ML20087B716

Forwards Response to Issues Raised at Ge/Nrc 911209-10 Meetings Re Inservice Insp Relief Requests for Reactor Pressure Vessel Bottom Head Weld & Reactor Pressure Vessel Bottom head-to-shell Weld

ML20087B716
Person / Time
Site:	05000605
Issue date:	01/06/1992
From:	Marriott P GENERAL ELECTRIC CO.
To:	Pierson R NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
EEN-9204, NUDOCS 9201130255
Download: ML20087B716 (16)

Text

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GE Nuclear Empy h.

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I january 6,1992 MFN No. 008-92 Docket No. STN 50-605 EEN 9204 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention:

Robert C. Pierson, Director Standardization and Non-Power Reactor Project Directorate

Subject:

GE Response to Inservice Inspection (ISI) Issues of' GC/NRC Meeting December 910, D91 Enclosed are thirty four (34) copies of the GE responses to the subject issues.

- Relief requests for the reactor pressure vessel bottom head weld (Section 5.2.4.8.2) and the reactor pressure vessel bottom head to-shell weld (Section 5.2.4.83) are no longer necessaiy for the following reasons:

Section LL412 ASME Section XI, Table IWB 2500-1, specified that the accessible" length of all head welds be examinea, therefore coverage of this weld, while partial, should be sufficient to sa:isfy the Code requirement. Access to the bottom head weld for ultrasonic examination is limited due to penetrations in the bottom head for the reactor internal pumps, control rod drives and incore monitors. The bottom head design, however, has been optimized to the extent possible, minimizing 'he number of welds in the bottom head.

SssWm 5.2.4.83 The obstruction caused by the RPV skirt pedestal which limits accessibil y fer uitrasonic examination, will be eliminated by redesign.

- The remainder of the issues are addressed as additional modifications to selected SSAR pages.

Sincerely, _

P.W. Mdtriott, Manager Regulatory and Analysis Serv lces M/C 382, (408) 925-6948 cc: F. A. Ross (DOE)

N. D. Fletcher (DOE)

C. Poslusny, Jr.

-(N RC)

R. C. Berglund (GE)

J. F. Ouir k (GE)

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ADWR uutmsn Standard P. ant nv c I

years in BWR applications. Estessive laboratory tests base demonstrated that XM 19 is a suitab;e material and that it is resistant to stress corrosion in a BWR environment.

! 4.<3 Interfaces 4.33.1 CRD Inspection Program The CRD inspection progran, shall include provisions to detect incipient defects before they could become serious enough to cause operating problems, [See Subsection 4.5.1.2(2)]

The CRD nogle c n d C F.0 boikr3 areswe6ded m 4k,gw3,y.vgec h34C I M S f C C.k s o e pro f ckvv%.

w bit 5. 2 - B, S g.s he Numh4f B i l /Bt *2.] CBD boldiw3 iS cvcu \\ ab\\ e f or In s ervs c e e a n, n sho+ s awm +

v.cv e o\\\\9 s chedm\\ ect cs.o um aw a ce.

l Amendmeni is

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Jtandard Plant-

%c areas to facilitate servicieg of pumps and valm.

IWA-2232 (a), and Section V, Article 4 in addition the l'latforms ano ladders are p osided for access to ultrasonne examinstion system shall meet the pipit.g wells including the pipe-t+ reactor vessei requirements of Regulatory Guide 1.150 as described in nozzle welds Removable thermalinsulation is Table 5.2 9. RPV welds and nonles subject to provided on welds and componems which require eum' nation are shown in Fquie 5.2 7a.

frequent av.ess for cumination or are located in high radiation areas. Welds are located to permit The GE reactor vesselinspection system (GERIS) t,lerasonic examination from at leut one side, but racets the detection and sizing equirements of where component geccetries permit, ac..ti.s Regulatory G6.ide 1.150, as cited in Table 5.2 9. Inner 6

from both side.;is prosided.

radius euminations are perforn,ed from the outside of the norrie uung several compound angle transducer Restrictions: For piping systems and wedges to obtain complete coverage of the required portions of piping systems subject to vo'umetric examination volume. Electronic gating used in GERIS and surface examination, the following piping system records up to 8 different reflectors designs are not used:

simultaneously to assure that all releva.a indications are recorded. Append:x 5A dernonstarted compliance with (1) Valve to Valve Regulatory Guide 1.150.

