ML20083N714
| ML20083N714 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 05/02/1995 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20083N549 | List: |
| References | |
| CNC-120600-02-0, CNC-120600-02-0007, CNC-120600-2, CNC-120600-2-7, NUDOCS 9505230259 | |
| Download: ML20083N714 (18) | |
Text
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ATTACHAEW j vm oton <nax CERTIFICATION OF ENGINEERING CALCULATION STATION AND UNIT NUMBER d)J 5 i e7- -
TITLE OF CALCULATION 90- 05~ GEL ot0lN 4 57W/A>/MS StRel IkN L]a ins .._,.
CALCULATION NUMBER C13 CL 17_.OL m-nV ~0007 ORIGINALLY CONSISTING OF: -
PAGES I THROUGH 1 TOTAL ATTACHMENTS 8 TOTAL MICROFICHE ATTACHMEN O TOTAL VOLUMES / TYPE I CALCULATION INo /ANALYSIS TYPE i REVIEW FREQUENCY'I.MTE'E ii THESE ENGINEERING CALCULATIONS COVER QA CONDITION 1 ITEMS. IN ACCORDANCE WITH ESTABLISHED PROCEDURES, THE QUALITY HAS BEEN ASSURED AND I CERTIFY THAT THE ABOVE CAL-CULATION HAS BEEN ORIGINATED, CHECKED OR APPROVED AS NOTED BELOW:
ORIGINATED BY Mb [hh '
DATE I!2!O[
CHECKED BY O/devakf[hia %J DATE SA f!*!W-d443 APPROVED BY _. b. /d DATE f /2 [
ISSUED TO DOCUMENT MANAGEMENT f du ,3 DATE C'/d b-RECEIVED BY DOCUMENT MANAGEMENT DATE MICROFICHE ATTACHMENT LIST: 0 Yes C No SEE FORM 101.4 CALCULATION PAGES (VOL) ATTACtiMENTS (VOL) VOLUMES ORIG CHKD APPR TE NO' REVISED DELETED ADDED REVISED DELETED ACOED DELETED ADDED R DATE DATE DATE DA 1
ES 9505230259 950511 PDR ADOCK 05000413 p PDR
x File No. CNC 1206.00-02-0007 NRC GL 90-05 Cal on RN 4" Stainless Steel Butt Welds i
1.0 PROBLEM STATEMENT This calculation evaluates a through wall pitting located on a 4" butt welds on the RN system piping.
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 Condition Piping addressed by this calculation is QA condition 1 and is a QA condition 1 calculation.
3.0 DESIGN METHOD This calculation evaluates using the rules 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 StmeturalIntegrity 5.0 DESIGN INPUTS Not Applicable 6.0 PS AR. FSAR 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 l
Pane 1of2
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File No. CNC 1206.00-02-0007 NRC GL 9045 Cal on RN 4" Stainless Steel Butt Welds -
9.0 EVALUATION This calculation evaluates the through wall region identified as the heat affect zone, HAZ, near the weld area. The evaluation approach is the "through-wall flaw" per "NRC Generic Letter 90-05" Attachment 3, the calculation meets the requirement of t'K" less than 135 ksi(in)". This calculation uses the worse case generic sizing of the flaw. This is consistent with the lower-bound fracture toughness property in ASME Code Case N-463. The worse case flaw size is 3/8", in the pipe wall, Met Lab Report 1812. The actual examination of the pin hole with a magnifying glass while still installed was less than a 0.15", with a weepage ofless than I drop per minute. A walk down of the all RN stainless steel piping, %" to 8", was' completed by a Spoc team attachment 2 is a list of the 4" weld numbers identified.
