ML20084S565
| ML20084S565 | |
| Person / Time | |
|---|---|
| Site: | Catawba |
| Issue date: | 05/23/1984 |
| From: | Tucker H DUKE POWER CO. |
| To: | Adensam E, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8405250214 | |
| Download: ML20084S565 (34) | |
Text
{{#Wiki_filter:. Duxu PowEn GOMPm P.O. HOX 33180 CI1AHLOTTE, N.C. 28242 IIALH. TUCKER TELEPHONE ~ .l~ ""1 May 23, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Ms. E. G. Adensam, Chief Licensing Branch No. 4 Re: Catawba Nuclear Station Docket Nos. 50-413 and 50-414
Dear Mr. Denton:
Section 6.2.7 of th'e Catawba Safety Evaluation Report discusses Confirmatory Item 18, Fracture Prevention of Containment Pressure Boundary. This section notes that additional information is needed by the Staff to confinn that the lowest temperatures which will be experienced by the limiting materials of the reactor containment pressure boundary under the conditions cited by GDC 51 will be in compliance with the temperatures identified in the Staff's analysis. addresses compliance with GDC 51 for power piping and mechanical penetrations. addresses compliance with GDC 51 for containment structures. Compliance with GDC 51 is addressed for power piping and mechanical-penetrations in Enclosure 1 and for containment structures in Enclosure 2. Based on the-detailed review of the containment pressure boundary materials used in the Catawba Nuclear Station, it is concluded that the requirements of GDC 51 have been met. Very truly yours, h 0.YLLCbs4W Hal B. Tucker ROS/php Attachment-cc: Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303 NRC Resident Inspector 1 O gk Catawba Nuclear Station B400250214 940523
- 2 PDR ADOCK 05000413
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~Mr. HaroldLR. Denton, Director May 23,1984 Page 2 cc: Mr. Robert Guild, Esq. Attorney-at-Law-P. O. Box 12097 Charleston, South Carolina 29412 Palmetto _ Alliance 21351.Devine Street Columbia, South Carolina 29205 Mr. Jesse L. Riley Carolina Environmental Study Group 854 Henley Plac.e Charlotte, North Carolina 28207 1 4 i a l 9 y e d f Catawba Nuclear Station Power Piping and Mechanical Penetrations Compliance with GDC 51 Section 3.1, page 32 o'f the Catawba Final Safety Analysis Report addresses General Design Criterion 51 of Appendix A of 10CFR Part 50. This section states that the reactor containment boundary shall be designed with sufficient margin to assure that under operating, maintenance, testing, and postulated accident conditions (1) its ferritic materials behave in a nonbrittle manner and (2) the probability of rapidly propagating fracture is minimized. This section also states that the design shall reflect consideration of service temperatures and other conditions of the containment boundary material during operation, maintenance, testing and postulated accident conditions, and the uncertainties in determining (1) material properties, (2) residual, steady-state, and transient stresses, and (3) size of flaws. Duke Power Company has complied with these commitments for mechanical penetrations through selection of materials used in design of the mechanical penetrations. These materials have proven reliable and not subject to brittle fracture in Duke Power's operating plants and in general industry service. Mechanical penetrations for Catawba meet all code requirements. The effective code for mechanical penetrations is the 1974 edition of the ASME Boiler and Pressure Vessel Code, Section III, Subsection NC including summer 1974 addenda. In addition to complying with the FSAR commitments and code requirements, the mechanical penetrations comply with guidelines for GDC 51 compliance of Standard Review Plan NUREG 0800 for power operation including power transient conditions. In accordance with NUREG 0800, an assessment of material fracture toughness is made using fracture toughness data presented by NUREG-0577 and ASME Section III, Summer 1977 Addenda, Subsection NC. Using this method a Permissible Lowest Service Metal Temperature (PLSMT) is established for pressure boundary materials. Applying this method to mechanical penetrations, the limiting materials are the main steam and feedwater penetration flued heads, the main steam penetration process pipe, the main steam process pipe and the main steam process pipe fittings. Each of these items is assigned a PLSMT of 107"F by NUREG 0800. Duke Power's review concludes that main steam and main feedwater operating conditions will exceed a PLSMT of 107'F during power operation including power transient conditions. During unit maintenance and testing activities, the main steam and feedwater systems will be at ambient temperatures but not pressurized such that the PLSMT would not be violated. Main steam and feedwater system components required for containment integrity during Design Basis Accidents will also be exposed to temperatures in excess of 107 F. Sufficient margin is included in the 107 F value (30 F) to conclude that ~ GDC 51 requ'.rements are met by the mechanical materials identified above.- m. Catawba Nuclear Station Containment Structures Compliance with GDC 51
