ML20094M274

Submits Clarification of Second Interval Inservice Insp Program Relief Requests,Submitted Via Util . Updates Attributed to Use of Improved Exam Equipment, Advances in NDE Technology & Selection of Components

ML20094M274
Person / Time
Site:	Peach Bottom
Issue date:	03/19/1992
From:	Beck G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9203300226
Download: ML20094M274 (33)

Text

- _ __-__________ __ _______ __

t .

10CPR50.55a(g)(5)

I'llll ADEl.l' illa ELECTRIC COMI'ANY

, NUCLhAR GROUP llEADQUARTERS 955 65 CHESTER11 ROOK llLVD.

WAYNE. PA 19087 5691 (215) 640-6000 NucW:AR 1:NGINEl-RINO & $1 RYlCES IDAR1MLNT March 19, 1992 Docket Nos. 50-277 50-278 License Nos. DPR-44 DPR-56 U.S. Nuclear Regulatory Commission Attn Document Control Desk Washington, DC 20555 SUBJECT; Peach Bottom Atomic Power station, Units 2 and 3 Clarification of Second Interval ISI Program Relief Requeste

REFERENCES:

(1) Letter from G. A. Hunger (PECo) to USNRC, dated November 15, 1990 (2) Telecon between PECo and USNRC Staff, dated January 10, 1992 Dear Sir In the Reference 1 letter, Philadelphia Electric Company supplied a revised edition of the " Inservice Inspection (ISI)

Program Second Ten Year Interval" for Peach Bottom Atomic rawer

' (l Station (PBAPS), Units 2 and 3. As part of this transmittal, seventeen (17) Relief Requests were submitted for information or review and approval. In the Reference 2 telecon, additional clarification regarding four (4) of the seventeen Relief Requests was requested. In response to this telecon, attached are updated copies (Revision 1) of the four Relief Requests.

The attached document contains the clarificarions g requested during the telecon, and additional updates resultifig from review of the latest examination date. The original Relief Requests (Revinion 0) contained in the Reference I letter were primarily developed from examination data obtained from the first ISI [

Inspection Interval. Since that time, subsequent ISI examinations and physical plant changes occurred which have yielded updated examination results. These updates can also be  ;

attributed to use of improved examination equipment, advances in NDE rechnology, changes in selection of components subject to examination, and clarification of examination results.

Because of these changes, the remaining thirteen (13)

Relief Requests submitted in the Reference 1 letter have been

((

b 92033OO22f 920319 (

PDR ADOCn 05000277 l P PDR

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Pago 2

• Peach Bottom Atomic Power Station, Units 2 and 3 Clarification of Second Internal ISI Program Re,11of Roquests reviewed. Hocessary changos hevo boon identified in an additional throo (3) of thirtoon requests (RR-4, RR-6, and RR-14). Revised copios of Rollof Roquests RR-4 and RR-14 are attached. Rollof Roquest RR-6 is still under review and WJ11 bo submitted by April 17,1992. In accordance with 10CFR50.55a(g)(5), we will continue to develop or reviso the ISI Relief Roquests as situatione dictato.

Summary of Changes to PBAPS 2 and 3 ISI Relief Requests Rollof Hoquest RR-05 Additional Information Requested Does the percent completo information portain to surface or volumetric cxaminations completed? Additionally, identify the ASME Code Item Humber associated with each component examination-listed.

Response

.The percent completo information for volumetric and surface examinations has boon added to Tablo RR-05-1 and RR-05-2. The ASME Code Item Numbers have also boon added to the Tables.

The following additional clarifications are being provided to this ro11of request:

Tablo RR-05-1, Unit 2:

1) Examination coverage has been increased for two components (1-B-7LD & 1-D-12).

i

2) Four components have boon doloted Lince subsequent examinations have achieved Codo required examination coverago (1-B-15, 1-B-15LU, 1-C-15LU, 10-IA-2).

3) Four components have boon added to the Relief Request (1-D-7LD, 10-IB-15LU, 10-IA-15LU, 10-0-35LD).

Tablo RR-05-2, Unit 3:

1) Examination coverage has boon decr ased for one component (1-A-7LD).

2) Two components have boon doloted sinco subsequent examinations have achjoved Codo

Poach Bottom Atomic Power Station, Units 3 and 3 Pago 3 Clarification of Second Internal ISI Program Ro,11of Roquesto required examination coverago (10-IA-14A, 10-IB-14B).

Rollof Roquest RR-07 Additional Information Roquestod Does the porcent completo information portain to surface or volumetric examinations completed? Additionally, identify the ASME Code Item Number associated with each component examination

- listed.