10.0 CONCLUSION
The pin hole leaks in the HAZ on 4" RN stainless steel butt welds are acceptable per NRC Generic Letter 90-05 using the "Through-Wall Flaw" approach. The leaking RN piping 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 butt welds are operable with these pin hole leaks.
l Prepared By Ernie McElrov Date_5/02/95 1
Checked By I/<dir a Date dd/hY Y r l
Page 2 of 2
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j Attuhnwnt 1
- The pinhole leaks in the stainless stal portions of the RN system piping pose no threats from either a flooding or pipe rupture perspective. 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 affect-d zoneof the welds. These weld locations were reviewed as part of the moderate energy piping water rj.ay ste+j 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 aircady in place at the giant. The only portions of piping which are excluded are those equal to or less than !" in diameter. Since 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 T 4" PIPING Attachment 2 i
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WELD #s l IPIPE DIA.) l ORN 187 2 4" ORN 187 22 - 4" ORN 187-43 4" ORN 187-44 4" ORN 187-5 . 4" ORN 187-7 4" ORN 189-15 4" ORN 189 4" ORN 189-7 4" ORN 191 14 - 4" ORN 191-4 . 4" ORN 196-18 . - 4" l ORN 196 4" l ORN 200-3' , 4" ORN 222 2 4" ORN 223 4" ORN 22415 '
4" .
ORN 224 2 . 4" ORN 224-6 4" ORN 22615 4" ORN 227-10 4" og [ A R tJ-124 - I'l 512 6 4"
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Page1
Attachment 2A i
Butt Weld Flaw Characterization I Two of the three 4" Butt welds were section for flaw characterization. The ID penetrations were ,
3/16" to 3/8" from the toe of the weld. Each leak was reported on the underside of the pipe. The !
corrosion in the butt weld is described as propagating through wall starting as a pin hole, enlarging to - %" axially and circumferentially, and necking down to a pin hole as it exits the pipe's OD. 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. The worse considered flaw in the butt welds is the first described leak in the Met Lab 1812 report. It is a pin hole leak on the bottom of the pipe with two tubercle on either side of the leak, figure 1. This assumes a through wall leak under every tubercle. The two tubercles approximately 3" either side of the bottom are far enough apart to consider them as three different leaks. There was no evidence of linking (cracking) between the pin holes. The two tubercles did have pitting occuring under them. One size,3/8",
per pin hole was used for butt welds and socket welds. This is the maximum cavity seen in the stainless steel RN piping. This is considered the worse case of all the observed leaking welds.
Case 1: 4" piping with one 3/8" hole, with reduced section modulus of the holes 3" apart.
This is analyzed in case 1, attachment 3 on 4" piping and is acceptable. The maximum weepage from any of the pin holes is less than 1 drop per minute. Using this as the maximum leaking flaw found in SS Butt welds in the RN system, and the maximum stresses applied, this passes generic letter 90-05, using the through wall flaw approach. The third butt 4" weld was left intact for NDE use.
3 b
90-05 Evaluation of Flawed Butt Welds I
1 (Attachment 3) ;
(
L j l- Statement of Problem / Purpose ]
The purpose of this calculation is to evaluate the structtiral integrity of the thm-wall leaking flaws t
, that exist in the stainless steel butt welds as listed in Table 3 (see sheet 4 _ ). The flaws were l characterized in attachment 2A of this calculation. The characterized flaws will be covered by -l one case. l Quality Assurance Condition ,
I l This calculation is QA condition 1 because it serves as the basis for the qualification of a QA l condition I stmeture, system or component.
Analysis Methods Used This condition will also be evaluated using Generic Letter 91-18 section 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. For Piping Analysis Calculations, see Table 1 l 2. NRC Generic Letters 90-05 and 91-18
- 3. ASME Code Case N-480 l
- 5. For weld isometric see Table 2
- 6. Vector Mechanics for Engineers: Statics & Dynamics, by Beer and Johnston Catawba Nuclear Station Unit 1 & 2 Page: I 90-05 Evaluation of Flawed RN Butt Welds File No.: CNC-1206.00-02-0007 Rev. O, Attachment 3 By:QM Date: 5-Z-96 Check: O/Vb Date: 7-2-9 I
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Assumptions
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Listed' as used in body of calculation Characterization .
The following case was considered based on attachment 2A of this calculation. For this case the flaw was assumed to be thm-wall for the entire length.
Case 1 - considers a 4" sch 40 pipe with 3-0.375" flaws located 3" apart.
Evaluation Per section C, part 3, of generic letter 90-05, the stmetural 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.
Since the flaw consists mainly of a subsurface 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 of 3", these flaws were considered far enough apart to be considered separately.