- 1. LOWESI gg8 MICE HEI6L IEUPEB81gBE (L!!I)
The lowest service metal temperature is identified as the limiting temperature which will be experienced by the limiting materials of the containment pressure boundary during the performance of the containment function under operating, maintenance, testing and postulated accident conditions. Calculations based upon conservative assessment of the ambient atmospheric conditions, the insulation and enclosure provided, and the specified minimum containment atmosphere temperature show the LSMT to be 490F for the steel containment vessel, personnel locks, penetration sleeves and penetration insert plates. The exterior face of the equipment hatch is exposed to ambient outdoor air conditions, and therefore it will experience a lower LSMT than the remainder of the steel containment. The LSMT for the equipment hatch is calculated to be 35ep, 4
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- 2. gggIgIggEHI EBE33MBE BgMHQ88Y !$I581663 (EEBBIIIg)
Containment pressure boundary materials have been reviewed within the context of General Design Criterion 51. The' aaterials of the following components were characterized with respect to fracture toughness' l A. gIEf', gg!IflHgEMI YE!!EL, EEB!g!!EL kgggg, EgyIEHEMI H6 Igg, egg PENE -- _TRAT_Iu_l SLEEVES
- 1) General As stated in Section 3.8.2 of the Catawba FSAR, the steel containment la designed, fabricated and erected in accordance with Subsection NE of the ASME Code, 1971 Edition, including addenda through Summer 1972. This Code edition providea for material fracture toughness by requiring drop-weight testa or Charpy V-notch testa at 30" F or more below the lowest service metal temperature.
This temperature was identified in the procurement specifications as 10c F for the steel containment vessel, equipment hatch and penetration sleeves, and as 48'F for the personnel lock. These temperatures are below the calculated LSMT for each component. Consistent and acceptable Charpy V-notch test resulta have been obtained at test temperatures at least 300F below the specified lowest service metal temperature, insuring that the material la acceptable for its intended service. To further demonstrate the suitability of these materials, the discussion below establishes that the service conditions for the material are well removed from the nil-ductility region. Generic nil-ductility transition temperatures for each type of material are used when data is available. i 4 1 i s
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- 2. gggIgIggg!I PBES!MBE Bgg!QABI M6TEBI6LS (ggBBIIIg) (cont'd)
A. !IEEk Cg!IAINMENT Vgg!EL, PgR!gNNEL LggK!, EgyIP!!!T HATgH, ANQ PENETRATION ELgEVEg (cont'd)
- 2) gingI gentgiunget vens,I SA-516 Gr 60, normalized, 1", 3/4", and 11/16" thick are identified as having been applied. Typical certified mill test reports for 1"
plate show Charpy V-notch test data which does not support the use of the Charpy test temperature as the LSMT within the context of the ASME Summer 1977 Addenda Class 2 rules. However, these ASME rules, NUREG/CR-3009, and CBI in-house data will support assigning a nil-ductility transition temperature of 0*F and a permissible lowest service metal temperature (PLSMT) of 30 F for these materials.
- 3) Penetratigg Insert Plates Thickened insert plates are installed in the containment vessel at some penetrations. SA-516 Gr 60, normalized, 3/4",
1 1/4", and 1 3/8" thick are identified as having been applied. Certified mill test reports for typical 1 3/8" plate were submitted for review. As was the case for the steel containment vessel itself, ASME Summer 1977 Addenda Class 2
- rules, NUREG/CR-3009, and CBI in-house data will support assigning a nil-ductility transition temperature of 00F and a PLSMT of 306F for these materials.
