Text

Containment Sump Check Valves Weld Overlay Repair Design
	ML20064E491
Person / Time
Site:	Palisades
Issue date:	03/04/1994
From:	Froehlich C; AFFILIATION NOT ASSIGNED
To:	;
Shared Package
ML18059A868	List: ML20064E445; ML20064E462; ML20064E483; ML20064E491; ML20064E501; ML20064E530;
References
	0054-00101-001, 0054-00101-001-200R0, 54-101-1, 54-101-1-200R, NUDOCS 9403140322
	Download: ML20064E491 (31)
	v • d • e

ATTAcilMENT 5 Consumers Power Company Palisades Plant Docket 50-255 CONTAINMENT SUMP CllECX VALVES WELD OVERLAY REPAIR DESIGN March 6, 1994 Y

9403140322 940306 PDR ADOCK 05000255 P PDR '

1

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0054-00101 001-200 ,

Revision 0 VECTRA 00s4.00101.001.200 CALCULATION PACKAGE CONTAINMENT SUMP CHECK VALVES WELD OVERLAY REPAIR DESIGN PALISADES NUCLEAR PLANT Prepared for:

Consumers Power Company Prepared by:

VECTRA Approved by:

~ ~

Date: '

Carl H. Froehlich, P.E.

Project Engineer

,e ,-- .,w. , e-- ,

_O REVISION CONTROL SHEET 4

TITLE: Calculation Package Containment Sump DOC. FILE NO.: 0054.00101.001.200 Check Valves Weld Overlay Repair Design Palisades Nuclear Plant.

(0054-00101-001 200)

Carl H. Froehlich / Staff Engineer- dMh !

NAME/ TITLE ' INITIALS -

James A. Brown / Staff Engineer lh NAME/ TITLE )lNITIALS Jarnes W. Axline / Staff Engineer f[ po,s Jag NAME/ TITLE

' INITIALS NAME/ TITLE INITIALS AFFECTED DOC. PREPARED ACCURACY CNTERIA PAGEIS) REV. BY/DATE CHECK BY/DATE CHECK BY/DATE REMARKS lssued for use.

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PAGE 1 OF 1

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- iii - 0054-00101-001 200 VECTRA Revision 0 TABLE OF CONTENTS Pace

1.0 INTRODUCTION

1 2.0 MATERIALS 3

3.0 DESCRIPTION

OF INDICATIONS 4 4.0 WELD OVERLAY DESIGN CRITERIA 5 5.0 LOADS / STRESSES 11 6.0 WELD OVERLAY DESIGN METHODS AND RESULTS 15 6.1 Overlay Thickness 15 6.2 Overlay Axial Length 16 ;

7.0

SUMMARY

AND CONCLUSIONS 19 f I

8.0 REFERENCES

20 APPENDIX A - CK-ES3166 Indication Location Sketches A.0 j APPENDIX B - CK-ES3181 Indication Location Sketches B.O I

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0054-00101-001-200 i VECTRA Revision o l

1.0 INTRODUCTION

A leak leading to the shutdown of Consumer Power Company's Palisades Nuclear Plant was identified in a check valve (CK-ES3166) in the auxiliary building west engineering safeguards room on February 17,1994.

Subsequent nondestructive examinations also identified indications in another check valve (CK-ES3181) and additional indications in valve CK-ES3166. As shown in the Reference 1 system diagram, these valves are part of the Engineering Safeguard System (ESS ; Safety injection, Containment Spray, and Shutdown Cooling Systems). The general location of these valves is shown in Figure 1.0-1. The identified indications are located in the downstream end of the check valves which are each welded to a 24" x 24" x 14" tee fitting.

The ESS was originally constructed in accordance with ASA B31.1-1955.

For the purposes of inservice inspection (ISI), the ESS is currently treated as an ASME Class 2 system. This calculation package presents the design of Code-approved weld overlay repairs for these check valves.