Responso This Relief Request has boon doloted and is therefore withdrawn. 10-21186-13 is an Examination Category C-F Item No.

C5.11 componont. This component requires a surface examination only, which has boon completed in accordance with Code requirements.

Rollef Roquest RR-13 ,

Additional Information Roquestod a) Why are the examination coveragos small relative to the Code required oxemination volvmo?

b) Why is the 45 degroo para 1101 scan impractical?

c) Why is a bottor examination coverage achieved with the 60 degree transvorso scan versus the 45 degroo transvorso scan?

-Responso a) Overall examination coverages are low due to the barrel type nozzle configuration which restricts the examination scanning to one side of the wold. The one sided examination is further limited by interferences of tho-scanning equipment with nearby components.-

b) The 45 degroo parallel scan is impractical because-skowing of the 45 degree transducer (to examino the subject wold metal at the-nozzlo inside surface) during the parallel scan would cause the sound beam to be-directed noarly perpendicular (transverse) to-the weld conter11ne. This would rondor the examination inoffective as a parallel scan.

c) Sinco examination is only possible from one side of the wold,-the 60 degree transverso beam will scan the largest

-w--v+ , - , , ,..,..---.,,-,.,.n-~, . n n- nn - ,,w.. ,.,r, --a, ,,,,...,.,,-..,---,,..,---,,w,-n,- -.-. ,-,c- , ,, ,w. , , , , - ~ - , -- -

Pago 4' Peach Bottom Atomic Power Station, Units 2 and 3 Clarification of Second Internal-ISI Program Ro,11of Roquests .

r portion of the Code required volume, as depicted in the drawing F

on Attachment 1.

As.an additional update, thia Rollef Request has boon

, expanded to define specific examination coverage for each nozzlo previously examined. Originally, generic coverages woro provided for each group of nozzlos. All examination data portains to volumetric oxaminations, and is the maximum offectivo examination coverage which can be achloved given the noLzle configuration. Attachment 1 providos a diagram of the nozzio to vessel weld configuration, along with an indication of the maximum extent.of manual coverage.which can be achieved versus Code requirements. As indicated, the 60% transvorse scan produces the maximum coverage of the Code required volume.

Relief Request RR-15 Additional Information Roquested Provide a diagram which will support the request for relief from performing complete examinations.

Rosponso Attachment 2 contains a sketch of this pump support

• configuration.  :

As an additional update to this relief request, the extent of examinations completed has been reduced from 50% to 20%. -

This reduction in coverage is the result of a plant modification which added reinforcing plates to the original pump support

-structure. -These reinforcing-plates cause three-of the four i reinforcing rib attachment welds to be inaccessible for surface >

examination.

The Following Additional Updates are Being Provided i

g Relief Roquest RR-4 The-wording in the " Alternate Provisions" section has been revised to more closely reflect the Plant Technical Specification wording regarding allowable Reactor Vessel pressures and temperatures. ,

Relief Request RR Code Cases N-460 and N-461 have- boon deleted from this-Relief Request since they have been adopted for use per Regulatory-Guide 1.147.

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-_....~____._...a_..__

4

^

Poach Bottom Atomic Power St.ation, Unita 2 and 3 Pago 5 Clarification of Second Int.ornal ISI Program Ro, lief Roquests Those revised Rollof Roquests will be formally incorporated into the ISI Program Specification following the completion _of their review by regulatory authorities.

This letter was originally due to tho Nuclear Regulatory Commission on-March 13, 1992. In a tolophone conversation with the Nucioar Regulatory Commission Project Manager (R. Clark) on March 11, 1992, a one wook extension to March 20, 1992 was granted.

If you have any questions, please contact us.

Sincoroly, Apf,, Bock b George J.

Manager Licensing Section cci J. J. Lyash, USNRC Senior Resident Inspector '

T. Martin, Administrator, Region I, USNRC f

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Specific 4tbn

• M 733,lyv. 0 PilAPS 2 A .1 151 l'ropam Appendis A 4 i Pare 1 of 2 Itl'.l.11;l' It1;Qt?lM No. It1b04 lievision 1 l

1. l!21M13ElC6111N .iLCOMl'ONIEffi All ISI Clau 1 pressure- retaining comp <ments, Code examination Category Il P, item Numbers 1115.11,1115.$1,111541 and 1815.71.

I1. [11Ql1,JiliQtilRERiiNTS

.  ! El(OMlVJ!!![1littillli!LifLl!!iQlill4lfj]

a ASMll Section XI 1980 lidition Winter 1981- Addenda, Code Category 11l' requires that a systun hydrostatic test of the pienure retaining components within the systern boundary be performed once per irnervice inspection interval, in accordance with the agsplicable system preuure test requirements of IWil 5000.

