ML20080C309
| ML20080C309 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 01/31/1984 |
| From: | NUTECH ENGINEERS, INC. |
| To: | |
| Shared Package | |
| ML20080C268 | List: |
| References | |
| COM-71-020, COM-71-020-R00, COM-71-20, COM-71-20-R, NUDOCS 8402080045 | |
| Download: ML20080C309 (15) | |
Text
'd Attachment 4 COMMONWEALTH EDISON COMPANY
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QUAD CITIES UNIT 2 s RECIRCULATION SYSTEM SUSCEPTIBILITY
SUMMARY
January.1984 NUTECH Engineers San Jose, California 8402080045 840127 PDR ADOCK 05000265 G PDR l COM071-020 Revision-O -
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REVISION CONTROL SHEET
- TITLE: Commonwealth Edison Co. COCUMENT FILE NUMSER: COM071.0200 Quad Cities Unit 2 Recirculation System Susceptibility Summary D. R. Pitcairn/Engineerina Director P64 fMhk s/gp/g N AME / TIT *.! INITi A LS R. H. Buchholz/Proiect Director Tb i
lNI TI A LS N AME / TITLE NAME/ 7;TLE INITi A LS NAME / TITLE IN 6Tr A LS NAME / TITLE INITI A LS AF:ECTEC 00C l 7AE7aAEC ACO*., A ACY CSITE9lA 8 AGEiS1 *EV SY / OATE OsECx sy / CATE CHECK SV #CATE l
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RECIhCULATION SYSTEM SUSCEPTIBILITY
SUMMARY
The recirculation. system and all other piping systems attached
/ to the reactor pressure vessel to the first isolation valve were constructed in accordance with Section I of the ASME Boiler and Pressure Vessel Code. Af ter the first isolation valve, the piping was constructed to USAS B31.1.0-1967 and the quality assurance / control requirements were established by the designers.
For the ASME Section I portion of the piping, the material trace-ability, authorized inspection, and data report. requirements were applied. These requirements did not require traceability of each piece of material to the certified material test report (CMTR) .
It did require CMTRs for material to be part of the data report.
For Quad Cities, carbon content values from the CMTRs for 1the recirculation system have been tabulated and the range for each piping component determined. This data is presented in Table 1. It can be observed that all carbon contents are above 0.05%. The only exception is the 28"x4" weldolet used for the recirculation bypass line (which has been cut and capped).
Table 2 lists the stress rule indices for.all stainless steel welds.
Without joint specific carbon contents, the traditional " sus-ceptibility matrix" cannot be constructed. In its place, Tables 1 and 2 provide a summary of all available information.
1
TABLE.1: iRECIRCULATION SYSTEM PIPING CARBON CONTENT COMPONENT JSIZE, INCHES. ' CARBON CONTENT, %
Riser Pipes 12 0.056 - 0.071 (0.062 Avg.)
Riser Elbows- 12 0.058 - 0.066 (0.062 Avg.)
Sweepolets 12 x 2'2 0.059 Elbows 28 0.05 - 0.064 (Discharge) 28- 0.058 - 0.077 (Suction)
Crosses 28 x 20~ 0.08 Tees 28 x 14 0.08 28 x 18 0.05 Weldolet 28 x 4 0.03 Other Pipe Not Given 0.027 - 0.077 (Per A358)
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/, ~ TABLE 2: STRESS RULE INDEX EVALUATION
SUMMARY
SYSTEM -
LINE NO. WELD ID COMP. TYPE SRI Recirculation 2-0201-22"A 02A-S10 CPIPE 1.11
__ __02A-S9 TEE 1.22 02A-S8 TEE 1,25 02A-S7 TEE 1.26 02A-S3 TEE 1.24 02A-F5 TEE 1.~ 3 2 02A-S2 TEE 1.29 02A-Fl CPIPE 1.14 02-Fi CPIPE 1.14 02-FlD CPIPE 1.15 02-FIE CPIPE 1.13 02-F2 CPIPE 1.15 02B-Fi CPIPE 1.13 020-92 TEE 1.26 i 02B-S3 TEE 1.33 i
02B-S4 TEE l 44 02B-F5 TEE l 31 02B-S7 TEE 1.45 I