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0054-00101-001-200 l VECTRA Revision 0 l l

Figure 1.0-1 i

GENERAL LAYOUT OF CONTAINMENT SUMP -

CHECK VALVES 1

SAFETY INJECTION REFUELING WATER TANK (1) TO HP & LP SAFET/ INJECTION &

CONTAINMENT SPRAY PUMPS V V CONTAINMENT SUMP _

4 (1)

(1) 4 __

A ,

_L 3181 r CONTAINMENT 4, 'f >< ll W PENETRATIONS 4, Nj >< "

- *--n 3166 24' x 24' x 14" TEE V ,

(1) l l

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1 0054-00101-001-200 :

VECTRA Revision 0 l 2.0 MATERIALS The Reference 2 stress isometric drawings indicate that check valves CK-ES3166 and CK-ES3181 are in a 24" piping system with an HC-3 designation. Per the Reference 3,4, and 5 piping class sheets, an HC system has an ANSI B16.5 rating of 150# and is made of austenitic stainless steel.

The Reference 6 and 7 spool drawings indicate that the tees welded to the check valves are ASTM A-358, Class 1, Type 304. The Reference 8 procurement documentation indicates that the bodies of check valves CK-ES3166 and CK-ES3181 are ASTM A-351, CF8M.

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V 0054-001o1-001-200 VECTRA Revision o

3.0 DESCRIPTION

OF INDICATIONS The Reference 9 and 10 documents present background information detailing the discovery and investigation of the check valve indications.

Replication and etching of these valves indicate multiple weld repairs prior to operation of the Palisades Nuclear Plant. One large repair was found adjacent to the through-wallleak.

Appendices A and B contain indication location sketches for the check valves based upon visual (VT), ultrasonic (UT), liquid penetrant (PT), and radiographic (RT) examinations. Indication 8 shown in Appendix A for valve CK-ES3166 is the flaw found leaking on February 17. Because of their location in the cast valve body transition areas adjacent to the valve-to-tee weldments, volumetric UT was unable to determine the depth and through-wall position of the indications.

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. .Y 0054-00101-001-200 VECTRA Revision o 4.0 y(ELD OVERLAY DESIGN CRITERIA i The weld overlay repairs to be applied to check valves CK-ES3166 and CK-ES3181 shall meet the requirements of American Society'of-Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPVC)

Case N-So4-1 (Reference 11) and Paragraph IWB-3640 of ASME BPVC Section XI,1983 Edition with Winter 1985 Addenda or later Editions and.

Addenda. The weld overlay repair designs presented in this calculation package shall use the Reference 12 Edition / Addenda of Section XI. l 1

l The outside circumference, L ,, of a 24" nominal outside diameter pipe is as follows:

.)

~l L , = 24"

rr = 75.4" .)

The total length of the circumferentialindications shown in Appendix A'for check valve CK-ES3166 is clearly greater than 10% of L,.. Therefore, the design of the weld overlay repair for valve CK-ES3166 shall be based upon an assumed 100% through-wall by-360* long flaw. Consequently, because the weld overlay repair to be applied to valve CK-ES3166 shall be made using the Gas-Tungsten Arc Welding (GTAW) technique, ASME BPVC Section XI Tables IWB 3641-1 and IWB 3641-2 shall be utilized (Table IWB-3641-1 usually governs).

The total length of the circumferentialindications shown in Appendix B for check valve CK-ES3181 is clearly less than 10% of L, . Therefore, as; permitted by Code Case N-504-1, the design of the weld overlay repair for

- _~ . . _ _ _. . . . _ _ _. -

n V/

0054-00101-001-200 VECTRA R evisio n 0 valve CK-ES3181 could be based upon an assumed 100% through-wall-by-l actual total length flaw. However, due to the small magnitude of loads acting at valve CK-ES3181, the design criteria employed for valve CK-ES3166 provides the thinner weld overlay repair while still meeting the requirements of Code Case N-504-1 and Section XI without introducing unnecessary additional weld overlay axial shrinkage. Therefore, the weld overlay repair design for valve CK ES3181 shall also be based upon an assumed 100% through-wall-by-360* fong flaw.