Itclief is requested from meeting the hydrottatic test pressure as required by Table IWib52201, "l'ett Pressure *, (i.e.,1082 psig at 212'F).

Ill, JMh]S 1;OlLJllit llili PilAPS Plant Technical Specifications require primary contain'nent intepity be

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tnaintained whenever the reactor water temperature is above 212 depees Fahrenheit and fuel is in ll.c vessel. Primary conininment integrity requires the drywell- to be intact and all automatic primruy containment isolation valves to be operabic or deactivated in the isolated position. Ilowever, to facilitate visual inspection of the reactor prepute vessel head flange and head spray nonic areas, the drywell head must be removed. -Therefore, a complete Code hydrostatic test cannot te performed at reactor water temperattires above 212 dettees Pahrenheit.

Per Table IWib52201, a test temperature of 212 depecs l'abrer'icit corresponds to-a i

test pressure of 10S2 psig. PilAPS wouhl hke -to ennduct the hydrostatic test with all relief valves in plaec and perform the h drmtatie 3 test at a pressure 30 psig below -

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Sguifu ntion

. M 7.13, Itet. 0

. I'll Al's 2 & 3 ISI l'iort.im Appendis A 4 parc ? ef 2 Ill'1 IIT 111 Qtil:S! NO. Illt 01 (CONlit) linition l l the Imvett itlid vahe setting ( t his setting is determined at the tim: of the hydrostatic test based 'on the s no '.1 current relici vahe l'etah test data ) Garring and/or rtrnosal of the four (4) luctt tct ietief vahrs is costly in teth nitical path time and pctmnnti ty osure and b imptactical for a irlatively small incirase in picuure to snect ccJe requirementt (10s2I nig u.1075 i 11 psir) lY. blil l l@61'I' PPsOYlSIUISS code category 11 P bydrostntic testing will t.e paronned at a test pressure approxirnately 30 p*Jg 1.elow the lowest verifiable tehti valve $ct point, nominally 1075 i 11 psig (aesuming l'ench test data of 1105 psig for the lowest relief vahe se t ting), and'at the applicable

• Safe Operating 1(cylon* test ternperature determincd from the plant 'lechnical Specificatinm,1:igote 3 (..l.

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Specification bl 7.0, llev. 0 PilAPS 2 & 3 151 Prortain Arlendia A 5 s l'are I of 5 Iti:1111 Ill'Qt T SI N O. Illt 05 liesi* ion I l

1. .lDl XI.lilCA'l;i9M f Ol l OhlEON M E ist Class I prenure :ctaining u tids in i,iping imluding circumferential and lonpitudinal wtids, bramh t ipe (onnntion utids and mdtt utids, Code l'samination Category ll J, item Numbces 119.10 through 11%10 inclusive.

11. CODit IWQttllti MI:NIS 1:ltOM WillCll 111:1.1F1: Is iti QUl:r.TilD ASMit Section XI 1950 l'dition Winter 1981 Addenda, Code Category 113 tcquires a volumrtric and/or surla,e ruuninntion of enentially 100% of the weld length of all veinted circumfriential, nod lonritudinal u tids, bran..h pipe connection welds and sodel welds during the second insenice inspection interval.

Itelief is reque.ted imm perform:mcc of a complete eta'nieiation of the Code ~quirnt arca! volume of the weld due to Innited accessibility as a result of plant desir.n, tomponent configuration and/or metallmf cal i or environmental restraints.

i 111. J1 AS.lS_10ll Illil IFF The affected welJs are individually detnited in Tnble Rib 051 for PilAPS Unit #2 and in Table Rit 05-2 for l'IIAPS l'oit //l The examination covetarr indicated is the maximum practical without undue hardship to Pil A PS. Increar.ed examination c ovciare is not pos<ible without costly plant iederir.n/inodification and/or encuise personnel exposure.

Pattial examinations and examination of other similar selected uchh in the system provide reasonable assuiance of acht stimtural intepity. In addition, the alTected

Specifiention M.7.1.1, llev, O

+

1'llAPS 2 & 3 151 l'mr. tam Appendh A 5 Vaye ? of

• It1:111:1 Iti QlilNI NO.11Il 05 (CONil).)

llevision i {

wehh aie subject to Code Inamination Cateroiy ll l' requiremcnts and are visu.dh examined during 5:,st:m puuuie toting throughout the inte: val IV- dill .I SINYI I/_I_'!$NSSI9bS ror circorniciential welds where candnation is completriy impractical (cumination 0% c ornplete), nn additional Code Calerary 11J uctd will l>e rdected for exarnination.