- 4) Peggtratiog gleeves SA-333 Gr 6, 24" Schedule 100, 1.531" thick, normalized, is identified as a limiting material. Certified mill test report indicates that the material was Charpy V-notch tested at -30*F to criteria consistent with the ASME Summer 1977 Addenda Class 2 rules, giving a PLSMT of -30*F.
Formed, welded, and stress relieved sleeves _ applying normalized SA-516 Gr 60 in 3/4", 1 1/4", and 1 3/8" thicknesses are identified as limiting materials. Subsection NE rules required qualification of the forming process, including tests to determine that required impact properties are met after straining. Proceduro qualification was required to be conducted using material of the same specification, grade or class, and heat treatment. Certified mill test. report data for 1 3/8" thick normalized material indicate that the material, before and after fabrication, met Subsection NE Charpy-V-notch requirements. While the Charpy results at -30*F do not meet ASNE Summer 1977 Addenda Class.2 rules to support the test temperature as the LSMT, they do support a PLSMT of 490 F or Icwer. A similar analysis is applied to 3/4" and 1 1/4" thick materials. l i i
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- 2. gggIgIggEMI EBEgggBE BQMHg6BI 56IE816LS (EEBBIIIg) (cont'd) i A.
HIEEk gg!I61!!EHI VE!!EL, EEggggMEk (QCH!, EggIPHEMI H6ICH, 8Hg PENETRATIQH @LEEVgg (cont'd)
- 5) Personne1' Airlock SA-516 Gr 70, normalized, 2 1/2" thick is identified as a limiting material. Charpy V-notch mila lateral expansion data at -300 F do not meet ASME Summer 1977 Addenda Class 2 rules to support the test temperature as the LSMT. However, these rules would assign a nil-ductility transition temperature of O'F and a PLSMT of 300F to the material.
SA-333 Gr 6, 6" Schedule 80, 0.432" thick, and 3" Schedule 40, 0.216"
- thick, identified as containment pressure boundary materials, would be exempted from Charpy V-notch testing by the ASME Summer 1977 Addenda Class 2 rules. Certified mill test reports, however, indicate that the materials were C
Charpy tested at -50 F, to Charpy V-notch mils lateral expansion supporting a PLSMT of -500F. SA-350 Gr LF2 fitting, -Scrd. coupling, 1"-3000#, is identified as a containment pressure boundary material. Based upon dimensioning of commercial forged steel fittings, ASME Summer 1977 Addenda Class 2 rules would exempt the material from testing. However, certified mill test reports indicate that the material was Charpy V-notch tested to energy criteria consistent with the ASME Summer 1977 Addenda Class 2 rules supporting a PLSMT of -50c F for the i material.
- 6) Eguipment Hatch SA-516 Gr 70, normalized, 3" thick, used in the hatch barrel, is identified 3
as a limiting material. Certified mill test reports for the material show Charpy V-notch testing at -30'F. The ASME Summer 1977 Addenda Class 2 rules would require no testa if the service temperature.were above 400 F.' NUREG/CR-3009 Table 4.4 assigns a 904 confidence nil-ductility transition temperature of -50 F~ to - the material. CBI in-house. data shows-typical nil-ductility transition temperatures for auch material of -10CF and below. ASME Summer 1977 Addenda Claan 2 rules can therefore assign a PLSMT of 35'F to the material. SA-516 Gr70, normalized, 1 1/8" thick is applied for the dished hatch cover. Consistent with the analysis for the barrel above,.ASME Summer 1977 4 C Addenda Class 2 rules would' assign a PLSMT of 25 F to.the material, i 1 i -