. The existing stresses for each weld location are tabulated on sheet E These stresses were taken from the existing Superpipe Analysis Runs for the problems listed in Table 1 (see sheet 4- ). The maximum A.SME 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 an Emergency allowable.
l Catawba Nuclear Station Unit 1 & 2 Page: 2.-
90-05 Evaluation of Flawed RN Butt Welds File No.: CNC-1206.00-02-0007 Rev. O, Attachment 3 By: CD Date: 5 9_f Check: d4#D Date: S W
/
1
i l
l Evaluation (cont.)
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 was then used to calculate the 90-05 bending stress using the section modulus at the extreme fiber. The 90-05 '
pressure stress was then conservatively calculated using PD/4t. These stresses were added together to determine the tota l 90-05 stress. The above case was evaluated using the maximum stress from all weld locations (see sheet 6
).
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 (see sheet I( ). The equations used to calculated the section properties are derived on sheets '7 through 9 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 "uncracked" / Ac " cracked") (see sheet (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 at the next scheduled outage, making the evaluation of a secondary thermal stress oflittle concern, especially from a fatigue standpoint.
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 this case, calculated on sheet (v is 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.
Catawba Nuclear Station Unit 1 & 2 Page: 3 90-05 Evaluation of Flawed RN Butt Welds File No.: CNC-1206.00-02-0007 Rev. O, Attachment 3 By:
O, %,J Date: 6-2-95 Check: 6_ /4d_9 Date: c W t
Table 1 Micro Calculation Calculation Prob. Fiche Superpipe Run File Rev.
No. Attach Date Time No. No.
3RN M6 02-20-91 17:20:33 CNC-1206.02-84-2023 19 4RN M8 08-22-91 15:28 48 CNC-1206.02-84-2019 17 6RN M9 02-27-91 11:54:34 CNC-1206.02-84 2015 26 Table 3 Table 2 Nominal Wall Weld Weld #'s Diameter Schedule Thickness Isomtric Drawing ORN-lH7 2 4" 40 0.237 Drawing Resision ORN-187-22 4" 40 0.237 Numbers Number ORN-187-43 4" 40 0.237 CN-ORN-187 7 ORN 187-44 4" 40 0.237 CN-0RN 189 3 ORN-187 5 4" 40 0.237 CN4RN 191 6 ORN.I 87-7 4" 40 0 237 CN-ORN 196 10 ORN-189 15 4" 40 0.237 CN-0RN 200 8 ORN 189-16 4" 40 0.237 CN-0RN-222 0 ORN 189-7 '
4" 40 0.237 CN ORN 223 0 ORN 191 14 4" 40 0.237 CN 0RN-224 2 ORN.I 9 I-4 4" 40 0.237 CN4RN-226 2 ORN-196 18 4" 40 0.237 CN-ORN-227 0 ORN 196-23 4" 40 0.237 ORN 200-3 4" 40 0.237 ORN-222-2 4" 40 0.237 ORN-223-3 4" 40 0.237 ORN-224 12 4" 40 0.237 ORN-224 15 4" 40 0.237 ORN-224-2 4" 40 0.237 ORN-224-6 4" 40 0.237 ORN-226-15 4" 40 0.237 ORN-227 10 4" 40 0.237 i
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l Catwaba Nuclear Station Unit 1 & 2 Page 4-90-05 Evaluation of Flawed RN Butt Welds File No.: CNC-1206.00-02-0007 Rev. O, Attachment 3 Dy: OO Date: 5- l- 9 f Check: 8 Date: 9 /'I
