ML20083N732
| ML20083N732 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 05/02/1995 |
| From: | Joseph Willis DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20083N549 | List: |
| References | |
| CNC-1206.00-02, CNC-1206.00-02-0008, CNC-1206.00-2, CNC-1206.00-2-8, NUDOCS 9505230270 | |
| Download: ML20083N732 (26) | |
Text
.2 Form 01077 03-94) MFW A CERTIFICATION OF ENGINEERING CALCULATION STATION AND UNIT NUMBER b /
TITLE OF CALCULATION
- M e L O e L h_% kO~Ob d~d4 O/Ul/U 567eA/ZesS 5deel CALCULATION NUMBER. d. AM_, ____. _
12Cio.60-02 ~~OdOI ORIGINALLY CONSISTING OF:
- PAGES- / THROUGH- E TOTAL ATTACHMENTS AbW'l TOTAL MICROFICHE ATTACHMENT O I
TOTAL VOLUMES TYPE i CALCULATION / ANALYSIS es YNo TYPE I REVIEW FREQUENCY Tuoc N THESE ENGINEERING CALCULATIONS COVER ,7- OA CONDITION ITEMS. IN ACCORDANCE WITH CULATION HAS BEEN ORIGINATED, ESTABLISHED PROCEDURES, .
HECKED OR APPROVED AS NOTED BELOW:
ORIGINATED BY - C- m/! N DATE d2/%
CHECKED BY _ /x M&tde $ 8Mb i
$5tA/ DATE C zh9CW2/n SltkS APPROVED BY __ / [dr DATE S'/L /#IS '
ISSUED TO DOCUMENT MANAGEMENT b mM DATE 5[J/9T RECEIVED BY DOCUMENT MANAGEMENT DATE MICROFICHE ATTACHMENT LIST: O Yes C No SEE FORM 101.4 CALCULATION PAGES (VOL) ATTACHMENTS (VOL) VOLUMES ORIG CHKD APPR NO REVISED DELETED ADDED DATE REVISED DELETED ADDED DELETED ADDED DATE R DATE DATE DA 9505230270 950511 PDR ADDCK 05000413 P PDR
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File No. CNC 1206.00-02-0008 NRC GL 90-05 Cal on RN Stainless Steel Socket Welds 1.0 PROBLEM STATEMENT >
This calculation evaluates a through wall crack located on RN stainless steel' socket welded connections. The piping, is ASME Class 3 piping. This evaluation is required by NRC Generic Letter 90-05 and is referenced in PIP 0-C95-0527, 2.0 OA Cpfgij.lica Piping addressed by this calculation is QA condition I and is a QA condition I calculation.
3.0 DESIGN METHOD This calculation evaluates using the mies imposed by NRC Generic Letter 90-05, NSD 203 and ASME Section III.
4.0 APPLICABLE CODES AND STANDARDS (1) ASME Section III 1974 Edition with addenda through summer 1974. (CNS Plant Base Code)
(2) Guidance For Performing Temporary Non-Code Repair of ASME Code Class 1,2, and 3 Piping (NRC Generic Letter 90-05)
(3) Duke Power Co. Nuclear Station Directive: 203. Operability (4) ASME Code Case N-463 (5) Tech Spec 3/4.4.10 StructuralIntegrity 5.0 DESIGN INPUTS Not Applicable 6.0 PSAR. FS AR CRITERIA FSAR Volume 3, Table 3.2.2-3 identifies piping as complying with ASME & ANSI Codes.
7.0 ASSUMPTIONS None 8.0 INFORMATION SOURCES (1) Flow Diagram CN-1574 (2) Met Lab Report 1812 (3) PIP 0-C95-0527 I
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File No. CNC 1206.00-02-0008 NRC GL 90-05 Cal on RN Stainless Steel Socket Welds 9.0 EVALUATION This calculation evaluates the through wall region identified at the fillet weld. The evaluation approach is the "through-wall flaw" per "NRC Generic Letter 90-05". Using NRC Generic Letter 90-05, attachment 3, the calculation meets the requirement of "K" less than 135 ksi(in)". This is consistent with the lower-bound fracture toughness property in ASME Code Case N-463. The characterized flaw, attachment 2A, uses 3/8" hole per pin hole found in the welds. This is approximately %" larger -
than could be seen on the pipe OD, Met Lab Report 1812. The actual exanunation of the crack with a magnifying glass while still installed was ~ 0.15". The pin hole weepage is less than 1 drop per minute.
A walk down of all the RN stainless steel socket welded piping was completed by a Spoc team attachment 2 is a list of the socket weld leakers The weld numbers are used for identification.
10.0 CONCLUSION
The characterized flaw of the RN stainless steel socket welds is acceptable per NRC Generic Letter 90-05 using the "Through-Wall Flaw" approach. The leaking RN connnections will be replaced or repaired per a repair plan. The repair plan will be initiated as soon as possible, but will not force the system availability. The RN socket welds are operable with these leaks.
Prepared By _Ernie McElrov Date_5/2/95 Checked ByYA(44 Date W/h $
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Anachment i I
The pinhole leaks in the stainless steel portions of the RN system piping pose no threats from either a flooding or pipe rupture peispective. The flooding scenarios at the station are based on worst case pipe ruptures of various systems. These leaks are bounded by breaks already postulated. These leaks are all -
located in the heat affected zone of the welds. These weld locations were reviewed as part of the moderate energy piping water spray study for their potential affect on safety related equipment. A crack was postulated at each weld location in all moderate energy piping greater than 1" in diameter. These leaks are therefore also bounded by studies already in place at the plant. The only portions of piping which are excluded are those equal to or less than 1" in diameter. Sincs these are all located in areas oflarger piping already reviewed for water spray effects, these leaks are also acceptable.
