAN SWHARf EXAH RELIEF ALTERNATE DE SCRIPT ION REgE IREREEE ROIIEEE RIRI 8-L-I lPPESSNIE RETA)HING lKQS IH P~ CASINGS B)2 ~ IQ Pnap Coslng Welds HO PIHP CASING TELOS 8-L-2 PHP CAS)I@i p)2,2g f'Lotp Co sing IRR-I PRESSURE RETAIHIHG liELDS
/g 1/ALVE BODIES P)2.3Q Volvo Body Nelds NO VALVE BODY MELDS VALVE 800 IES P)2.4Q Volvo Body, Exceeding 4 ln.
licEalnol Pipe Size VT-3 /RR-2
)HTERINI OF REhCfNI VESSEL Reoctar. Vessel BI3 ~ Ig. Vessel Interior VT-3 ACCESSIBLE AREAS
7/LE 6.0-) fENNSTLVANIAPOKR 4 SUSQUEHANNA L )CIIT CO%'AHZ STEAN ELECIRIC Q M STATION - UNIT I lD N ISI PLAN QJOlhRV ~ 0 w w- I (a R 0 0 I I~ EX+ RELIEF ALTERNATE o
. CAT(BOW NNBER DESCRIPT I OH ~UIRENEIK REQUEST EXAN g ot 8-g2 (tffE68hLLT lKLDED CORE SUPPORT STRUCTISES hN) )HTERIOR IITTACIHEHfS $ 0 REACTOR VESSEL)
/cocher posse( (B)R)
B)$ .20 )pter)or Attachments ACCESSIBLE TELOS 8(3.2) ~o Support Structure ACCESS ISLE SIRFACES Ra)OymE CORE SmmT STRUCTIWES
/sac/el i]ossa( (PNR) NO PNPONENTS (BWR)
BI3t30 Cole Support Structure PRESQSE RETAIHIHG TELOS
)tf CONIROL ROD HOUSINGS Roactcl passel 8)$ ~ IO Holds )q CRD Housing IDOL OR SlSF (05 PERIPHERAL CRD HOUSINGS
. 8-P ALL fRESQSE RETAINING C()(POHEHTS Reactor Vessel BI5 ~ )0 Pressure Rota)ning Bounds P-2 SfSTf)I LBKAGE'EST EACH IIEfKL)NG OUTAGE BIS ~ I) Pressure peto)ning Boundary VT-2 SYS/EM NTCRO/EST
T 6.0" I PEHNSf LVAHIA POHER 4 SUSQUEHANNA L I 8 IT CO%'AHT STEAN ELECTRIC SThl'ION UNIT } Q H O M ISI PLAN SIHNARf v I ta R IVI EXAN RELIEF ALTERNATE 0 w CATEBSV NU(BER OESCRIPI'I ON RBBUIRBIENT REQUEST 6IAN O o
/messy}zel )}0 CCNPOHENTS (BNR) 8}s.go }f'assure Reto}n}ng Boundary 8}5.2} Pressq e Redo}n)ng Boundary Steca Generators )}0 CCNPONEHTS (BHR)
}}}5 (30 PFessu e Reta}ning thundery 8}5,)} Pressu e Rata}ning Boundary
}lao} Exchange} s )}(} COIPONEHTS (81$ )
}}}5<$0 }'FessLre I}efalnlng Ihundary 8}5)$ } . Press@'e Refo}ning Boundary
}'}ping Bl 5.50 /Fess+ e Re}'a}ning Boundary lg-2 STSTEH LEhf(AGE TEST EACH
})EFUELING OUTAGE PRIOR TO PLAIIT STARTIP 8}5,5} Pressure Retalq)ng Boundary lff-2 SYSTB} HYCROTEST gasps p}).60 }'Fess@ e Retalnlng Boundary VT-2 SYSTBI LDKAGE TEST EACH
}IEFLKLIHGOUTAGE PRIOR TO
} LANT STARTUP 8}5.6} Press< e Retolnlng Boundary Vg-2 STSTBI HYCROTEST 8}5.$ 0 Press' Re/a)ning thundery VT-2 STSTBI LElKAGE TEST EACH REFUELING OUTAGE PRIOR TO PPLHT STARTUP 8}5,$ } Pressure Rata}n'Ing Boundary VT-2 )YSTBI HYCROTEST
'Q TABLE 6,0-1 PENNST LVAH/A PONER C SUSQUEllhNNA LIQIT N'ANT STEAN ELECTRIC STATION - UNIT f gH IS I PIAN SINHARf
~" H v- I Q H IlW EXAH RELIEF ALTKRNATK 0 l CAlMRf INJIBER DESCRIPT I OH ~UIRBlEIIT REQUEST BIBI O +O ~ SlKAH GENERA~ PBIIhI ~ONENTS (BNR) Bt6.)P Stoas Generotor fublng ln StroIghf ruby Des lgn B)f,ZO Steaa Generofor 'fublng ln U-Tube Destgq
T 6.0-l PENNSYLVANIA PQfEP 4 SUSQUEHANNA LIGHT COFQg STEAN ELECIRIC gH STATION - UNIT I ISI PLAN SUOIARf H
- .".7 EXAM RELIEF 0.a'ATEGORY NNBER D ESCA IPI'ON ~IIIRBIENf REglKST g O Q C)
~
A fSESQWE PETAINIW i@LOS ftf fSESQSE VESSELS Cf.)0 She)I Clrceaferentlel Molds VOL RHR HEAT EXCHANGER NELDS hg %0SS STRlCTISAL DIS-CO(f f ffUITY ONLY C),20 Heed Clrcumferentfel Holds YOL RHR HEAT EXCHANGER HEAD TO SHELL 'HELD C),30 fubesheet-to-Shell Hold NO TLSE SHEE/ TO SHELL HEADS G-8 fSESQRE PETAINltG NOZZLE lKIOS IN VESSELS CZtIO pozz)es lp Vessel < I/21n, Haal pe) Thickness POZZLES < I/2" C2.20 Nozzles )n Vessel > /21n. fkaal po) Thickness C2.2l Nozzle-To-Shel I Veld YOL AND SURF PHR HEAT EXCHANGER C2.22 ~lfozzle fpslde Radius Section YOP PHR HEAT EXCHANGER
)NIEGRAL ATfMHENTS FOR VESSELS, P IP IIQ, PINPS AN) VALVES Pressure Vessels C3>)0 lntegrelly Welded Attechaents SURF P% HEAT EXCHANGER
I. P TABLE 6.0-1 PENNSf LVANIA PPtEg 4 SOS'ENAHHA LIGIIT CQ%'AHY STEAN ELKCIRIC STATION'NIT f IS I PULH SUNIARf EXAN RELIEF ALTERHATE RETIRINf PER HER DESCRIPTION REgRIIRRERT RBBIBET EXBI et')pg C3t$ 0 )r}tegrolly Welded Attachaents SlgF I Puepq C3ITg )ntegrIII IY Jaded httacINIents IN INTEGRALLY I tfLOEO PTTACII4ENTS I I gal yes I C3tt00 )ntegrally Welded AttacIPnIents lo INTEGRALLY
%LDED ATTACISENTS EE-'jy)b)R .)
1" fPPSSlHE RETAINltB BOLTIIS GREATER 'fIUMl 2 Ip IH OIANETER pressIs e Vessels
~ lg Points and Studs NO BOLTS ANO STUDS > 2" I'Iplpg P.2g Bolts and Studs BOLTS AND STUDS > 2n Pueps 9.3g Bolts and Studs Q POLTS AND STUDS > 2" Valves C4.40 Bolts and Studs lt0 BOLTS NN STUDS > 2" PRESSNIE RETAINIIQ i%LOS IIl PIPIT IRR-3.