(2) Valve to Reducer (3) Valve to Tee 5.2.43.2.2 Visual Examinatlan (4) Elbow to Elbow (5) Elbow to Tee Vis>ial ramination methods, VT 1, VT.2 and VT 3, (6) Nozzle to elbow shall be conducted in accordance with ASME Section (7) feducer to cibow XI, IWA ?210. In additior., VT-2 c.tamications shall (8) Tee to tee meet the requirernents of IWA 5240.

_(9) Pump to valve Direct visual, VT 1, examinations shall be Straight sections of pipe and spool pieces conducted with sufficient lighting to resolve a 0.8mm l skai! be added between fittings. The minimum black line on an 18% neoaal grey card. Where direct length of the spool piece has becc determined by visual, VT.1, examinations are conducted without the

~ l using the formulate L = 2T + 152mm, where L use of mirrors or with other siewing aids, clearance (of -

equais the leogth of the spool piece-(nos at ! cast 610mm of clear space) is provided where feasible l j

including weld preparation) and T equals the for the head and shoulders of a man within a work pipe wall LW~

arm's length (508mm) of the surface to be examined, i

5.2.43 Examinatla Categories and Methods At locations where leakages uc normally expected and leakage collection systems are located, (e.g., valve 5.2.43.1 Examinatlos Categories stems and pump seals), the visual, VT 2, cumination shall verify that the leakage collection system is -

The examination category of each item is listed operative.

in Table 5.2 8. The items are listed by system and line number where applicable. Table 538 Piping runs shall be clearly identified and laid out

- also states the method of examination for each such that insulation damage, leaks and strucsural distress item. The preservice and inservice examination wiu be evident to a trained Msual examiner.

plans will be. supplemented with detailed drawings showi.y the examination areas. such as.

5.2.43.23 Surface Examinatlos Filures 5.2 7a and 5.2 7b.

WSEFT A Mtgnetic particle and liquid penetrant examinat on i

5.2.43.2 Examination Methods techniques shall be performed in cecordance with ASME Section XI, IWA-2221 and IWA 2222, i

Ultrasonic Examination of the respectively. Direct cramination access for magnetic 5.2.4.3.2.1 Reactor Vessel partkle (MT) and penetrant (PT) examination is the same as that required for direct visual (VT 1)

Ultrasonic examination of the RPV will be examination (Subsection 5.2.4.3.2.3), except that i

conducted in accordance with ASME Section XI, l

Amendmsna 1.5 32 17 i

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y Forfthe preservice examination, all items selected for inservice examination, with the exception of the visual VT-3 examination of valve body and: pump casing internal. surfaces:(B-L-2 and B-M-2, respectively), and the

' visual VT-2 examinations for. categories B-E and B-P, shall be performed once, prior to initial plant startup, in accordance-with ASME Section XI, IWB-2200,

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Standard Plant an c additional access shall be prosided as necessary to may result in improvemcots in examination reliability enable physical contact with the item in order to and reductions in personne! exposure.

perform the examina'ian Remote MT and PT generally are not appropriate as a standard 5.2.433 Data Recordlog examination process, however, boroscopes and mirrors can be used at close range to improve the Manual dats recording will be performed where angle of vision. As a minimum, insulation manual ultrasonic examinstions are performed.

removal shall expose the area of each weli plus at Electronic data recording and comparision analysis are icast 152mm from the toe of the weld on each to be ernployed with automated ultrasonic camination side, insulation will generally be removed 406mm equipmer.t. Signals form each ultrasonic transducer on each side of the weld.

will be fed into a data acquisition system in u hi;b the

'sey parameters of any reflectors will be recetded. The 5.2.4J.2.4 Volumetric Ultrasonic Direct data to be recorded for raanual and automated methods Examination are:

Volumetric ultiasonic direct examination (1) Location shall be performed in accordance with ASME (2) Position Section XI, IWA-2232. In order to perform,he

)) Depth belcw the scannmg surface (4) Length of the reflector l examiention, visual eccess to place the head and shoulders within 50smm of the area of interest (5) Transducer data including angle and frequeccy shall be provided where feasible. Nine inches (6) Calibration data between adjacent pipes is sufficient spacing if there is free access on each side of the pipes. The The data so recorded shall be compared with the trar:sducer dimension his been considered: a results of subsequent examinations to detertaine the l 38mm diameter cylinder,76mm long placed with behavior of the reflector.