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, ACTUAL LEAKING WELDS OR SIGNS OF LEAKAGE RN SS Socket Wclds Attachment 2 j WELD #s PIPE DIA. l l 1
1RN 423-80 1 2" )
IRN 526 3 2" ]
1RN 527-3 2" i iRN 527-4 2" . .
1RN 529-3 2" 1RN 529-6 2" 1RN 530-5 2" 1RN 530-7 2" ;
IRN 531-6 2" i j 1RN 531-9 2" 2RN 184-14 2" {
i 2RN 439-17 2" (
I l 2RN 439-19. 3/4" 2RN 439-23. 2" WO,' 43^ 2" M SkS[
2RN 440-22 1" 2RN 441-1 2" 2RN 442-13 2" j 2RN 442-15 2" l '
2RN 442-17 2" 2RN 442-19 2" 2RN 442 21 2" l j 2RN 442-25 2" 2RN 442-26 2" 2RN 442-7 2" 2RN 443-11 2" ;
l 2RN 445 2" 2RN 445-5 2" 1
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l Attachment 2A l Socket Weld Flaw Characterization Eight socket welds were sectioned for flaw characterization. The general corrosion path traveled from the weld root outward through weld metal at a 45' angle. The typical geometry of the flaw ;
was Wx DxL ,0.15" x 0.25" x 0.38"(max). This similar geometry is in seven of the eight welds sectioned welds. Weld 2RN442-15,45 elbow, has a similar geometry as the above seven but has . j indication of sensitized pipe and forging. The elbow was sectioned in five locations 1/4" apart. :
The sectioned locations all showed some form of attack, but had no indication oflinking. If ' )
assumed linked, the crack would be considered to be approximately 1.25". This is analyzed in j case 4 of attachment 3 on ?" piping and is acceptable. i The worst flaw in the sectioned areas is in weld 2RN442-25, %" socket weld. This weld had l three pin hole leaks approximately 120' apart. These pin holes were far enough apart that they are !
considered as three different leaks, there was no evidence of cracking between the pin holes, l linking. The corrosion in the 4" butt welds is described as propagating through pipe wall would start as a pin hole, enlarging, and neck down to a pin hole as it penetrate the pipe's outside diameter. A conservative estimation of the flaw size is to use the maximum enlargement of the - )
cavity in the pipe wall, due to the changing geometry. One size, 3/8", per pin hole was used for '
butt welds and socket welds. This was the maximum cavity seen in the stainless steel RN piping. I This is considered the worst case of all the observed leaking welds. The other analyzed cases are ;
as follows:
Case 1: 3/4" piping with one 3/8" hole, with reduced section modulus the three hole 120' apart.
Case 2: 1" piping with one 3/8" hole, with reduced section modulus the three hole 120* apart.
Case 3: 2" piping with one 3/8" hole, with reduced section modulus the three hole 120* apart.
The maximum weepage from any of the pin holes is less than i drop per minute. Using this as the maximum leaking flaw found in SS socket weld in the RN system and the maximum stresses applied, this passes generic letter 90-05, using the through wall flaw approach.
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90-05 Evaluation of Flawed Fillet Welds (Attachment 3) l l
Statement of Problem / Purpose The purpose of this calculation is to evaluate the structtiral integrity of the thm-wall leaking flaws that exist in the stainless steel fillet welds as listed in Table 3 (see sheet 5 __ ). The flaws were characterized in attachment 2A of this calculation. The characterized flaws will be covered by 4 cases.
Quality Assurance Condition This calculation is QA condition 1 because it serves as the basis for the qualification of a QA condition 1 stmeture, system or component.
1 s Analysis Methods Used This condition will also be evaluated using Generic Letter 91-18 sectic,n 6.14 (Flaw Evaluation).
Paragraph's 3 and 4 state that moderate energy Class 3 piping (maximum operating temperature less than 200 degrees F and a maximum operating pressure less than 275 psig) may be evaluated using Generic Letter 90-05.
References
- 1. 1974 ASME Code Section III, Subsection ND, Fig. ND-4427-1 ;
- 2. 1989 ASME Code Section III (Winter Addenda), Subsection NB, Table NB-3681(a)-1 and NB-3683.4 (c)(2)
- s. For Piping Analysis Calculations, see Table 1 Catawba Nuclear Station Unit 1 & 2 Page: I l
90-05 Evaluation of Flawed RN Fillet Welds File No.: CNC-1206.00-02-0008 Rev. O, Attachment 3 By: Oh) Date: 5 95 Check: 6A))O Date: f- 24(
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.. References (cont.) -
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- 4. NRC Generic Letters 90-05 and 91-18
- 9. For v eld isometric see Table 2 -
, 10. . Vector Mechanics for Engineers: Statics & Dynamics, by Beer and Johnston Assumptions
- Listed as used in body ofcalculation
' Characterization P
The following 4 cases were considered based on attachment 2A of this calculation. In each case <
the flaw was assumed to be thru-wall for the entire length.
Case 1 - considers a 3/4" sch 40 pipe with 3-0.375" flaws located 120 degrees apart.
Case 2 - considers a 1" sch 40 pipe with 3-0.375" flaws located 120 degrees apart. l Case 3 - considers a 2" sch 40 pipe with 3-0.375" flaws located 120 degrees apart. i Case 4 - considers a 2" sch 40 pipe with 1-1.25" flaw.