C3tlq PIPIng Holds I/21n. Nominal Wall Tnlckness C5~2! Clrceaferentlel Weld SINF AIO VOL IRR-3 C5,22 Longlgudlnal Wold SNF AND VOL C5,30 Pipe Branch Connections C5,3l Clfcuafereqtlaf Wold C5~32 Longltudlna) Wold IfO LOIfg I TUB I NAL P IPE BRANCII CONNECTION WE LOS fSESSNIE RETAI lf) IG WELDS IN PIMPS AIQ VALVES Pmps C6,IO f'sap Casing Holds SINF IRR-4 V+3 Va)ves
$ 5,2II Va)ye Body Welds IIO VALVE BODY WELOS I'LL PRESSNIE RETA)HIND CQ%%HEHTS esse'e lfpssa)s CT ~ )0 Pressu e RetaIIIIng Coeponents VT-2 SYSTEM PRESSURE TEST DURING SYSTEM OR COIPONENT FUNCTIONAL TEST CT~/I Pressure Retalnlng Caaponents VT-2 SYSTBI fIYIIIOSTATICTEST
TABLE 6.0-I PENHSYLVAHIA (%ME/ 4 SUSQUEHANNA LIQIT COL'AHY STEIW ELECTRIC QH STATION - UNIT I ISI PLAN SINHARY v I Q Rfl.lfP Gl tTPt ALTERNATE 0 I CATKORY HIIIBER OESCRIPI'ION tuglLIRBIEHT RBBlKST EX~ 5 O Q ~. O lP)ping C7.20 Press+ e Rata/ning Components 'P-2 SYSTBI PRESSURE TEST DURING SYSTBI OR CCHPONENT FUNCTIONAL
/EST C7.2( Pressw'e Ptalplng Components YT-2 SYSTEH HYCROSTATIC TEST Pgps
+,30 Presse Reta)nlrb Components YT-2 STSTBI PRESSURE TEST DURING SYS'/EH OR C9%%NEHT FUNCTIONAL TAT f'resale pate)ning Components SYSJBI HYISOSTATIC TEST
~ ~ - ~ el,'A falyeq C7,)0 Press' petalnlng Components P-2 SYSTBI PRESSURE TEST DURING SYSTBI OR COIPONENT FUNCTIONAL
'fEST C7 4f Pl essw'e Retalnlng Components VT-2 SYSJBI NYNOSTATIC TEST
6.0-I PENNSYLVANIA ~R 4 SUSQUEIUWHA LIQIT QHPAHY STEAN ELECTRIC STATIC - UNIT I ISI PIAH SUGARY EXAH 'ELIEF ALTERNATE OESCRIPTIOH REgU IllBIEHT RIIUEsT ENNI SfSTBI$ lg SllVORT OF REACTNI SISlIXM( FUN'TIOH NO SYSTEHS PSTBlS Ig SHORT OF EHEfSEHCT COPE COOL)IN, COHTAIHIEHT HEAT RBIglf+
$ %0+HERE CLEAHN', AIQ RE~at RESIDUAL SKAT RBIOVAL 02 ~ )Il Finesse'e patalnlng Ooeponents 'P-2 S/STBI FUNCTIONAL TEST V+2 SYS/BI NTINOSTATIC TEST 02.20 )ptegral Attachment g Reponenf Supports and Restraints VT-3
)qtegra) Atfachaent
<< fIechanfcal and IIydraullc Snubbers VT'-3 02 4g )ntegral Attachaenf
- Spl }ng Type Supports 02 50 Integra) Attachment
- Constant Load gype Supports VT-3 02.60 )ntegra) Attachment
- Shock Absorbers YT-3 0-C SYSTBIS IH SllVORT OF RESIDUAL IIEAT REHOVAL FROI SPENT FUEL STNUGE POOL IP STSTEHS
TABLE 6,0-I r PENHSVLVANIA POtEII $ SUSQUEHANNA LIOIIT COIPAHJ STEAN ELECTRIC QM STATION - UNIT I e U) ISI PIAH QUART
- r. MI r0 t-I Ol I
CATEGORY l}TBI IANBER DESCRIPT I ON EXAN
~UIIIRRRRt
- RELIEF RRRRIRRt ALTERHATE RXRR J 0 Ch I ~
o F-A F-) R2,3 'IATE AN QfIL TVPE QR%TS r-i Nechanl eel nttachaents, Including bolting VT-3 IRR-8 VT-2 F-2 Welded attachments VT-3 IRR-8 VT-2 Component dlsplnceaent, setting of guides V+3 I RR-8 tfT-2 and stops, mlsallgnment of supports, .. nsseably of support lteas f"I )2 f3 LIWR TTFE SSVORTS Nechanlcal attachments, Including bolt/pg -Rl I VT-3 IRR-8 VT-2
~
F-2 lded attachments ~,'t VT-3 IRR-8 'VT-2 F-3 Gomponent dlsplaceaent, setting of guides VT-3 IRR-8 P-2 and stops, mlsnllgnment of of support lteas supports'sseably F-C F-) R213R4 IXNROt&IT STANARO SSVORTS
~ F-) Nechanlcnl attachaents, Including bolting VT-3 IRR-8 VT-2 F-2 Welded attachments VT-3 IRR-8 VT-2 F-3 Gotaponent dl apl aceaent, setting of guides VT-3 IRR-8 VT-2 nnd stops, mlsal Ignment ot supports,
~nsseably of support lteas F-I Spring type and constant load type supports, VT-d I RR-8 VT-2.
. shock absorbers, hydrnulfc and mechanical SNUB IRR-9 VT-2 snubbers
SECTION 7.0. RELIEF REQUESTS FOR SSES', UNIT. Ol. E 7p 1 ISI-T-j'06 0 7-l Revision l
RELIEF REQUEST NO ~ IRR-1 IDENTIF ICATION OF COMPONENTS AND IMP RACT ICAL CODE
'REQUIREMENTS Susquehanna SES Unit-l has an ZSI Class-1 recirculation pump in each of the two 28-inch diameter recirculation loops. These. pumps (1P401A AND lP401B) function; dur;ing normal. reactor operation to provide forced recirculation through, the reactor core.
Section XZ requires that one of these recirculation pumps be examined visually (VT-3) during'ach inspection interval . Specifically, the area. of examination includes all pump casing internal pressure boundary surfaces (Category B-L-2.). As discussed in. detai3 =below, Pennsylvania Power a Light requests relief from the Section XZ examination requirement to visualLy: examine the recirculation pump internal. surfaces on-the. basis of impracticality., ZZ BASZS FOR RELIEF The basis for this relief request is predicated on the following two points: 1 . The har4ships associated with pump disassembly far exceeds any beneficial safety improvements that migh< be achieved, by such an examination, and'he structural'. integrity afforded. by the pump casing material utilized will not, signifi-cantly degrade over the lifetime of the pump. ISZ-T-106" 0 7-? Rev.is ion
~ ~ I ~
1 RELIEF REQUEST NO. ZRR-1 (cont'd) Zt is expected that approximately 1000 man-hours and 50 man-rem exposure would be required to disassemble, inspect, and reassemble one pump. Performing this visual examination under adverse conditions such as high dose
)
rate. (30-40 R/hr) and poor as-cast. surface condition, realistically, provides. little. additional information as to the pump casing integrity. The recirculation pump casing material, cast stainless steel (ASTN A351-CF-8), is. widely used in the nuclear industry and has performed extremely well. The presence of some- delta ferrite ( typically 5% or more) imparts substantially increased resistance to intergranular stress corrosion cracking. The delta ferrite also results. in. improved pitting corrosion resistance in E chloride. containing environments Pennsylvania~ Power; &.;Light. feels that adequate safety margins are inherent=-.in. the. basic pump. design. and. that the hea1th and, safety of the public will. not. be adversely effected by performing the visual examination of the pump internal pressure boundary surfaces only when the pumps are required to be disassembled for maintenance. Furthermore both pumps will be VT-2 examined every refueling, outage during leakage tests. and once in the interval during. hydrostatic tests. ZSI-T-106.0 7-3 Revis ion 1
RELIEF REQUEST NO. IRR-l. (cont'd) III. ALTERNATE PROVISIONS As stated above, it. is not felt that the visual examination required 'by Code each ten year interval is warranted. However, as; standard. maintenance- practice dictates, when a. recirculation. pump is disassembled. for maintenance, a VT-3 examination of the internaL casing pressure. boundary surfaces will be performed. The~ pump maintenance procedure will. address the need for this examination while the pump is disassembled. ISI-T-106 0
~ 7-4 Revision I
RELIEF REQUEST NO ZRR-2 IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS The Susquehanna SES Unit-1 Class-l systems contain 57 valves.-. which are greater. than four inches, nominal pipe size.'hese: valves. vary
)
in size, design, and'. manufacturer but are all manufactured. from- ei,ther cast or forged: stainless steej or carbon steel.. None, of the valve bodies are welded. Section XZ requires a visual examination (VT-3) on the internal. pressure boundary surfaces of one (1) valve body in each group of valves of. the- same constructional design and. manufacturing, method that perform similar. functions. in the system These examinations are required. to be completed. each inspection interval (Category. B-M-2). tl V
'Since- these, examinations'. must be performed. whether or not the. valves have to be d.isassembled for maintenance, this. requirement is considered impractical.
ZZ. BASIS FOR RELIEF The requirement to disassemble primary system valves for the sole purpose of performing a visual examination of the internal, pressure boundary surfaces has only a very smal3 potential. of: increasing, plant, safety margins and a very disgroportionate. impact. on. expenditures of plant
- manpower and".,radiation exposure.,
ISI.-T-106.0 Revision l.