Table 4.0-1 presents Table IWB-3641-1 from ASME BPVC Section XI (Reference 12). Because this table has an arbitrary cut-off point at a stress ratio of 0.6, VECTRA has developed an expanded version of Table l IWB-3641-1 as shown in Table 4.0-2 that has been previously presented to the United States Nuclear Regulatory Commission. The expansion of this table is based upon the source equations presented in Figure 4.0-1.

y 0054-00101-001-200 VECTRA novision o Table 4.0-1 ASME BPVC SECTION XI TABLE IWB-3641-1 ALLOWABLE END-OF-EVALUATION PERIOD FLAW DEPTH"'-TO-THICKNESS RATIO FOR CIRCUMFERENTIAL FLAWS NORMAL OPERATING CONDITIONS (Reference 12)

Ratio of Flaw Length, f,, to Pipe Circumference (3) p* pb (2) s* 0.0 0.1 0.2 0.3 0.4 2.0.50 1.5 (4) (4) (4) (4) (4) (4) 1.4 0.75 0.40 0.21 0.15 .(4) (4) 1.3 0.75 0.75 0.39 0.27 0.22 0.19 1.2 0.75 C.75 0.56 0.40 0.32 0.27 1.1 0.75 0.75 0.73 0.51 0.42 0.34 1.0 0.75 0.75 0.75 0.63 0.51 0.41 0.9 0.75 0.75 0.75 0.73 0.59 0.47 ;

0.8 0.75 0.75 0.75 0.75 0.68 0.53 0.7 0.75 0.75 0.75 0.75 0.75 0.58 '

10.6 0.75 0.75 0.75 0.75 0.75 0.63 NOTES: i (1) Flaw depth = a, for a surface flaw

= 2a, for a subsurface flaw t = nominal thickness Linear interpolation is permissible. l (2) P. = primary membrane stress (P.10.5S.) !

P. = primary bending stress S. = allowable design stress intensity (in accordance with Section lil) i (3) Circumference based on nominal pipe diameter.

(4) IWB-3514.3 shall be used.

I l

l 0054 00301 003 200 l VECTRA Revision 0 Table 4.o-2 EXPANDED TABLE IWB-3641-1 ALLOWASLE END-OF-EVALUATION PERIOD FLAW DEPTH"'-TO-THICKNESS RATIO FOR CIRCUMFERENTIAL FLAWS NORMAL OPERATING CONDITIONS i

p Ratio of Flaw Length, f,, to Pipe Circumference (3) j

. p, (2) ;

s'" 0.0 0.1 0.2 0.3 0.4 2.0.50 1.5 (4) (4) (4) (4) (4) (4) 1.4 0.75 0.40 0.21 0.15 (4) (4) 1.3 0.75 0.75 0.39 0.27 0.22 0.19 1.2 0.75 0.75 0.56 0.40 0.32 0.27 1.1 0.75 0.75 0.73 0.51 0.42 0.34 1.0 0.75 0.75 0.75 0.63 0.51 0.41 0.9 0.75 0.75 0.75 0.73 0.59 0.47 0.8 0.75 0.75 0.75 0.75 0.68 0.53 0.7 0.75 0.75 0.75 0.75 0.75 0.58 0.6 0.75 0.75 0.75 0.75 0.75 0.63 ,

0.5 (5) 0.75 0.75 0.75 0.75 0.75 0.68 0.4 (5) 0.75 0.75 0.75 0.75 0.75 0.73

,s;.,0.36 (5) 0.75 0.75 0.75 0.75 0.75 0.75 NOTES:

(1) Flaw depth = a ofor a surface flaw

= 2a, for a subsurface flaw t = nominal thickness Linear interpolation is permissible.

(2) P,, = primary membrane stress P, = primary bending stress S,,, = allowable design stress intensity (in accordance with Section lil)

-1 (3) Circumference based on nominal pipe diameter.

(4) IWB-3514.3 shall be used.

(5) Derived using source equations. ,

'l .

. V 0054-00101-001-200 VECTRA Revision 0

% ~u _

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PAATwnwPm FOR 6 + B < 180*:

5n - e _a p= (radians) 2 SF(SR) - 0.5 6(2 sin p a sin e) = 0 ,

n t FOR 6 + # >._180*:

x(56 a) p= t (radians) 8 2

t SF(SR) - 0.5 6(2 a) sin p = 0 n t Figure 4.0-1 SOURCE EQUATIONS FOR ALLOWABLE END-OF EVALUATION PERIOD {

FLAW DEPTH-TO-THICKNESS RATIOS FOR CIRCUMFERENTIAL FLAWS )

IN AUSTENITIC PIPING (References 13 & 14) l 1

v 10 - 0054 00101-001-200 VECTRA Revision o WHERE:

0= half crack angle (radians)