- 3. gg6LIII eSggg6 hcg ggCUMENI6IIgg [QB LIMIIING M8IEBI6Lg A. CMTR NNI File #46 (1" plate SA-516 Gr 60) (Steel Containment Vessel)
B. CMTR NNI File #50 (1 3/8" plate SA-516 Gr 60) (penetration insert plates and fabricated penetration sleeves) C. CMTR NNI File #187 (24" diameter Sch 100 SA-333 Gr 6) (penetration sleeves) D. CMTR Lakeside Bridge and Steel, Heat #T68952 (3" plate SA-516 Gr 70) (Equipment hatch barrel) E. CMTR Lanco Industries Heat #67302 (2 1/2" plate SA-516 Gr 70) (personnel airlock) F. CMTR US Steel Heat #A01359 (6" diameter Sch 80 SA-333 Gr 6) (Personnel Airlock) G. CMTR US Steel Heat #N14522 (3" diameter Sch 40 SA-333 Gr 6) (Personnel Airlock) H. CMTR Metalloy Heat #8865304 (1" blind flange, SA-350 Gr LF2) I. NNI Quality Assurance package for containment plate assembly 1-3-13 (Shows forming process for thickest fabricated sleeves and stress relief of entire assembly following penetration installation.) J. NNI Quality Assurance package for containment insert plate assembly 113-1 (Shows thickest penetration insert plate, sleeve fabrication and stress relief of assembly after 41eeve installation.) l l l l
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M NOTARY PUBLIC i MY COMMIESION EXPIRES MARCH M,1982 MATERtAL DESCRIPHON OUAN. T OR PIECE N#@ % A WEIGHT HEAT NO. BEh ME@ $% M-LENGTN PSI P$I IN 8' IN 2* AREA s.0000 ' 60.000 ' 180 g_g 1 9189 T68952 01 W2 + 3 54000 82500 29.0 '+
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. -. -. v.. e c.... co........-. v.y.. ~ TNS 6222 015383-6817 RAIL 'IP: 821989 8-31-76 7001293 9-29'-76 air M; RAHOR N o. YlELD TENSf LE DENO HOMO DESCRIPTION DHN PL ATE No. PCS. PSI PSI ELONG. :1E D UC1. TEST TEST ORIEN TEMP. 1 2 3 AVG. ~ STEEL PLT CARBON ASME SA516 GR 2 Ih~ I 73 FOR PV NORM +S3 SIWHT @ 1100*F i FOR 2-1/2aHRS ET UP & COOL D0;U 'd 160'F/HR MAX +SS CVNL EA PLT 20/ ,' l 7 IS FT LBS G -30*F NUCLEAR MAT'L Il To ver*P Asyn ntPV CODE _1971 rnT'r inn WINTER '73 ADDENDA SEC III DIV 2 CL MC g ( 2! ' 2G 2 HEAT 67302 2-1/2 x 120 x 130' P57908 2 47900 7640 30. L -30*F 15 h / g f %SIIEAR 20 20 20 20 f g. j j / . y LTE j 18 j,TO--29 7-22g 'g; /// P58031' , 2 49900 77400 23.0 L -30*F 27' 31 3I 3d /' 0[ ' % EHEAR 20 20 20, 20 /, t L.E 25 30 30 28 ,g BODI PL'1S & "EST CPI S WERE NCINAL1 ZED G 1G50* F, "IME 9 TEMP: 30 MIUUTES & A::R COOLED. F. 'IEST CFI S-QD,Y-WERE-STRESS-RBLitn.u 6.L..00*F, unss TEMI : lbo Mm un.S-TTURNACE L'Dd1E.D.*.Ll
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a. s NOWport News Industrb! Corporation SHIP-OUT NEWPORT HEW 5 5HIPBUILDING AND DRY DOCK CDmF ANY a nasce O' HEWPORT HEWS, VIRGINIA Subsidiary of Newport News Shipbuilding INSPECTIOt [0R: NEWPORT NEWS INDUSTRIAL CORPN. kea,- h oco w y REPORT __J A TE_NNECO CO. )_ EBRUARY 28, 1977 ...... o.... --.m i = ~, vi=- .e m 4.502.A (451.N)- [s] co, *.,,......, s.