RELIEF REQUEST NO. IRR-2 (cont'd) Performing these visual examinations on poor as-cast sur faces provides little additional information as to the valve body integrity. For approximately 20 percent. of these valves, the reactor vessel core must be. completely" unloadecL~ and. the: vesse1 drained, to permit: disassembly for= examination., The performance of both carbon. and stainless cast and forged valve 'bodies has been excellent in all BWR applications. Based on this experience and both industry and regulatory acceptance of these alloys, continued excellent. service performance is anticipated A more practical. approach that would essentially provide an equivalent= sampling program and significantly reduced radiation; exposure., to.>> plant: personnel is to inspect. the internal,='pressure: boundary of. only- those valves that. require disassembly for maintenance. purposes:. This would still provide- a reasonable. sampling of primary system valves and give adequate assurance that the integrity of these components is being maintained. III. ALTERNATE PROVISIONS When a valve. within- a particular valve grouping is disassembled= for maintenance purposes, the internal. pressure- boundary surface of that: valve body will. be examined"to meet. the. Section. XZ requirement. for that group of -va3ves. The valve maintenance procedure- wi11 address. the need for. this. examination ISI-T-10 6"'0 7-6. Re.v,is'ion 1
0 I ~ IDENTIFICATION RELIEF REQUEST NO. IRR-3 OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS ISI Class 2 pressure retaining welds in piping are the subject. of this relief request. In accordance* with 10CFR50.55a (b) (2) (iv) ", (A) Appropriate Code. Class 2, pipe welds in Residual Heat. Removal Systems, Emergency Core Coo1ing Systems and Containment Heat Removal Systems, shall be examined. The extent of examination for these systems shall be determined by the requirements of paragraph IWC-1220, Table IWC-2520 Category C-F and C-G, and paragraph IWC-2411 in the 1974 Edition and; Addenda through the Summez. 1975 Addenda of. Section XZ of. the ASME Code. ( B) Foz."-a. nuclear power plant whose. application for a construction- permit, i;s:,docketed'rior. to July 1, 3.978, the extent'. oC examination. for Code: Class ? pipe welds may be determined'y the requirements of paragraph IWC-1220, Table IWC-2520 Category C-F and C-G and paragraph IWC-2411 in the 1974 Edition and Addenda through the Summer 1975 Addenda, of Section XI of .the ASME Code or other requirements the Commission may adopt. PPS.L. has'lected. to implement 10CFR50 .55(a)(b)( 2)( iv) (B). Therefore,. the extent of examination for all ISI. Class 2: systems. will. be determined by the requirements of ASEE. gentian, XZ, '19T4: E'ditian thtaugh end/'including the Summer.,I&7.5 Addenda. is requested from the following I'elief code requirements: IS I-T-10 6.. 0 7-7 Revision L
~
A
~
e 1.) RELIEF REQUEST NO.. IRR-3 Paragraph (cont'd) IWC-1220 in the 1974 Edition through and including the Summer 1975 Addenda of ASME Section XI (74S75) defines the components. that may be exempted from the examination requirements of IWC-2520.
? ) Paragraph ZWC-243.I:(e) in the 1974'dition <hrough, and including the Summer 1975 Addenda of; ASME. Section XI (T4S75) indicates: that the required examinations assigned to the components in each stream of the system shall be completed by the end of the service 1 ifctime.
In lieu of the above, Pennsylvania Power and Light'roposes to upgrade these specific Code: sections. to the corre-sponding Code requirements found in the 1980 Edition through and, including- the Winter 1980 Addenda of ASME. Section'Z., BASIS'- FOR'EZ'ZEF 1.) Certain exemption criteria in ASME Section XI, 1974 Edit.ion through and including the Summer 1975 Addenda, paragraph IWC-1220 do not have' sound technical basis. More recent: Edition and Addenda of the Code provide updated. exemption criteria. Pennsylvania Power a. Light will exempt, ISI Class ? pressure retaining welds; based on the exemption criteria provided." in the Alternate, Provisions section. of this. relief request:.. 2.' . ASME Section. XI., 3.977 Edition. through and.'ncluding
'-'8 the"Summer 1978 Addenda: to present. (Summer 1983 Addenda) has incorporated, requirements for focused weld seZection. The purpose of focused weld" selectior ZS I-T-106 ..0 Revis.ion'
RELIEF REQUEST'O. IRR-3 (cont ') is to examine a group of welds most likely to develop indications. This group of welds is examined during first. interval. and. reexamined during subsequent 'he. intervals.. The requirement of paragraph IWC-2411(e), 74S75 is impractical. because the superior technical approach of: focused.. weld". selection cannot: be. implemented;. Per: IWC-2411(e), 74S75,, a different group of; welds; must be examined each interval. Pennsylvania., Power a, Light. will examine ISI Class 2 pressure retaining 'piping welds,based on the extent of
\
examination definition provided in the Alternate Provisions section of. this relief. request.. ZZZ ~, AZ'TERNATE P. ROVIS ZONS h L ):- 'he exemption ci:i',.teria: for, ISI, Class 2 pressure
':..retaining- piping-'elds: wi13- be- taken;,fram: ASNE. Section XZ .-'X9&0; Edition" through; and. including the Winter 19&0 Addenda.:
IWC-1220 Components Exempt from Examination The following components shall be exempted from the inservice. examination re'quirements of. IWC.- 2500'. I'o4 Components'f; systems or; portions of systems that= during; normal. plant: operating conditions; are: not required to operate or: perform a system function" but. remain. floodec. under static conditions at; a- pressure of at ISZ-T-106.. 0 Revis'ion .1.
RELIEF REQUEST 'NQ., IRR-3 (cont'd) least 80% of the pressure that the component or system will be subjected to when required to operate. b., Components- of'ystems or. portions; of.' systems, other: than. Residual. Heat.'Removal. Systems and Emergency Coie Cooling Systems, that are; not. required; to operate. above a pressure of'75 psig (1900 kPa) or: above- a temperature of, 200'F (93 C). c., Component, connections (including nozzles and pumps.), piping and associated in'essels valves',, and, vessels and, their. attachm'ents that: are~ 4! in;. nominal- pipe. size, and smaller . A '2 )'he. extent= of'-examination: for: ISI; Class; ?'iping welds Ks'efinedl such:=that= the- welds; initially selected. for examination during the. 1st inspection. interval. shall, be: reexamined'uring each subsequent inspection interval. By focusing the examination program. on, those welds having a historically higher probability of. failure, this inspection program is more likely to detect. incipient. generic defects.. Examination. of the same; welds. each. inspection interval: permits'eaningful data>> trending. not: possible- when different. welds are being; examine* each. interval See Note. 3. in Section 10'..0;- oK this:'document. for; specific. information on
., Class.:,'2: Weld Se1ection ..
/
ISI-T.-106"0 7-10. Revision 1
REZIEF REQUEST NO ~ IRR-4 IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS'usquehanna SES Unit-1 has four (4) Core Spray Pumps. and fo~ (4) Residual Heat. Removal. Pumps, The, primary functions.- of: these. pumps are decay heat: removaL,. suppression pooL heat: removal,, and emergency core cooLing,. Section XI requires a surface examination of the discharge elbow to sleeve forging weld and the discharge elbow to bottom plate flange weld, and. the pump casing welds located below floor elevation 645'-0" (Category C-. G) .. Since: this requirement. is impracticaL due to inaccessi-biLity,, relief; is= requested, fram the aforementioned
- examination: requirements,..
j BASIS FOR RELIEF Both the discharge elbow to sleeve forging and the discharge elbow to bottom plate flange weld are located within the pump casing (see Figure IRR-4.1, welds 361-6<< 7', 361-2-6 and. 361-7-8 are typical), thus they are not accessible without removal of. the. pump motors.. Failure; of, either weld. would. cause: the discharge water. to be circulated; back. to the. suction water;.. The. pump. casing, welds located- below Q.oor elevat.ion 645'" (359 L ? ~ 359 2 L2~ 359 2 2~ 359 2 LL~ 359 ?- and 359-3-7 typical) are surrounded by concrete and. the pump casing is flooded with water, thus they are not accessible.. ISI-T-106. ~ 0 "7-.1'1, Revis.ion L
RELIEF REQUEST NO. IRR-4. (cont'd) The hardships associated with pump motor removal. and/or pump disassembly far exceed any beneficial safety improvements that might be achieved. by such an examination. e These: pumps; are: subject. to: testing. unde+ INR= Since-each pump is: subject: to. a. quarterly test: for. pressure differenti;al and, flow,, any loss. of. integrity. of the subject welds would'. be detected by these. tests. Furthermore these components are subject to the pressure testing, requirements of IWC-5000. Additionally, the statistical significance to the inspection" sampling- program will. be negligible- due to the- small. number; of welds: involved'. ALTERNATE P ROVIS IONS';
.-':'-. 'Those. we1dsl one the. subject: pumps made: accessible during pump- moto~ removal. or pump d'isassembly as; required; for maintenance purposes will, be visually (VT-3')'xamined.
