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{{Adams
#REDIRECT [[HNP-10-098, Response to Request for Additional Information Regarding Relief Request I3R-06]]
| number = ML102861818
| issue date = 10/04/2010
| title = Response to Request for Additional Information Regarding Relief Request I3R-06
| author name = Caves J R
| author affiliation = Progress Energy Carolinas, Inc
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000400
| license number = NPF-063
| contact person =
| case reference number = HNP-10-098
| document type = Letter
| page count = 32
| project =
| stage = Response to RAI
}}
 
=Text=
{{#Wiki_filter:Progress Energy2010 Serial: HNP-10-098 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTENTION:
Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 11 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST 13R-06
 
==References:==
: 1. Letter from D. H. Corlett to the Nuclear Regulatory Commission (SERIAL: HNP-10-004), "Relief Request From ASME Boiler and Pressure Vessel Code, Section XI Requirements forthe Service Water System," dated April 15, 2010 2. Letter from M. Vaaler, Nuclear Regulatory Commission, to C. L. Burton,"Shearon Harris Nuclear Power Plant, Unit No. 1 -Request for Additional Information Regarding a Relief Request to Defer an American Society of Mechanical Engineers Code-Required Repair of a Service Water System Weld until the Next Refueling Outage (TAC NO. ME3765)," dated September 22, 2010 Ladies and Gentlemen:
On September 22, 2010, Harris Nuclear Plant (HNP) received a request from the NRC (Reference
: 2) for additional information needed to facilitate the review of proposed Relief Request 13R-06. HNP submitted this original request as Serial: HNP-10-004 (Reference 1).Enclosure 1 to this letter provides the requested additional information.
Enclosure 2 to this letter provides a revised section, 6.5 GL 90-05 Through-Wall Flaw Evaluation, of relief request 13R-06. Inputs to the flaw evaluation were changed after review by HNP's Mechanical/Structural Engineering.
The deadweight contribution to total stress was eliminated because the line is in a vertical orientation and attached to a massive pipe.Additionally, the mean pipe radius calculation was revised to conservatively assume a pipe thickness equal to tmin. The previous calculation assumed a pipe thickness equal to tnom.This document contains no new or revised Regulatory Commitments.
Please refer any questions regarding this submittal to me at (919) 362-3137.Progress Energy Carolinas, Inc. / 1\ 7 Harris Nuclear Plant P. 0. Box 165 New Hill, NC 27562 HNP-10-098 Page 2 Sincerely, J. R. Caves Supervisor
-Licensing/Regulatory Programs Harris Nuclear Plant JRC/kms
 
==Enclosures:==
: 1. Response to Request for Additional Information Regarding Relief Request 13R-06 2. 10 CFR 50.55a Request 13R-06, Revision 1 to Section 6.5 cc: Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Mr. L. A. Reyes, NRC Regional Administrator, Region II Ms. M. G. Vaaler, NRC Project Manager, HNP T Enclosure I to SERIAL: HNP-10-098 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST 13R-06 Summar By letter dated April 15, 2010, Progress Energy Carolinas, Inc. (the licensee) submitted relief request (RR) 13R-06 for the U.S. Nuclear Regulatory Commission (NRC) review and approval.Pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g)(5)(iii), the licensee requested relief from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI, requirements for the service water system. RR 13R-06 pertains to a temporary non-Code repair of ASME Code Class 3 piping (i.e. interface between a sockolet and sockolet-to-pipe carbon steel weld on line 3SW3/4-1630SA-1 to a three-quarter inch supply piping to root valve 1SW-1344) in the service water system.The NRC staff has reviewed the information provided by the licensee in RR 13R-06 and finds additional information is needed to complete its review.Request 1: Please state the current operating temperature and pressure of service water in the subject pipe for which relief is requested.
Response: The current operating pressure and temperature of 3SW3/4-1630sA-1 is 64 psig and 89°F while operating on the NSW pump. On July 28, 2010, while 3SW3/4-1630SA-1 was supplied by the"A" ESW pump, the operating pressure and temperaturIe was 59 psig and 88°F. Per the design basis, the maximum operating temperature and pressure are 95°F and 130 psig respectively.
Request 2: On page 7, Section 6.4, it is stated that "the maximum pipe stress ratio from'Calculation 8050-79 at this location is 0.466." Please explain h6w 0.466 was obtained.
In addition, state the technical purpose behind it and how this value affects the American Society of Mechanical Engineers Coderequired flaw evaluation., Response: The reference to the stress ratio of 0.466 was an error inadvertently transcribed from a previous evaluation.
It is not needed for the GL 90-05 evaluation as reflected in the Supplement to the Relief Request 13R-06 (Enclosure 2).Request 3: In addition to the information requested above, please provide a detailed description of the input parameters, assumptions, and methodology used in Calculation 8050-79, such that the NRC staff can perform a comprehensive evaluation of this calculation.
Response: Stress calculation 8050-79 is provided in theAttachment to this Enclosure.
Page 1 of 1 Attachment to Enclosure 1 to SERIAL: HNP-10-098 SHEARON HARRIS NUCLEAR POWER.PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST 13R-06 Attachment
-Stress calculation 8050-79 MN/ML NG.: I L/ PRELIMINARY ,ASME SECT,ý I I."CLASS.,2q&A-3
--.ANALYST;CNECKLIST 1r'THERMAL
_ CASES), O ASL E ASE S" WEIGHT OPERA TING GEF. ONLY.{WEIGHTTEST REF iONLY I~JRELIEF.
VýAL YE. THRUST tI!ý'WIND/TORNAIDO:EP.FEC-TS, FLU ID (WAT ER/STEAM )H AMM ER VIBRATION 2 5 SEISMIC I TNERITIA Rl.BE).~7 SEISMIC BUILDING DI.SPLACEMENT (OB-E)7 1SEISMIC BUILDING DISPLA.CEMENT IDPE)W'EISMIC-SECONDARY-DISP.LACEMENT (0 8E) /'SEI SMOC' SECONDARY, DI SPL ACEM ENT (DB E)@SETTLEMENT JET IMPINGEMENT Ei 2'EQU ATION. NO. 8, 4 LIIEQ-UATION NO.ý 10, LIII E QUA T ION NOk 0.Eg.RUPTURE' EQUATION 14PIPE 00 -(IN.) MAX.. FORCE' ____(LB)@ MX-ISTRESS INTENSIFICATION F~ACTOR-_____
L INTER.IM MAx .STRESS>RATIO,(<I
_ iC_____"___
LOADCASE AL C. NO* See memo MN/MI. #ALL ITEMS MUST BE ,ERIFIED [] OR INDICATED AS NOT REQUIRED , OR NOT AVAILABLE -OR PENDING/LATER EBASCO SERVICES INCORPORATED NEW YORK; NY STRESS &#xfd;NA.YSIS DEPARTMENT SU&#xfd;MMARY SHEET PROJECT- SHEARON-MARRIS UNIT I TO 4 SYSTEML -\ -ANLS &#xfd;7WMLZ DATE-&#xfd;PL q&#xfd;'J 3 YISOMETRIC NO, *REV CHCE .IATE&#xfd;622.3 (SHI 4-78 MN/ML. /SHEARON HARRIS CHECKER'S REVIEW CALC. No..INPUT AND-OUTPUT .ISOMETRIC' SWAS CORRECT DBUILDING RESPONSE SP'ECTRA ENVELOPED WIT 15% SHI~fTER ALL, NHi ECS HW ON ISO PRSMO AL'WERE--CORRECT OPTIO~s.-ELECTEDI(N 2t0 PROGRAM Li HA&#xfd;"AN ALYSIS TA.