02B-S8 TEE 1.25 023-S9 CPIPE 1*
02H-F6 TEE 1.26 2-020lH-12"A 02H-S4 ELBOW l.18 l
02H-S3 ELBOW l.17 02H-F2 TRANS 1.00 l
3 l
. - . ~ _ _ - , . . . . , . . . , . . . , , - _ , , , _ - _ _ , . _ - - - - - - - . - . . . . . _ , , - . . , . - . . . _ . , , - , , ,
C fy TABLE 2 : STRESS RULE INDEX EVALUATION _
SUMMARY
(continued)
SYSTEM -
LINE NO. WELD ID COMP. TYPE SRI Recirculation 2-020lJ-12"A 02J-F6 TEE 1.29 (Continued) 02J-S4 ELBOW 1.19 02J-S3 ELBOW l.19 02J-F2 TRANS 1.02 2-020lK-12"A 02K-F6 TEE 1.27 02K-S4 ELBOW l.17 02K-S3 ELBOW l.25 02K-F2 TRANS 1.06 2-0201L -12"A 02A-S4 REDUCER 1.43 02L-F6 REDUCER 1.48 02L-S4 ELBOW l.21 02L-S3 ELBOW l.24 02L-F2 TRANS 1.06 l
2-0201A-23"A 02AD-Fl TEE 1.29 Loop A 02AD-S2 TEE 1.28 02AD-S5 TEE 1.27 t
02AD-S6 ELBOW l.20
2- 02 0lM-12"A 02M-F7 TEE 1,29 02M-F6 ELBOW l.22
[ 02M-54 ELBOW l.22 4
i
TABLE 2: STRESS RULE INDEX EVALUATION
SUMMARY
(continued)
SYSTEM LINE NO. WELD ID COMP. TYPE SRI 02M-S3 ELBOW l.40 Recirculation 2-020lM-12"A- 02M-F2 TRANS 1.17 (Continued) -
2-0201C-12"A 02C-F7 TEE l.41 02C-S6 PIPE 0.97 02C-S4 ELBOW l.24 02C-S3 ELBOW l.38 02C-F2 TRANS 1.15 2-020lD-12"A 02D-F6 TEE 1.45 02D-S4 ELBOW l.34 02D-S3 ELBOW l.45 02D-F2 TRANS 1.20 2-0201E-12"A 02E-F6 TEE 1.38 02E-F6A PIPE 0.96 1
02E-S4 ELBOW l.23 02E-53 EL30W l.23 02E-F2 TRANS 1.05 2-0201F-12"A 02BD-SlA REDUCER 1.46 02F-F6 REDUCER 1.73 02F-S4 ELBOW l.42 02F-S3 ELBOW l.38 02F-F2 TRANS 1.17 2-0201B-28"A 02BD-S1 TEE 1.43 Loop B 02BD-S2 TEE 1.40 02BD-55 TEE 1.29 5
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I d,
TABLE 2: STRESS RULE INDEX EVALUATION
SUMMARY
(continued)
SYSTEM LINE NO. WELD ID COMP. TYPE SRI Recirculation 2-0201B-28"A 02BD-S6 ELBOW l.30 (continued) Loop B 02BD-F8 ELBOW 1.32 02BD-F9 TRANS 1.02 02BD-S10 TEE 1.33 02BD-F12 TRANS 1.02 1-02013- 02G-F6 TEE 1.36 02G-S4 ELBOW l.16 02G-S3 ELBOW 1.49 02G-F2 TRANS 1.22 2-0202B-28"A 02BS-F2 ELBOW 2.02 Loop B 02BS-S3 ELBOW l.59 02BS-F4 PIPE 0.94 02BS-S5 TEE 1.64 02BS-F6 TEE 1.55 02BS-F7 TRANS l.09 02BS-S9 ELBOW 1,31 02BS-312 ELBOW l.31 02BS-F14 ELBOW l.42 02BS-S15 ELBOW l.41 1.02 2-0202A-28"A 02AS-F2 TRANS Loop A l.25 02AS-53 ELBOW l.25 02AS-S4 ELBOW 0.91 02AS-F5 PIPE PIPE 0.91 02AS-S6 6
_- - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - -- - - - - - - . -- - -a
.. y TABLE 2: STRESS RULE INDEX EVALUATION
SUMMARY
(continued)
SYSTEM LINE NO. WELD ID COMP. TYPE SRI Recirculation 2-0202A-28"A- ^~ '
(continued) Loop A 02AS-S9 ELBOW 1.29 02AS-S12 ELBOW l.22 02AS-F14 ELBOW l.27 02AS-S15 . ELBOW l.31 Control Rod 2-0308-4"A 03-Fil ELBOW l.51 Drive 03-F10 ELBOW l.52 03-59 PIPE 1.14 4
03-S8 ELBOW l.58 03-S7 ELBOW l.40 03-F6 ELBOW l.20 03-F5 ELBOW l.40 2-0308-3" A 03-F4 REDUCER 1.41 03-S3 ELBOW 1.98 03-F2 ELBOW 2.03 03-F1 TRANS 1.33 Reactor Water 2-1202-6"A 12S-S24 TRANS 1.37 Clean-Up 12S-F26 ELBOW l.67 i 12S-S27 ELBOW 2.13 12S-F29 TRANS 1.56 12S-F23 ELBOW l.59 12S-S22 ELBOW l.54 12S-S21 ELBOW l.73 12S-S20 ELBOW 2.00 t 7
TABLE 2 : STRESS RULE INDEX EVALUATION
SUMMARY
(continued)
^