IS I-T-.10 6 '7-1? Revis.ion l 0
.FIGURE IRR-F 1 PUMP CASING NELDS CORE SPRAY PUMP IP-206Ai Bt C~ D AND RESIDUAL HEAT REMOVAL PUMP IP-202A B~ C~ D I 5 I. CESS OQ IITS
&I)-I.Y 6, I 7 6+
-5 6 SUCTION 56I.5 Ih OISCHlIIQE
+ 56I 6<<7 K ltd' 56I% 6 56 I KOOa a os&O I ~5 ~ g.ao.. ~ .
QZ 359-I- 4
~ ZZ+
Z<1
~ Ae-2-S +
Nfl> 'cW teog S~ ~ ', II
~ INA'CCESSIBLE WELDS:
I e ISI-T-106 ~ 0 7-13 Revis-ion '1.
RELIEF REQUEST NO. ZRR-5 IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS Susquehanna. SES Unit-1 has two ISI Class 1 recirculation pumps. each containing 16 bolts which, attach the pump motor. to the pump casing.. Section XI requires that all. pump bolts. be= volumetrically'xamined during the inspection interval (Category B-G-1) . Pennsylvania Power. a Light requests relief from Section XI. examination requirements; for one of the bolts (1P401B-STUD-14) based.'n inaccessibility. BASIS FOR RELIEF Ore Reactor.. Recirculation; Pump "B""; the boy. located at 300'" pump azimuth is'"partially inaccessible for ultrasonic examination due to a small pipe obstruction. Removal of the bolt for examination would result in expenditures of manpower. and radiation exposures that would not. be commensurate with the added assurance of safety. The entire bolt can be examined from the center hole of the. bolt The partially restricted scan would. be from the top" face. of: the bolt. ALTERNATE. PROVZSZONS'he'ubject bolt wil'1 be volumetrically examined to the extent possible during the inspection interval.. Additionally, the bolt will be examined during. system ISI-T'-106.. 0 7-l4 Revision. 1
REL'ZEP REQUEST NO. ZRR-5 (cont'd) leakage testing every refueling outage and once every interval during the hydrostatic pressure test. Should the pump be disassembled during the. inspection interval, a complete examination will be performed. ZSI-T-.106 .0 7-.15 'Revision 1.
0 IDENTIFICATION RELIEF REQUEST OF COMPONENTS NO ~ IRR-6 AND IMPRACTICAL CODE REQUIREMENTS Susquehanna SES Unit 1 has two reactor recirculation loops whose function during norma1 plant operation is to provide forced .coolant recirculation". through the reactor core., In accordance with NUREG-0313, Revision 1, piping welds on non-conforming, service sensitive lines are subject to augmented volumetric examination. These examinations are to be performed in accordance with the requirepents of Section XI. The ring header sweepolet/reducer to riser welds (Figure IRR-6.1) in the. reactor recirculation system can not be examined, in accordance with" the requirements of Section
*~
XX BASIS" FOR RELIEF Due to geometric and metallurgical constraints, the heat affected zones and weld root of the subject components can only be partially examined. As shown .in Figure IRR-6.1, the construction of these weld joints is extremely complex. The signals obtained from ultrasonic examination of these. joints are very difficult to interpret and. the- results are not. easily duplicated. As'peciEied in. NUREG'-0'313 the risers have corrosion resistant cladding. to minimize the joint.'s suscepta-bility to Inter Granular Stress Corrosion Cracking. In addition, Susquehanna SES Unit 1's leak detection system design conforms to the requirements of NUREG-0313. ISZ-T-106 ~ 0 7-16 Revision 1
RELIEF REQUEST NO.. IRR-6 (cont'd) III. AL'TERNATE PROVISIONS Visual. examinations of: the.. weld. will, be- performed during system pressure tests required by IWB-5000 of. Section XI:.. Volumetric examinations of the weld. will= be performed: to- the extent; practical due to the." geometric. and; metallurgical. constraints'escribed. above.. IS?-T.-.l06 0 "7-3.'7' Revision, Z.,
FIGURE IRR-6.1 (Sheet l of 2) Reactor Recirculation Rin Header Swee piet to Riser Weld TO REACTOR VCSSSI-DETAIL A-, s~ee~o~st/ see sHT.z zavucsa R1 NC HEAP<R. Weld Ident l t icatlon Dutchian Bul ldup Counterbore Clad Lb I ckness Cl adding to Inboard IIua bar Len "A" 'Len "Brr I en r>> Qll Break Len "E" VRR 831 I'"FWAIO>>AIOM 23/32 11/64 6/32 2 15/64 VRR 831 I FWAI I rhl IM 19/32. 18/64 45/64 7/32 2 5/64 YRR 831 I FWA12,AI2M 16/32 31/64 7/32 2-18/64. YRR 831 I FWAI3,A13M 18/32 11/64 7/32 2 5/64 VRR-831 I "FWA14 r A14M 21/32 40/64 6/32 2 24/64 YRR 831 2 FWBIOrBIOM 18/32 21/64 6/32 2<<8/64 VRR-831 2 FWBI I rBI IM' 14/32, 52/64' 6/32. 2 35/64 3/64- 7/32. 2 19/64 YRfH61 2~FWB12;812M>> VRR 83"t 2 FWBI3rBI3M 18/32'1/64 17/32'RR 22/64. 53/64 6/32;, ( 2 26/64. 831 2 FWB14rBI4M 19/32 9/64 -45/64 7/32 2 12/64 IS I-T-106. 0 7-18' Revision 1
e FXGURE IRR-6.1 (Sheet 2 of 2) Reactor RecircUlation Rin Header Swee piet to Riser Wel 6 XT'CR NAI Ct AD
'~lQRt. b BUt LD-IJP DOTCH MAN (RISKED. p<p<m>,
SVJGQPOl-E.7/ REDoaaa. DETAl,t ZS ?-T=1 0 6 ~ 0 7-'-19 Revis:ion 1
RELIEF REQUEST NO. IRR-7 I ~ IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS. Susquehanna SES Unit-1 has two Feedwater Inlet Nozzles, N4A and N4D, which can not be.. completely examined Section XZ requires 100% volumetric: examination of the nozzle. to vessel weld. and adjacent, areas. as defined in Figure IWB-2500-7'(b) each inspection interval (Category B-D) ~ Pennsylvania Power a. Light. requests partial. relief from Section XI, examination requirements for Feedwater Inlet Nozzles N4A and N4D due to geometric restrictions as discussed below. t BASIS FOR. RELIEF The. close'roximity of'ozzles N11A. and N11B to the subject,'feedwater; nozzles preclude complete examination of the nozzle to vessel weld. The spacing of 4.5" between the nozzles does not permit automatic,. examination of approximately 60'f the subject welds. The basis for this relief request is predicated upon the following. L the. excluded., area= represents only 16.67 percent. of the weld: seam,, the remainder. can be,,completely
~
examined'.. 2;. The four remaining nozzles of the same configu-ration and service can be completely examined. IS I'-'T-3. 06 ~ 0 7-20 Revision L
RELIEF REQUEST NO. IRR-7 (cont'd) III. ALTERNATE PROVISIONS The areas identified will be manually examined to the extent possible. Additionally, these nozzles will be. visually examined. each refuel.ing outage during the leakage. tests'nd e'ada. interval. during the: hydrostatic." pressure test. 4 'ISI-T-l06 ..0 7-23 Revision l, .
REZ'IEF 'REQUEST NO. IRR-8 IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS The purpose of this relief request is to define the exemptions and selection criteria for component supports that PPaC. plans.. to. implement in its first. ten year interval., This request: does not pertain to snubber functional. testing (IWP-5000). 1.) Exemption >> Each subsection of the Code contains a subarticle on the components within the. respective class that are exempt; from examination. In subsection IWF (component support examination),. subarticle IWF-1230 is reserved for: the. description. of. support exemptions; This subarticle". is; still.. in, the course of preparation in the: 1980'dition: through. and including the Winter 198C Addenda. ( the. Code applicable to the f'irst ten year intervaL for SSES, Unit. OL) and the: 1983 Edition. Therefore, it is the utility's responsibility to develop exemption criteria that provides..a degree of
. safety and reliability commensurate with the other subsections of the Code.
2.) Selection Criteria Examining pipe supports on a statistical. sampling basis: is, being requested; to, achieve ~a representative cross-section; oC al3 Class L, 2. and 3 systems, all support.'ypes., (e:.g.. snubber, spring, rigid,, anchor) and. all. plant environments. Statistical sampling provides a high degree of confidence on the integrity of all the supports.
'S X-'T-10 6.,0 7-'22 Revis:ion 1
REL'IEF REQUEST NO. IRR-8 .(cont'd) BASIS FOR RELIEF 1 ..) Exemption ASME Code: Interpretation XI.-1-79-14. is the, basis for: the: exemption portion of; this. relief: request;. The: code interpretation. states. that "it. is the- intent. of: Section, XI.'o exempt from examination supports- of Class 2'iping; and components that are exempt from. examination, as in IWC-1220." In IWC-1220 the intent of the word. "examination" is limited to volumetric and surface examination only. The specific Class 2. interpretation provided, in the. Code has been extended to include. Class 1, and. 3 supports also.