Evaluation :
Per section C, part 3, of generic letter 90-05, the structural integrity of a through wall crack like flaw may be evaluated using, part 3.a ("Through-Wall Flaw" Approach). The following is an :
evaluation using this method except as noted below. -
Catawba Nuclear Station Unit 1 & 2 Page: 2 90-05 Evaluation of Flawed RN Fillet Welds l File No.: CNC-1206.00-02-0008 Rev. O, Attachment 3 l By: d9%.) Date: 5 if Check: 6/Vb Date: E-2M
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. _ . . . _ . _ , , . . _ . . - . . _ . , . _ . , - . . _ , ,_ g -..-_. . - . . .
Evaluation (cont.)
Since the flaw consists mainly of a subsurfa:e void, it was assumed to be thru-wall for the entire length, therefore the maximum diameter of the void will be used for "2a", and nominal thickness will be used for "tmin" Based on the maximum size of the flaw (3/8"), and the minimum distance apart (120 degrees) on a 3/4" pipe, these flaws were considered far enough apart to be considered separately.
The flaw assumed for case 4 is 17% of the circumference of the nominal pipe, which exceed the limit of 15%. This is considered acceptable by engineeringjudgement due to the conservatism of assuming that all the small flaws would link together .
The stresses in the fillet weld, normal to the crack will be conservatively estimated by using the C1 and C2 primary plus secondary indices for a class I fillet weld. These indices, when applied to the nominal stress in the pipe, would yield the maximum primary plus secondary stress intensity in the weld. Per the 1989 ASME Section III Winter Addenda, Subsection NB, Table NB-3681(a)-1 the C1 and C2 indices would be 1.8 and 2.1 respectively. The existing stresses for each weld location are tabulated on sheet _ lo These stresses were taken from the existing Superpipe Analysis Runs for the problems listed in Table 1 (see sheet 6 ) The maximum ASME Section III Equation's 8, 9,10 and 9E stresses and ratio's are listed. The Equation 9E stresses at Catawba are used to evaluate functionality by comparing faulted stresses too and Emergency allowable. The stress to be used for the 90-05 evaluation will be the summation of the maximum thermal stress (EQ 10), plus the maximum pressure stress, gravity stress and SSE earthquake stress. The above 90-05 stresses (Eq 10 thermal + pressure + weight + SSE inertia + SSE SAM's) were then manipulated to determine the maximum bending moment. This moment times the C2 indices divided by the section modulus at the extreme fiber was then used to calculate the 90-05 bending stress. The 90-05 pressure stress was then conservatively calculated using the Cl indices times PD/2t. These stresses were added together to determine the tota 190-05 stress. The above was repeated for each case using the maximum stress from all weld locations (see sheets
~7 through / C ).
Catawba Nuclear Station Unit 1 & 2 Page: 3 90-05 Evaluation of Flawed RN Fillet Welds File No.: CNC-1206.00-02-0008 Rev. O, Attachment 3 By: OM Date: 6-2.-95 Check: 6/#k7 Date: s-1M
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Evaluation (cont.)
To qualify the existing ASME Section III stresses, the section modulus of the cracked section "Ze" and the area of the cracked section "Ac" was calculated for each pipe size (see sheets . l 6 through I'l ). The equations used to calculated the section properties are derived on sheets ll through l 3. The existing maximum stress ratio's for ASME Section III Equations 8,9, and 9E were factored by the larger of(Zun "uncracked" / Ze " cracked") or (Aun "uneracked" /
Ac " cracked") (see sheets ~~/ through l O for calculations). The existing maximum ratio for ASME Section III Equation 10 was not factored since generic letter 90-05 requires that a code repair be perform dat the next scheduled outage, making the evaluation of a secondary thermal stress oflittle concern, especially from a fatigue standpoint.
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Conclusion Since the piping is made of austenitic stainless steel, the critical stress intensity factor K will be 135.0 ksi(in)^0.5 (ref. Generic Letter 90-05). Since the stress intensity factor K for each case calculated on sheets 7 thru 1 O are less than the critical value, the requirements of generic letter 90-05 have been meet, except as previously noted. The ASME Section III Equations for primary stresses are also acceptable since the factored ratio's are less than 1.0.
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. j Catawba Nuclear Station Unit 1 & 2 Page: #-
90-05 Evaluation of Flawed RN Fillet Welds File No.: CNC-1206.00-02 -0008 Rev. O, Attachment 3 By: CM Date: $-2-?I Check: O4MO Date: 5-2 ~/T-
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L Table 1 Micro Calculation Calculation Prob. Fiche Superpipe Run File Rev.
No. Attach. Date Time No. No.