REVISED TO INDICATE NEWDATES.-*.iANALYST, CHECH ERETC."*ERE A~~~~~~~~~~~~~~~L-LAND.
U.ATEST:'-REF,..DOCiE'SsiVEONhiETc:
' " ! -- ./.' -Q. E A. D LTS R. .. L ISTED ON I.O.E.RIC L.J HAS &#xfd;VENT AND DRAIN 'FIX B -EEN',INDICATED,'
IF REQUIRED L J WERE. ALL PIPING PHYSICAL rDATA INPUTf ESPECIALLY SPECIFIC *17 GRVT,' A RVSOBOX BOEEIN REVISED &#xfd;TO RE FL E C-T CHANGES&#xfd;L:WERE ALL- TEMP AND-I'RgSS DATA'I4PL'TVCORRECTLY, " L WERE, sEISMIC DEVICES LOCATED PER WEIGHT SPANS:, FOR REV 0&#xfd;PRELIMINARY ANALYSIS ..L WAS EQUIPMENT, IF. FLEXlBLE ."MOD'ElCR.ECTLY 4,1,ND WAS MODELI" '- F U".D.. .NDICATEDONISOTR
"... ....O WALS AND COLUMNS SHOWN ANDU LOCATE.-DEVICES WRE INDICAED.
AL&#xfd;L TPUNNIONS,'
UCJG, ANGIORS, ETC al-A AND E'FSD-DT SI'.,S ATC-EHAS LE. DWG" TXBLE BEEN REVISED TO INDICATE-ALLNEW.AND REVISED DATA~WERE ALL ASSUM PTINOREG'EIG 10EET1~IAE ON SOMTRI KS EQUIPME$ORE*,&#xfd;SIINDiI D ODGEHENTSINDICATED ON ISOMETRIC WAS EjIPMENT," lRIGID SO OmDCATEDON ,RA" T C WER AL 'O'AINGAN
-74CNAION S F SCONSIDERED PER PIPINGi'DESIGN SE F &#xfd;-L'I ER AL OAIIIGAN JMDNAIO CSF -SP~t_ il HAS AINI REO6&#xfd;D-,TO CjtOMAPLETE 4AALS*S &#xfd;TABLE,'BEEN'CHI-CKIEDOFF PF&#xfd;IP'ING
&#xfd;WAS&#xfd;D'ECOUFLLI WAS C0PR FE~ DAA FROM OIN 'RU INUT CORRECTLY' H A45MISING.,DAT.,A ,RESOL-VED ,ITrEMSB3E'E'N.LINEDOU'bT'.ZJWERE.EXCESSIVE.
FORCES:-AND MOMEN,TSl
:,ERiF.LD
-: ;HAVE &#xfd;,CROSS-REFERENCED:'DATA (ITEMS THAT :APPEAR ON' OTHERISOSI BEEN LiWERE STRESSiRATIOS E'IFIED IND-cATED,.... ... -,&deg;,< -,: -:- CHECK ,IHEETS , ----- ".-. -1'L[#ERE SNUBBER RrSTR!CTIONS CONSIDERED
--f ",. " H AVE --ALL CHECK.OFF BOXES ANDBLANK :BEEN 'FIL INCORRECT-"DEVICE SPRINGDCONSTA-TS.'AIPT , i .-' ..--.-, -" "2,J HAVE ALL SIG NATU R E BOXES"BEEN FILLEDIN.LJLJ ERE WALL AND.'FLOO.)P!ENET&#xfd;RATIONS i.4r-E~tfED PDF.R,&#xfd;ESTRiC:TI6NS
-.r------------------------
6- (DOESiTHE PE"ETRTIN ATASA NI.R ...."i .... :H"AS':DAT&#xfd;A
'REQUIRED'
.-jl AVE DIFFERENTIAL NI'BETWEEN;SU1LDING BEEN d_ _ EADSTRINT_.
.., NPUT COREI'TY -HANGER2.AND R~ESTRAIN" :- P4 WERE:FRICTION FORCES IF REQUIRED, INCLUDED-AND&#xfd; IN CORRECT'DIRECTION EH-AS 1/31,G LOAD;i4G CA.,EF3EFH'SELECTSD FOR SECONDAR -SEISMIC EFFECTS* -wIL WREr SPRING HAANGERS/SUPPO-RTS INPU T CORRECTL'Y AND SHDWN &#xfd;Oi ISO D SNUBB10E R" AT IN l&#xfd;,II-'-ENENTIAL CASE MI[D. IIHEPFDL LASE(S.'u~- -~ /Ia I IFB EP DEVIC&#xfd; WAS, RELOCATFD BY ANALYSTW AS-I.T JUSTIFIEDA,'L MOMEiNT, TAND STRESSA.LLOWALCEERIFIED (EQUP PEN V! ALVES), ,'"-:P-' jj WER EBP PDE SIONS VERIFI EDJ STAMPED 'RE VIEWED; AND DEVIATIONS INDICATED.RC LOCA IF AP'PLICABLE, i : -- oN ; ' * ! .. " .--., --EiI&#xfd;&E NYDRODY'NAMIC.-
F'FE CTS; CONSi DERED- -IL 4s_.;G.,oPR:DECK SP ECtVA IN'CLUDED1N-SIN
--D ANAL.YSIS S-A W". ",iI WA --AND2. .. .- .-"EEI-WAS.
WV/ESTNGHOI.JSE L0 EISMIC DISPLACEMENT$'CONIIERE. " " " "ALLITs MUST BE VERIF!ED ,OR..- ALL'ITEMS.
/faS7&#xfd;f ." -* E a-, I-*) -aai161ei C&#xfd;m ~pna-pe&#xfd;r,-Shearon--Harri-sroeue'4r-on 6t-re~s &#xfd;-atcdulat4-n-
-"APPROVED-INbICATED:AStNOTTREOURED
' i OR. -01 SNOT &#xfd;AVAII',ABLE, ,,OR -.- ' , --: .-. ... .DA .. ___________,_, _.. " -- " ., ." , ." , -/ ..'4 p ;D ATE /u 4-- -ISO-METRIC NO. REV,-t4'l~l (ir s-la<I.B
...ASCO SEAVICLS INCORPORAT.tO
'2' , STRESS ANALYSIS DEPARTMENT SWEET O -CAROLINA POWER AND LIGHT COMPANY 2 CLIO ClNT " FS NO. _ _ _ __7 .SHEARON HARRIS UNIT #1. r No ,____"_FI.ANG-REVALUATION SKEET.-az1t I'd N -IqRun ate- iso- Nc. (Rev. No..I ri i +V mOm EtaT: IN IT B BNdING TORSIONAL;LOADING OR I_____ E_____ L NTS, .. ALLO I ARLE.-PT.. LIMITS TT: IM .TIAMN .-THERMAL Susta~ined Loads:4 ____OBE -O"casi I, Loads./DBE -Occasional Loads, :_"_____.___
tat c A&B Therfa+ Sustained Loads 0/'lynamic lAmB ThZrmat.SustaincdLoads+OBE
: ...... .........
.. t.. ..... ....... !aI n d. ... .. ..... -4 .%, V .Susta ..... Loa s -_ _ _ _ .ODBE,-Occasional'Loads -" _._:, " OBE,- Occasional Loads .'Staiic A&B Theral,4.tustnedVLoads 1, 49 Airk ThAtm3I4.
Su~t~ind ~j~-~- I -~Th~&O 174, 7-77 Thbimilw-Sustained Lcads+'4I Ihermal utie od+D T pq' &NOTES: and J&#xfd; Is .. : : 2. If torsi6nit
.e than beinding m,,me-nt.
onaee torlsonal moment wi~tallowablelmomen..
