HNP-10-098, Response to Request for Additional Information Regarding Relief Request I3R-06

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Response to Request for Additional Information Regarding Relief Request I3R-06
ML102861818
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 10/04/2010
From: Caves J
Progress Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
HNP-10-098
Download: ML102861818 (32)
v • d • e


Text

Progress Energy OC*I*A 2010 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). to this letter provides the requested additional information. 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).

~

7SEISMIC 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 ýNA.YSIS DEPARTMENT SUýMMARY SHEET PROJECT-SHEARON-MARRIS UNIT I TO 4 SYSTEML

-\\

ANLS ý7WMLZ DATE-ýPL qý'J 3YISOMETRIC NO,

  • REV CHCE

.IATEý 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 HAý"AN ALYSIS TA. T*BLEýBEEN 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 ýVENT AND DRAIN 'FIX B

-EEN',INDICATED,'

IF REQUIRED L J WERE. ALL PIPING PHYSICAL rDATA INPUTf CGRRECTL*Y. ESPECIALLY SPECIFIC 17 GRVT,'

A RVSOBOX BOEEIN REVISED ýTO RE FL E C-T CHANGESý L*:WERE ALL-TEMP AND-I'RgSS DATA'I4PL'TVCORRECTLY, L

WERE, sEISMIC DEVICES LOCATED PER WEIGHT SPANS:, FOR REV 0

ýPRELIMINARY 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. ALýL 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*,ýSIINDiI 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

ý-

L'I ER AL OAIIIGAN JMDNAIO CSF

-SP~t_

il HAS AINI REO6ýD-,TO CjtOMAPLETE 4AALS*S ýTABLE,'BEEN'CHI-CKIEDOFF PFýIP'ING

ýWASýD'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

ý,CROSS-REFERENCED:'DATA (ITEMS THAT :APPEAR ON' OTHERISOSI BEEN LiWERE STRESSiRATIOS E'IFIED IND-cATED,

,°,<

  • CHECK,IHEETS 1'L[#ERE SNUBBER RrŽSTR!CTIONS CONSIDERED f

H AVE --ALL CHECK.OFF BOXES ANDBLANK

BEEN

'FIL IN L*JWERE CORRECT-"DEVICE SPRINGDCONSTA-TS.'AIPT i

"2,J HAVE ALL SIG NATU R E BOXES"BEEN FILLEDIN.

LJLJ ERE WALL AND.'FLOO.)P!ENETýRATIONS i.4r-E~tfED PDF.R,ýESTRiC:TI6NS r------------------------

6-(DOESiTHE PE"ETRTIN ATASA NI.R "i

H"AS':DATýA 'REQUIRED' TOICOMPL.ETE"ANALYSIS-'BEEN'-INDI*CA*TED

-jl AVE DIFFERENTIAL,EIS,',aiCDISPLACE4*

NI'BETWEEN;SU1LDING BEEN d_

EADSTRINT_.

NPUT COREI'TY

-HANGER2.AND R~ESTRAIN P4 WERE:FRICTION FORCES IF REQUIRED, INCLUDED-ANDý 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 ýOi ISO D SNUBB10E R" AT IN lý,II-'-ENENTIAL CASE MI[D.

IIHEPFDL LASE(S.'

u~-

-~

/Ia I IFB EP DEVICý WAS, RELOCATFD BY ANALYSTW AS-I.T JUSTIFIED L*.j*ERE A,'L

  • ppRCE MOMEiNT, TAND STRESSA.LLOWALCEERIFIED (EQUP PEN V! ALVES),
P-' jj WER EBP PDE SIONS VERIFI EDJ STAMPED 'RE VIEWED; AND DEVIATIONS INDICATED

,i*jjWE=RE.RC L*O.P.- LOCA D.D!PL.*ACEM'ENTfSCONID'*RED; IF AP'PLICABLE, i

oN *P'RIN:T-.-"

EiIý&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.

/faS7ýf

-* E a-,

I-*)

-aai161ei Cým ~pna

-peýr,-Shearon--Harri-sroeue'4r-on 6t-re~s ý-atcdulat4-n-

"APPROVED

- INbICATED:AStNOTTREOURED '

i OR.

-01 SNOT ýAVAII',ABLE,

,,OR PIENDIN*G/LATER

.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.

/5s*

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 2*

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 Jý Is

2.

If torsi6nit homentsla*r e than beinding m,,me-nt. onaee torlsonal moment wi~tallowablelmomen..

Torsionaf::moment is M*

3.

Flane Material i

KI' Design Temp.,

J i F

S, 3

ŽK.

'by

-s~

"T never S /36',..

be-ore tering by p36i (7h JIs.

nevert,takn...

as, greater tha n' 4nilty:)ý- 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 Mz*

  • OI'ld :be*,

reckded fojq the local o-,or*mrnate printout.