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Existing Butt Welded Stresses Micro 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 ORN-187-2 6RN M9 02-27-91 11:54:34 C10A 108L pd/d 115 mean 0.029 0.039 0.345 0.035 % 84 1141 10825 1.8 ORN-187-5 6RN M9 02-27-91 11:54:34 109 II3R pd'd i15 mean 0.068 0. I i 1 0.279 0.105 7845 3482 11327 1.8 ORN-187-7 6RN M9 02-27-91 11:54:34 C09A Il4L pd/d 115 mean 0.068 0.101 0.198 0.093 5563 3070 8633 1.8 ORN-187-22 6RN M9 02-27-91 11:54:34 D08A 123L pd/d 115 mean 0.052 0.116 0.167 0.120 4695 3944 8639 1.8 ORN-I S7-43 6RN M9 02-27-91 11:54:34 E07A 41L pd/d 115 mean 0.053 0.142 0.046 0.151 1284 4998 6282 1.8 ORN-187-44 6RN M9 02-27-91 11:54:34 D07B 37R pd/d 115 mean 0.047 0.118 0.025 0.125 707 4106 4813 1.8 ORN-189-7 6RN M9 02-27-91 11:54:34 370 206R pd/d i15 mean 0.072 0.090 0.451 0.078 12648 2553 15201 1.8 ORN-189-15 6RN M9 02-27-91 11:54:34 1501 208L pd/d 115 mean 0.078 0.121 0.274 0.114 7683 3733 11416 I.8 URN-189-16 6RN M9 02-27-91 11:54:34 1503 210R pd/d 115 mean 0.074 0.135 0.209 0.132 5858 4374 10232 1.8 ORN-191-4 6RN M9 02-27-91 11:54:34 C06B 26R pd/d 115 mean 0.053 0.096 0.060 0.094 1671 3104 4775 1.8 ORN-191-14 6RN M9 02-27-91 11:54:34 1001 14L pd/d 115 mean 0.043 0.066 0.057 0.062 1612 2029 3641 1.8 ORN-196-18 3RN M6 02-20-91 17:20:33 520 86L pd/d 115 mean 0.056 0.092 0.135 0.088 3790 2891 6682 1.8 ORN-196-23 3RN M6 02-20-91 17:20:33 496 85 pd/d I15 mean 0.060 0.097 0 144 0.092 4039 3033 7072 1.8 ORN-200-3 4RN M8 08-22-91 15:28:48 C06B 14R pd/d 115 mean 0 080 0.073 0.133 0.053 3743 1725 5468 1.8 ORN-222-2 3RN M6 02-20-91 17:20:33 C52B 322R pd/d 115 mean 0.029 0.040 0.162 0.036 4544 1183 5727 1.8 ORN-223-3 3RN M6 02-20-91 17:20:33 F40B 230R pd/d 115 mean 0.047 0.080 0.246 0.077 6911 2541 9453 1.8 ORN-224-2 6RN M9 02-27-91 11:54:34 1505 472L pd/d 115 mean 0.047 0.113 0.131 0.118 3684 3900 7585 1.8 ORN-224-6 6RN M9 02-27-91 11:54:34 1510 478R pd'd 115 mean 0.107 0139 0.070 0.122 1956 4010 5966 18 ORN-224-15 6RN M9 02-27-91 11:54:34 *2 486R pd/d i15 mean 0.049 0.114 0.148 0.118 4165 . 3909 8075 1.8 ORN-226-15 6RN M9 02-27-91 11:54:34 *l 418R pd/d 115 mean 0.052 0.147 0.162 0.159 4543 5220 9763 1.8 ORN-227-10 6RN M9 02-27-91 11:54:34 1205 444R pd/d 115 mean 0.028 0.099 0.267 0.110 7483 3628 11III 1.8 ORN-224-12 6RN M9 02-27-91 11:54:34 C64B 492W pd/d 115 mean 0.046 0.118 0.086 0.125 2400 4122 6522 1.8 Max 0.107 0.147 0.451 0.159 Maximum Stress 15201 1.8 SIF at Max 1.8 1.8 1.8 1.8 SOP number at location of maximum stress = 206R Notes:
- 2. Weld is located between C638 and C64A. Press +Wt+SSE 2553 Pressure Term pd/d Pressure 115 Section Mod. mean Rev. Pref. Date Check Date Catauba Nuclear Station Units 1 & 2 0 &
q /-9r @AO S-/-9f 90-05 Eval. of Flawed RN Butt Welds Calc. File No. CNC-1206.00-02-0007 Page T Attachment 3
Thru-Wall Flaw Evaluation Using Generic Letter 90-05 for Butt Welding Piae Pipe Pipe Nom. Wall Code tmin One Half Mean O. D. Rickness See note 3 Total Crack Radius (in) (in) (in) (in) Length (in) c r A B 2.1315 4.500 0.237 0.237 0.I875 0.0280 8.994 5.7599 -11.7608 Enter I for carbon steel and 2 stainless steel 2 Piping Stress Allowble Stress Intensity Stress C ksi (Note 2) F K Intensity Ratio 19.5445 9.57 1.0255 10.55 135 0.03-Superpipe pressure stress-Enter I for Pd^2/(D^2<1^2) or 2 for PD/4t i Superpipe section modulus-enter I for mean or 2 extreme fiber 1 Existing SIF 1.8 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 EQ 9E stress (P) Stress Stress Moment Stress Stress Stress 12648 2553 115 461.23 2091.77 29010.81 9025.01 545.89 9570.90 i 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 I Uncracked Ze Zun Ratio Area Ac (in) (in) (in) (in^4) (in^4) (in^3) (in^3) Zu*n/Ze (in^2) 2.1315 2.0130 0.2370 6.4500 7.2326 2.7800 3.3827 1.2168 2.9210 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 .