Torsionaf::moment is : .* ..-: .!3. Flane Material i KI' " .. Design Temp. , J i F S, 3 K. .'by -s~ "T never .S /36',.. be-ore tering by p36i (7h JIs. nevert ,takn ...as, greater tha n' 4nilty:)&#xfd;-
beforeetgr -ng t n .ithe KAL OWABL, MtOMENT colui mnabove.,' 531,1J! Flianges:, Comparge '01,0omeint, -wIhSta tcN.rma,)
aind d'nami, (Upset)criteriaonrly.
-...5.. Mx, My ,and reckded fojq the local printout.6.TCulcaIpoet s "ieAddd algebracallyt&
S0to$ata 1&#xfd;nd i~ad n cmippl nts*.% tve, areter Of .this-au :the.stain_..
load cobSU h :aby:-dnents),absolutely ,ith :O1Eor DBE. -: 7. MB I's:cmputed byf. cdmblnn fily and K*, by the*,'RS$SSmetd." 8., Refer to SHNPP Procedr 055, 9. Desjgn Pressure d O ps -10 Class 2/3Flanges for ipe sizes large. than 24" Criterjia pfor Class .400 and 'above areL outside the, scope of .thbisvaluation shee:t. Eva'luate.Class 150 and Class 300 fl.anges only, ...VX.~ICA44&#xfd;AIUV
/ DATE 87A HEC~KED D w6~.kDT W EbA$scO SenVICEs mNc'OPORATtD ST.IrrSS ANALYSIS D'EPARTMiEwNT CAROLINA POWER -AND LIGHT COMPANY CLgCHT SHEARON HARRI S UNIT- #1 FLANGE EVALUAT I OM SREET SHEET6/>~O)FS NO. 47 DEPT H6. __________z J-Rtin Calc No:5>f7Rev,.
No.M14ASS PT.TSERV.L114 iTS.LOADING OR.tOMSINAT4ii CASE-MoMiNrTw 4FT LB-BENDING SI MO-ME:NTS 1115. VTT. Up WIOENTS NX FT LB;A LAWELNT mY_____ -~ I.. A .k -THERMAL-N /410 '.J OB cainlLoads
'ze- LUJ jI DBE -Occasional Loads.4?AV4 V Static A&B Therrma!+
Sustained Loads S- ~ 2C .5k Dynamic, A0B Thcena!+SUstaincd.Loads+OBEI L 4 ]9 -T>,UA _ _J C.~- I b-t- DE.-Occasion.,o~
~7. S~2--______.Stat Vc A& hh~a4sustiaiedLOadsK' U\j?.. TW .~ .....4~f.DiNa:L .i~c LZ4~& B.2~emI is~e od4 Bj'~~i~~1_
4 4Li__I TUC ,, I ; -..'1-C &D ria!4t. S`4taied'Loads+
DBEI 2 4~~ 10 ~32 , , ,,; , I 777-=7 4.. 7.1-I__________
I -.--.----
.--- --------.---
---- ________________
F=-NOTES: IW, ,f, bindinngl a b =t.
' ., 3. :'FlanIe mate~rial A ..... _. DesIgn Temp.....
S. ____e___-.:,ui~T ntbl 4,.-ue ov atgreaiter than :unjlt bh r ert-p i " h t1,ALL'OWABE 6OETcoui aoe SB31-., ftan ges: (Norma) and
'.
-., ..5.Myan d Mi 'sh,,ou.id, b&#xfd;&#xfd; rec Iorded f rai the Iocr-al Icoordlnat6%
~r.inKto'i 67.'7.Thermal components so-&tane. ccn`ponents.
The.greater of this sum and: the sustained 10ad, cbay orients) bbute]y MB scS iomputed by ,comblniVng
/ flyand Mz:: by;tfiweSR$SS method.8'. Refer to SHNPP Procedure 055.9. Desi:gn Pressure = \ OU *si 10 Class .2/3Fianges for p.pe, sizes, larger than, 24: Crter ia for Class 400 and above ae. outside -the sope f. thisevaluatipn ,sheet.;Eva!ua"e C ass: 1:50 and, C ass 3.0 3Y DATE S CHECKED BY ? -a,6 &#xfd;_.-4 ,oDATE A,. /,"<2 / , ,,;.. ..
-.** ~ "I F CAROLINA POWER AND LJIGHT COMPANY Ofs.No. 2667.390 Dept. No. 600 CLI ENT:)JECT::SUBJECT-'.Flange Size__ _SHEAR N 'HARRI S NUCLEAR POWERPLANT -UN , I .I .........____ FL:"ANGE ItVALUATIOWS HEETj-/2." Rating I 'Y 2A-4so...No.
~1 ReV'#MASS SERV. LOADING OR. :MOMENT IN -FT-L BENDING- TORSIONAL LI OMITS C ..NATION, CASE MOMENTS MOMENTS ALLOW.P MY MZ .MB FT -,:LB' MX 'FT--LB .MOMENT THERM'AL --... !*OBE -O'cca's~sion aT Loa d s ____ f ...''.____ DE-Oca(!ssional Loads.' 4\42YAI___________,S~tat~ic A&B [Therl+stie'od -TA~Dynam ici A&B' 'Ther'a'l
+Sujstai ned Loads'+OBE~l~
t! ~ 42 IDyrpamic CtD Therr~a l+'S'u tt'ained'LasD J9'ut HR-MAL S us&#xfd;,ta ned loads I OBE,E- O7ccassjo6a Loads F- -I, DB~K~c~.inal Loads'-I A B........ .a S. i. d L d'. ...... &#xfd;---- -- .. .s__ ._ .i____,-&#xfd;
_____ :_ 'I _.__it__e-d:
6 d. -.-... .... .. ..- : .Dynam ic ..... A-&B -.T eml +/-S s~~e od4 .-~Dnr '''Th~e'K iial'+Susas ined',Load's+OB'....
',,-' ... --.....--
....: -.--'- :.- ..-" .....:. :-"- " "__ ___ __* I ________ 4.NOTES.: 1.MY and :MZ :are b',endingq momenis,..
: 2. If torsii s' a]: .i..:
',compar.'e'-
toesfiona rqoment wi-th a allowab le moment;; 'Torsional moment is; M 3.......Fange Material ', "K " Dec igrl.Temnp, I Sy .' 6 &#xfd;S,,136- , ' ., ~ mult-Ipy 6tabe& nvalues by.. S,6h'ich-.s,..;never,.taken as greater S ani,'tethe:
ALLO tABEEMOMENT, tbl'urnn" above-,.B,31-.JF langes Cobmpare 2010 moments with Static (Norma])
c ite rj. [ o4 ly.':n....
,...... ... ..:-.>"': ., : '. ..'.,,. .5.&#xfd; Mx:,. My.tanrid.
Mz.,.slhoouI/d
'be" recoled& from., the lotaVl: ,o-.di-atepiinFtout..
: 6. Thermal c 'hsneih tsaa Loads, components.
The grea ter of. this isttum, ahd, fth:, ,sus-tainerd, load &#xfd;combJined
.(by c 6 mponen ts')' absolutely -with OBE orDBE., 7. MB iS' computecl by combining, My. and Mz by .the SRSS- method.86 Refer to SHNPPP. Procedure 055,.9. Design"Pressur&#xfd;,e.,=
-psi.. ...i .... .. .. .." " ' -. .10.; 'C1 ss. 2/3 Flaanges fior liipe siie's F'#rer than 24". 'Cr ite rifo1r.c " 400C and above are outside the scope of'this eValuation sheet.. Evaluate Class 300 flanges :only., BY 'V1io(,/Ai/?,/
'DATE &271,G, CHECKED 'W A --G..- 'DATE ,1Z , f.