6.TCulcaIpoet s

"ieAddd algebracallyt& S0to$ata 1ýnd 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.~ICA44ýAIUV

/

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

]9-04-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~~Ž1_

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.

TorsMYon*Zat,nomeiintlnsmen

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:

C.p.*a*ret*'.-oants WithS*t;iatu..c (Norma) and dy'namc:c(Ups*)

'. rteria*onl 5.Myan d Mi 'sh,,ou.id, býý rec Iorded f rai the Iocr-al Icoordlnat6% ~r.inKto'i 67.

'7.

Thermal components 4aread-d'ealgebrwa*ta11d so-&tane.

as:* 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
  • ",2-ý.8 CHECKED BY ?Ž -a,6

ý_.-

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

usý,ta ned loads I

OBE,E-O7ccassjo6a Loads F-

-I, DB~K~c~.inal Loads'-

I A B........

.a S.

t*

i. d L d'.

ý----

s

.i____,-ý

'I

_.__it__e-d:

6 d.

I*.

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..:

1aýrgethaiibI'*!n.g'moment;

',compar.'e'- toesfiona rqoment wi-th a allowab le moment;;

'Torsional moment is; M 3.......Fange Material "K

Dec igrl.Temnp, I

Sy.

' 6

ý 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])

and*dyndmicF(Upset) c ite rj.

[

o4 ly.':n....

.. :-.>Ž"':

5.ý 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 ýcombJined.(by c6mponen 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"Pressurý,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 CIlas175*O'arid Class 300 flanges :only.,

BY

'V1io(,/Ai/?,/ 'DATE &271,G, CHECKED 'W A

G..- 'DATE

,1Z f.

VI9ikCO ýSERVICfr 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.IOr42SR~EET Cal I oA§ c

'Run."Da'te IfýN4'Rv oý I t I

NOTES:

1. MY and MZ arebending gren1s 2V2..

Torsional moment la 1

3

  • Mt T-0b

ýumi*

4. B31 !-':Fl,ngesý-~ XonTpa~rrz'%2P0O tirenfsý:with ýStafti:'.*

ral ~an dnamic (Uset

- c.

tx

ý.,., 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:ý,t h art ý-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 BYý 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:

Lý' 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

§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-cuniri-*bve.

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 ý,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 N*

Cal c-No,.*)j*,4.L.R'un -late8*2 '*-*

4

'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

-0 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 cný

--- 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. Is* 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. M8 Is

~omputed ýb*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,°390 ýDept.

No.

600

CAROLI NA POWERi AND LIT fD; CLI ENT:

PROJECT:

S. jECT:-

Flange Size'.

SHEARON HARRIS NUC!EA(1/2POWER"PLANT UNIT #1 1/2F;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

  • oads+OBE

=

.,-. 4 Dynam,'c C&D Therma i+Sistained,oads+DBE

(

?.

THERMAL j1/2~.

'Ssustaned Loa-ds";____

09E1 Occas~sional Lnads

ý 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~t7ýaine'd'.LoaasT+D'BE."-ý4 --

t~7' 9

NOTES!: T.

MY'and MZý: 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

'1/2*'

3.

Flange M.aterial Aesyign Temp. -.

Xse S /36 multiply ý:ble Va ILu by Sh i.neve:r.ta ken' as greater t~an.- unit-y) bFe ore 'ente~r ing1/2ý.,!ý ;Tlle-ALLOWALE1/2t'l bMOE4-colm~aoe 4i. :B~.BI.-l 1/2.Flanges::

Compare !2O6j, momen'ts w!ith.Satc (N:!

)and c

ynam!i,..pset)

Cril*teria 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 :scýope of th.s: eval Uat io n sýIee~t-tvE a'lut C

'lass l5O and ;Class 300, flanges only.

By.

DATE CHECKED, BY

."DATE_.______________

VBASCO

%S$RVICLS INCCOKPOR*rTD

'ST RECSS ANALLYIS DrPARTMENt CAROLINA POWER'AND, LI0GH CO1PNY SHEAkR'ON HARRIS UVIT SMErT.Ž.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

¢#1Sust~inied

[Loads 2**

OccasioD.l Loads"..9*

?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 ibý 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 sýhee't.

6Walute,.C1assý, 150ý 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 /Ž

..1~

,7 a

C.

7v-J:24'.Iep 71'w:ý

.2.

7;'_-'~~

"~ ~ ~ ~~~~...

  • .[

ILI...

S,

~

V~3F.

.,.-i/A'C.

P1A~k/{t<&'

AIi?/(<4..'

S

~

.2

& -: 2.. I7¢*

.y

.................--.. 1 2.9~.4 SR/ sA-o15

Page No.