RN076 MI 06-21-90 11:06:59 CNC-1206.12 34-2076 3 RNI23 N/A 10-06-84 11:57:47 CNC-1206.12-34-2123 3 RN133 M3 09 04-90 08:38:09 CNC-1206.12-34-2133 7 RN144 MI 08-08-90 17:01:10 CNC-1206.12-34-2144 5 RNI S M2 08-09-88 14:39:07 CNC-1206.12 34-2015 9 RNS M1 06-13-90 13:26:14 CNC 1206.02-84 2024 5 Table 3 Table 2 Nominal Wall Weld Weld #'s Diameter Schedule Thickness Isomtric Drawing IRN 423-80 2" 40 0.154 Drawing Revision iRN 526-3 2" 40 0.154 Numbers Number iRN 527-3 2" 40 0.154 CN 1RN 423 12 IRN $27-4 2" 40 0.154 CN IRN 526 0 IRN 529-3 2" 40 0.154 CN IRN 527 0 IRN 529 6 2" 40 0.154 CN IRN 529 1 1RN 530-5 2" 40 0.154 CN 1RN 530 1 IRN 530-7 2" 40 0.154 - CN-1RN $31 0 1RN 531-6 2" 40 0.154 CN 2RN 184 5 1RN 531-9 2" 40 0.154 CN-2RN 439 1 2RN 184 14 1" 40 0.133 CN-2RN 440 1 2RN 439-17 2" 40 0.154 CN 2RN 441 0 2RN 439-19 2" 40 0.154 CN 2RN 442 1 2RN 439-23 2" 40 0.154 CN 2RN 443 0 2RN 440-22 2" 40 0.154 CN 2RN 445 1 2RN 441-1 2" 40 0.154 2RN 442-13 2" 40 0.154 2RN 442 15 2" 40 0.154 2RN 442 17 2" 40 0.154 2RN 442-19 2" 40 0.154 iRN 442-21 2" 40 0.154 2RN t42 25 2" 40 0.154 2RN 40 26 1/4" 40 0.I13 2RN 442 7 2" 40 0.154 2RN 443 in 2" 46 0.154 2RN 445 1 2" 40 0.154 2RN 445-5 2" 40 0.154 Catwaba Nuclear Station Unit 1 & 2 Page 6 90-05 Evaluation of Flawed RN Fillet Welds File No.: CNC-1206.00 02-0008 Rev. O, Attachment 3 Dy: O A, J 7
Date:5 - /- 9 f Check:
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.-) Date: 9/-9 I
Existing Fillet Welded Stresses Micro j Press. Section Eq 8 Eq 9 Eq 10 Eq 9E Thermal Pres + Wt Prob. Fiche Superpipe Run pd/d, Press. Modulus Stress Stress Stress Stress Eq 10 +SSE Total Weld #'s No. Attach. Date Time DCP SOP pd4t Mean/Extr Ratio Ratio Ratio Ratio Stress Stress Stress SIF 2RN 445-1 RN133 M3 09-04-90 08:38:09 C06A 34W pd/d 165 mean 0.065 0.070 0.121 0.056 3402 1841 5243 2.1 2RN 445-5 RN133 M3 09-04-90 08:38.09 BP3A 29W pd/d 165 mean 0.023 0.023 0.015 0.018 422 579 1001 2.1 2RN 439-23 RN133 M3 09-04-90 08:38-09 *1 45W pd/d 165 mean 0.145 0.196 0.360 0.175 10110 5748 15858 2.1 2RN 439-17 RN133 M3 09-04-90 08:38:09 C03A 50W pd/d 165 mean 0 132 0.177 0.349 0.156 9804 5174 14978 2.1 2RN 439-19 RN133 M3 09-04-90 08:38:09 C04A 48W pd/d 165 mean 0.194 0.231 0.243 0.194 6832 6405 13237 2.1 1RN 531-9 RN076 M1 06-21-90 11:06:59 BPIB 81W pd/d 165 mean 0.028 0.028 0.000 0.022 0 705 705 2.1 IRN 531-6 RN076 M1 06-21-90 11:06:59 C10A 77W pd/d 165 mean 0.100 0.203 0.098 0.206 2745 6757 9503 2.1 1RN 529-3 RN076 M1 06-21-90 11.06:59 C47B 38W pd/d 165 mean 0.065 0.070 0.404 0.050 11348 1841 13190 2.1 2RN 442-7 RN144 MI 08-08-90 17:01:10 BP58 IllW pd/d 165 mean 0.034 0.031 0.000 0.023 0 732 732 2.1 2RN 442-13 RN144 M1 08-08-90 17:01:10 Cl2B 121W pd/d 165 mean 0.042 0.389 0.284 0.142 7962 15345 23307 2.1 2RN 442-17 RN144 M1 08-08-90 17:01:10 BP6C 149W pd/d 165 mean 0.034 0.032 0 000 0.023 0 773 773 2.I 2RN 442-19 RN144 M1 08-08-90 17:01:10 BP6B 127W pd/d 165 mean 0.035 0.289 0.403 0.081 11309 II339 22648 2.I 2RN 442-26 RN144 M1 08-08-90 17:01:10 RED 4 135W pd/d 165 mean 0.072 0.428 0.746 0.260 20952 16470 37422 2.1 2RN 442-25 RN144 M1 08-08-90 17.01:10 BP7B 134W pd/d 165 mean 0.022 0.049 0.062 0.032 1738 1665 3403 2.1 1RN 423-80 RN15 M2 08-09-88 14:39:07 C03A 49W pd4t 130 extr 0.037 0.035 0.014 0.026 387 849 1235 2.1 2RN 184-14 RN123 N/A 10-06-84 11:57:47 27 34W pd/d 130 mean 0.028 0.119 0.035 0.135 975 4451 5427 2.1 1RN 529-6 RN076 MI 06-21-90 11:06:59 BP5B 43W pd/d 165 mean 0.019 0.019 0.033 0.014 913 478 1391 2.1 1RN 530-7 RN076 MI 06-21-90 11:06:59 BP3B 109W pd/d 165 mean 0.022 0.025 0.030 0.021 853 677 1530 2.1 IRN 530-5 RN076 M1 06-21-90 11:06:59 BP3C 140W pd/d 165 mean 0.033 0.029 0.000 0.020 0 666 666 2.1 IRN 527-3 RNS MI 06-13-90 13:26:14 BPSB 25W pd/d 165 mean 0.022 0.056 0.112 0.059 3139 1954 5092 2.1 1RN 527-4 RNS M1 06-13-90 13:26:14 BPSC 47W od/d 165 mean 0.033 0.030 0.000 0.021 0 707 707 2.1 1RN 526-3 RNS M1 06-13-90 13:26:14 FL6B llW pd/d 165 mean 0.086 0.15! 