?'..).' Selection Critexia .
T
'A'. sampling .plan: i'esi:gned.'o penalize the. plant; that
-'-':=has supports. in"..poor.- condi'tion while hot; penalizing;
'hose plants with. supports. in good, to excellent.
- condition.. This is the'ame: philosophy that forms the basis of the snubber functional test frequency found in the plant Technical Specifications.
IIL- ALTERNATE PROVIS IONS: 1 ..) Exemption
. Component: supports.. sha13 be- exempt. fr'om.
/ the VT-'3,and.
VT;-4". examination...requirements;. as .follows:: ISI-T-10 6. .0
~ 7-23'.
Rev.ision 1.
RELIEF REQUEST NO. IRR-8 (cont'd) a) Class I and 2 components which are exempt from surface and volumetric examination in accordance with IWB-1220, and IWC-1220 respectively of the Code, b) Class 3 components which are 4'.. inch nominal. pipe size and smaller-, in. accordance with IWD-1220.L of. the Code. The. component supports exempt from VT-3 and VT-4 examination will not be completely neglected. A visual examination (VT-2.) is required on all Class I,
- 2. and 3. systems. concurrent with a pressure test. This test and. associated examination is conducted at a minimum once. every period. During one of these tests in. the ten-yeax:,;imterva1, the associated VT-2 examination will'. include:.the requirement to verify
. that".~
aLI accessible; supports on. these. lines; are intact,". tha< is properly-. connected, from the: point. of pipe or component'ttachment to the building structure. The inspection record for this examination will be on system or isometric basis as will the pressure test record as opposed to a support by support basis as required for non-exempt support.
?.): Selection Criteria The selection criteria. for the Class I, 2 and 3 pipe supports ( tbis:relieC request. ia uot/applicable to equipment supports-) which are not. exempt from examination. is. based, on statisticaL sampling,. The sampling plan used is a= single sample, hypergeometric IS I-T-.10 6 ~ 0 7-24; Revision'
RELIEF REQUEST NQ. IRR-8 (cont'd) distribution which provides 95% confidence that a support population which contains 10 percent or more unacceptable suppports will be rejected (95/90 hypothesis). Sampling will be performed completely each. period. All non-exempt supports will, be separated; into four: populations. These. populations will .consist of snubber supports, spring type- supports, rigid. supports and anchor supports. A sample that corresponds with the population size for each type will be examined completely during a period, with a sample of different supports within each type to be examined in successive periods. Zf the'umber of.'efective: supports exceeds the maximum., allowed;- additional. examinations are required in: accordance wi:th the- sampling plan appropriate for the. population. si'ze .For.. these. additional examinations, the'opulation will. be based on the number of supports in the system associated with the defective support unless the defect is discovered on a spring or snubber type device. In this case, the population shall be based on the total of the respective type. In-. the- event. that, a. second genera ion of additional. examinations are* necessary, it wi11 be performed. in with Subarticle IWP-.2430(b) of the. Code. 'ccordance ISI-T-106. 0 T-25 Revision l,
0 RELIEF REQUEST NO. ZRR-9 IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS SSES Unit 41 Class 1, 2, and 3 piping systems are suspended by a= variety of. support, components including, snubbers Snubbers in Class 1, ?,, and 3 piping, systems are= the subject. of this rel.ief request. The Code states that, snubbers shall receive an inservice test in accordance with ZWF-5300 and ZWF-5400. IWF-5300 ( In the course. of preparation) applies to snubbers with a capacity of 50 kips or greater. and ZWF-5400 addresses snubbers with a capacity less than 5Q kips. Pennsylvania Power & Light requests. relief from the Section..XI. inservice.=testing requirements. in IWF-5300 and. ZWE-5400. BASIS'OR RELIEF The snubber inservice testing requirements in IWF-5300 and IWF-5400 of Section XI are not complete and Pennsylvania Power & Light has already imp'lemented a comprehensive snubber testing program. Pennsylvania Power &. Light.'s snubber testing program is defined in the plant Technical. Specifications, Section 3/4..7.4. The applicable. portions. of: the Technical. Specifications have been included in Eigure ZRR-9.1. ISI-T-1'06 . 0 '7-'26 Revis'ion 1
RELIEF REQUEST'O. IRR-9 (cont'd) III. ALTERNATE P ROVIS IONS The functional testing requirements of Technical Specif ication 3/4.7.4 wil1 be implemented in lieu of the Code; requirements in IWF-5300 and INF-5400. VZ-3 and. VT examinations will. be performed in. accordance.. with. Section XI. IS I'-T-106 <<0 7-27 Revision 3
FIGURE IRR-F 1 Snubber Functional Testin Technical S ecification tfopoeec Tochnscal specsfscatson.~ IN@-ddoo, II.M. Ouctksito A~ schuencec. S/la/o41
~a(assr'eats S/4-. 7. 4 SSntddSSS
'OTTTOO COngmo>> sos Cpsaa~p s.7.4~ all snuooers shall oe opddadts.
apstscadlt~s OpsdaTTonat memons s. d. Sno l. OpsdaTTOwt ~fi':cps 4 cOHom oil so we I ~ y t fne atDAIV I L afQATt0tuL LOTTO': ulth One Oreareisnupoers InOOeraOle en any Syaten, vitnin Td nOurs replaCe er restore tne'neoes'sole snooper($ 7 to opBASLS sta us sn4 )erfsro an engsneering evaluation oer SoecIficatIan $ .7.sg on tha attacneo camsonent or oeclare tne at&C1eo Sys~'Inaoeraal ~ anC,fellev She aoprOor1ate ~ON Stains ftr QNt systen, susvf I. ~ ucs. Ssov Ndusvfs 4.7;4 Sech Snooper shall Oeioeoonstrstec OpddadLv y perforoancs ef the
. Ol lovingaugoentec. Inservl ca. Insoectson progrsn snc tne- reeuireeents of Specification 4.0.5.
4 ~sns .ir~nT oes
+aasuaacsln>thISS SPSCif'ICJtienl. tyoe~af Snooper Shall Oean~snuoparsr
- of'tho sane 4esign anc>nanufacturor, lrresoec Svelter.capacity.
Snuooers-are ooerstior. categoritec as Inaccessiole er a~sioi ~ curing reacar Seen of these gsouos (InaccassIol ~ anc accassiol ~ 1 wy oe. Insoactec Incaoenoantly accorcing to tne Scnecul ~ oelov. The first inservics visual InspectIon of eacn type of snooper Shel) oe perforoec after 4 eonths Out vithln 10 nontha ef csnoenalng POvgd Olddnflpll anc shall Incluce all Snuooers. Tf all snuuers of eacn type on any sys teo are faun4 opdpadts 4urlng t:w first inservice viswl Inspec:Ion, tne secono inservics vlswl Insoection of -wt systao snail oe per fosoec at tne fIrst refwl ing outage. Cshervlse ~ suoseouent visual Inspections of ~ 01ven systeoisnall oe perfosoec In accorcanca.vtth theifollouing scneoules SIISOOshahnn:-:Ipisr l. e ISL-T;l06.0 . 7' Rev is ion l.
~~<<~ ah>>4>>e <<>><<<<1 k>>)>><<<<a>><<as<<l>> ~ vls4.>><<w>><<<<4<<~ >> w<< ~ >> ~ >>~<< FIGURE IRR-9.1 (cont I d) Ecoposee Technical specification chance (PIP Dos, N,M, cuscss to'A Ccauencec, 5/lo/oal
'I PUKT SYSTEuS SU CE CEOVIEEuE>>ttS teshti huee ao. Ihooerso) ~ 5nuooers ef Each Type eh Ahy Syscaa
~-<< Suoseewnt visue I eer Inseam!eh ~ hs sct!eh Pariocvt aencna 1 2 aon>>as - E~
I C oentas 4 IS" 5,4 55a eays S,C,T CE eays z Z~ ~
~ or oars 51 eays I>>
VIswl Iasovcc!oh ae ratshev Cr!CPHC v1 swl Iasoections shall verify (1) t:>>c. '>>re are vis!bi IneicatIons of eaaace er Isis!roe OPEAACI>>LITT'. (5) cae teuneation er suooortInO strur~ ar~ts ne ~ are secure. ane (1) futaners ta for attacnaehc of cae snuooer co Qlt csnooneht.ahe ca cae shuooer actsracs are secure. Shusaere <<hiCn aooear Iheeerael ~ as a result Of viaual Iacpeaiena aay Oe eatarniaee OpEEACLv ter Cae Surpeae Of estaaIIsnihO 0>> neat viswl insoeriea Interval, prsvieinO Case: (1) cae cause of cae re)ectIoh Is clearly escaalisaec an4 reaeeIee. for eat particular snuooer ane for ether snuooars irresoecciw of type eh tnat systea chat.nay oe.Ocher!cally specs<<t!ol ~; sne (5) cne
~ ffactae snuooer Is functional'ly castac Ia cne as touae mneition ane eetaraihee opvdÃLv par spacitIcatIcps s.t.af. per >>se snuooers Ceaaen. Ca acre Caen One: Syatan, Cae OpflACECnT Of SuCn Stv>>cora Snail IN coasleeree Ih usooa'InQ. cao'surwi I lance'c'>>eul ~ tor esca ef cne rolaco4 systaaa>>
Trans! vent hsoor I eh' An ll Inspection shall oo parforaee of ~ snuooers,sr~4 co sec t1ons ot systoas tact save aaoeriencae unuoer>>ae, potantIally eaoag InO transients as eecarainee froa a revi ~ ef operational eats ane a visual InspeccIon ef cae systaas vita!a C aehtas tollovino sum an
~ vent. la aeelcion to satisfy!no cae vlswl inspect!en accaocanca criteria, treeeanwfwetion of aecnanical snucoers saall I>> verifiee uafhO at lout One Of Cae tell pvihcl (1) nanually Iaeueae Pe@acr
~ owaent; or (I) evaluation et I~lace snuooer piston set Inc; or (5) strocIno cae aecaaaical snuooet throu'ts full rshoe et travel.