CAROLINA POWER' & LIGRT COMPANY SHEARON HARsI,SUCLE*R PO,*ER PLANT CALCULATION S C.

7 71 RUN DATE:

s7:

ISO6 #

REV.~-

~

~

-ANAtYST,

i*,y, DATE'-/L.- P-CHECKER__________ DATE /7/,

1 "6

.. 7 H,,"-

.,b,,I.*

/

2-2 l

- v i* - -*.

= -- " ="* * "*

/

"& -;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 2',*

/

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

'6ý- 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

  • 4'-*

7 6________

____7 STATIC A & B TH.: + SUSTAINED LOADS 3-24f

,YNAMIC A & B T-H..,I.--SUST.. LOADS +/- OBE 92.2' OF 4*-

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

ýgreater 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 NOý6zzLE ACTUALS TO ALLOWABLES.

LOCAL 'COORDINATE SYSTEM CA C

  • O CONDITION LýOADING -

,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 ViŽ~ 1A

"~

1 T

-7J§L I

.1 -

~

--a-k,0OR0ZZ L-E A LLOWABLES,

'i DT i3-'-/

N F& ýBOVE

'R'E SUL-7AN T-,

R'ESULTAN T IF RC

-* MOM

/MNT'0 RCMMET 500 I~o Xý 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

'4JcZVl)*D 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.

/b&-,*5S-

)S:

."Q DO M** 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,,/ý.

.I57

.4-/

c EXIBLE ALLOWABLES NOZZLE LOAI EQUIPMENT J1S EQUII'MENT MODELED?

U YES-I, e

NO. U NOT REQD' REF. DOC.

FOR NOZZLE LOADS*:,

. -*,6.

2:..

ACTUAL"-1 EQ-IPMENTMODEL:___ _

FORCESý -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-Eý 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 l7*

A k

S'

.... L '.. °,"

t... -,...

z

-I

ient:

Projpect:

Subject:

Carlolina Power anid LIght' Company Shearon Harris Nuclear PowerýPlant+ Unit 41 NON-ACTIVE VALVES Ofs No. 2667.390 Dept.

Page

/

of _

600

'7 V

/

~~1 YSTSRESS CALC.

NO.:

-fMY

-" i'-;W :.

M*-*.,X*

REF;:

PR~oJEC*T SP:EC.

CAR-,SH-M-i45

!NOTE::

CG FACTORS7 ARE,CALCULATED FROM.GLOBAL

-"i:.-.. :CO-ORDINATE. (DBE*)""

6-...

CG. STRESS VALVE TAG.

VALVE: SIZE :

VALVE' VALVE C

'iALCULATEDIEMRK PT.

NUMBER"*

AND TYPE EMDRAC"No.

wEIGHT "G -

FACTOR R

A.--K-_

% o CD..

ýSE t

X D R m-' 3 0, 7,1

,, /.

'*,,"*P I

'"7,I*

  • D,

!NO't:- t~6 FACOR AR CACLAE FRO GLOBAL 7-YL C-4. S E

E T V

S z

l--.

z

---A

  • ~~~~~~~~~ ~ ~ ~~

~~~~~~

E*()* M R

K:SL"

,4

(.)."

PT NUMBE A,:N D,

T E

,E:--:.

AC.

G H

G-.-

ACTO

-R......

&.*. lm::* *;P-*:>*

q..,,:{** 7..- ;., 4-*

_.;.r m

,-..*" ",* t,' :

.....:s H * '* -......:

]..,

.j

, I.... : "....'. : ",, i *- !L

".' Y '.

... i...... "

=

L - *,..

375~~~ ~ ~~ ~~~ ~~~~~

~~~~~~~

L 1- -.

...i.... ;.

.*:'Z

... i....*.

' 7 ' r' T -

". t -**j */

", A,"

,, > /, U hc '+ -

,..

  • 1 *

<'7

  • i "

<" -7. :

',-*~h 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 FýýdL afi

,,*+I+,

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 sU*PORTS ONWALL VALVES.-

)

ISOMETR*IC-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

-704q6 I

0A r~w j~1 z iL, A

~-c~ A7~4

-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

_t*;

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-.l4ý"`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.

('2)*

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

ý-1 HPESý SYA CQLEARA.NCE. 'REV.1EWED),.X.,..-

BYTE C14ECKED BY:,

.CODESý:

(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-

,*
'.t.i<..

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.

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dh-1/3 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)° 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,, 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 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.ýa=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 103 psi Total Stress (per HNP Engineering)

Rr 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 103 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°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 A15 = 15 x o 0.495 in Flaw Length 2a < 15 percent of the pipe circumference Page 2 of 3 (1

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.

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Pag'e3 of 3

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