0.114 0.147 3201 4840 8042 2.1 2RN 441-1 RN144 M1 08-08-90 17:01:10 C06A SIW pd/d 165 mean 0.073 0.089 0.034 0.073 946 2496 3442 2.1 2RN 440-22 RN144 M1 08-08-90 17:01:10 COSA 53W pd/d 165 mean 0.063 0.079 0.134 0.065 3755 2244 5999 2.1 2RN 443-II RN133 M3 09-04-90 08:38:09 BP6B 134W pd/d 165 mean 0.034 0.033 0.100 0.025 0 814 814 2.1 2RN 442-15 RN144 MI 08-08-90 17:01:10 Cl3B 123W pd/d 165 mean 0.049 0.367 0.229 0.154 6421 14327 20748 2.1 2RN 442-21 RN144 MI 08-08-90 17:01:10 Cl4B 129W pd/d 165 mean 0.095 0.411 0.57 0.110 15645 15402 31047 2.1 Max 0.194 0.428 0.746 0.260 Maximum Stress 37422 2.1 SIF at Max 2.1 2.1 2.1 2.1 SOP number at location of maximum Pressure Term pd/d stress = 135W Notes: *l. Weld is located between C06B and COSA. Pressure 165 Thermal EQ 10 20952 Section Mod. mean Press +Wt+SSE 16470 Catawba Nuclear Station Units 1 & 2 Rev. Pref. Date Check Date 90-05 Enl. ofFlawed RN Fillet Welds 0 Q -hJ 5-/- 55 $sO s- /M Calc. File No. CNC-1206.00-02-0008 Page G Attachment 3
Thru-Wall Flaw Evaluation Using Generic Letter 90-05 for Socket Welding Pipe Case 1 Pipe Pipe Nom. Wall Code tmin One Half Mean O. D. Thickness See note 3 Total Crack Radius (in) (in) (in) (in) Length (in) c r A B 04685 1.050 0. I I 3 0.113 0.I875 0.1274 4.146 1.9335 -1.9564 Enter i for carbon steel and 2 stainless steel 2 Piping Stress Allouble Stress Intensity Stress The C1 and C2 indices urre used in the 90-05 stress C ksi(Note 2) F K Intensity Ratio to estimate the discontinuity stress in the fillet weld.
9.9071 48.39 1.0839 56.35 135 0.42 Superpipe pressure stress-Enter I for Pd*2/(D^2-d^2) or 2 for PD/41 1 Cis I, Cl indice 1.8 Superpipe section modulus-enter i for mean or 2 extreme fiber i Existing SIF 2.1 CIs 1, C2 indice 2.1 Existing Existing Existing Existing Exist. EQ 9E Existing 90-05 90-05 Total Superpipe Superpipe Pressure Pressure Bending Bending Bending Pressure 90-05 EQ 10 Stress EO 9E stress (P) Stress Stress Moment Stress Stress Stress 20952 16470 165 264.52 16205.48 1579.13 47007.66 1379.87 48387.53 1s the total crack length less than 3" Yes N/A Is 'he total crack length less than 15 percent of the pipe circumference. Yes N/A Evaluation of Existing Stresses Using the Cracked Section See sheet for calculation of cracked section modulus (Zc). Cracked Uncracked Cracked r ri t I Cracked i Uncracked Zc Zun Ratio Area Ac (in) (in) (in) (in^4) (in^4) (in^3) (in^3) Zuri/Ze (in^2) 0.4685 0.4120 0.1130 0.024 0.0370 0.046 0.0779 1.6939 0.219 Uncracked ASME Area Aun Ratio Maximum Equation Existing Cracked Notes (in^2) Aun/Ac Ratio Number Ratio Ratio 1. For acceptance see sheet N/A .
03326 1.5189 1.6939 8 0.194 0.329 2. See sheet i for existing stresses.
9 0.428 0.725 3. Used pipe nominal wall thickness see sheet 3 .
9E 0.26 0.440 4. " Ibis evaluation assumed the flaw w2s thru-wall for the entire length.
.s Rev. Orig Date Check , Date Catawba Nuclear Station, Unit 1 & 2 0 oN g- /- 7r J6 / dah S/8 /9r/ Shw90-05 Evaluation of Flawed RN Fillet Welds
/ Calc File # CNC-1206.00-02-0008 Page 7 , Attachment 3
l l Thru-Wall Flaw Evaluation Using Generic Letter 90-05 for Socket Welding Pipe Case 2 Pipe Pipe Nont Wall Codetmin One Half Mean O. D Thickness See note 3 Total Crack Radius (in) (in) (in) (in) Leneth (in) c r A B 0.5910 1.315 0 133 0.133 0.1875 0.1010 4.444 2.2287 -2.7128 Enter i for carbon steel and 2 stainless steel 2 l
i Piping Stress Allowb!c Stress Intensity Stress The C1 and C2 indices were used in the 90-05 stress C ksi(Note 2) F K Intensity Ratio to estimate the discontinuity stress in the fillet weld.