I access at a right angle to the scrface to bc

+- l N G G fact B examined. The ultrasonic examination instruuent

$2.4.4 Inspection Intervals l

has been consideied as a rectangular box 305 x 305 x 508mm located within 12m from the The inservice inspection intervals for the ABWR l.

transducer. Space for a second exarainer to will conform to laspection Program B as described in l

monitor the instrument shall be provided if Section XI, IWB.2412. Except where deferral is necessaey.

permitted by Table IWh.2500-1, the percentages of examinations completed within cach period of the losulation removal for inspection is to a!!ow interval shall correspond to Tabl: IWB-2412-1. Items sufficient room for the ultroonic transducer to selected to be examined within the 10 year inte:vals are scan the cramination area. A distance of 2T plus ieseribed in Table 5.2-8.

f 152mm where T is pipe thickness,is the minimum required on each side of the examination area.The 5.2.4.5 Evaluatlon of Examination Results l inst.lation design generally leaves 406mra on each side of the weld, which neceds minimum Examination results will be evaluated in accordance requirements.

with ASME Section XI,IWB-3000 with repairs based l

on the requirements of IWA 400n and IWB-4000.

5,2.43.2.5 Alternative Examinatian Te:bniques Re-examination shall be conducted in accoriace with the requirements of IWA-2200. The recorded results As provided by ASME Section X1, shall meet the acceptance standards specified in IWA 2240, alternative examination methods, a IWB.3400-1, combination of methcds, or newly developed techniques may be substituted foi the mathods 5.2.4.6 System leakage and Ilydrostatic Pressure Tysts specified for a given item in this section, provided that they are demonstrated to be equivalent or 5.2.4.6.1 System Leakage Tests superior to the specified method. This provision allows for the use of newly developed As required by Section XI, IWB 2500 for Categor) examination methods, techniques, etc., which B-P, a system leakage test shall be performed

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TNSGRT 8 5.2.4.3.4 Qualification of Examination Systens and Personnel for Ultrasonic Examination Personnel performing ultrasonic examinations shall be qualified-in accordance with ASME Section XI, A9pendix VII.

Ultrasonic examination systems will be qualified in accordance with an accepted industry progra.n for implementation of ASME Section XI, Appendid, VIII.

(Note:

Appendix VIII was added to ASME Section XI in the 1989 Addenda to the 1989 Edition.)

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odside sudace ABWR msegr c mu

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j in accordance witb IWB 5221 on all Class 1 Section XI, Table IV B 2.M/F1 for category B.D. will tw components and piping within the pressure j inaccessible for ultra,onic examination. The ultrasonic i

retaining boundary following each refueling

' examination is conc ucted from the cuiside surface of outage. For the purposes of the system leskage the RPV ard, as sugh, the outside radius of the nozzle

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test, the preuure eetaining boundary is defiried in forging limits the /ntvement oi the ultrasonic search Table IWB.2500-1, Category E P, Note 1. The QtfThe typica%can limitation resulting from Ewoi33 t h

system leakage test shallinclude a VT 2 geometry is illustrated in Figure 5.2 7c.gThe ex! cat of cumination in accordance with IWA 5240. The the cuminatior. toverage limitation for cich nozzle vill system leakage test will be conducted be determined during the preser.u exur ination of the appion:mately at the maximum operatic; RPV oozzle.to vessel welds.

pressure and teenperature indicated in the applicable process flow diagram far the svstem as 52E Heactor Pressure Vessel Bottom Head WeD indicated in Table 1.71. The system hydrostatic test (Subsection 5.2.4.6.2), when performed is Access to the bottom head weld for ultrasonic acceptable is. lieu of the system leakage test.

j examination is limited due to penetrations in the DJSERT p bottom head for the reacter internal pumps, control rod 5.2.16.2 flydrostatic Pressure Tests drives and incore monitors. Partial coverage will be possible. The exterit of the examination coverage As required by Section XI, fWB-2500 for limitation for each noz2Je will be determined during the l

Category B-P, the bjdrostatic pressure tes; shall preserMce cumination the RPV bottom head weld.