VI9ikCO &#xfd;SERVICfr IJCOAPOrIATtD' STR$5SWANALY&IS DL-PARTMENT CAROLINA POWER. AND LGHT :COMPANY-SW4EET ~a OFSN. 4&CPT NO. 67 S HEA RN0HA RS R ' 4N. I T' A I Flange Size: Rating. rJ 'FLANGE IEVALAT.IOr4 2 SR~EET Cal I oA&sect; c 'Run."Da'te If&#xfd;N4'Rv o&#xfd;I t I NOTES: 1. MY and MZ arebending gren1s .2V2.. ..Torsional moment la 1 3 *Mt T-0b &#xfd;umi*4. B31 !-':Fl ,nges&#xfd;-~ XonTpa~rrz'%2P0O tirenfs&#xfd;:with
&#xfd;Stafti:'.*
ral ~an dnamic (Uset-c .tx &#xfd;. ,. , I r ... .. " criteria only.5. Mx, My and Mzist'houldd
:e!.recoradd
'ro.the:1oaI'l co-ordInate prInt.out.
eatercf~ ~~-aim and the- ".4 J u;1It ) z sol.tely with .OE or: I..7.. 1B Is tomp"ted by. co:V*rn: ?4y7.5R 41zhy ti, eThSS nethcmd,.8,. Refer to SHNPP Procedure.055.
Design Pressure-k, D psi 10 Class 2/3Flanges for pipe sizes laeger:&#xfd;,t h art &#xfd;-2 i I C'Iriteri~a
-.fbrCass 40,0 and -above are outsi-de, the scope of this evalua, n~he. viaeCasi5 n ls 0 flanges only.., ,. \2 ~iA 4,DATE;.,~3~
CHECKED BY&#xfd; VkC-( A 4DATE WSP-CO SERVttiCE iICeORPORATtD STRESS'ANfALYSIS CPARTMEN CAROLINA-POWER~AND LIGHT, COMPANY&W E ET --- -ol E NO. 4 4;6 SHEARON-, HARRIS SIVUNIT4 #1 ri qOJr U Flag.SzeW Ra- In I LOA MIASS .SERV. : COMBJN T f. I H4I TS/2 .Ca tic No.. 7-,ku-yn-Da-Rev. No.'ATioft CASE MOUENT IN 'VT LB FU T LA TOM-INAL 4 E MLNTS'-Mx +-T Ls ALI.O'JABLE
)4DMENT A MY Sustained Loads.Z__C OBE -Occasional Leads DBE --Ocaional i oa __ 3__ ' 7 :___a6ti VC B Thelmal+ Sustairted Loads?. '(7.Z~4 mnam~rc A&B Thctmal+'SUstAined Loads+OBE J 7(~C D te r a.. ... .. ! "s+ D B "-._ _ _ _ _ _ _ ......_... ._ _ _ __, .. ..." -'i r ....... ':. .... ' : _ _ _ _ _ _ F ' ,'S taedLoads__
_ _ ___ _ _ _ _-BE, Occas ionalL. 'ads j _... ......'ITc A S B 7helmsa4 Ssl ie:od'_ _ __ _ _ _ __ _ _ _ _CSD:' UTecmal+ Suitiined Laazls+DBE 4______ ____________
_____N0O7ES: L&#xfd;' MY4 .Ne a.e bending Umfilefints
"' '....2 * :I. ..b r. s i.on a i, .m o , e t i a e e. .~ig o e t o & e o l o a '. -e.t .-i.. ..a l o v a l m , -'. , ...*Torsiol momenas S X. T ange ___ ___ ___ ___ ___ &sect;K_ _ __ _ _ _ _______ ____s,.s/36 ".-, mult~ply~table~va~ues~by'S 36 -6Whih is ,neVertakeh a: g reate than inity) befori. 6nterIng in thei'Ac.WA1 M-a OMNT-
: 4. 831 .1Fl~anges:
CoVnpare M "oments uth at ' and dynamic (Up...)r iterla only.5'..M, My and M should- be, recordede.
frdt.it e'hi loca lco-ordinate, pr irtout.~.XericaOnenhtL,'jret ade lerialCt ~t1ldLastqne!PtsL.
'The g.reater :of: .thssm Ind the ,,sisstaned toiad &#xfd;,ribnediJ;"(!,6y biponuiti')
absollutely with ' oD"r, DBE. 4" 7. 1 Is 'computed by combining H. and.vzby:the SS ethod .-B. Refer to SHNPP: Procedure
.055.9. Design' Pressure -VC, psi lass .2/3.FILanges.
for ;p ipe,- .s izes a larger L:than; 24"': Criterifa,.
for CJ'assA400 and above.,are 0uts"de the scope of this :eval.Uat'ion.
sheeit.. Elvluaute Ciass 150 and. Class 300 flanges only.3 .~ ,6@4r/DAE 6~-84CHECKEO BY --K -DATE, 9 !v ) PLY, tVASCO SERVICES INCORPORAkTD STRrSS' ANALYSIS "DEP:ARTMENT SNEETC7 J< 0 CAROLINA POWER AND LIGHT COMPANY SHARN LICN! OF$ NO.HARRISW UNI!TT #1.FLA-NGE VAoLUATIO-SIvT .Cal 24's~o :O;--::.-.-
Rev. No Flange Si.ze /.Rat-ing/ta MASS, PT..L -OOADING OR SR .-COMBINATIOW CASE'LIISj'MOENT r wTLa* *ENOING-~MOSS ENTS MU FT L3 TORSIONAL.
J4WNtTS -ALLOWABLE 14DMENT WV.THERMAL*SsandLoads  IZSIL IDBE -Occisional Leads-7---'14.a-t 1c A&B Thernal+ Sustait'nd LoadsI yna rnlc A&B Th cr t~ina? Sutained Lo ads+OBE 07 3 1 C& D Thtma+-Suitain'
-Loidis+/-DBE.
-74j,___I_____
BE -Occasoamas,,.
A-EDBE -oOe______
_____~at~c A&B hftanl,4:
Sited iads .. 7-----T .o cn&#xfd;--- 7A I I C ~O[ThemaI+us~aned~adsV-1E L az I i~' j --.S ____________________________________________________________________
NOTES: .....M .... .. ......nmom nt ...... ... ;.: .. :-,.: ".. ... ..:, -- ;," ..:,,: ,. .L. IiftorSionatmbr nn ii lstgert i'an bending6 oment, coipa-men
" Toisional momentr i .... ." ..' ..i -...r g e .,'01-:-.S /36 b-n , j'ti'py .table ,"alues by 36 (wh:ch. never taken-thanO ENT to'L Umin abo!ve.eate unl~ty,) before ,ente.rig in the ALLO:0ABLEIIOMENl g B31 I Flanges::A Conare' 2010 .mnoients with a: .(torma1)'and dyn (Upset)criteria only...5. Mx, My and Mz ,should be.recorded from. the ;loca co-ordinate printout.i. ..Therima1 coitonp1.are, adde~d a1gbr'k1 'a JS if 'n" Lims prens.'h'greater.
of '.4his-wmi nd thie 'ustinela o~ie b ~o~ ~ bjoj'Utejy r witfh ODE w DDE.. .. .... ...."..-.. .... .. ...7. M 8 Is ~omputed &#xfd;b*y combining ftyand Mz* by "the SRSS meithod.8. Refer to SHNPP Prctedu'er055" 9. Design Pressure, " psi 10. Class 2/3Fl:anges for :pijpe sizes ,largerv, than24": ,Criteriafor.