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.p, d "a"*4a 'a'a a14.PCS. fdN"' ' /C9fa #- M CKaGEs CONTENTS p? ROVED BT Qg-6. DONE IIISERT WELDHENT ASSEMBLIES 111 1 THRU 1116 IBIG.288113. aIP' ff N..,. . =v 6. DOME INSERT WELDMENT ASSEMBLIES fit.7 THRU !!!.12 DWG. 288113. Ba 1.$ HELL INSERT WELDMENT ASSEMBLY 113 1.DWG', 288229 I. SHELL litSERT WELDIENT ASSEMBLY 113 2 - DWG.288229 NE an y. v.s co. naves antiau, co.nera. "/A A5 PER 'L IST ATTACHED. fklYo va.s eta nas iaanviattv ete ams>== Daffo LESS DUNNAGE ( &,o arruc ast e :=se rctions apeucast e o4Ta ORDER NOT COMPLEft s aca c'** cat * 'a*** c'= a a*
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w t b 3 out.t routa Cons Auv QUALITY AssuRANCC DirARintNT f' - SUPPLith QUAL 41T AssURANCL CER13flCAf toit PAf f9Cil'C /J:P $11tl'I'll:C P.f tttflit t7t?TS siame of supptser frevport Iteus industrial corporation case If#ftMf'1 */s IM'? Specification flo. C:8S-II44.09-1 Date N'6stOM'1 D, E ' Address of 5.pplier Plant 230 41st' Street allt Po.ee Order No. A-9Ril? N'evrmr t News. Vtr.Inla M60) Dube jgen er Req. me, y 144,0g.g Level A B C 1 Special spec. . E s-1144.00-t me, ,,4-Special supplier so mos. ' As noted per attachert shipour inspr.ce' ten Repores ya2 *h0 T1 -3$ -M 7 Description of Componeat(s) er naterlatts) br L*2 L-T-Avsmatss lit-i awcow 111 g_ 2. Pt.crActf:n (Atl51 N45.2.2 - 1972, Section 3 and Appendic A3) Nifi_t Tw sty Avrmst Fut3-t.t_)i3-2 Level A B C 1 S CC361 P a 3 Speclai Instructions aisached on aeasetten c ecs att Componeais/neserrais a nitt e e order. 'I AttMhed DM aentation covers partial shipneat of Componeass/nateriais on Rill Pender order. 3. SHIPP111C (AF:St N45.2.2 - 1972, The felte.sas lsted tests, laspections and reports have been ces,tened as ree.tred by the Section 4.2) i a s, clelcagi.ar Ca'rrier 0n Closed Special 2 Special Instructions 1 Physical & Chemical Analysis _ najor Repair Records & Charts _ siydro (Test Press.re - PstG 1 1 Personnet Q alifications on Record . _ pessoa seport _ seress Report ,,X_ neat v.naemt Shipment via Train
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Ship Other 1 mediographic Tes: . us erasoase Test i, negaevis rarticse _ penetraar Tes Repair Not ,,,,,,,_ t ieaallaess Description of other means _ Operatlag Test Perforaeace Cor,e _ Asnt Data Report 1 Disrational Check
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4. 10ADt!:C f. TPus ti (A!J5t lif 5.2.2 - 1973, Section 4.3) g . 5pecial Inst ructions for loading, rigging, hand 1Ing, preservative s, coatings, seals, stacking and vandalism precautions Thi> certifies then the listed CM, :(s) or nacerialis) cearer.. the 'ree.ireneens of she ai> e NevDort News fndustrial Corooration Instruction 451-NC-s00] rete: eased 0 ke P e 40*-Gaine als codes, staaderds. eest res.sreneats and Qvaiser Ass rance seg. ire = ears g 4 3 .a. . Y @0RD~' 5 lorrrvirscATror: Ar:0 MARrl!!G (AtJ53 ):y.2.2 - 1972 Apperadix A3.*) / htWi-dn.u. E. Ih RW l.IIMsppggsag' item itarkings newoorr wcus Yneustrf at corocration eravine and item / ep str' * $.ppteer Repres,a445 a.sheri,vd sieaaiore assembiv numbers and oualtry Cmtrot numbers W Title OA Manarer Date ' 2 *23 ~I~f - (see casar.caleas) Coatainer t'. arkin 95_ t*niform freteht classif teation rules form g3eLI A / Rev. 3 b 3 g i ~~ Torre 30t.li -O.
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