L, = total circumferential crack length B= neutral axis location angle (radians) a= flaw depth (inches) t= pipe thickness (inches)

OD = outside pipe diameter (inches)

R= mean pipe radius (inches) = ( OD - t i / 2 S. = allowable design stress intensity P,, - primary longitudinal membrane stress (10.5S )

P, = primary bending stress P. = ut: concentrated expansion stress For Base Metal and For SMAW and SAW GTAWlGMAW Weldments: Weidments:

SR = P* + P* M(P + P3 + P* )

Sm SF SR =

S, SF = 2.773 SF = 2.773 x 1.449 - 4.018 For SMAW Weldments: For SAW Weldments:

M= 1.0 when OD 124" M= 1,08 when OD 5 24" M= 1.0 + 0.01(OD - 24) M= 1.08 + 0.009(OD 24) when OD > 24* when OD > 24" Figure 4.0-1 (Concluded)

SOURCE EQUATIONS FOR ALLOWABLE END-OF-EVALUATION PERIOD FLAW DEPTH-TO-THICKNESS RATIOS FOR CIRCUMFERENTIAL FLAWS IN AUSTENITIC. PIPING (References 13 & 14)

V 0054-00101-001-200 VECTRA neyision o 5.0 LOADS / STRESSES The design criteria described in Section 4.0 requires that the following primary axial (P m) and bending (P )e load / stress combination be determined for check valves CK-ES3166 and CK-ES3181:

Pm + Pe = P + N + WM or %E) where:

P = axial stress due to design internal Pressure DW = Deadweight OBE = Operating Basis Earthquake SSE = Safe Shutdown Earthquake Table 5.0-1 presents axial forces and moments provided in the Reference 15 design information transmittal.

As discussed in Section 2.0, the check valves are in a piping system with an HC-3 designation. Per the Reference 16 piping class summary, an HC-3 system has a design internal pressure (P,) of 60 psig.

Per the Reference 17 and 18 thickness measurement reports, the valve side of the CK-ES3166 check valve-to-tee weld has an average as-built thickness (T3 ae) of 0.61" and the valve side of the CK-ES3181 check valve-to-tee weld has an average as-built thickness (T 3i ,,) of 0.58". Both check valve-to-tee weldments have a nominal diameter (OD) of 24".

Therefore, the following geometric properties can be determined:

V 0054-00101-001-200 VECTRA nevision o i

ID = inside diameter ,

= OD - (2

T)

ID 33 , = 24" - (2

0.61) = 22.78" ID3i,, = 24" - (2

0.58") = 22.84" l

A = cross-sectional area A = n/4 (OD2- 1D 2)

A,33

= n/4 [(24")2 - (22.78")2] = 44.8 in.2 A 33 ,3 = n/4 [(24")2 - (22.84")2] = 42.7 in.2 S = section modulus S = [n / (32

OD)] (OD' - lD')

S,33

= [n / (32

24")] [(24")* - (22.78")'] = 255.6 in.

S,33

= [n / (32

24")) [(24")* - (22.84")'] = 244.0 in.'

With these geometric properties, the following stresses can be determined for applied mechanicalloads:

F = Axial Force P,, = F/A M = Bending Moment P, = M/S Table 5.0 2 presents these stresses for the applied mechanicalloads presented in Table 5.0-1.

V 0054-00101-001-200 VECTRA nevision o The following axial stress, P, can be determined for the piping system design internal pressure:

P = (P,

OD) / (4

T)

P,33 = (60 psig

24") / (4

0.61") = 590 psi P,3i = (60 psig

24") / (4

0.58") = 621 psi These stresses are included in Table 5.0-2.

Table 5.0-1 CHECK VALVE-TO-TEE FORCES AND MOMENTS (Reference 15)

VALVE CK-ES3166 VALVE CK-ES3181 LOAD CONDITION AXIAL BENDING AXIAL BENDING FORCE (F) MOMENT (M) FORCE (F) MOMENT (M)

(Ibs.) (f t.-lbs .) (lbs.) (f t.-lbs.)