ass 00 andr 1above are out side. the s f this eva Jiuat-ioih.t Evaiua'te'C fa s' 15s0-and .-Cla ss 300 flanges oniy.V, iL iA ZDATE& 27 4,CHECKED BY. -LDATE
'"Ofs No. 2667,&deg;390
&#xfd;Dept. No. 600:CAROLI NA POWERi AND : LIT fD;CLI ENT: PROJECT: S. jECT:-Flange Size'.SHEARON HARRIS NUC!EA(1/2POWER"PLANT
-UNIT #11/2F;LANGE EVALUATI ON SHEET Ra t i ng. Ci:No. $c "' "7..Rn eK4~ s No. ,VsJ- Rev- #U1-1 MASS SERV .LOADIN "OR ... MOMENT IN FTLB "BENDING O ToRSIONAL MASS,- M ... .' M EN 4OMENTYS::
.... 'a--.- MMOMENTS A..LLW PT. LIMIT.M COIZNATION CASE M MB". FIT&-B' MX.. f T- LB MOMENT..... : TH.R.HER ..-: , .- , uti~netj Loads-'B ~ A Q ______ j j OB -Ocassional-od
___Stnati * ...A&B.. ..Therma I +Sus ta i ned Loads.. " Z-I "' --,] 0, _Dynam:c. A&B T ermal+Sustained
... -= .. .___...-__.'
.. ___.:___ .,-. 4 Dynam,'c C&D Therma i+Sistained ,oads+DBE ( .... .... _______ ?.THERMAL j1/2~. -'Ssustaned Loa-ds";____
_____09E1 Occas~sional Lnads &#xfd; ___________ _____ DE -Occassional
'Loads'S t at1:c 1/2 A'9:1 Thermai+SustaiTIned Loads____Q
' 'DyI; ,f&< A Ther -lASuti~ain'ed Load-s+OB 2)E1*",'''
D~ynamtwit C&D Th'ermai+Stfs~t7&#xfd;aine'd'.LoaasT+D'BE."-&#xfd;4
--t~7' 9 'NOTES!: T.MY'and MZ&#xfd;: ared. bending: m6ments.2.. If torsional momen t i s l a rger ithan b'endi~ng' moment,, compa -re,-tborsibna6 moim'lent" Withi al. al.mmn...osi~a.JcenhsM.
'. .... 1/2 3. Flange M.aterial Aesyign Temp. -. Xse , S /36 .multiply &#xfd;:ble Va ILu by Sh i.neve:r .ta ken' as greater t~an.- unit-y) bFe ore 'ente~r ing1/2&#xfd;.,!&#xfd;
;Tlle- ALLOWALE1/2t'l bMOE4- colm~aoe 4i. :B~.BI.-l 1/2.Flanges::
Compare !2O 6 j, momen'ts w!ith .Satc (N:! )and c ynam!i,..pset)
Ord ..'~ -" ' * ...... -....o..... ..--5. Mx, My and, shouild' be .recr.de r... tf h a.. la ..co:o ...t.... n. L .6:. Thermal components are ta-de a'gUbra'i1y tb-'.sta.iihed L6a'd''-LLcomponemts.
-.The ,greaite-r, of, :hi! sum and the1/2.uta rned t6&sasuim -and- d "ly wi th OBE or DBE. " ''. ' ,. .. '.by.-on-p" en'.s) b 7. MUs i6so onputed b'ycobinTing My' andMzi by' the SRSS method.8. Refer to ,SHNPPPro-cedure.
055.9. Design Pre-s-s'ure D psi 0 Css/ g or pirpe sizes atgger,'th i 24 'r teria, f or Class 0' and 'abov.arbutside .the :sc&#xfd;ope of th.s: eval Uat io n s&#xfd;Iee~t-tv''E a'lut C 'lass l5O and ;Class 300, flanges only.By. DATE CHECKED, BY :' ''."DATE_.______________
VBASCO %S$RVICLS
'ST RECSS ANALLYIS DrPARTMENt CAROLINA POWER'AND, LI0GH CO1PNY SHEAkR'ON HARRIS UVIT SMErT ..or 4;Size''ilange R-a t i Pg.-LNE (V ALUATI ON SKEET/c o: -zR-un Date U so tNoY Rev. o R'50 OR 1 MOMENT IN' FTll _U91 SENDN TfVl~i ORSIONlQ i~ casz fi JM N~h~1 OMENTS, ALLOWARLE n-r40 MX- TT MDt4ENT MASS PT'.SERV., LII:ITS TODI THIERMAL0&#xa2;#1Sust~inied
[Loads -..:, ---.:.<,- OccasioD.l
?f....OBE ;- O~ccas ionall Leads -A&A therrmal*,Susitaie Leadsf________________
nami A&B Trinail t.5ustailine i Loas.O ,,.-_______
U IB, T .e m %... Su i fi in% , C & D .. .. ....u. ed ...........
-Susainied LOadW&_ _ __ _ _ _ __ _ _ _ _BE .- Occzsional od _______DOE -Occasional, Loads, _______ Z it I!c AS er aonat.- Sustained" oads A&B lTherma.+
Sustained Loads .OBE 1 C 1D : I..ermak Su.tai..d
..ads..DB tEP _ __ _ __ _......2. iti lon ib&#xfd; t ila by,. bendng -. is foment or+r tris al aomlo w\oable .Tviinaimomntis MI.1 / 3t6ia _ _ _ _ _ _ _ _ _ _ 1eig T epMu l:t i l t a e v a6 l u e s b y SI3 w h c h Is h e v e r lt a k e n S reerterng n the ALNOWABLE MMEN PoIed" 0 .... .." 831. Fo langes: Corp)re 2010 mom ent with Sa tic (Nr ma ) a d dynamic (Ups e crEtIeia onl-.-h- 14 yad rsol be 'recorde, d firo the loal c-rdnate printout bfea lrkflhs-jkn:
and "the sustained" load comb~ie (by- tzoq ons) ab'olutel with 0DWiE rDBE. p K. Ml s tom-p'uted by combining fry anpd Mzb-iyte3S ehd 8:. Wefr to S!HNIPP Procedu're
'05,5-.9.Deslg Prsur ps 10 Classt 2/3tjlang-es
'for pipie sizes targer, than 24"'.' Crfieria f'or Clajs. 400 -and, above are, outsi~de the soe of thi s' e6vca1:uati on s&#xfd;hee't. 6Walute,.C1ass&#xfd;, 150&#xfd; and Class, 300 fla nges. o~nly.1 I1i .DT8'S HCEDB (P~,DT DATE CHEC.ktD V ATE... .. ... ....
Page No.CAROLINA POWER &,LIGHT COMiPANY SHEARON HARRIS. ~'LEARPOWER PLANT.CALCUTATION
'SHEET CALCULATION"Zso 77.'RUN DATE: " 4".....UNDA I6SO,?J REV.~ANALYST,________
DATE / rCHE CKER A 6 1I 2-.: DATE /..1~,7 a* , .:, C. 7v- J:24'.Iep 71'w:&#xfd;.2.7;'_-'~~"~ ~ ~ ~~~~... ... .... .... ...... .... ...... .... .... ..... .. -, , , ;. " ILI. ...,.- S, ~V~3F..,.-i/A'C.
P1A~k/{t<&'
AIi?/(<4..'
S ~.2& -: 2.. .y.................--..