Tl>> InspectIon Interval tor aaca type of sauooer on ~ oiven systaa sac)i aot ae Iengtaenee nore chan one suo at ~ tioe unless a Ceneric ortolan au peen 14ahcifi ~ 4 ane carrecceel In chat event tae Inspection Interval aay oe Iehctaehee one Sup tae first tine ane Cve staos ~reaftar It na Iacoeraai ~ snwoers ef that type are fouho en Coat syttaa. PTI>> provisions ef Specification 4.O.Z are nec aoplicsale. SOSOOE)IAaaa.- IOIST 1 ISZ-T-106 ' '7-.29 Rev.ision 1
FIGURE IRR-9.1 (cont'd)
'ysopoeed.Technscal speosfscatson chan9oi Isao. psh zzoo, N.N. curtis to.A. schvencoc, 5/18/oil PCANT ~5% 5 Su. I/NCT STCOISSNTNTS Csnsinvvol ~
FsHKciollal T~ scs Ourin9 uw first refuelin9 snusoswn and at least ence oer )8-nonchs thereafter Ourin9 Snutcovni 4- repreaentative SanOI ~ of snuooers shall Oa taatedluain9 One Of the fOllOvin9 Senal ~ Olana fe'r Oau Cyoe af snuooer. The~ sasol ~ plan snail oe solaced prier to the says oeriod and cannes oe nan944 ourln9 the sass period. The NNC le9ianal Acoin IitratOr anal) Oa notified in vritind Of the SanO'I ~ Plan I~ IOCsed prier co tne cast period Or the sandie plan used In the prior Cast period snail oe Iooleoentad:
- 1) At least 1P of the total of each type ef snuooer shall oe func tlonally tasted ~ Ither ilrP)ace er In 4 ooncn sass. Fer eaCh Nwooor 4f 4 syp ~ that does not ooe'c she functional tas's accede~
ance criteria of soecificstien O.T.af. an accitIonal~
<<'wt ./pe.of snuooer shall oe. funotfenally tasae until ne nore
~ of failurea are found Or unt11 all Snueeere et Shat tyOO nave peen funcsionally sostedi or
- 1) A representative SanOI ~ of ewe tyoe ef'snucoer"Snail Oe func t1onally castadiin accordance <<1th FI9uro-.a,T.4 L c Is the ~ ,
total nuooer ef snuooers ef a type found noc oeetIn9 ale OCULO v cence reeulrenensa,of soecifitat1on a.y.af. The.cwvlatIve numler 4f slwooors 4f 'a. cyoe Cascade'ls 4444'cad oy "lr, At che onc of"each csy's. Cessin Ie>nmv values of N and "- {pre vioua Cay' total plea C~nt'ay'S aiecwd'on'FIOurei a.y.z ) l~nsa) Shall Oe. If at any"Inei the point plot~, fallavin Shee SOIOCS reCICN all Sneoert Of Stat ./pe Snail Oei funcclonallyi tnssaa If at any tlm;cno: point platted falls In
",sho- Accept re914nr-cestin9.eflsnucoers of'chat type nay oe ~
unen Cheipoint plattadv11es: ln tho ContIIWO.Test 'arninated in9. replan; ac I ionol snuooers of tnat. Cypeishall oe.tested until the point falls: In sha ~act re9144 4l che zejoct radians or all cho Snucoere ef tnat typo. nave Oeen tasted. Tes in9 eouipnenc fa'livre curin9 functional cassin9 oay 'Invalidate Chat Oay's tastin9 and ~ llov that Oay'S teatin9 to reswo-anev
~ t a lasort1<<; PrOVidin9 ~ ll SNWOert taataa vith -W failed
~ oulsssenc curin9 tha day of acuipnent failure are rotassadl or
- 1) An initial reoresentat1ve seep)e Of 6 snuooers of aan type Snail Oe funCtiOnally Coated. FOr eadh Smnmer tyOO vniCn OOee not neet the funct14nal cess tcraptanca criteria, another sanol ~
ef ac least one half uw size of s:w Initial saopl ~ shall oe tasted untl) the total ncaoer tasted ls eoual to che InitIal Sanpl ~ 'SIZO Oultiolied Oy She faCCOr, 1 ~ Vz, vnere 'C IS the nlaaaer Of Snucaera feun4 vnICN 44 not neet Che funstionai SSSC accaosanca criteria. The. results~ flv>> tnIs sanol ~ plan snail oe Platted ualn9 an ACCSPC'ine vniCn fOlleva the eduatIOn N ~ SS(1 v C/1). Sech shunner point" should he<plotted as soon as Che Snuoaerle teated If'Cha POint PIOttad salle On sroelev che Accsos IInel sastIn9 ef tet type of snuooer aay oe Carol<< nassd. If the point plat.ad falls aoove.che Ac!sot" line, test in9;oust'ontInw unt11 the p4int falls In che 'Acceot 's91on Or'all chaa Snuoaarslof'that Sypeinavecoeen tasted susousNANNA <<ONST IS?-T-106 . 0 7-.30 Revision I
FIGURE ZRR-9 . 3 (cont ') proposed Technical spectftcation change Isee rlk 2104, v.u Artss to
~
A Sclwellcerr 5/14/oal SU LLSnCT SSOUIlf<<fuTS /contin<<eel The representative sasol ~ soledad for the func lanai test sano)a plans shall berrsndooly I ~ ledged free '>> snuaberi ef Ssoh type and revie<<ed before beginning tw tasting. The revie<<shall ensure-aa far as brac Ical that they are reoresentative Of the various can figuratIons, operating envirocaents. range ef s1 a, and caoacity ef snuooers of each type. Snappers olaced in tneisaoe lacatiens as snuooers <<hich failed the previous func foul test shall be retsstad at the tIOe Of Ihe naht funC IOnal taa but Shall net be inCI<<aad In the sandie plan. If during the funC:lanai tasting, aedItlonal saooling is reouired due to failure of only one tyoe sf Inuooer, tne functional tasting results shall be.revl~d at na t>ae to eater
~ Ine If soditlaaal I~les snould be 11 ~ Itsd ta u>> tyoe ef s>>cour
<<nich has faIIK the functIonal tasting.
fvnc.ionsl Test actvptsnee Critv<>snubber funCIenal tost shall veHfy ~JI4t; L) ac Ivstion (restaIning ac Icn) 's s .levee.<<I hin .e Csdifia range< in both tension and coeoressson;
- 2) Snwoer oleed er release rata ~ reouirec, Is present.in beth tanSIOn and ~reaaien, vi nin U>> SOeCified range; s) uhemreouired<< the fares reouired to.initIats er uaintain a)
~
notion af '>>rsnuocer is vI t1n s s self lac range in both
-directions of'ravel:
%%dr Inuooersr soecifIcally reouired nc,
- displace vnder continuous. load, a>>i ability. ef'tno snuoaer to, <<Ithstand, lead
<specified If tnese.results can be correlated ta U>>i speCI fled: paranetars through ~ s~llsneo eet'Nes ~
functional fest Sail ansi<<sis AniengineeHng evaluation*shall Inoperableoe naos of each failure to eeet the functIonal test accaotanca criteria to eetaruine the cause of the failure. Tho results of this evaluation shall oo used. If applicable,
'In soled Ihg 5INt5srs to be tasted In an effort to cataruIne t>>
opQASTLTTT sf at>>r snuabers Irresoec:Ive of type <<nich eay oe subject to the sane failure aoda
%%dr the snuooers found , an engIneeHng evaluation shall oe perforoed on the coopenents to <<nich the ineoeraol ~ snuoberi are attached Tl>> purpose ef this engineering evaluation Ihal'I be to dataruine If the coeOonents to <<nich tha Ineperabl ~ snubeere are ataoad vere adversely effaced by >> Inoperability of be snuobeH In arear to ensure thee the cow>>nant reoalns caoabl ~ ef oeetIIvf the designed-service.