DW 107 14610 111 8842 OBE 3193 40018 3614 44911 SSE 6386 80035 7228 89823

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Table 5.0-2 CHECK VALVE-TO-TEE AXIAL AND BENDING STRESSES VALVE CK-ES3166 VALVE CK-ES3181 LOAD CONDITION AXIAL BENDING AXIAL BENDING STRESS (P.) STRESS (P,) STRESS (P.) STRESS (P,)

(psil (psi) (psi) (psi)

P 590 N/A 621 N/A DW 2 686 3 435 OBE 71 1,879 85 2,209 SSE 143 3,757 169 4,418 Table 5.0-3 CHECK VALVE-TO-TEE AXIAL AND BENDING STRESS COMBINATIONS VALVE VALVE LOAD CK{S3166 CK-ES3181 CONDmON p , p. p , p.

(psi) (psi)

P + DW + OBE 3,229 3,353 P + DW + SSE 5,179 5,646

V 15 - 0054-00101-001-200 VECTRA sevision o 6.0 WELD OVERLAY DESIGN METHODS AND RESULTS 6.1 Overlav Thicknen To utilize ASME BPVC Section XI Paragraph IWB-3640, the allowable design stress intensity, Sm, must be determined in accordance with ASME BPVC Section lli (Reference 19). As discussed in Section 2.0, the bodies of check valves CK-ES3166 and CK-ES3181 are ASTM A-351, CF8M and the tee fittings welded to these valves are ASTM A-358, Class 1, Type 304.

Also as discussed in Section 2.0, the check valves are in a piping system with an HC-3 designation. Per the Reference 13 piping class summary, an HC-3 system has a design temperature of 300*F.

Therefore, the following S mvalues are provided in ASME BPVC Section ill for the check valves and tees at 300"F:

MATERIAL (psi)

ASTM A-351, CF8M 17,100 ASTM A-358, Class 1, Type 304 16,600 l

l l

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I 0054-00101-001-200 VECTRA Revision 0 l l

Therefore, taking the highest normal operating condition primary stress 1

combination * (P + P, = 3,353 psi' *) provided in table 5.0-3 and 1 1

dividing it by the lowest design stress intensity value presented above (S.

= 16,600 psi) provides a stress ratio (SR) less than the lowest stress ratio I 1

presented in Table 4.0-2 ((P. + 3P ) / S = 0.20 < 0.36). Therefore, per l Table 4.0-2, the maximum allowable flaw depth (a)-to-thickness (t) ratio is:

a/t = 0.75 a = 100% x T T = per Section 5.0 t = combined pipe wall + overlay thickness l

= T + t, l

t, = weld overlay thickness l l

Therefore: T / (T + t o) = 0.75 and: t, = T / 3 l

l l

For check valve CK-ES3166: t, = 0.61" / 3 = 0.20" For check valve CK-ES3181: t, = 0.58" / 3 = 0.19" l

l 6.2 Overlav Axial Lonath Code Case N-504-1 suggests an overlay axial length, Lwon., beyond each end of any observed flaws as follows:

For load combinations involving SSE to control the design of the weld overlay repair, these load combinations must have a magnitude greater than 2 times load combinations involving OBE.

No credit for overlay thickness included.

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Y 0054-00101-001-200 ,

VECTRA Revision 0 !

hor, > 0.75 viiT where, prior to overlay application:

R = outer pipe radius

= OD / 2 = 12" T = per Section 5.0 For check valve CK-ES3166: Lwon. = 2.0" ,

For check. valve CK-ES3181: Lwon- 2.0" The indication location sketches in Appendices A and B show that the check valve-to-tee butt welds are 0.85" wide and that indications extend l as far as 2.2" (valve CK-ES3166) and 2" (valve CK-ES3181) into the i

valves from the edge of the. butt welds. Therefore, per Code Case N-504-1, the axiallengths of the weld overlay repairs, Lwon~, measured from the center of the butt welds onto the valve bodies should be:

For valve CK-ES3166: Lwon.. = Lwon. + (0.85" / 2) + 2.2" l

= 4.6" !

For valve CK-ES3181: Lwon- = Lwon. + (0.85" / 2) + 2"

= 4.4" i Because no indications have been observed on the tee-side of these weldments, the weld overlay repairs will only be extended onto the tees per the Code Case N-504-1 suggested length from the centerline of the butt welds.

4 1

V 0054-00101-001-200 VECTRA Revision o f

The design thicknesses and upstream / downstream axiallengths for the .

valve CK-ES3166 and valve CK-ES3181 weld overlay repairs are illustrated in Figure 6.0-1.

i WELD

^

f h '

i 45 min.