1 2.9~.4 SR/ sA-o15 Page No. .____CAROLINA POWER' & LIGRT COMPANY SHEARON HARsI PLANT CALCULATION S -'C .'. 7 " 71 .RUN DATE: .s7: ISO6 # REV.~- -~ -~ --ANAtYST , -" DATE'-/L.-
P- CHECKER__________
DATE /7/, 1 "6: .. 7 ". ..-. H,,"- " .... .* ' ..,b ... -.-, .-/ 2- 2* l : -v -.-- ' = --" * / "& -;7"" ..-... ..*7....... .. ..--. ..". ,".. " SE/SA-.015-Page No. /0 CAROLINA POWER & LIGHT COMPANY SHEAR0Nt HARRIS' NUCL'EAR P'OtTE]R PLNT.LATG ,E --EV.kTUATIN SHEET..X ::. Y. : 47 -?. " ,.#FLANGE SIZE-'- ' .'1' RATING /- #CAL.. NO. iko1~&75 .RU DATE" 2-.3/4' {>"" ' " MASS, SERV. LOADING OR MOMENT IN FT-LB BENDING TORSION LOW M~- OMENT S MOMENITS MMN iTr LIMITS COMBINATION CASE ' b FTL MOMFT LLOW.MV Mz Mfb. FT.-LB. Mx FT-LE THERMAL 2-7c 7?", ,SUSTAINED LOADS ____.- / -OBE-OCCASIONAL LOADS -? -_/DBE-OCCASIONAL LOADS /i _________STATIC A & B TH. + SUSTAINED LOADS ,Q'.' :57qr .. Z."Z c L' q`7,1!5YNAIIC A & B TH-. 4: SUST. LOADS +O OBE 0 i2_ 6" O '6&#xfd;- q 3)YNAMIC C & D TH., + SUST:. LOADS. DBE 7197 6/$'i , (3 ]19 LI. A'5- q-4s"7--j SUSTAINED LOADS 223 _____ _____*OBE-OC.CASIONAL LOADS !2,'' 2,q3 9 1 _ 2 f DBE OCCASIONAL LOADS; 3 7 6________
____7 STATIC A & B TH.: + SUSTAINED LOADS 3-24f __--_- --_____- _ " ,YNAMIC A & B T-H.. ,I.--SUST..
LOADS +/- OBE 92.2' OF 41o -'L.)YNATIC C & D TH. -SuST. LOADS +/- DBE ..'?' '/ r .is.NOTES: *,1. My and Mz are. be'nding .nomdnts..I 1f torsional moment is larger than bendfng: moment', :compare torsional moment with al`lowable'moment.
Torsibnal moment is .Mx.3,. 'Flange Ma-terial b " :e'ign .. 'Te ; , p.-.____Sy/36 /d , multiply table:values by Sy/3, 6 (which is never taken-as&#xfd;greater than.-urity,).
before entering in the, ALLOITABLE MOMENT column above.4.: B3,1.1 Flanges: C ompare 20i0 momentsi with, 'Static .(Normal) and Dynamic (Upset)criteria only'.5. Mx, 'My and Mz -shoUld be recorded from .the local coordinate, piintouqt.
: 61. Thermal components are added algebraically -to Sustained Loads -components.
The, greater of this s'um and the Sustaihedload combined (by components) absolutely with 'OBE or DBE.7. Mb is computed..'by combining My and Mi by the SRSS'. method.,8. Refer to Design Guidelines.
for Piping Stress Attachment B.9. Design Pressure = e psi.10. Class 2/3 Flanges for pipe sizes 'larger. ,than. Z4"': Criteria.for Class 400 and above are outside the scope of this. evaluation sheet. Evaluate Class 150 and Class 300 flanges only.By.,,!/ .... DATE f?-f?-'C" CHECKED BY _______DATE/t
'Z"f" SH/SA-006 MNAmL .COMPARISON NO&#xfd;6zzLE ACTUALS TO ALLOWABLES.
LOCAL 'COORDINATE SYSTEM CA C O CONDITION L&#xfd;OADING -,a FORCE (LB) 1- MOMENT$ (FT.LB).AL~
_____ ______________
_______ ____ ALLOW. ALLOW___ ______ ______ ______PIIA~ COMB- CAS ACTUAL ",ACTALM PLANT__ PI_______
v, y V a ' :,- I T _ _ _ _ _ _ _ _ _ _ _ _ _!2 .-7 a--'l4~2~1 .1 Vi~ 1 A"~1 T-7J&sect;L I.1 -~ --a- -k,0OR0ZZ L-E A LLOWABLES, 'i DT i3-'-/ N F& &#xfd;BOVE'R'E SUL-7AN T-, R'ESULTAN T IF RC -* MOM /MNT'0 RCMMET 500 I~o X&#xfd;20 A ./2 Z 40A + j ' t ~Codnt A/! 2 .a I e IL"A' 125Z '00A 7Z)1/-Un L/DDat~~g IllRigid [llIlex~ible odeled? []Yes []]No: E114/ ne No -.A1Al6wables udYjVrd, Ebasco Nozzle Loads: jD0 [] "DO NOT meet the allowale cr iter i a.,..:Ref..Doc.
For Nozzle tod __:, __ _-_-* See:'memo MN/ML #.Equipment.
is: is Equipment mI PIPING ARRG-TDWG 6.-tL' dv-EQUIPMENT LOCATION ,/,/ / , )EQUIPMENT DW, \. z , ";A NOZZLE SIZE .N1_ .O.NOQZ-UPLEE IDNO.a'Jo' , , .." EBASCO SERVICES INCORPORATED NEW YORK, NY STRESS ANAL.YSIS DEPARTMENT CHECKLISTS PROJECT SHEARON HARRIS UNIT'NO. 1 SYSTEM , PI -AN T0STfhS'2
.5'T ISOMETRIC NO. REy , I -.E .-APPROVEDOh' 4_>F.a D"AT-J7'" / .622.4 fSH) 3-.0 CAROLINA POWER &11IGHT C-MPARY-SIIEARON HARRIS NUCLEARIPOWER PLANT COMPARISON OF NOZZLE ACTUALS, TO ALLOWABLES CALtC.ATION U 0P;'50- 'RIJN ' ATE " ....S .-,"".5 .S #:AxIAL_ -TRQUE BENDINC TO S ..-.. .I NT*SHlEAR. ..ORC E--Y- -FjD~ 'Mj 4 r :REMARS Z,;-V- -F_- _ _ _-~~- --- -- --ci. /1.00 USED:,. M'VENDOR' I EBASCO .PIPING, ARRj'T DJJ r" ,-,05 7 -5 ..NOZZLE-ALLOWABLES AS EQUIPMENT LO,-S .- i e.d ..P -(./C Sl-PER' CAR-SH-M-71 EQUIPMlENT DWG.
.)S: ."Q DO NOT MEET NOZZLE SIZE '/" POINT'NO.ALLOWABLE CRITERIA (REF.. TO SH/SA-013).