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Specification

. .- M.73.1, llev. 0 PilAl'S 2 & 3 151 l'rogram Aprendix A 5

, l' age 3 of 5 Iti:Iil:I' Iti: QUI'ST No. Illt 05 (c0NID.)

Itevision 1 l TAlli.F, Itll 0EI, UNil' #2 EXAMINATION

/\lMA 111 SYSTF.M/ l.lMillNO  !!XAMINATION ltXAM CAT /Ofkl, goNrlGURElil]h' J CONDITION U COMI'Lir1JJ 1117 Main Stearn/ Accen limited due 86 %

11 J 119.11 Tec Pipe to pipe support volumetric l components within the examination area 1Il7LD Main Steam / Accen limited duc 35% cach 11 3, 119.12 lengitudinal to pipe support surface &

Scam Weld components within volumetric the examination area 1118 Main Steaml One sided 70 %

ll J,119.11 Pipe Cap examination due to volumetric l rnaterial and/or design configuration with phys: cal plant obstructions on remaining side 1118LU Main Steam / Accen limited duc ' 0%

.- Il J,119.12 longitudinal to pipe support surface &

Scam Weld components within- volumetric the examination area -

l 1D9 Main Steam / Access limited due 50 %

Il j,11911 Pipe-Elbow to pipe support volumetric l components within-the examination area 1D9LU Main Steam / Accco limited due 0%-

lengitudinal to pipe suppmi surface &

11-J, 119.12 Seam Weld' components withh. volumetric ]

the examination aren

• Specification

- hl.7.tJ, iter. 0

• l'lIAl'S 2 A 3 ISI l'mgram Appendix A 5

. l'are 4 of 5 1:1.1.11:l' ill,Qll!'51' No. Illt.M (CONil).) ,

llevision ! l 1 A1)] I _11! U E L LC O N Iin UNil' #1 liXAhilNA*110N AIUM_lj)b SYS'l Lhl/ l.lM'" NO  !!XAhllNATION ILXAhLCKIRillhL f0Emil11MIlW3 OLNL 9 ILGlhlEIElli 1 1) 12 hiain Steaml One sided 40 %

ll J,119.11 l'ipe Valve c$ amination due to solumetric material and/or design wnfiguratien with physical plant obstructions on re!!)nlidng f.ide

11) 7LD hiain steam / .- Accen limited due 45% each 11 J,119.12 . l Amritudinal - to pipe support surface k -

Seam Wcld components within volumetric the examination nrra 10 Ill 1$LU llesidual llent - Accen limited due 10% each 11 3, 119.12 llemoval/ to pipe support 6urface &

longitutinal components within volumetric Seam Weld the examination area

. 101A 1$LU ltesidual lleat Access limited duc 10% each 11 J, !!9.12 Itemovall to pipe support surface & .

Longitudinal _ components within volumetric Seam Weld the exainination area 10 0 451 D Residual lleat . Access limited due f 6% each 11 J,119.12 1(crnovall to penetration surface &

longitudinal volumetric Scam Weld E

l

Spc cification bl.7.1.\ Itev. 0

, I'llAPS 2 & .1 151 Piepam Appendin A 5 Pare 5 of 5 111.1.11:1 lil'.QUl'.S l NO. Illt-05 (CONI D.)

lievision I {

glli l'. Itit 05 7 UNil #.1

!!X AhllNN1 lON Altt:A 111 SYS~llibl/ 1.lNitTINO l X AhllNATION CONDilION *L.C1Q11'l 1r111

)$ Alii'Nhlilhl CON 1 lGlil(N1 lo N

1. A.?! ]) hia!n Steaml Access liinited due 50% each II.J 119.12 l ongitudinal to pipe support surface &

Seam Wtld components within volumetnc the examinniion arca 1117 blain $ttam! One-Sided bbU l

!!.j, 119.11 Tec Pipe exainination due to volumetric I inaterial and/or de',irn configuration with phpical l'lant obstructions on iemaining tide 1 1171 D hiain Steam / Access liinited doe F<'a cach ll.), 11912 1 onr,itudinal to pipe support surface &

Searn Weld cornponents within volumetric the examination atra i

n e

Specinc.ition hl.7.1.1, ller. 0

. l'11Al'S ? A 3 151 l'aepain Appendix A 7

, l'are 1 of 1 111 1.11'.1' lll'Qlll31' NO.111107 lieviion I ikkte 1 i

e M

_ _ _ _ _ _ _ _ _ . _ _ _ . - _ _ - _ . . - - _ _ _ _ - _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ m'

Specification M 733, Itev 0

• l'llAl'5 2 & 3 151 l'rogram '

A[tendit A 13 4

l' age i of 8 Ill:1.ll;l' ItEQl!!$1' NO lill 13 llevision i l

1. JDFN11BCATION OF COMl'ONIY1]i 151 Class I full penetration noule to senel utids in the reactor pressui. vessel, Code thatnination Category D D, licm Number 11.190.