' (typ.)

NOTE 2 g i

, j'

\ t-3

--[ -. __

3 -------______ ____d.x _

i

-._b_

(V T,WPG) ;

r WELD OVERLAY REPAIR DIMENSIONS VALVE ;

NO.

t,(1) A B-CK-ES3166 0.20" 4.6" 2.0" ,

CK-ES3181 0.19" 4.4" 2.0"'

1 NOTES: I l

(1) t, = minimum design thickness. l (2) Final contour to be determined based upon examination requirements.

Figure 6.o 1 WELD OVERLAY REPAIR DESIGN DIMENSIONS l

. V 0054-00101-001-200 VECTRA Revision 0 7.0

SUMMARY

AND CONCLUSIONS This calculation package presents the design of weld overlay repairs for containment sump check valve-to-tee we!dments at the Palisades Nuclear Plant. These weldments are on the downstream side of check valves CK-ES3166 and CK-ES3181 and contain indications attributed to IGC caused by original construction, repair, and reinstallation welding heat input sensitization as verified by metallurgical examinations.

The weld overlay repair designs presented in this calculation package are based upon the requirements of ASME BPVC Case N-504-1 and Section XI, Paragraph IWB-3640. Because of the small applied mechanical and design internal pressure stresses at these weldments, the weld overlay repair design thicknesses are the minimum 1/3 of the average as-built pipe wall thickness prior to overlay application as defined by IWB-3640. Due to the location of the indications in the check valve bedies as shown in Appendices A and B, the weld overlay repairs shall extend axially a minimum 0.75 V'(R T) distance beyond the end of the observed indications on the valve bodies and 0.75 V(R T) from the centerline of the valve-to-tee butt weld onto the tee.

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8.0 REFERENCES

1. Consumers Power Company Palisades Nuclear Plant Drawing No.

M204, " System Diagram - Safety injection, Containment Spray, &

Shutdown Ccoling System *, Sheet No. A, Revision 5.

2. Bechtel Drawing No. 03319, " Stress isometric - Safety injection, Containment Spray, & Shutdown Cooling System", Sheet 1 of 8 (Rev. 4) and Sheet 4 of 8 (Rev. 4).

3. Bechtel Drawing No. 5935-M-260, " Piping Class Sheet - Class HC -

Palisades Plant - Consumers Power Company", Sheets 1/HC (Rev. 23), 2/HC (Rev.14), 28 (Rev.1), 29 (Rev. 2), and 30 (Rev. 2).

4. Bechtel Drawing No. 8-M-260, " Piping Class Sheet - Class HC -

Palisades Plant - Consumers Power Company", Sheets 1/HC (Rev. A) and 28/HC (Rev. A).

5. Bechtel Drawing No. 260, " Piping Class Sheet - Palisades Plant -

Consumers Power Company", Sheets 2A/HC (Rev.10) and 2B/HC (Rev.1).

6. Southwest Fabrication & Weld Company Drawing No.

MK-HC-3-24"-D, VEN-M107-Sht.132-Rev. 3.

7. Southwest Fabrication & Weld Company Drawing No. ,

MK-HC-3-24"-L, VEN-M107-Sht.143-Rev. 3.

8. Chapman Order No. CV-04038-8 for 24" List 123A Tilting Disc Check Valves, pages P2045926 thru P2045932,

9. Palisades Nuclear Plant Corrective Action Report E-PAL-94-008.

10. Sargent & Lundy Document No. CMED-058599, " Check Valve Leak ;

Root Cause, Engineering Analysis, and Repair / Replacement Options", Revision O.

l l

V 0054-00101-001-200 VECTRA Revision 0

11. American Society of Mechanical Engineers (ASME) Boiler and Pressuro Vessel Code (BPVC) Case N-504-1, " Alternative Rules for Repair of Class 1, 2, and 3 Austenitic Stainless Steel Piping -

Section XI, Division 1", Approval date: August 9,1993

12. ASME BPVC Section XI, " Rules for Inservice Inspection of Nuclear Power Plant Components",1992 Edition with 1992 Addenda.

13. Ranganath, S. and Mehta, H.S., " Engineering Methods for Assessment of Ductile Fracture Margin in Nuclear Power Plant Piping" Elastic-Plastic Fracture: Second Symposium, Volume II-Fracture Resistance Curves and Engineering Applications, ASTM STP 803,1983, pp.11309 to 11-330.