NOZZLE ID NO. /i f -.JAJ .k"7 '4 IS: RIGID ]FLEXIBLE
:LINE- I J,,/&#xfd;. .I57 .4-/* , c ' ...EXIBLE ALLOWABLES NOZZLE LOAI EQUIPMENT J1S EQUII'MENT MODELED? U YES-I, e NO. U NOT REQD'REF. DOC. FOR NOZZLE -.2:..ACTUAL"-1 EQ-IPMENTMODEL:___
_FORCES&#xfd; -IN .POUNDS, MOMENTS, IN FT-LB.. ,& LOCAL COORDINATES I Cl k,,t: Proj.ect:
 
==Subject:==
Carolina Power and Li~ght'Company Shearon Harris7Nuc:lear Power Plant- Unit #1 NON-ACTIV-E&#xfd; VALVES. .Ofs No. 2667.390 Dep.t. No.' 0 Page!7f 4' of %'V+Y rT .~~~STES5S CALC. NO.: c~/4 Fx Fz 0.SEISMIC LOADS:- X DI R. 3.Og / ---N.- ...... .. -.... Y DI"R.--2 Og--.. GR -4.6 9g .9 Mz Z DI:Ro 3.Og.+Z -+X ....REF; :!PROJECT SPEC. CAR-SH-M-45
..C .../ ..... .. G- FACTORS ARE CALCU.LATED FROM GLOBAL.. ....... ...~~.. ....NTE: OOR [NATE (D BE)C.G. STRESS:: VALVE TAG. V;ALVE SI`ZE VALVE ""VALVE. 'ALCULATED R E M A R S..-, '- ...NUMBER!TMO W G -FACTOR .-E -AC.'....., i ' 1 3 '.: !Y...T' Y=,E M --. .F..................... z : J. ....... ..' ... ........ ..- ... I.........
45 .z=Ic'. J -. .. ..., f .-..I ,, f * ., .*"e'.-' t ,.Y= " -; "7 A k S'.... L '.. &deg;," t ... -, ... ... .., , , ', :z-I ient: Projpect:
 
==Subject:==
Carlolina Power anid LIght' Company -Shearon Harris Nuclear Power&#xfd;Plant+
Unit 41 NON-ACTIVE VALVES --Ofs No. 2667.390 Dept.Page / of _600'7 V/~~1.. YSTSRESS CALC. NO.: _ , .-fMY-" i'-;W :. REF;:
SP:EC. CAR-,SH-M-i45
.. ......,> !NOTE:: CG FACTORS7 ARE ,CALCULATED FROM .GLOBAL....., ..... ...: -' -"i:.- .. :CO-ORDINATE
... .-....:... -..... 6-... , ,,'CG. STRESS VALVE TAG. VALVE: SIZE : VALVE' VALVE C :'iALCULATEDIEMRK PT. AND TYPE :: EMDRAC"No.
wEIGHT "G -FACTOR R --A.--K-_...." ...;, " .... .! -.. .* : % o .-. " -CD.. &#xfd;SE t ... ..- X D R m-' 3 0,  7,1 ..,, / .I " ' ' '"7 " --. ..!NO't:- t~6 FACOR AR CACLAE FRO GLOBAL 7- YL C-4. S E -----------E T V S z l--. z .---A .-..........
~ ~ ~~ ~~~~~~ M ... ...R " K:SL" ,4 '< .(.)." PT NUMBE A,:N ... D, , :':: ...: ;, ,, T E ,E:--:. AC. G H -G-.- .. .....ACTO -R ...... .. .... ."-. ....: .q.. 7 ..-; ., _.;.r m ..,-. ." t ,' : -: ... .... .. .." " ':.. ..... ... .. .. .! ..... .. ... .... ... : .. .... ..... ... ..... ..:s H -.... ..: .... ..... ..... ... .:- -....... , .] .. , ...... .... .... ... .;.j.... .. ., ... ..,, , ..,. ., I .. .. : " ....'. : ",, i !L " .' Y ' .... i .... .. " ..., -."' = .... .....L -, ..., " 375~~~ ~ ~~ ~~~ ~~~~~ ~~~~~~~ L 1- -.". ...i ....;. .. .. .., :,' ' : : ., ; ' : .. .. ... i ...; : : '. ,. ......... ", '. ... ; .; ', -:.: -, .. : : : ' " .; ' ' 7 ' r'
* T -" .t */ " , A," :,, > / , U hc '+ -_ , , ..1 .. ...<'7 .. ..' , -, i " ' <" -7 .: " .... " "" .. ' ',,,:." *" X ,/3037---I -~'1~-Y=
}lent:, Project: Su~bjec t: Carol ina Power :and. Llijht 'Company Shearon Harris 'Nuclear Power Pl!antt- Unit #1 NON-ACTIVE VALVEES Ofs No. ,2667.390 Dept. f Page d- of 1 600 JI STRESS CALC. NO.: Az+y.SEISMIC LOADS: X DIR-. 3..Og F&#xfd;&#xfd;dL afi Z," 7'' Y+ DIR.. .+ ,... 2..o0 4.699"'o__
M. z Z DIR. -3.0'g 4 I. m +, RE.. .PROJECT SPEC, CAR.,oS-M-45 EA : G FACTORS ARE CALCULATED
;FROM GLOBAL IFy CORDI'NATE.(DBE)-C.G. STRESS VALVE! TAGi VALVES CALCULATED PT. NUiBER ANDI TYPE: EMDRAC-N .. WEIGHT .G FACTOR....... .... -,-- , 7/ + -, ."" ,,, .,.. .< ,'f),i -A%- -.i-4~ H ' 1= ,Y=~ZoA., .C O7 -X='".""Y=, i+ ........ .... .... .... ..... .. ..... .... .... 7 i I .... ...... ...V ..I/A Ofs No''.:2667.390 Del No. 600 C.LiENT: PROJECT:
 
==SUBJECT:==
CAROLNA. POWER ;AND L!IGHT COMPANy .'._\ ...,Y/S.. SHEARON HARRIS ANUCL EAR: POWER, PLANT -'. ,U,NIT 1,: .'. ..B-P ONWALL VALVES.-)
NO REv t,... ...... ] ....!CA.LC SUPPOR F I R. E M.A R. K S 4.. p i~k~-2:& W 2 I.' fit A-f-~, .; u.~ SN ~ ~N b-314 f-7.3
/~O \2 77.C~j. N6. DA-7 0 4 q6 I 0A r~w j~1 z iL, A~-c~ A 7~4-c bce4-I.'T ,s.ZETT I-HFiES 'S AA I CLEARNCEE:
r.::: 3,Y'-DATE:CHECKED BY.CODES: () No' further act-inar required:by construdtin,.
..".-(2) 'Constrnctod -shall -i:/r'uiove insulation "per above.. oiants", (3) lhitiate FCR/PW as requiired.
,. ..,:
9 .J .... 2, I,1.,CL. ....... 7. 1 FxA3 --SO. ..-.. /CALC. No,. -C DAT* ... .".,KDO t ,,., SSECIALIST' E Io./-5 T ,1 i i i.. ... ..................
.. .OTL .CODE, 0.. L CODE V ..... .. .* .......: !' ...... ._ ' , , , " _ _ .; _.'.-_ _ _ .1...... .~....'_ -"-,. ;; V.S. .D B, ..CHECKED.BY CODES: urther action required by. construction,.
,*6 f, ,--- .__ 4a;? -.... , .. ..........
... " ........ "..............., (2) Contrutio shlltrim/remove insulation
:per .above coments'.-() nItiat~e FCR/P.W as require4.d
.-B" ..79-.l4&#xfd;"`PIPING:CLEARANCE -REVIEW 7 ..FAB ISO .N o ." 1-; W -f ' 0P A EO CALC. No. _ -___ .,SE I DATE OITL # 1DESCRIPTION/SKETCH
; RE .CDE COMMENTS.... .. ..L "." ~ / 6 ' , -* .. --*-.... *_... .._--_ _ __,_ _,_,._ _._.._ _._ _,._ _: : .. ,i , ......i -".'. .._ _ _ _ _ _ _ _ ....__ _ _ _ _ _I -.HPES S/A CLEARANCE REVIEWED BY DT:If$ CHECKEDBY CODES: '(1) "No further action required',by
.6onstructioil.h Cnstructibn shall trim/rermvoe .insul'ation...per ab6ve comens..(3) Initiat'6 FCR/PW as required.