11. [ODILlyiQ1]lRiihjlW))L!)10M WIllCl! lll!L1111' 11 !KQUliSJJiO

_ L

-- ASMll Section XI 1980 Edition Winter 19S1 Addenda, Lode Category 11 D requires volumetric examination of the noule to vessel welds (full penetration) of all nonles in the tractor pressure vessel during the f*ccond inservice inspection interval.

Relief is requested hom performance of a complete ctarnination of the Code teckuired volume due to access teatrictions as a consequence of plant design and/or component cenfiguration.

111. jnSIS FO)LjLillllilj PIIAPS has thirty (30) Code Category ll D nozzle to vessel attachment welds on each unit, many of widch cannot be completely examined due to vessel nonle forging configuration. The barrel type nonle forg]ng configuration prechides complete ultrasonic exnmlnation r,inte_ scanning of the wcld is only practical from one side of the weld. Also, in support of ALARA, inany of the nonle to vessel welds are to J

be examined utilizinh- a remote automated nonle scanner; thereby, slightly exaggerating

' L the limitations, versus a manual examination, due to scanner design, in addition to the nonle forging configuration, physicat plant design restrictions, such - as adjacent

- components, further litnit the availalk scan path.

2

Specification

• M 73.1. Iter. 0

• l'lIAPS 2 & 3 151 l'ropam Appendix A 1;. ,

Pare 2 of 8

~. .

Iti:1.ll:l' lll:QUlWT NO,1t1113 (CONID.) i I

llevision i Tables RR 131 (Unit ll2) and RR 13 2 (thiit //3) Ikt the nortle to venel welds and detail the extent of exeminations completed (for nonles already cumined), or provide the expected examination coverare (for nozzles not yet c>ninined).

All cuuninations are performed to the mixhnum exitnt practical, in the case of examinations performed utilizing scmote notomatic equipment, only a stry slight increase in examination covttnpe (= 5%) can be realized nith supplemental mnnunt exams; howeser, this small increase cornes with a sirnificant inerense la personnti exposure, and, therefore, manual examination was not perfonned.

El.hnited volumetric examination coupled with the visual examination requhements of Code -- !!xntnbintion . ' gory ll P during system pressure testing provide trasonabic

• nssessment of wcld st, ural-intepity.

} IV. dI.l.IfJib'AllilBfB'IS10Mi I

! No alternate provisions are practical for them examinations.

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• y ification M.733, Rev. 0 or PDAPS 2 & 3

- 151 Program Appendix A 13 -1

- Page 3 of 8 REl,lEF ItEQUEST No. 111113 (CohTD.)'

Revision 1 l TABLE RR O-1 Effect of Nozzle Design Configuration on Cc:nponent inspectability 8 Examination Category B.D. Item No 'B3 90 tinit #2 Nozzic '

. ldentification/ Type  % Code .  % Inner 1/4T Scan' Complete' Code Complete *

. Mcrintion NIA 45T 17.2 (A) 41.5 (A)  ;

Recirculation Outlet 60T 28.3 (A) 66.9 (A) 60P- 23.6 (A) 57.2 (A) -

N2A 45T 29.1 (T)- 51.5 (A)

Recirculation inlet 60T 37.4 (A) 71.1 (A) .

60P 23.0 (A) 43.9 (A)

N2B . _ _

45T 28.7 (A) 50.S(A)

Recirculation Ialet 60T - 36.9 (A) 70.1 (A) 60P 22.,7 (A) 43.2 (A)

N2C .

45T 28.7 (A) 50.8 (A)

Recirculation Inlet 60T 36.9 (A) . 70.1 (A) 60P 24.0 (A) . 45.8 (A) i N2D- 4ST 29.5 (A) 52.2 (A) -

Recirculation Inlet 60T 37.9 (A) 72.1 (A) 60P 23.4 (A) 44.5 (A)

N2E 45" 32.0 (A) 56.7 (A)-

Recirculation inlet 60 i 41.1 (A) 78.1(A) 60P 25.7 (A) - 43.9 (A)

.N2P -

45T 28.2 (A) 50.0 (A)'

Recirculation inlet 60T 36.3 (A) _69.0 (A) s= 60P 22.4 (A) 42.6 (A) ,

N2H_ 45T 33.6 (A) : - 59.6 (A)

Recirculation inlet 60T 43.2 (A)' 82.2 (A) 601' 26.7 (A) 50.8 (A)-

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Specification i M.733, Rev. 0 P11APS 2 & 3 -

}? ISI Program .