be performed in accordance with ASME Seuion IWB 5222 on all Class I components and piping 5.2.4.1.3 Reactor Preuure Vessel Bottom Head to Shell wabin the pressure retaining boundary once Weld during each 10 year inspection interval. For purposes of the hydrostatic pressure test the Access to the RPV bottom head to-shell weld for pressure retaining boundary is defined in Table ultrasonic cumination is limited due to the proximity of IWB 2500-1. Category P-P, Note 1. The system the RPV SLkt pedestal on the Shell side, and the curved hydrostatic test shall include a VT 2 enmination surface of the bottom head itself interferes with in accordance with IWA 5240. For the purposes examination from the bottom head side of the weld, of determining the test pressure for the system Only limited examiestion coveraSe can be achieved on i

hydrostatic test in accordance with TWB-5222 (a),

this wcid, however, the actual extent of the examinatico coverage will be determined during th the nominal operating pressure shall be the examination of the RPV bottom head-to shell weld.

maximum operating pressure indicated in the process flow diagram for the nuclear boiler system. Figure 5.13.

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J A 5 5.2.4.7 Code Esemptions

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As provided in ASME Section XI,

.Qu cks,a.drw oc33 *th by^^

fWB 1220, certain portions t.f Class 1 systems are cg, 3 e e, n coy q y eq e,

,;;, 2,, L 3g exempt from the volumetric and surface examination requirements of IWB-2500. These s s c e k I w-Acl cx + O 4- \\"S\\ d &

portions of systems are specifically identified in 3 w pct c,,,, o {'- Q v c s 3 e l. A Table 5.2 3.

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Due to tbc inherent geometry of the RP

l noules, sorae portion of the nozzle to-vessel weld required volume as rpecified in ASME I

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$W2 Amendment 13

I NJ S G R T C In order to increase scan accessibility for ultrasonic examinations conducted from the vessel outside surface the size of the nozzle forging flange must be increased.

Increasing the size of the flange is undesirable from a design standpoint because it increases the length of the weld.

In addition increasing the flange sizes may cause overlapping welds to occur between_ nozzle welds (instrument nozzles compound the problem) or between nozzle welds and RPV seam welds.

I N S E RT 0 As technology is developed to perform examinations from the inside of the vessel, access may be improved to unobstructed nozzles above the shroud, e.g., main steam.

Technology may also be developed to examine unobstructed nozzles below the shroud.

A combination of outside and inside surface examinations would result in a significant improvement in the examination coverage without redesign of the nozzle forging, but it'is foreseeable that there would still be some percentage of the weld that would not be examined.

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EXAMINATION CATEGORIES no R

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Quality System System

. ' System P&ID Sec. XI Items

' Exam 5%(

Group Number.

Title Description' Diagram Exam Cat.

Examined Method A

B11/821.

Reactor

' Reactor Pressure Vessel Figure' E

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Pressure 5.1-3 Vessel /

Vessel Shell Welds B-A Welds

. UT Nuclear

-(Note 7)-

Boller Vessel Head Welds B-A Welds UT

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'(Note 7)

Shell-to-Flanga Weld B-A Weld UT-U', MT Head-to-Flange Weld B-A Weld T

Nozzles for:

B-D

Welds, UT Main Steam, Feedwater, Inner

'SD Outlet, CCS(Fidg.) &

Radius 50 Inlet, 50.- RWCU t

SD Outlet, CCS(Spray) &

SD Inlet Nozzles for CRD, RIP &

B-E External YT i Instrumentation Surfaces (Note 8)

+

B-G-2

6. M s v T-t Closure Head Nuts B-G-1 Nuts MT Closure Stads' B-G-1 Studs UT, MT (Note 9)

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f Threads ~ in Flange B-G-1 Threads UT Closure Washers, Bushings B-G-1 VT-1 Integral Attachments 8 -11 Welds UT or HT

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%e 6.ti PRESERVICE AND INSERVICE

&6.1.1 Class 2 System Itoundary Description INSPECTION AND TESTING OF CIASS 2 AND 3 COMPONENTS AND PIPING Those portions of the systems listed in Subsection 6.6.1 within the Cissi 2 boundary, as This st.bsection describes tbc preservice and described in Regulatory Guide 1.26 for Quality inservice inspection and system pressure test Group B, arc as follows:

programs for t@0 Quality Groups B and C,i.e.,

ASME ik3e; xd hm.. i's w: (& respec)tively.j 3&tV Code (1) Portions of ibe reactor coolant pressure E.a ;;; ;.nd X3 Class 2 and 3 item boundary as defined in Subsection 5.2.4.1.1, but It describes those programs implementing the which are excluded from the Class 1 boundary requirements of abecciise ;WC.m! iWL m' dh pursuant to Subsection 5.2.4.1.2.