10.6506 48.19 1.0662 55.21 135 0.41 Superpipe pressure stress-Enter I for Pd^2/(D^2-d^2) or 2 for PD/41 I Cls 1. Cl indice 1.8 ,
Superpipe section modulus-enter I for mean or 2 extreme fiber 1 Existing SIF 2.1 Cls 1, C2 indice 2.1 1' 1
Existing Existing Existing Existing Exist. EQ 9E Existing 90-05 90-05 Total l
i Superpipe Superpipe Pressure Pressure Bending Bending Bending Pressure 90-05 EQ 10 Stress EO 9E stress (P) Stress Stress Moment Stress Stress Stress 20952 16470 165 288.74 16181.26 2955.41 46720.16 1468.25 48188.41 is the total crack length less than 3" Yes N/A Is the tota! crack length less than 15 percent of the pipe circumference. Yes N/A Evaluation of Existing Stresses Using the Cracked Section See sheet for calculation of cracked section modulus (Zc). Cracked Uncracked Cracked r ri t I Cracked I Uncracked Ze Zun Ratio Area Ac (in) (in) (in) (in^4) (in^4) (in^3) (in^3) Zurf/Ze (in^2) 0.5910 0.5245 0 1330 0.063 0.0873 0.005 0.1459 1.5362 0.359 Uncracked AShE Area Aun Ratio Maximum Equation Existing Cracked Notes f (in^2) Aun/Ac Ratio Number Ratio Ratio 1. For acceptance see sheet N,/4 0.4939 1.3757 1.5362 8 0.194 0.298 2. See sheet [o for existing stresses.
9 0.428 0.658 3. Used pipe nominal wall thickness see sheet 1 9E 0.26 0.399 4. This evaluation assumed the flaw was thru-wall for the entire length.
Rev. Orig l Date Check Date Catawba Nuclear Station, Unit I & 2 0 gM s - / - 9f Jify / f9; TAO 5// /gr chy90-05 Evaluation of Flawed RN Fillet Welds
/ Calc File # CNC-1206.00-02-0008 Page R , Attachment 3 l
4 - _ _ _ _ . . - _ _ _ _ _ . _ _ _ _ _ _ _ .__ _ _ _ _ _ _ _ _ _ _ _ _
Thru-Wall Flaw Evaluation Using Generic Letter 90-05 for Socket Welding Pipe Case 3 _
Pipe Pipe Nom. Wall Code tmin One Half Mean O. D. Thickness See note 3 Total Crack Radius (in) (in) (in) (in) Length (in) c r A B 1.I105 2.375 0.I54 0.I54 0.I875 0.0537 7.2II 4.5720 -8.7169 Enter i for carbon steel and 2 stainless steel 2 Piping Stress Allowble Stress Intensity Stress The C1 and C2 indices utre used in the 90-05 stress C ksi (Note 2) F K Intensity Ratio to estimate the discontinuity stress in the fillet weld 16.5525 47.23 1.0517 53.37 135 0.40 Superpipe pressure stress-Enter I for Pd^2/(D^2-d*2) or 2 for PD/41 1 Cls 1 Cl indice 15 Superpipe section modulus-enter I for mean or 2 extreme fiber 1 Existing SIF 2.1 Cis I, C2 indice 2.I Existing Existing Existing Existing Exist. EQ 9E Existing 90-05 90-05 Total Superpipe Superpipe Pressure Pressure Bending Bending Bending Pressure 90-05 EQ 10 Stress EQ 9E stress (P) Stress Stress Moment Stress Stress Stress 20952 16170 165 515.27 15954.73 11996.46 44936.23 2290.18 47226.41 is the total crack length less than 3" Yes N/A is the total crack length less than 15 percent of the pipe circumference. Yes N/A Evaluation of Existing Stresses Using the Cracked Section See sheet for calculation of cracked section modulus (Zc). Cracked Uncracked Cracked r ri t I Cracked 1 Uncracked Ze Zun Ratio Area Ac (in) (in) (in) (in^4) (in^4) (in^3) (in^3) Zun/Zc (in^2) 1.1105 1.0335 0.1540 0.563 0 6657 0.474 0.5 % 6 1.2587 0.913 Uncracked ASME Area Aun Ratio Maximum Equation Existing Cracked Notes (in*2) Aun/Ac Ratio Number Ratio Ratio 1. For acceptance see sheet ,h .
1.0745 1.1769 1.2587 8 0.194 0.244 2. See sheet 6 for existing stresses.
9 0.428 0.539 3. Used pipe nominal wall thickness see sheet 1 9E 0.26 0.327 4. This evaluation assumed the flaw was thru-wall for the entire length
~ ~
Rev. Orig Date Eheck . Date Catawba Nuclear Station, Unit 1 & 2 0 QN f 9f JT6/'
r%XO s/e/9 f G/4( 90-05 Evaluation of Flawed RN Fillet Welds Calc File # CNC-1206.00-02-0008 Page 9 , Attachment 3 l
l l
I l Thru-Wall Flaw Evaluation Using Generic Letter 90-05 for Socket Welding Pipe Case 4 Pipe Pipe Nom. Wall Code tmin One Half
, Mean O. D. Thickness See note 3 Total Crack Radius (in) (in) (in) (in) Length (in) c r A B l.I105 2.375 0.I54 0.I54 0.6250 0.1791 7.211 4.5720 -8.7169 Enter I for carbon steel and 2 stainless steel 2 Piping Stress Allowble
- Stress Intensity Stress The C1 and C2 indices were used in the 90-05 stress C ksi(Note 2) F K Intensity Ratio to estimate the discontinuity stress in the fillet utld.