~ Appendix A.13 -

Page 4 of 8 l- .

REl,lEP REQU13T NO. Itn.13 (CONID.) l

-Revision i TAltlE RR-131 (CONI'D.J '

Unit #2 Nonle

_ Type - % Code  % Inner 1/4T Identincation/ Code Complete

• Complete' Descriptio3 Beati'

-45T 9.6 (A) 314 (A)

N3A 60T 217 (A) 65.9 (A)

Main Steam _-

60P 11.3 (A) 40.1(A) 45T 8r x 31.2 (A)

N3D f: Main Stem 60T M i4 62.5 (A) 60P ."d *

.; 36.7 (A)

T 45T 28.8 (M)' 66.5 - (M)* .

N4-63f 100.0 (M)'

- Feedwater 45.5 (M)$

(Typ. of 6 noules) 60P 27.0 (M)' 62.6 (M)'

45T 23.6 (A) 46.7 (A)

NSA 60T 14.2 (A) 65.1 (A)_

Core Spray 60P 19.7 (A) 39.4 (A) '

1 4ST 23.6 (A) 46.7 _(A)

I NSU _

60T 34.2 (A) 65.1(A) 1-4t Core Spray -

60P 19.7 (A) 39,4 (A)-

s-3: -

1p 45T 92.4. (M) . 100.0 (M)

}! NRA Jet Pump - 60T_ ' 93 0 (M) 100.0 (M) .

5.: - 817 (M)

Instrumentation 45P- 80.1 (M) j -- -

60P 80.1 (M) 83.7 (M) .

~

l( 71.6 (M)*

45T ' 31.1 (M)' .

Y N9 _

60T. 46.6 (M)* 100.0 (M)'

Control Rod Drive dSP 17.4 (M)* 37.3 (M)'

b Nozzle '

62.5 (M)*

_( Typ. of 1 nozzle) 60P 27.5 (M)'

(!V 4  : Footnotes:

.!} .

$k Component inspectability based- on actual examinatica results or evaluation of_ noule design

$' 'l).

cor$guration for each given , type / size nonic.

f'# Unless _inclicated,' a 45 degree paralici scan is not practical due to wcld configuration.

2)

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- . . . . _ _ _ . . . - . - . . _ .~._ _.._._ _ _ _ . _ ~ . . _ . _ _ _ _ . _ _ . . . _ _ _ . . . _ . . . _ _ _ _ _

Specification

- h1733. Rev. 0 PilAl'S 2 & 3 ISI Program Appendix A-13 Page 5 of 8

~ ,

REl. LEI' ItEQUEST NO. 1111-13 (CONID,)

Revision !  !

3)  % Code complete is that percent _ of the AShlii Code requ: red examination volume widch can effectively be examined using automated (A) er manual (hl) ultrasonic examination techniques.

. 4)  % Inner 1/4T Code cornplete is that percent of the critical inner 1/4T wall volume which can effectively be examined - using automated (A) or manual (hl) ultrasonic examination techniques.

5) -

N4 Feedwater and N9 Control Rod Drive nonic % complete is optimum based on estimated accessible- Code Volume utilizing manual ultrasonic techniques; actual automated ultrasonic examination _ data,- (not available at this time) is expected to yield slightly reduced coverage to due equipment limitations.

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Specification l M 7M, llev. 0

, PilAl'S 2 & 3 ISI l'rogram Appendix A-13 l' age 6 of 8 I 111:1.11T RI;OUl'SI' NO. 111113 (CON'ID.) g Revision 1 Alli.E 1111-13 2 Effect of Noizie Design Configuration on Component inspectability'

!!xamination Category D Du ltem No. U3.90 Unitjg Nonlc Identification / Type  % Code  % Inner 1/4T ~

Description Stat? D"Mhte' Code Cornplete' e N1A 4ST 6.2 (A) 27.0 (A) liecirculation Outlet 60T 18,9 (A) 635(A) 60P 12 4 (A) 4i.6 (A)

N2A 45T 16.1 (A) 40.4 (A)

Recirculation Inlet 60T 30.5 (A) 70.2 (A) 60P 13 ') (A) 34 3 (A)

N2B 45T 14.9 (A) 37.4 ( A)

Recirculation Inlet 60T 28.3 (A) 65.1 (A) 60P 12.8 (A) 31.8 (A)

N2C 45T 17.1(A) 42.8 (A)

Recirculation inlet 60T 32.3 (A) 74.3 (A) 60P 14.7 (A) 36.4 (A)

N2D 45T 16.4 (A) 41.0 (A) _

Recirculation inlet 60T 310 (A) 71.2 (A) 00P 13.9 (A) 34 3 (A)