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(2) Systerr r, or portlons of systems important to 6,6,1 Class 2 and 3 System Boundaries s

safety that are designed for reactor shutdown u

or residual beat removal.

The Class 2 and 3 system boundaries for both {-

preservice and laservice Mspection programs and the j (3) Portions of the steam systems extending from system pressure test program iududes all those items a the outermost containment isolation valve up to within the 3 boundary and applicable items within 9 but not including the turbine ctop and bypass the 4 boundary, respectively, on the piping and f+

valves and connected piping up to and induding instrumentatinn drawinge (P&lDs). Thu.e -

the first valve that is either normally closed or boundaries indude all or part < l the following-3 capable of automatic closure during.11 medes of normal reactor operation.

(1) Mah steam system s

(2) Fec4 water sptem 5(4) Systems or portions of systems that are (3) Reactor core isolation coolmg system f,

conneeted io the reaetor coolant piessure (4) IUgh pressure core flooder system boundary and are not capable of being i*olated (5) Standbyliquid control system 1

from the bound. y during all modes of normal (6) Residual heat removal system.

'l reactor operation by two valves, each of which (1) Reacto 1 vater dean up system p

is normally closed or capable of automatic (8) Control rod drive system closure.

(9) Supression pool dean-up system

)

(10) Purified make up water system 1-(5) Systems or portions of systems important to (11) \\tmospheric contaal system safety that are designed for (!) emergency core (12) Radwaste system cooling,(2) post accident containment heat (13) HVAC normal cooling water system removal, or (3) post accident tission product (14) Service air system removal.

(15) High presrure nitrogen gas supply system D 6 (16) Instrument air system b.6.1.2 Class 3 System Boundasy Description (17) Reactor building cooling water system (18) 19ammability control system p

Those portions of the systems listed in (19) Fuel pool cooling and dean-up system ASubsection 6.6.1 within the Class 3 boundary, as 4

(20) Reactor acrvice water system described in Regulatory Guide 1.26 for Oaality k Group C, are not part of the reac*or coolaM pressure

• boundary but are as follows:

L j(1) Cooling water systems or portlans of cooiing

• Items as used in this Section are products water systerns important to safety that are constructed under a Certificate of Authorization s designed ior emergency core cooling, (NCA-3120) and materia! (NCA 1220). See Sectron [

post accident contsiameat heat temoval, Ill, NC4-1004 foomote 2 o

post accident containment atmosphere deanup,

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c< residual heat removal from the reactor and from the spent fuel storage pool (including a

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Amendmeni 13 y

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1

I, ABWR

-n Standard Plant

,, e primary and secondary cooling systems),

for performance of uitrasenic and surface (magnetic Portions of these systens that :e required for particle or liquid penetrant) examinations and their safetv functions end that do not operate sufficient access to supports for performance of during any mode of normal operation and visual, VT.3, examination. Working platforms are cannot be tested adequately, however, are provided in some areas to facilitate servicing of included in Class 2.

pumps and valves. Removable thermal insulation is provided on welds and components which require (2) Cooling water and seal water systems or frquent access for esam nation or are located in portions of these systems important to safe:y high radiation areas. Welds are located to permit that are designed for functioning of ultrasonic examination from at least one side, but components and systems irrportant to safet".

where component geometries permit, access from both sides is provided.

(3) Systems or portions of systems that are connected to the rector coolant pressure Restrictions: For piping systems and portiom boundary and are capable of being isolated of piping systems subject to volumetric and urF.e from that boundary during all modes of normal examination,Ibn following piping de;igns m not reactor operation by two valves each of which is used:

normally closed or capable of automatic closure.

(1) Valve to valve (2) Valve to reducer (4) Systems, other than radioactive waste (3) Valve to tee management systems, not covered by items a, b (4) Elbow to elbow and e above, that contain or may contain (5) Elbow to tee radioactive material and whose postulated (6) Nonle to cibow failure would result in conservatively calculated (7) Reducer to cibow potential offsh doses (ref. Regulatory Guides (8) Tec to tee 1.3 and 1.4), tt.4t exceed 0.5 rem to the whole (9) Pump to valve body or its equivalent to any part tef the body.