..
79,,14'4 PIPING' CLEARANCE" REVIEW .FAB IS. .. N6. PAGE OF CALC. N. ....WALKDOW. SPECIALIST DT OITL D# DESCRIPTION/SKETCH
." --..-,- -...-..OIL#CDE, REVIEt O I N S OT# CD EVE O@ET&#xfd;-1 --.....................
...HPES&#xfd; SYA CQLEARA.NCE.
'REV.1EWED),.X.,..-
BYTE C14ECKED BY:,.CODES&#xfd;: (I.~ "No-furthe, 'ac~tilbn ieq ,ua'u'r~ed.by cons truction.(2Y~dnstucioisa~ll
-Eim/~remo-,Ae insulation pgr-above comments.(3), Initiate FCR/PW ais reequiied.
.U FAB ISO.. No.79.14 PIPING CLEARANCE REVIEW PAGE -___ OF_DATE .CALC. No.OITL #"# DESCRIPTTrION/SKETCH
-.-.ITL# .COE REVIEW /COMENTS 6tiT# CODE REVIEW. COMMENTS.
-OPE'S S/A CLEARANCETREVIEWE-D BY- -DATE + CHECKED BT, Y: CODES. .d by cqA4,,'-ction.
.-, N..HE S/A CLAf NC u RVI ftE her-requir /t (2) Construction shall trim/remove infsulation per above comments'.
(3)) Initiate' FCR/PW as required..1 I.
SHEARON HARRIS NUCLEAR PROJECT"'AS-BUILT VEZIF.ITIPON PIPING.CONFIGURATION CHECKLIST/N* \Calculation No. 3i- -7 ?Stress Item No. Item Requiring .Verificatlion , Wheregerified
.Acceptablej , 1. 1 ' -2 1 ,.. I .W he e Vrified i.2 3..4 6: 10.II.1'31 Piping geometry Pipe Outside Diameter Valye Location, TigNumbers Valve Operator:
Oriehtation Reducer Location Type of. Elbows, Tees Floor/ Wall Sleev'e :Clearance, Clearance Between 0ip Ie Ia nd Structural Members Pipe Embedded in-Wall SI/R Loca'tion and, Function InInsulation Ltocation&#xfd; of InstrumentTaps., Slope of Pipe Weld.Locations on Class -1 WP- 141 CQC 19, Form QA 28'WP-141 WP-. 141 WP- 141 Sw Fab 'NPP- I Code D.R.WP- 141 WP-1.L41 WP- 1'0/WP, 141 Line List WP-14L'Yes'L Il No--.r tV/,Z -/VQ~f ~6Q~I~I~Rerhatks:....... ,. ............
rformed by Checked by.. Dateb// -dh-1/3 Enclosure 2 to SERIAL: HNP- 10-098 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 10 CFR 50.55aREQUEST:
13R-06 Revision 1 6.5 GL 90-05 THROUGH-WALL FLAW EVALUATION GL 90-05 "through-wall" flaw evaluation criteria were used to evaluate the pinhole leak in ESW line 3SW3/4-1630SA-1.
The GL 90-05 criteria are applicable since this line is ASME Section III, Class 3 piping per the Engineering Design Basis (EDB).The allowable stress for the pipe material ASTM A106, Grade B per EDB is: S = 15000 psi ' reference ASME Section III, Appendices The pipe properties for 3SW3/4-1630SA-1 (three-quarter inch, schedule 40 pipe) are: (
 
==Reference:==
 
EDB, Calculation 8050-79, NAVCO Piping Datalog)Do = 1.050 in Outer Diameter tnom = 0.113 in Nominal Thickness t = 0.103 in Actual Measured Thickness (which is greater thanttmin) p = 150 psi Design Pressure T = 95 deg Maximum Operating Temperature The allowable stress intensity factor (K) for determining the acceptability of flawed piping under the applied load is: Ksi = 35 ksi(in)&deg;5  (reference NRC GL 90-05) where, ksi 1000 psi Minimum required wall thickness due to hoop stress, per ASME Section III, Class 3 Equations:
/ pDo -0.005 in m -2(S+0.4p)
The following through-wall flaw evaluation is performed in accordance Wvith GL 90-05, Enclosure 1, Section C.3.a. The stress intensity factor for through-wall flaw (including safety factor of 1.4) is: K = 1.4 (s)(F)(3.1416*a)O
., where: the geometry factor "F" is: F = 1 + (A)(c)'-" + (B)(c)2" 5+ (C)(c)3" 5 , where: Page 1 of 3 Enclosure 2 to SERIAL: HNP-10-098 SHEARON HARRIS NUCLEAR POWER PLANT,. UNIT NO. 1 DOCKET-NO.
5024OO/RENEWED,:LICENSE NO. NPF-63, 10 CFR 50.55a REQUEST: 13R-06 Revision, 1, 2a = the flaw length, in, (reference GL 90-05).Sa=005,in 2a 0.10 in, (Note: The flaw length.(2a) is.basically the di ,meter.,of, the pin ho!e which is les's than.0.0625"-
However, 0.05 is conservatively used f6ri'a". (2.&#xfd;a=2*0.05=0.100>0.065"))
R mean pipe radius = D -t 0.522 in.(3.1416)(R)
=0.030 's = 3.135 x 10 3 psi Total Stress (per HNP Engineering)
R r 99.9 Stm A = -3.26543 + 1.52784r -0.072698r 2 + 0.0016011r 3= 1.02 x 10'B = 11.36322 -3.91412r + 0.18619 r 2 -0.004099r 3 = -2.608 x 10 3 C = -3.18609 + 3.84763 r -0.18304r 2 + 0.00403r = 2.572 x 103 F = 1 + (A)(c).5 + (B)(c)2'5 + (C)(c)3" 5 = 6.015 Therefore, K = 1.4 (s)(F)(3.1416*a) 5 5 10.462 ksi(in)0 5 K < Ksi = 35 ksi(in)0&deg;5 Per GL 90-05 criteria, the flaw length "2a" (0.10 inches) shall not exceed either three inches or 15 percent of the length of the pipe circumference.
Pipe circumference A = 7c x Do = 3.299 in A 15 percent of the length of the pipe circumference A 1 5 = 15 x o 0.495 in Flaw Length 2a < 15 percent of the pipe circumference Page 2 of 3 (1 Enclosure 2 to SERIAL: HNP-10-098 SHEARON HARRIS NUCLEAR POWER PLANT; UNIT NO. 1 DOCKET NO. 50-400/IRENEWED LICENSE NAO. NPF-63 1 0 CFR 50.55a7 REQU EST: 13R-0 6 Re v isioii 1 Note: The stresses considered in originhalrRelief Request 13R-o06,Re6v.0 wre conservatively evaluated to be 7461 psi. The stresses used in the abov'e calculation, 3135 psi, are based on a more realistic approach to account for all loading condifions to which this pipe is subjected.
The deadweighlt contribution to total stresswas eliminated because the line is" in &avertical orientaltibriarn d;attaihed t a" massive pipe'. Additi6nally, thie mean pipe radius calculation was revised to conservatively assunmea pipe thiokness-equal-to train. The previous calculation assumed a pipe thickness equal to tnom.The through-wall flaw evaluations for the pinhole flaw demonstrate that the piping, including the weld joining the pipe to the sockolet for line 3,SW3/4-1630SA-1 is structurally adequate per GL 90-05." , " ..s .,: I. " .( ' , : " " -:.; : :: , : .:: , : Pag'e3 of 3}}

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