N2E 45T 16.6 (A) 41.6 (A)

Recirculation inlet 60T 31.4 (A) 72.3 (A)

, 60P 14.3 ( A) 35A (A)

N2F 45T 16.1 (A) 40.4 (A)

Recirculation Inlet 60T -

3tA (A) 72.3 (A) 60P 14.3 (A) 35.4 (A)

N211 45T 16.8(A) 42.2 (A)

Recirculation Inlet 60T 31.9 (A) 73.3 (A) 60P 14.3 (A) 35 4 (A)

Specification

- M 733, Rev. 0 PilAPS 2- & 3 ISI Program Appendix A 13 Page 7 of 8 IlktlEF ItEQUFSI' NO,11I113 (CONTD.) l Revision 1 -

TAIII.E - 1111-13-2 (CONTI).)

Unit U Nor21 Identification /: Type  % Code  % Inner 1/4T Description Scan' Complete' Code Complejg*

-N3A 45T 9.8(A) 38.1(A)

Main Steam 60T 24.3 (A) 76.4 (A)

- 60P 11.4 (A) 45.0 (A)

N3D 45T 9.4 (A) 36.6 (A)

Main " team 60T 23.4 (A) 73.4 (A) 60P 11.0 (A)_ 43.4 (A)

N4 45T 24.6 (M)' 63.3 (M)'

Feedwater - 60T 41.7 (M)' 99.1 (M)'

.(Typ. of 6 nozzles) 60P 23.0 (M)' 59.2 (M)'

NSA 45T 19.9 (A)' 44.0 (A)

Core Spray GOT '31.3 (A) 65.4 (A) 60P 15.1 (A) 35.6 (A)

N5D 45T 20.2 (A) 44.7 (A)

Core Spray : 60T 31.8 (A) . 66.4 (A) 60P 15.3 (A) 36.2 (A)

NSA 45T 91.8 - (M) - 100.0 (M)

-Jet Pump- 60T 92.5 (M) 100.0 (M):

= 1nstrumentation 45P_ 77.3 (M) 80.7 (M) 60P 77.3 (M) 80.7 (M) _

l

! N9 4;T 29.0 (M)* 70.6 (M)5 l Control Rod Drive 60T 45.0 (M)' 100.0. (M)'

Nozzle 45P 14.9 (M)$ _ 34.S _(M)*

25.4 (M)' 61.0 (M)*

[ (Typ. of -1: nozzle) 60P l

L Footnotes:

Component inspectability based on actual examination results or evaluation of nozzle design

!)

configuration for each given type / size non!c. j l

. . . 2) Ur(ss indicatal, a 45 degree praallel scan is not practical due to weld configuration.

L, 8

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Specification

- M 733, Rev. 0

• P11APS 2 & 3 ISI Program Appendix A l.T Pare 8 of 8 ItE1.11:l' 111:QOl:ST NO.11It 11 (CONTI).) i I

Revision 1

1) "A Code complete is that percent of the ASMF. Code required examination volume which can effectively be examined using automated (A) er manual (M) ultrasonic examination techniques.

4) *4 Innei 1/4T Code complete is that percent of the critical inner 1/41' wall volume which can effectively be exainined using nutomated (A) or manual (M) ultrasonic examination techniques.

5)

N4 Feedwater and N9 Control Rod l >ris e noule *A complete is optimum based on estimated accrr.sible Code volume utilie.ing manual ultrasonic techniques; actuai automated ultrasonic examination data, (not available at this time) is expected to yield sliyhtly reduced coverage to due equipment limitations 9

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' ' . Specification M 733i Rey, 0

• P11APS 2 & 3 -

151 Program '

Appendix A 14 Page i of 2 HCLIEF lti:QUPST NO, ItR 14 .

Revision I i

l. SCOlli This relief request is applicable to those ASMli Code Cases adopted for use in this ISI Program which have not 'ocen mecifically endorsed for use by the USNRC in Regulatory Guide 1.147 (rcTerence 1,1.24).

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11. DISCl!SSIO_?! ,

Code Cases are periodicauy published by the ASME for the purpose of either clarifying the intent of Code rules or for providing mles and regulations for circumstances which are not currently covered by existing Code rules but need to be I

addressed in a timely manner. Use of these non mandatory Code Cases for inservice inspectlun is subject to USNRC acceptance of the Code Case (s). Regulatory Guide- 1.147' lists those Code Cases that have been reviewed by the NRC and -are generally . acceptable for ' implementation in an ISI l'rogram. Other Code Cases may

$ be used provided specific uthorization is requested pu.suant to 10CPR50.55a.

g; 1

61

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The purpose of this relief request is to request authorization of the adoption of

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specific Codo Case (s) for implementation in the PI)APS 2&3 IS! Program.

f J

4 IIL . CQDE CASES REQUIRING AUTl10RIZATION s'

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.The following Code Case (s) require specine authorization for . use in the i PIlAPS 2 & 3 ISI Program:

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a- .