~ ~
l 16.5525 47.23 1.2685 117.53 135 0.87 Superpipe pressure stress-Enter I for Pd*2/(D*2-d^2) or 2 for PD/4t 1 Cls I, CI indice 1.8 Superpipe section modulus-enter I for mean or 2 extreme fiber i Existing SIF 2.1 Cls I, C2 indice 2.1 Existing Existing Existing Existing Exist. EQ 9E Existing 90-05 90-05 Total Superpipe Superpipe Pressure Pressure Bending Bending Bending Pressure 90-05 EO 10 Stress EO 9E stress (P) Stress Stress Moment Stress Stress Stress 20952 16470 165 515.27 15954.73 11996.46 44936.23 2290.18 _ j7226.41 is the total crack length less than 3" Yes N/A --
Is the total crack length less than 15 percent of the pipe circumference. Unacceptable See note 1 Evaluation of Existing Stresses Using the Cracked Section See sheet for calculation of cracked section modulus (Zc). __
Cracked Uncracked Cracked -
r ri t I Cracked i Uncracked Ze Zun Ratio Area Ac (in) (in) (in) (in^4) (in^4) (in^3) (in^3) Zun/7x (in^2) 1.1105 1.0335 0.1540 0.419 0.6657 0.299 0.5966 1.9954 0.895 Uncracired ASME Area Aun Ratio Maximum Equation Existing Cracked Notes (in^2) Aun/Ac Ratio Number Ratio Ratio 1. For acceptance see sheet .3 1.0745 1.2006 - 1.9954 8 0.194 0.387 2. See sheet (o for existing stresses.
9 0.428 0.854 3. Used pipe nominal wall thickness see sheet 1 9E 0.26 0 519 4. This evaluation assumed the flaw uns thru-wall
- for the entire length. ,
Rev. - Orig Date Check Date Catawba Nuclear Station, Unit 1 & 2 0 C) M r - / - 95 S/ DMO '7'/ F / W/ht90-03 Evaluation of Flawed RN Fillet Welds
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Catawba Nuclear Station Unit 1 & 2 Rev. Perf. Date Check Date 90-05 Evaluation of Flawed RN Piping 0 09v g /,9( J76 5///9" Calc. File # CNC-1206.00-02-0008 Pace /6 . Att. 3
Calculation of Section Properties for Flawed Section Case 1 Angle 1 Angle 2 S S
(
0 0 5 Wall Mean 6 First Area First Area 6 S S Radians Radians 0 Thick. O. D. Radius Area Moment x Moment y lx ly Ixy Note 3 Note 3 Radians (in) (in) (in) (in) (in^3) (in^3) (in^4) (in^4) (in^4) 0 000 0.714 0.714 0.000 1.050 0.525 0 000 0.000 0.000 0.000 0.000 0.000 0.714 2.094 1.380 0.I13 I.050 0.469 0.073 0.005 0.031 0.003 0.013 0.002 2.094 2.809 0.714 0.000 1.050 0.525 0.000 0.000 0.000 0.000 0.000 0.000 2.809 4.189 1.380 0.113 1.050 0.469 0 073 -0 030 -0.011 0.012 0.004 0.004 4.189 4.903 0.714 0.000 1.050 0.525 0.000 0.000 0.000 0.000 0.000 0.000 4.903 6.283 1.380 0.113 1.050 0.469 0.073 0.024 -0.020 0.009 0.007 -0.006 Total First Area First Area Area Moment x Moment y Ix ly lxy (in) (in^3) (in^3) (in^4) (in^4) (in^4) 0.219 0.000 0.000 0.024 0.024 0.000 ybar xbar Ixbar lybar Ixybar (in) (in) (in^4) (in^4) (in^4) 0.000 0.000 0.024 0.024 0.000 Imin Imax Zmin Zmax (in^4) (in^4) (in^3) (in^3) 0.024 0.024 0.046 0.046 Notes 1. Zmin. and Zmax. are calculated using imin. and Imax with c equal to the radius to O. D. plus the resultant of 3bar apd xbar.
- 2. See shect'qfII- /3 for forumlas used in the above calculations.
- 3. Angle i represents the angle at the start of flaw and Angle 2 represent the angle to the end of the flaw, for each flaw, see sketch on sheet /4-Rev. Perf. Date Check Date 0 Qy 5 1 ')f JTT, SidW Catawba Nuclear Station Units 1 & 2 90-05 Evaluation of Flawed RN Fillet Welds Calc. File No. CNC-1206.00-02-0008 Page f(o Attachment 3
(
Calculation of Section Properties for Flawed Section Case 2 \#
Angle I Angle 2 5 6 0 0 $ Wall Mean 5 First Arca First Arca S S S Radians Radians 0 Thick O. D. Radius Area Moment xMoment ) lx ly Ixy Note 3 Note 3 Radians (in) (in) (in) un) (in^3) (in^3) (in^4) (in^4) (in^4) 0.000 0.570 0.570 0.000 1.315 0.658 0.000 0.000 0.000 0.000 0.000 0.000 0 570 2.094 1.524 0.133 1.315 0.591 0.120 0.015 0 062 0.009 0.033 0.006 2.094 2.665 0.570 0.000 1.315 0.658 0.000 0.000 0.000 0.000 0.000 0.000 2.665 4.189 1.524 0.133 1.315 0.591 0.120 -0.062 -0.018 0.032 0.009 0.007 4.I89 4.759 0.570 0.000 1.315 0.658 0.000< 0.000 0.000 0.000 0.000 0.000 4.759 6.283 1.524 0.133 1.315 0.591 0.120 0.046 -0.044 0.022 0.020 -0.014 Total First Arca First Arca Area Moment xMoment y lx ly Ixy (in) (in^3) (in^3) (in^4) (in^4) (in^4) 0.359 0.000 0 000 0.063 0.063 0.000 ybar xbar Ixbar lybar lxybar (in) (in) (in^4) (in^4) (in^4) 0.000 0.000 0.063 0.063 0.000 Imin Imax Zmin Zmax (in^4) (in^4) (in^3) (in^3) 0.063 0.063 0.095 0.095 Notes 1. Zmin. and Zmax. are calculated using Imin. and Imax with c equal to the radius to O. D. plus the restdtant of ybar apd xbar.
- 2. See sheet d iI-13 for forumfas used in the above calculations.