14. ASME BPVC Section XI Task Group for Piping Flaw Evaluation,

" Evaluation of Flaws in Austenitic Steel Piping", Transactions of the ASME - Journal of Pressure Vessel Technology - Pressure Vessel and Piping Codes, August 1986, Volume 108, pp. 352 to 366.

15. Sargent & Lundy Design Information Transmittal (DIT) No.

I DIT-CPC-017-02,

Subject:

Design Axial Forces and Bending Moments for valves ES3166 and ES3181, Page 1 of 1.

16. Consumers Power Company Palisades Plant Piping Class Summary M-259, Sheet llHC, Revision 8.

17. Consumers Power Company NDE Testing Services Thickness Measurement Examination Report, Sheet No. DLH-1, dated 3-1-94.

18. Consumers Power Company NDE Testing Services Supplementary Sketch, Sheet No. DLH-1, dated 3-1-94.

19. ASME BPVC Section ill, " Rules for Construction of Nuclear Power Plant Components",1989 Edition.

V

-A -

54- 1 1- 1-200 VECTRA Revision 0 Appendix A CK-ES3166 INDICATION LOCATION SKETCHES

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- B.O - 0054-00101-001-200 VECTRA sevision 0 Appendix B CK ES3181 INDICATION LOCATION SKETCHES

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e VALVE TEE 1 WELD

A B E 45 min.

' (typ.)

NOTE 2

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K 1---- ------------ '_____ . 4 y

A m

\ ,s (V T.WPG)

NOTES:

(1) This repair shall comply with the technical requirements contained in Document No.

0054-00100-001-101, Revision O.

(2) Final contour to be determined based upon examination requirements.

(3) "t," is the minimum required design thickness.

DESIGN DIMENSIONS WELD NUMBER FLAW CHARACTERIZATION COMMENTS Valve CK-ES3166 100% thru wall-by- o.20' 4.6" 2.0" Per ASME BPVC Case 360* length N-5041 0 W 34fp [ 37479,9, M 3/4fgg, @ gy4_,[ FW4 DLJ g lssued for Construction.

PREP.BY/ CHK BY/ P.E. APPR./ E.M. APPR./ P.M. APPR./

REV* DESCRIPTION DATE DATE DATE DATE DATE JOB NO.: REV.

PLANT / UNIT:

y 0054-00101 PALISADES sHT. 1 0

FILE NO.: DWG. NO.: op j o054.00101.001.300 0054-o0101-o01 300 VECTRA (3166 WOR.RV0) ,

~

l

. VALVE TEE l l

1 l

l ct WELD i l

A B

_45 min.

NOTE 2 ' (typ.)

/

K \ --- ---- --------__-_

.N y 1 l

. ... i_ / 1 I

v l mT.wea) l NOTES:

1 1

(1) This repair shall comply with the technical requirements contained in Document No. l 0054-00100 001-101, Revision O. l (2) Final contour to be determined based upon examination requirements.

(3) "t o" is the minimum required design thickness.

DEslGN DIMENSIONS WELD NUMB A FLAW CH AR ACTERIZATION COMMENTS Valve CK-ES3181 100% thru wall by- c.19" 4.4" 2.o" Per ASME BPVC Case 360* length N-504-1 o 05) 3pg gjg CPff yg WyggB~g8 J lssued for Construction.

PREP.BY/

' CHK. BY/ P.E. APPR./ E.M. APPR./ P.M. APPR./

REV. DESCRIPTION DATE DATE DATE DATE DATE i l

REV.

JOB NO.: PLANT / UNIT: y oos4-oolot PALISADES sHT. 1 o

FILE NO.: DWG. NO.: op 1 00s4.00101.001.30i oos4-ootoi-oot.3oi VECTRA (3181 WOR.RVO)

_ _

ML20064E491

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Text

1.0 INTRODUCTION

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SUMMARY

8.0 REFERENCES

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ML20064E491

Text

1.0 INTRODUCTION

3.0 DESCRIPTION

SUMMARY

8.0 REFERENCES

1.0 INTRODUCTION

3.0 DESCRIPTION

SUMMARY

8.0 REFERENCES

Subject:

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