3.1740 1.0866 1.2168 8 0.107 0.130 2. See sheet 6 for existing' stresses.
9 0.147 0.179 3. Used pipe nominal wall thickness see sheet 2.
9E 0.159 0.193 4. This evaluation assumed the flaw was thru-wall for the entire length.
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l Catawba Nuclear Station Unit I & 2 Rev. Perf. Date Check Date 90-05 Evaluation of Flawed RN Piping 0 QN 5- /. 9.f -J TL @l sr Calc. File # CNC-1206.00-02-0007 '
Pace /O . Att. 3
Calculation of Section Properties for Flawed Section Angle I Angle 2 6 6 0 6 Wall Mean 6 First Area First Area 6 6 6 0
Radians Radians 0 Thick. O. D. Radius Area Moment x Moment y Ix ly Ixy Note 3 Note 3 Radians (in) (in) (in) (in) (in^3) (in^3) (in^4) (in^4) (in^4) 0.237 4.500 2.132 0.787 1.077 1.063 1.803 1.774 1.147 0.000 1.558 1.558 1.725 0.167 0.000 4.500 2.250 0.000 0.000 0.000 0 000 0.000 0.000 1.558 3.058 1.333 0.237 4.500 2.132 0.674 -0.974 0.908 1.609 1.451 -1.113 1.725 3.225 0.167 0.000 4.500 2.250 0.000 0.000 0.000 0.000 0.000 0.000 3.058 4.558 1.333 0.237 4.500 2.132 0.674 -0.974 -0.908 1.609 1.451 1.113 3.225 4.725 0.167 0.000 4.500 2.250 0.000 0.000 0.000 0.000 0.000 0.000 4.558 4.725 6.283 1.558 0.237 4.500 2.132 0.787 1.077 -1.063 1.802 1.774 -1.147 Total First Area First Area Area Moment x Moment y Ix ly Ixy (in) (in^3) (in^3) (in^4) (in^4) (in^4) 2.921 0.205 0.000 6.823 6.450 -0.000 ybar xbar lxbar lybar Ixybar (in) (in) (in^4) (in^4) (in^4) 0.070 -0.000 6.809 6.450 -0.000 Imin Imax Zmin Zmax (in^4) (in^4) (in^3) (in^3) 6.450 6.809 2.780 2.935 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 sheets "7 thru A for forumlas used in the above calculations.
- 3. Angle 1 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 iO Rev. Perf. Date Check Date 0 9%) 5?M m givinc
/
Catawba Nuclear Station Units 1 & 2 90-05 Evaluation of Flawed RN Butt Welds Calc. File No. CNC-1206.00-02-0007 Page ll Attachment 3
(Revision 7) '
DESIGN ENGINEERING DEPARTMENT OPERABILITY EVALUATION Station: Catawba Unit: 1&2 PIR Number: 0-C95-0527 Structure, system, or component ' (SSC) .in question:
4" RN Stainless Steel butt 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 _YesX,No Summary / Comments:
The 4" RN Stainless Steel butt welds had .no safety significance issues during the investigation period of the pin hole leaks, per NRC 90-05 calculation, CNC-1206.00-02-0007.
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.
Originated by: Ernie McElroy Date: 05-02-95 Reviewed by: Date:
Approved by: Date: