ML20116L374
| ML20116L374 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 08/31/1992 |
| From: | Fox J GENERAL ELECTRIC CO. |
| To: | Poslusny C NRC |
| References | |
| NUDOCS 9211180281 | |
| Download: ML20116L374 (4) | |
Text
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To Dave Terao rax No.
George G eovq t ev a
a This page plus __L_ page(s)
From Jack Fow Maii code m 175 Curner Avenue San Jose, CA 95125 Phone (408) 925-- 4 B Li FAX (408) 925-1193-or (408) 925-1687 Subject RPV suvv e.dbw c e - tLesuk M d Message weLax elm n e c - w eAcl w e c %.
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$183daldEIAnt preparation of impact testing proce.
safety to those required for shells and dures, calibration of test equipment, beads are demonstrated using a 1/4 T postu-and the retection of the records of lated defect at all locations, with the ex-these functic as and test data comply ception of tbc main closure flange to tbc j
with the requiren.ents of tbc ASME Code, head and s'nell discontinuity loestions. Ad-a c etici. Ill. Personnel cochetir.g ditional instruction on operating limits is l
impact testing are qualified by caperi-required f :r outside surf ace flaw aires ence, train!ng or qualification testing greater than ?.0 mte at the outside surface l that demonstrates competence to perform of the flange to shell joint based on tests in accordance with the tenting pro-analysis made for ABWR reactor vessels using j
the alculations methods shown in WRC f
cedure.
it will be demonstrated, using a test mockup (4) Charpy V Curves for the RPV Deltline of these creas, that sruller delects can be (0 IIIA and G IVA 1) detected by the ultrasonic inservice examine-tions procedures required at the adjacent A full transverse Charpy V curve is de-weld joint.
termined for all beats of base material and weld metal used in the core beltline region with a minimum of three (3) specimen tested at the 2ctual TNDT-Tbc minimum upper shelf energy level for base insterial and weld metal in the l
beltline region is 10.4 kg fm a-re-quired by G IVA.I.
(7) Fracture Toughness Magiris in the Contrei of Resetivity (Appendix G IV A).
In regard to G !!! A, it is understood that separste, unirtadiated baseline ASME Code, Section 111, Appendix G, was used specimens per ASTM E 185, Paragraph in determining pressure / temperature limita-611 nll be used to determine tbr tran-tisns for all phases of plan operation.
sition temperature curve ol the core beltline base material, HA2. and weld
$J.1.6 Matarial Suncillance in e t B l.
53.1.6,1 Compliance with Reactor Yessel (5) Bolting Material Matuial Surwillance Progract Requirements All botting material cacceding onc. inch The materials surveillance program monitors diamete.t has a minimum of 6A k8 fru changes in the fracture touganess properties of
.y charpy-V energy and OM mm lateral ex.
ferritic materials in tbe ecactor vessel o
pansion at tbc midmum bolt preload tem-beltline region resulting from caposure to j i
perature of 21 oC.
neutron irradiation and therinal environrnent, w
I 5
(6) Alternative Procedurcs for the CaleJla-Resetor vessel materials surycillaDce-g E
specimens are provided in accordance with re-quirements of ASTM E 185 and 10CRF 50, Ap tion af Stress intensity Factor (Appen-Q' o
dix G.IV A) d H; Materials for the program are selected to rep-Stress intensity factors are calculated resent n aterials used in the reactor beltline y m
by the methods of ASME, Sec' ion lit, region. Spcime n are manuftetured from a t *4' L 8
3 Appendix G. Discont'nuity regions are et-forpng actually used in the beltline regg y
evaluated as shell and head arcan, as and 3 weld typical of those Jthe beltline
'c part of the detailed thermal and stress region and thus represent base metal, wdd mate-y analyses in the ressel stresa report. rial, and the weld he:at affected zone snaterial.
E N"
Thet ewe =4wel# ate heat treated in a7anner l
Considerations are given to membrane and.
bending stresses, as outlined in Para. which simult.tra the actual best treatment per-t d**- of t he i
grapb G 2222. Equivalcut margins of formed on thr: core region shell/rt%g 3M Amendment 13
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2 A610 14
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' s m td u m ult temperature at end of life is less than 34 C,
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comp!cted vest.el. Each in rcactor surveillance capsule contains 36 Charpy Veoich and 6 tensile and (be end of life upperabelf energy exce kg m. (See respocse to Question 251.5 for the specimens. The capsule loading consists of 12Charpy V Specimena each of b y
beabaffected zone material, and 3 tenQlc estimat2).
specimcas each from base metal e d weld tuetal. Atet of out o6teactor baseline Cha and Methods of Attachment @ppendix it.!! B (2))
spreimens, tensile specimens, and archke materk are provided with the st.rveillance te stMNeutros dosimeters and temperetur; ( Surveil common elevation in the core spe cime ns.
raonitors will be located within the capsules as re *re+-atimuths abeltline region. Tbc healed capEtes p
quired by ASTM E 185.
tached to the vessel but are in welded capsule f;.#
I A-h+ cepsulchre provided,6-ee**edwed holders. The capsuir holders are mcchanically re.
pC Nr ud\\Wr-i.x L p tained by tap h ~ Act brackets welded it, ti e nqdneeeMCFF " WL !'s
".ince reactor vessel spe cifi-n r,. g[')
yu.dicted cod of the adjusted reference temperature vessel cladr.
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of the reactor vessel. teel is less than 38 C.
cetions require ihat sti low-alloy steel pressure g#
- N vessel bount ary materials oc produced to oN [
The followiny proposed witbdrawal schedule is fine grain pr,ctice, underdad cracking is of no E
ihe capsule bolder brackets allow the hg :
concern.
P' gge**Mb ASTM E ili5.
remova' and reinsertion of capsule holders. A1 First enpsult:
After 6 effective full power thou/..ot code parts, these brackets are de-
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j g[f sige d, f at eicated, aud analyzed to the rettuire-
'2.0 ments of.sSME Code Section III. A positive years Secc d capsule-Af ter h effective full power spring-loaded locking device is provided to re-n W Hsdca psule: Schedule determined based on tain the capsules in Nsitloe throughout any an-
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y ars %f4 d
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results of first ge capsules per ASTM E 165, ticipated event du' ring the lifetirne of tbc Par agr aph 7.6.2.
requirements perteining to materials and ([7 ON vessel.
f(
D Fracture toughneu. testing of irradiated cap. survellance capsules.
suit specimens vdll be le accordance with require-in arers where brackets (such as the surveil-g ments of ASTM E 185 as called out for by 10CFR50, lance specimen holder brackets) are located, addi-g qj Appeu& H.
tivnal nondestructive examinationi are performed on the vessel base metal and atainless steel 94 5.11.fo2 Neutron Flus and Fluence Calculatine weld deposited cladding or weH buildup psds gd j
A description of tLe methods of analysis is during vessel manulacture. The base metal is ut.
contained in Subecetioc. 4.1.0 a nd 4.3.2.8.
trasonically examined by straight beam techniques j., uJ to a depth 4t least equal to the thickness of the p
bracket beig joined. The area examined is the f
wq 53.1.6J Prtdicted Irradiatlon Erretts on arcs of width equal to at least half the thick-cg
- 6 hittine Materials ness of the part }cined. The required stainless fa
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Transition temperature changes and changes in steel weld deposited cladding is sicci-larly exarr.-
ined. Tbc full penetration welds are liquid-pen-upper shelt energy shall be calculated in accor-Cladding thickotu is required dance with the rulet of Regulatory Guide 1.99. etrant examinedto be at least 12 mm. These r:quir.
f.
Reference temperatures shall be established in ac-cordance with 10CFRR Appoda G, and NBJ23M of been auccessfully applied to a nriety of brack t
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j desiges which are attached to weld deposited p
the ASME Code.
stainless steel cladding or weld buildups in many T
Since weld material chemistry and fracture oper atind BWR reactor pressure vessels.
G
- oughness data are not at:ilable at this time, Inservice inspection examinations of ccte F
the limits in the purchase tpecification werc beltline pressure retaining wehis are perforraed y
used to estimate wc rst.ca;t iiradiation eUcets. from the cutside surface of (be reactor pressure These ratimates show that the adjusted reference
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