- 3. Angle i represents the angle at the start of flaw and Angle 2 represent the angle to the end of the flaw, for each flaw, see sketch on sheet 14 Rev. Perf. Date Check Date 0 QL) 5-1-% JTh Sle/G(
Catawba Nuclear Station Units 1 & 2 90-05 Evaluation of Flawed RN Fillet Welds Calc. File No. CNC-1206.00-02-0008 Page (7 Attachment 3 l
1
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Angle i Calculation of Section Properties for Flawed Section Case 3 Angle 2 6 6 j
0 0 6 Wall Mean 6 First Arca First Area 6 6 6 i' Radians Radians 0 Thick. O. D. Radius Area Moment xMoment y Ix ly Ixy Note 3 Note 3 Radians (in) (in) (in) (in) (in^3) (in^3) (in^4) (in^4) (in^4) i 0000 0 316 0.316 0.000 2.375 1.188 0.000 0 000 0.000 0.000 0.000 0.000 0.316 2.094 1 779 0.154 2.375 1.111 0.304 0.105 0.275 0.111 0.264 0.069 2.094 2.410 0.316 0.000 2.375 1.188 0.000 0.000 0.000 0.000 0.000 0.000 2.410 4.189 1.779 0.154 2.375 1.111 0.304 -0.291 -0.046 0.286 0.089 0.032 l 4.189 4.505 0.316 0.000 2.375 1.188 0.004 0.000 0.000 0.000 0.000 0.000 4.505 6.283 1.779 0.154 1.375 1.111 0.304 0.186 -0.229 0.166 0.209 -0.101 Total First Area First Area Area Moment xMoment y lx ly lxy (in) (in^3) (in^3) (in^4) (in^4) (in^4) 0.913 0.000 0.000 0.563 0.563 0.000 ybar xbar Ixbar I) tar lxybar (in) (in) (in^4) (in^4) (in^4) 0.000 0.000 0.563 0.563 0.000 Imin Imax Zmin Zmax g i (in^4) (in^4) (in^3) (in^3) r 0.563 0.563 0.474 0.474 Notes 1. Zmin. and Zmax. are calculated using Imin. and Imax with c equal to the radius to O. D. plus the resultant of ybar and xbar.
- 2. See sheet % /1- /3 for forumlas used in the above calculations.
- 3. Angle I represents the angle at the start of flaw and Angle 2 represent the angle to the end of the flaw, for each flaw, see sketch on sheet (4 Rev. Perf. Date Check Date 0 O h) (-/df Jh sb h1 Catawba Nuclear Station Units 1 & 2 90-05 Evaluation of Flawed RN Fillet Welds Calc. File No. CNC-1206.00-02-0008 Page IS Attachment 3
Calculation of Section Properties for Flawed Section Case 4 Angle 1 Ang!c 2 S S 0 0 6 Wall Mean 5 First Area First Area S S S Radians Radians 0 Thick. O. D. Radius Area Moment xMoment y lx ly lxy Note 3 Note 3 Radians (in) (in) (in) (in) (in^3) (in^3) (in^4) (in^4) (in^4) 0 000 2.615 2.615 0.154 2.375 1.111 0 447 0.095 0.354 0.230 0.322 0.027 2.615 3 668 1.053 0.000 2.375 1.188 0.000 0.000 0.000 0.000 0.000 0.000 3.668 6.283 2.615 0.154 2.375 1.11I 0.447 0.095 -0.354 0.230 0.322 -0.027 Total First Area First Area Area Moment xMoment y lx ly Ixy (in) (in^3) (in^3) (in^4) (in^4) (in^4) 0.895 0.191 0.000 0.460 0.643 0.000 ybar xbar lxbar lybar lxytar (in) (in) (in^4) (in^4) (in^4) 0.213 0.000 0.419 0.643 -0.000 Imin Imax Zmin Zmax (in^4) (in^4) (in^3) (in^3) 0.419 0.643 0.299 0.459 Notes 1. Zmin. and Zmax, are calculated using Imin. and Imax with c equal to the radius to O. D. plus the resultant of ybar and xbar.
5
- 2. See shect# tt-13 for forumlas used in the above calculations.
- 3. Angle ! represents the angle at the start of flaw and Angle 2 represent the angle to the end of the flaw, for each flaw, see h sheet 15 t
Rev. Perf. Date Check Date 0 G hv slik< Jr, #W
( l I Catawba Nuclear Station Units 1 & 2 90-05 Evaluation of Flawed RN Fillet Welds Calc. File No. CNC-1206.00-02-0008 Page I9 Attachment 3 I
I (Revision 7) ]
DESIGN ENGINEERING DEPARTMENT OPERABILITY EVALUATION j Station: Catawba Unit: 1&2 PIR Number: 0-C95-0527 Structure, system, or component (SSC) in question:
RN Stainless Steel socket welds Design basis reference application: FSAR volume 3, Table 3.2.2-3 Technical Specification section applicable: 3/4.4.10 Structural Integrity The SSC in question is recommended to be:
X OPERABLE CONDITIONALLY OPERABLE INOPERABLE operability Evaluation expiration date:
FSAR change required _YesXNo 10 CFR 50.59 Evaluation required _,YesXNo Summary / Comments:
The RN Stainless Steel socket welds had no safety significance issues during the investigation period of the pin hole leaks, per NRC 90-05 calculation, CNC-1206.00-02-0008. The leaking RN connnections will be replaced or repaired per a repair plan.
The repair plan will be initiated as soon as possible, but will not force the system availability. The RN socket welds are operable with these leaks.
Origina'ted by: Ernie McElroy Date: 05-02-95 Reviewed by: / tam ,_.' Date: g/2 /f h Approved by: Date:
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