SUSUUQIlINA ~ UNIT ISZ-T-406 0-Rev is ion l.
FIGURE IRR-9. 1 (conti d) rropooed Technscal SpecSSScation Change (See rD 220$ . H.'N. Cuesta to
- l. Schuencec, S/1$ /sal QtSVT isucv lepIITSvuPITS C htinvoel lf any snuooer selectee for func:lonal teatime eitner fails w, loot up~or failS ta OOVe, I ~ ~ . fresco I~lass, thecoauae vill he.
~ va)wtao anoiif causao Oy oanufacarer er Oeaipn oeficiency all snuooers of't>> sas>> type IupjeC tO tne Sane Cefec: shall oe func.
tionally teston., This tastlnc reouireoent snail oe Inceoeneent ef tne:recuirenents statac in SoecifIcstien a.l.ae. for snuoaers not ooetinc the functional test acceptance criteria. Sync.ionel Testi of Seoairve sno Seolscee Snuooers snuooers vnIa fail tne visual InsoectIen er tne functional tait acceotanca criteria shall ae reoairec or.rsolacec. Aeolacenent snuooers anc snuooers unicn have reoairs.vnicn nisnt affect ther functional test result snail oeitastac to neet ee func:ional test Criteria,hefare.inatallatian in tne-unit. netanisal SnuOOerS Sna'I'I net tne<aCCSOtance triter'uoseeuent to JNIr'cost recent nave service. and'tnei f~fmt1on test oust nave peen oe~ vIthin'~2 eentne Oefere acing'InatalieC In tne uni nuooer.So~ice I<e aeoIaceeent S . se r TheSSerVICez life>Of all Snuooere; Shall 5e aenitereo. ta secure that tne~ierVICa I l feil a not'atee>>C. Oe~~n~ Sur vei I lanoe inSOe. Iona.
- The.eanieun eaeeotao SerVICOvlife fer VarIOua scale. SarinCS. ano et!'ec critical para snail.oeicetefnil>>o~anc estaol isnec casao en
~ncineerin0 InfornatIen~anc shall so~estanoao er snerteneo aasec on
~ onitorec. tact: results. ancsfeilurei nistory. Critical para snal l. he i replaoaSSVtnatstne+naainl>>s SerVI Cat life vill net Oe "enteeeau'.Curing
. ~."a: perieu,vnen tne SnuaaeriIS~reouiree~ta'Oe~0pSSSSLS. Tha peru replacenentassnal1 oo cocs>>entac anc:the cecaeentation/snail oe retainec in accorcance elm Soeciflcatien ~ .10.2.
SIISCIIaweln,.-lpIST l. ISI-T-106;.0 Revision. l.
'<<<<4a<<a<<a ssvss~ s ~ M<<~I .Ik+<<s<<~ I acr o ~ s FIGURE IRR-9.1 (cont'ci) pcopoaec TechnlcaL Specification change <see ptA 2104, R.ss. cssrcia to a Chhsencers S/1d/44) 10. M~KCT s CGA s ssvvsK TESTING'CCEPT 10 20 30. 40 50 60 70 SO SF 100 N F!CVlE 4,7.4~1 SlfstLEsFLAII Z) FOl QQECER f!NCaaClSal, W~
'S'I'-'T.-1,0 6, ~ 0 '7'-33:
Rev ia ion 1.
~s
RELIEF REQUEST NO. IRR-10 I ~ IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS ISI'lass '. pressure retaining welds in .piping are the subject. of this relief request. PP&L has chosen the; allowed 10CFR50.55a(b) (?) (ii) option to use. the 1974 Edition through and including Summer of 1975 Addenda: for Class 1. weld selection, Relief. is requested. from the requirements of Tables IWB-2500 and IWB-2600 of the 1974 Summer 1975 Code in the following areas: L..) Zt= is unclear whether inspection schedule requirements are to be taken from the 1974 Edition through and. including, the Summer 1975 Addenda or later.. editions,,='and. q4 A 2". )" Table IWB-2600,:.- specifies" examination methods which have since been changed. in later Code editions and addenda to methods. more appropriate for the component being examined (e.g.. ultrasonic. examination vs. surface examination for small pipe welds and thin wall pipe) . BASIS FOR RELIEF 1..) Since: 10CFR50 55a(b).(2) (ii) does not specifically reference. the use. of'aragraph IWB-2'420(c.), it is uncertain, what. requirements're to. be applied;. Relief is being, requested to utilize the ISI-T-106. 0 7-34 Revision
RELIEF REQUEST NO. IRR-10 (cont'd) provisions of Table ZWB-2500-1, Note 42 of the 1980 Edition through and including the Winter 1980 Addenda. This note states that the- welds initially selected for examination during the first interval shall. be re-examined during subsequent. intervals. Re-examination of the same welds, combined with a focused weld selection (-whereby welds are selected that have a higher probability of failure that others) is more likely to detect incipient generic defects. In addition, examination of the same welds each inspection interval permits- meaningful data trending. not possible when different welds are being examined each interval. ~
~
pw
~
Z ) By .uti1izing; the'lass l. weld. examination methods from the 1980 Edition through and including the Winter 1980 Addenda, a more conservative overall approach is taken. The only exception is for piping greater than 1" NPS.and. less than 4" NPS where a surface exam is specified as. opposed to a volumetric exam. Attempting to perform volumetric" examinations on these welds is impractical due to weld configuration and/or wall, thickness All. other exam methods. are either more. conservative or the same between the two Code years. ISI-T-106 .0 7-'35 Revision 1
RELIEF REQUEST IRR-10 {cont'd) III. ALTERNATE PROVISIONS 1.) Class 1. welds will be selected based on the following, focused selection guidelines. The. welds initially'elected: will be re-examined.'uring, subsequent inspection intervals.. a) Terminal ends in pipe or, branch runs connected to the reactor vessel ( pipe to safe-end welds). b) Terminal ends at. the reactor coolant pump.
.c) Terminal ends at; containment penetrations'.
"d) TerminaL ends at".pipe..support anchors.
S,
~i ei) i Welds'ith a cumulative usage factor greater..
than 0'..4 f) Welds with the highest stress intensity ratio. N It is important to note that this is guidance and not mandatory weld selection cr'iteria; Deviations from these guidelines. may be necessary- to avoid. selecting, the- same corresponding weld: on each loop of a multipl'e
.loop system,. and, to. avoid'. selecting, numerous-
/
- welds'- ad'jacent. to one-. another. In addition,,
welds- that. are inaccessible and/or are. of.. such. design that meaningful ultrasonic data is not possible,. will not be selected.. . ISI'-T.-'1.06- ~ 0 7-36 Revision l.
RELIEF REQUEST NO. IRR-10 (cont'd) 2.) Class 1 welds wil'e examined per the examination requirements found in Examination Category B-J, of Table IWB-2500-1, of the 1980 Ed'ion with Winter 1980 Addenda.. IS I-T-106. 0
~ 7 37 Revision. 1.
RELIEF REQUEST NO. PR-ll Z. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL. CODE REQUIREMENTS Susquehanna SES Unit 41 RPV circumferential shell. weld "AD" and. longitudinal shell welds "BK" and "BM" cannot be completely examined per. Section'I Code Requirements ASME Section XI Examination Category B-A requires 100% volumetric examination of all circumferential and longitudinal. shell welds (Figures No. IWB-2500-1, 2) during; the first ten-year inspection interval. Pennsylvania Power and Light, requests partial relief from the. Section- Xl .examination requirements. for weld seams "'A'D,. BK and. BM".'ue to plant design. 4 BA'SZS 'FOR RELIEF'n RPV insulation support steel ring, girder is located fram approximately 8.25 to 10.0 inches above weld "AD"', thereby limiting the available scan path for inspection of weld "AD" and precluding access. to portions of welds "BK" and "BM". Due to obstruction, approximately 20% of weld AD and 78% of: BK/BM cannot be examined by manual. or remote automatic- inspection techniques. rZI.. - JUSZIEICATION-
/
The: -justi;fication;- for requesting. re1ief-'rom ASME. Section XI Examination Requirements is as follows-: ZSZ-T-106..0 738 Revision- 1
RELIEF REQUEST NO. IRR-11 (cont'd)
- 1) Plant modification to provide adequate access for the inspection is impractical and imposes undue hardship in the form of extensive plant modification and. ALARA exposure.
2') The. accessible areas. of the weld. and: required examination volume. shall be examined to provide evidence of continued integrity.
- 3) The Class 1 system leakage test is required each refueling outage; system hydrotest is required each inspection interval.