A. N 479 Boiling Water Reactor (IlWR)-Main Steam Ilydrostatic Test 94 N The Class 2 portion of the Main Steam system is ineopab!c of being isolated X from the Class I portion for purposes of performing a hydrostatic test. Use of y

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- Specification Al 733, Rev. 0 -

- PilAPS 2- A - 3 IS) Program Appendix A.14 Page 2 of 2

. 1 REl.lEli REQUENT NO. RR 14 (CONTD.)

Revision 1 l this Code Case allows testing to the niternative rules of IWB 5222 (Class 1),

which is most practical in this situation.

IV. ALTERNATE PR;),yjSIONS The alternative sules c4 the Code Case (s) in lit above shall be impicmented in the PI1APS 2 & 3 ISI Program for the second inscivice inspection interva!.

V. 11 ASIS FOR REl.lEF W

- All of the Cod: Case (s) discussed in til above represent technically acceptable attemative rules to ASME Section XI Code rules. The fact that these Code Cases have not ben endsrsed in the Regulatory Guide. in no way detracts from their technical adequacy since the major reason for .their omission is the timing of their publication with tespect to the most recent revision of the Regulatory Guide. - That is, the subject code Cases are relatively recent and it is expected that these Code Cases will be accepted in a subsequent revision of the Regulatory Guide.

Adoption of these alternative rules provides an acceptable level of quality and safety and does not compromise the ' adequacy of the PDAPS 2 & 3 ISI Program in meeting the intent of- ASME Section XI.

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Specifwation

- M 733, Rey, 0

.*- PilAPS 2 & 3 -

151 Program c-Appendix A 15 Page 1 of 3 REI,lEF. ItEQUI$sT NO. Itibl5 Revision !

I .. IDENTIFICATION OF COMPOFENTS ISI Class 2 integral attachments for vessels, piping pumps and - valves, Cods Examination Category C C, item Numbers C3.10 through 3A0. l li. - CODE RFOUIRENIENTS PROM WillCil Rlil.lliF IS REOUESTEi?

ASME Section XI 19S0 Edition Winter 1981 Addenda, Code Category C C, requires a surface examination of essentially 100% of the required area of each welded

. attachment relected' for examination du,ing the r,ccond inservice inspection interval.

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Relief is requested from performance of a complete examination of the Code required-area due to limited accessibility resulting from plant design, comp < ment configuration, and/or environmental restraints.

l.

f 111. 11 ASIS FOR REl,lEF i

?

1 Each of the four RIIR pumps have a base plate integrally welded to the pump 2-I casing, along with four radially oriented reinforcing ribs which are also welded to the i: pump casing. The base plate to pump casing weld is totally inaccessible, since it is f' under the base plate. Additionally, the reinforcing rib to pump casing weld on three of the four ribs are also inaccessibic due to pump support reinforcing plates' which r

cover these ribs.

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I 1

Examination of these wehls are perfonned to the maximum extent practical. Increased LI L examination coverage is not possible without costly plant redesign / modification.

]:

o The extent of examination coverage is identified in Table RR-l$-01.

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Specification M *133, n u, O

• l'lIAPS 2 & 3 -

ISI l'rogram Apivndix A 15

, Page 2 of 3 ItEl.lEl' Itt'QtilWl' NO. 111115 (CONID.)  :

" . Itc<ision i 1.

IV. /Ll!IERNATl! PilOVISIONS No alternate-provisions are practical for the components listed in Table RR 15 01, i

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~ Specification M 733, Rev. 0

• l'IIAPS 2 & 3 151 Program

- Appendix A 15 Page 3 of 3 1101.1E1' ItEQUliST NO. Ill't 15 (CONTD.)

Revision 1 l TAllt .I'. 1111-1501 UNlr 2&3 i I

l'xamination Category _CiC a iter; No CUO EXAMINATION AREA EXAMINATION LIMITING tlNIT  % COMI't.lil E , CONDITION ll2ENTIPlCATION 20 % C omplete exam is not PUMP-ll lWS '2 piactical due to support (RllR PUMP LUGS)

~

design; access restrictions exist on all of four (4) pumps.

PUMP A lWS 3 20 % Co uplete exam is not l pra tical due to support (RllR PUMP LUGS) desipt; access restrictions exist on til of four (4) pumps.

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