Straight sections of pipe and spoei pieces shall 6.6.2 Accessibil?v be added between fittHs. The ininimum length of the spool piece 1

, determined by using :he Allite;as within the Clast. 2 and 3 boundaries formulate L = 21

-.rches, where L equals the are designed, to the extent practicable, to provide length of the spoot pict (not including weld access for the examinations required by IWC-2500 preparation) and T equals the pipe wall thicknera, and IWD-2500. Items for which the design is known to have inherent access restrictions are describd in 6.6.3 Examination Categories ant! Methods Subsection 6.6.9.

6.6.2.1 Class 2 RIIR Heat Exchangers The examination category of each item is listed The physical arrangement of the residual heat in Table 6.6-1. The items are listed by system and removal (RHR) heat exchangers shall, to the extent line number where applicable. Table 6.61 also feasible be conducive to tne performance of the states the method of examination for e g

i required ultrasonic and surface examinations,

,pg Removable thermal insulation is pro *4ed for those 6.63.2 Essi ation Methods welds and no221cs selected for frequei., examination during the inservice inspection. Platforms and 6.6J.2.1 Visual Examla,ation ladders are provided as necessary to facilitate examination.

Visual Examination Mett ods, VT 2 and \\T.3, shall be conducted in accordance with ASME 6JL2.2 Class 2 Piping, Pumpa Valves and SupportsSection XI, IWA.2210. In addition, VT-2 examinations shall also meet the requirements of Physical arrangement of piping pumps and IWA 5240.

valves provide personnel access to each weld location Amendment 13 66-2

I N GE RT E For the preservico examination, all items selected for inservice examination, with the exception of: Lhe visual VT-2 examinations for category C-H, D-A, D-B and D-C, shall be performed once, prior to initial plant startup, in accordance with ASME Section XI, IWC-2200 and IWD-2200.

1 i

ABWR mama Standard Plot s

we At locations where leakages are normally Insulation removal for inspection is to allow expected and leakage collection systems are located, sufficient room for the ultramnic transducer to scan (e.g., vahe stems and pump seals), the visual, VT.2, the examination area, a ilstance of 2T plus 6 examination shall verify that tb leakage collection inches, where T is the pipe inickness, is the minimum systern is operative, required on each side of the examination area. The insulation design generally leaves 16 inches on each Piping runs shall be clearly identified and laid side of tbe weld, which eneceds minimum out such t u insulation damage, leaks and structural requirements, distress v.

e evident to a treined visual examiner.

64.1.2.4 Alternative Examination Techalques 6.6J.2.2 Surface ExaminatJoe As provided by ASME Section XI, IWA.2240, Magnetic Particle and Liquid Penetrant alternative examination methods, a combination of examination techniques 4 hall be performed in methods, or newly developed techniques may be cordance with ASME Section XI,IWA.2221 and substituted foe the methods specified for a given item IWA.2222, ecspectively. For direct examination in this section, provided that they are demonstrated access for magnetic particle (MT) and penetrant to be equivalent or superior to the specified method.

(PT) examination, a clearance (c' at least 24 inches nis provision allows for the use of newly developed of clear space) is provided where feasible for the examination methods, tevhniques, etc., which may head and shoulders of a man within a working artn's result in impronments in examination reliability and length (20 inchea) of the surface to be examined. In reductions in personnel exposure, addition, access shall be provided as necessary to enable physical contact with the item as necessary to 6.6.3.2.5 Data Recording perform the examination. Remote MT and PT generally are not appropriate as a standard Manual data recording will be performed examination process, however, borescopes and where manual ultrasonic examinations are mirrors can be used et close range to improve the performed. If automated rystems are used, angle of vision. As a minimum, insulation removal electronic data recording and coteparison analysis shall expose the area of each weld plus at least six are to be employed with automated ultrasonic inches from the toe of the weld on each side.

examination equ! pent. Signals from eacn Insulation will gencially be removed 16 inches on ultrasonic transducer would be fed into a data cach tide of the weld.

acquisition system in which the key parameters of any reflectors will be recorded. The data to be 6.6.3.2.3 Volumetric Ultrascale Direct Erasslaatjoe recorded for ma sual and automated methods are:

Volumetric ultrasonic d. rect examination shall (1) location; be performed in accordance with ASME Section XI, (2) position; IWA.2112. In order to perform the examination, (3) deptt below the scanning surface; visual access to place the head and shoulder within (4) length of the reflector, 20 inches of the area ofinterest shall be provided (5) transducer data including angle and where feasible. Nine inches between adjacent pipes frequency, and is sufficient spacing if there is free access on cact (6) calibration data.

side of the pipca. The transducer dimension has l

been considered: a 11/2 inch diameter cylinder,3 ne data so recorded shall be compared with l

inches long placed with the access at a right angle to the results of subsequent examinations to determine l

the surface to be examined. The ultrasonic the behavior of the reflector.

I examination instrument has been considered as a 4.

I e4 sis (W F rectangular box 12 x 12 x 20 inches located within 40 6.6.4 Inspection Iniervals feet from the transducer. Space for a second examiner to monitor the instrument shall be 6.6.4.1 Class 2 Systems provided if necessary.

The 'nservice inspection intervals far Cla:.s 2 systems will conform to Inspection Program B as Amendment 13 6.63

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-6.6.3.2.6 Qualification of Examination Systems and Personnel for Ultrasonic Examination Personnel performing ultrasonic examinations shall be

_ qualified-in accordance with ASME Section XI, Appendix VII.

Ultrasonic-examination systems will be qualified in accordance with an accepted industry program for implementation of ASME Section XI, Appendix VIII.

(Note:

3 Appendix VIII was~added to AS.E Section XI in the 1989 Addenda to the 1989 Edition.)

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/GWR uxstm Standard Plant Rev C performed in accordance with ASME Section ASME Section XI, Table IWC 2500 for category IWC 5222 on all Class 2 components and piping C B, may not be accessible for ultrasonic within the pressure setaining boundary once during examination. The examination is conducted from the each 10 year inspection interval. For purposes of the outside surface of the vessel anO _ i, the outside hydrostatic pressure test, the pressure retalning radius of the nozzle forging maylimit the mosement boundary is defined in Table IWB 25001, Category of the ultrasongearch unit.4The extent of the B.P, Note 1. The system hydrostatic test shall (examination coverage hmitaten for each nonje will include a VT 2 examination in accordance with { be determined during the preservice examination of the vessel.to nozzle welds. Wh o r*

IWA 5240. For the purposes of deletmining the test pressure for the system hydro:'atic test in covera,qe sa h ~ h d> a Suff " M "

\\

accordance with IWB 5222 (a), the system design cu4std*.auv-4c.e w % m m4 ton pressure as indicated on the applicable piping and SM M be pMoW M instrumer.!,ation diagram for the system, as shown in Table 1.71, sha!! be used for P,in z.!! cases.

% prom 6.6.7 Augmented Inservice Inspeellon A c < C Ss s 6 h

c. o All high energy piping between the

^D "N

contain.nent isolation valves are subject to the

• P K ; b M b J (kASV)" Of O^

following additionalinspection requirements:

hAJ h d* be w 5 2 b 4 C C*' *'#4 t.yoMelhaM -4k W kv-fWA 4!.

All circumferential welds shall be 100 percent volumetricarry examined each inspection interval as 5 W c,b M C-oW JJR * * ' O defined in Subsection 6.63.23. Further, accessibility, 4k (-

O oh 4 k gg b ])*

g 4# ' " #.)-g\\) d o n cramination requirements and procede.res shall be as discussed in Subsections 6.6.2, 6.6.3 and 6.6.5, M

respectively, Piping in these areas shall be seamless, thereby climinating all longitudinal ulds.

6.6 8 Code Exemptions l

As provided in ASME Section XI, IWC 1220 l

and IWD 1220, certain portions of Class 2 and 3 systems are exempt from the volumetric and surface and visual examination requirements of IWC 2500 and IWD 2500. These portions of systems are spahuy identified in Table 6.61 009 Relief Requests 6.6.9.1 Class 2 Hydrostatic Test Pressure l

For portions of Class 2 systems, which cannot be isolated from the reactor vessel, such as the branch connectior. of line 25A NB 728 to 50A NB 129, the system hydrostatie test pressure shall be in accordance with the system hydrostatic test pressure requirements for the Class 1 system.

6.6.9.2 Ri!R Heat Exchanger Nozzla-to Shell Welds Due to the inhe A geometry of vessel nozzles 3 some of the weld required volume as specified in Amendment 13 66-5 l

l

f g

- FEEDWATER NOZZLE 1

O

\\\\

M 0 WELD METAL COVERAGE NOZZLE

(

I h3 45" T - SCAN COVERAGE NOZZLE k

l 4

VESSEL h

)

I N

M 6'O T - SCAN COVERAGE NOZZLE l

5 t

VESSEL i

i Figure 5.2-7d SCAN COVERAGE LIMITATION l

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