IVo ALTERNATE PROVISIONS The. remote automated,.-equipment. has been modified to accomodate. a. specia+45. ':wedge: to" increase. examination. ik ~ coverage on; weld.AD,',80" coverage of: weld. "'AD" includes an additional. scan wi'th the- special
) . No alternate exam prov isions can be speci ied 45'edge f
for welds BK/BM. IS I-T-106 ..0 7"-39 Revision 1.
SECTION 8 . 0 INSERVICE INSPECTION AUGMENTED COMMITMENTS FOR SSES'NIT ISI-T '106' 8-1' Revision 1,
so AUGMENTED COMMITMENTS In addition to the requirements as specif ied in ASME Section XI, Pennsylvania Power 6 Light has committed to meet, the inspection. requirements contained in the following documents: A.. NUREG-0803 - "Integrity of BWR .Scram-Discharge Piping"' Referenced in letter PLA-987 dated December 29, 1981 From N. W. Curtis to A. Schwencer B. NUREG-0313, Revision 1 "Material Selection and Processing Guidelines for BWR Boundary Piping Coolant Pressure" Referenced: in letter PLA-927 dated September 15, 1981 From N W. Curtis to A. Schwencer C. NUREG-0619 "BWR Feedwater Nozzle- and Control Rod Drive Return Line Nozzle
'.Cracking" Referenced in letter. PLA-1075 dated May 3, 1982 From N. W.. Curtis. to A.. Schwencer D" FSAR Article- 6 '6.8 Volumetric examination of-high energy piping between containment, isolation valves.
ZSI.-T-106 0 8-2 Revision 3
9.0 REFERENCES
9.0 ~ 1 Regulatory Guide 1.26, Revision 3, February 1976, "Quality Group C'assi=ications and Standards for Water, Steam, and Radioactive Waste Containing Components of Nuclear Power Plants". 9.0.2. Code of, FederaL Regulations, Tit'le 10, Part,50". (10CFR50); revised January 1, 1981, modified by Federal. Register. VoL., 46, No. 251, dated December 31, 198K, pgs. 63208 and 63209. 9 .0 .3 10CFR50 .2(v), as of January 1, 1981 . 9 ~ 0.4 Standard. Review Plan (NUREG-0800) for She Review of Safety Analysis Reports for: Nuclear Power Plants, LWR Edition, U.S. Nuclear Regulatory Commission Specif ically Section 3. 2.2. "System. Quality Group Classification" Rev.ision 1., July. 1981'... r-9 0 5 Regulatory Guide 1'.. LZ. Instrument Lines Penetrating Primary Reactor Containment (Safety Guide 11,, March 10, 1971) Supplement to Safety'uide 11, Backf itting Considerations, February 2, 1972. 9.0.6 Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edit:ion through and including the Winter 1980 Addenda. 9 .0; 7 SSES Unit 51 Final. Safety" Analysis Report, (FSAR)
/
'Revision.- L'August1978,. through.. Revision 32 December 298.?"..
9.0.8 Generic. Safety Evaluation Report (NUREG-0803) Regarding Integrity of BWR Scram System Piping,. U.S Nuclear Regulatory Commiss ion. Published.: August, 1981. IS I'-T-10 6.' Revision 3
PP & L ' CODE CLARIFICATIONS The notes included 'n this section define PPGL's interpretation of Code requ'rements that may be ambiguous.. Each Code requirement subject to clarification is described by a separate note.. The note: numbers are referenced in the ISI Summary Plan, Table 6. 0-1 in the Remarks column. ISI-T-106 0 10-1 Revision 1.
NOTE SECTION XI REQUIREMENT: Examination Category B-E, Pressure Retaining Partial Penetration fields in Vessels. The Code requires a visual (VT-2) examination of the external surfaces. PP5 L INTERPRETATION: The Code does not specify whether the visual. (VT-2) examination of the external. surfaces shall. be a VZ-2 examination of the partial penetration weld external surface or the vessel external surf'ace. PPaL will, perform a VT-2. examination of the vessel external surface. The extent of examination is illustrated in Figure 10 .0-1. The. external. surfacem of the partial penetration welds shown. in., Figure. 10'-l., are, inaccessible for, examination., Evidence- oC leakage from. the. partial penetration welds: can be obtained by performing a VT-? examination of the vessel external surface. The VT-2 examination of the vessel external surface performed by PPEL will satisfy the intent of the Code. ISZ-T-106 0 10-? Revision 1
~ e
~ e ~ ~
<MIR5 hW L
NOTE 2 SECTION XI REQUIREMENTS: Examination Categorv B-F, Pressure Retaining Dissimilar Metal Welds and Examination Category B-J, Pressure Retaining Welds in Piping. Examination Category B-F and Examination Category B-J have duplicate examination requirements for: dissimilar. metal pressure; retaining welds in piping,. I While a. nozzle is the part; of a vessel designed for piping connections and a safe end is made of piping materials, the Code does define a transition point between vessel and piping components. Specifically, the Code does not define whether a, vessel nozzle to safe end weld is a. piping weld. PP&L INTERPRETATION: Dissimilar. meta3 nozzle to, safe-end welds and. dissimilar metal, piping'elds- will come under the jueisdiction, of Examination: Cat'egory B-F,. only., These welds. will. not-. be. included; in Examination Category B-.J. Similar- metal nozzle to safe-end welds and similar metal piping welds will be subject to the examination requirements of Examination Category B-J. Similar metal pipe to. safe-end welds will. be considered terminal ends for, the purpose of. weld selection. ISI'-T-106 <<0 10-4 Revision l.
( NOTE 3 CLASS 2 WELD SELECTION WELD QUANTITY DETERMINATION The quantity of. Class 2 welds to be examined. in the first: ten-year interval. is determined, by application of. the following,: steps = a) Determine which portions of: Class.- 2 systems, are single; stream vs.. multiple.- stream ( piping lines of the same. size, geometry and function that perform redundant functions).. b) For. multiple streams,. the average number of welds F per.. stream is theequivalent of, one loop". c.), In. systems. which- circulate. reactor. coolant, 25% of the welds. on: a'..single. stxeam or the* equivalent'f P
~.
, one. loop. shal3 k
be..selected:. for:.examination. in
.-.=accordance. with.:the" guidance. provided in Section.
II') In systems which circulate other than reactor coolant,, 12.5%,- of the welds on a single stream or the equivalent; of. one loop shall, be- selected for. examination in accordance with the guidance provided. in Section II.. e:) Eor- multiple: streams',. the number: of. examinations.
,sha13'e. spread'qually'o.-the: extends practical.
.among,'each. of:. the streams;.and: if th'e =number of.
1 Pipe. to pipe welds that are at structural. discontin-uities and dissimilar metal pipe to pipe welds shall be included in the weld. total. All. other pipe to pipe welds shall. not be included. 0
'SI-T-.106.
Revis'ion 3
areas subject to examination in a specific category is less than the number of streams, at least one such area shal'e examined. SPECIFIC, WELD SELECTION GUIDANCE Once the. quantity of welds is determined, specif ic. weld. selection. is fran. among the. foll'owing,: a) Welds at. locations where the. stresses under, the loadings resulting from Normal and Upset plant conditions as calculated by the sum of Eqs. (9) and (10) in NC-3652. exceed 0.8 (l.2Sh +. SA); b), Each, type of terminaL end. in each system will be selected., Zn. the Core. Spray system, for. example, '0 there is- a; total:-of, 8. terminal. ends corresponding each. pump .
'F, to- the.- suction; and. discharge attachment welds on Examining., al1 eight: terminal ends would, be," redundant;. and.'-- skew; the examination. sample to those. particular.- welds A: more. meaning ful examination program would result. from selecting only one pump suction and one pump discharge terminal, end. for examination.
Terminal. ends are identified at.'ystem anchor points, vessel, and pump. connections, and penetrations. 'ontainment. c) D'issimilar'etal. Welds d) 'Additional. welds; at. structural.. discontinuities; to achieve. the. required'ercentages- identified in Section I.. These random welds. shall be the higher ZSZ'.-'T-,l06. 0. L0-6 Revision l. 4
stress welds that remain to be selected which are not located adjacent to welds selected under a, b, and c above. Examinations will be performed per the examination requirements of Table IWB-2500-1, Examination. Category C-'.- of'. the 1980 Code Edition through. and: including- the. Minter 1980 addenda (Footnote 1 excluded).. IS I'-'T-10 6 0 '1.0'-7' Revision. 1.
NOTE 4 INTEQPALLY WELDED ATTACHMENTS Integrally welded attachments that are not loaded during Normal or Upset plant conditions will not be included in the. extent of examination.. Insulation lugs, lifting lugs, and. other types of. integrally. welded: attachments that. are. not part of a. support component and'ntegralLy welded attachments, associated with pipe whip restraints vill. not be subject... to the: requirements of Examination Categories. B-K-L or C-C. rsr-T-106.0 10.-8 Revision L}}