SYSTEM LINE NO. WELD ID COMP. TYPE SRI Reactor Water 2-1202-6" A 12S-S19 ELBOW l.94 Clean Up (Continued) 12S-S18 ELBOW 1.71 12S- F17 ELBOW 1.35 12S-S16 ELBOW l.58 12S-S15 ELBOW 2.13 12S-S14 ELBOW 2.21 12S-F13 TRANS 1.44 12S-F12 ELBOW l.66 12S-Fil ELBOW l.55 12S-510 ELBOW 1,74 12S-S9 ELBOW l.60 12S-F7 PIPE 1.11 12S-F6 CPIPE 1.38 12S-F5 CPIPE 1.43 12S-F4 CPIPE l 23 12S-F3 ELBOW l.88 12S-S2 ELBOW l.60 12S-FlA TEE 1.55 12S-F1 TEE 1.78 Residual Heat 2-1011-4" A 10HS-S13A TRANS 1.08 Removal 10HS-F12 TRANS 1 . 0 ,4 10HS-S10 ELBOW 1.33 10HS-S9 ELBOW l.32 10HS-S8A ELBOW l.26 8
TABLE 2 : STRESS RULE INDEX EVALUATION
SUMMARY
(continued) s
' SYSTEM LINE NO. WELD ID COMP. TYPE SRI Residual Heat 2-1011-4" A 10HS-F9 ELBOW 1.27 Removal (Continued) 10HS-F7 TRANS 1.63 10HS-S6 TRANS 1.51 10HS-S5 TRANS 1.53 10HS-S4 CPIPE 1.61 10HS-S2 ELBOW 2.55 10HS-S1 ELBOW 2.87 10HS-SlA TRANS 2.27 m
N6A-S2 TRANS 2.27 2-1025-20"A 10S-F1 TEE 2.18 10S-S2A. TEE 1.51 10S-33 ELBOW l.66 10S-F4 ELBOW 2.21 10S-F5 TRANS l.51 10S-S6 ELBOW 2.43 l 10S-57 ELBOW l.55 l
l 105-58 ELBOW 1,63 105-S9 ELBOW l.76 10S-Fil ELBOW l.76 10S-S12 ELBOW l.97 l
10S-513 ELBOW 2.50 10S-F14A EIEE 1.12 L
105-F15A TRANS 1.56 10S-S17 ELBOW 2.31 9
N s e
TABLE 2 - STRESS RULE INDEX EVALUATION
SUMMARY
(continued)
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SYSTEM LINE NO.. WELD ID COMP. TYPE SRI Residual Heat 2-1025-20" A 10S-S18 ELBOW l.80 10S-S19 ELBOW l.56 (C t nued) 10S-F20 ELBOW l.49 2-1012A-16"A 10AD-F1 TEE 2.40 Loop A 10AD-S2 ELBOW l.39 10AD-F3 ELBOW 1,91 10AD-F4 TRANS 1.30 10AD-SS ELBOW 2.10 10AD-S6 ELBOW l.89 10AD-S7 ELBOW l.34 10AD-F8 ELBOW l.88 10AD-59 ELBOW l.70 10AD-Fll TRANS 1 11 10AD-F12 TRANS 1 37 10AD-S13 TRANS 1 29 10AD-F15 TRANS 1 29 2-1012B-16"A 10BD-Fl TEE 1.45 E 10BD-S2 ELBOW l.18 10BD-S3 ELBOW l.66 10BD-S4 ELBOW l.59 10BD-F5 ELBOW l.68 i
l-10BD-F6 TRANS 1.14 i
! 10BD-S7 ELBOW l.69 l
l l 10BD-S8 ELBOW l.54 10 l
TABLE 2 STRESS RULE INDEX EVALUATION
SUMMARY
(continued)
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SYSTEM- LINE NO. WELD ID COMP. TYPE SRI Residual Heat 2-1021B-16"A 10BD-59 ELBOW l.53 Removal Loop B (Continued) 10BD-S10 ELBOW l.26 10BD-Sil ELBOW l.26 10BD-S12 ELBOW l.59 10BD-S13 ELBOW l.65 10BD-F14 TRANS 1.11 10BD-F15 TRANS 1.16 10BD-S16 TRANS 1.32 10BD-F18 TRANS 1.32 l
2-10ll-4"A 10HS-F13B TRANS 1.13 l-l l
l- 11 l
l
I m
TABLE 2
- STRESS RULE INDEX EVALUATION
SUMMARY
(continued)
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SYSTEM LINE NO. WELD ID COMP. TYPE SRI
. CORE SPRAY, 2-1403-10"A 14A-F19 TRANS 1.41 l LOOP A l 14A-F17 ELBOW l.88 l l
14A-S16 ELBOW l.87 l 14A-S15 ELBOW l.47 14A-F13 TRANS 1.22 14A-F12 ELBOW l.74 14A-Sil ELBOW l.33 14A-F10R PIPE 1.04 l
14A-F8AR ELBOW 2.16 l 14A-S8R TRANS 1.36 14A-F4R PIPE 1.09 14A-F2 TRANS 1.37 l
14A-S14 ELBOW l.49 l l
l l
t l
l I
a 12 l l
V '
n TABLE 2* STRESS RULE INDEX EVALUATION
SUMMARY
(continued)
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SYSTEM LINE.NO. WELD ID COMP. TYPE SRI CORE SPRAY, 2-1404-10" A 14B-S18 TRANS 1.34 LOOP B 14B-F16 ELBOW l.92 14B-S15 ELBOW l.92 r
14B-F14AR CPIPE 1.33 14B-F14 TRANS 1.22 14B-F13 ELBOW l.52 14B-S12 ELBOW 1.29 14B-FilR PIPE 0.97 14B-F8AR ELBOW l.99 14B-S8R TRANS 1.38 14B-F2 TRANS 1.22 i
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'N/ One Commonwealth ECson Attachment 5
~*
First Natt;nal Plaza. Chic'go, lihnois
'v ~7 Address Reply 13: P:st Office Box 767
. 'N / Chicago, Illinois.60690 September 30, 1983 -
l 1
Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Quad Cities Station Unit 2 IGSCC Inspection Order List of Welds Not Being Inspected NRC Docket Nos. 50-265 References (a): 'IGSCC Inspection Order Confirming Shutdown for Quad Cities Station Unit 2 dated August 26, 1983.
l (b): Cordell Reed letter to H. R. Denton dated September 6, 1983.
Dear Mr. Denton:
In accordance with Section III.C.2 of the referenced Order we are submitting a list of welds which will not be inspected this outage. Attachment I identifies the welds by system, location and size. Attachment II provides adequate technical justifications for not conducting these examinations.
If you have any questions on this matter, please contact this office.
One signed original and forty (40) copies of this letter l
l and its attachments are provided for your use.
t Very truly yours,
, /$.
B. Ryba Nuclear Licensing Administrator
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1 Toff cc: R. Bevan NRC Resident Inspector 7395N
1 Attcchmeat I - List of 304 c/o piping walds Q 4" n.p.o.) that will nnt be in pactsd durirg thic currant outrge. --
System L cation Elevation / Azimuth Comments -
ds (N S.)
RHR - Head Spray 01 4" Reactor cavity 660' Inaccessible for UT (1)
RHR - A LPCI Injection 01 16" Containment 590'!85 Inaccessible for UT (2) penetration X-13A 01 16" Containment 590'/85 Inaccessible for irr (3) penetration X-13A
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RHR - B LPCI injection 01 16" Containment 591'/265 Inaccessible for UT (2) penetration X-13B RHR - Shutdown cooling 01 20" Containment 605'/345 Inaccessible for UT (2) penetration X-12 01 20" Containment 605'/345 Inaccessible for UT (3) penetration X-12 Core Spray - A loop 01 10" Containment 642'/20 Inaccessible for UT (2) penetration X-16A Core Spray - B loop 01 10" Containment 642'/185 Inaccessible for UT (2) penetration X-16B Reactor Water Clean-Up 01 6" Containment 625'/90 Inaccessible for UT (2) penetration X-14 01 6" Drywell - 1st grating 602' Inaccessible for UT (4) 08 6" Drywell - 1st grating 610' Piping replacement with conforming material 07 6" Drywell - 2nd grating 615' Piping replacement with conforming material Recirculation - A Suction 01 28" Drywell - Basement 587' Not inspectable due to material structure (5)
Recirculation - B Suction 01 28" Drywell - Basement 585' Not inspectable due to material structure: (5) ,
9.
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ATTACHMENT II TECHNICAL JUSTIFICATIONS (1) This weld in the RHR system is located just above the point at which the line penetrates the floor separating the reactor cavity and the drywell.
The inacceptability is due to the pres'ence of a water barrier as shown on figure 1. Relief from Inservice Inspection requirement for this weld has been granted'by the NRC staff.
(2) These Class 1 lines, due to the design of primary containment penetration assembly, have one circumferential pressure retaining weld that is inaccessible for volrmetric examination. Figure 2 clearly illustrates the design constraints which make it extremely impractical to examine the subject welds by volumetric technique. Relief from Inservice Inspection requirement for these welds has been granted by the NRC staff.
(3) These Class 1 welds in the Reactor Clean up and RHR systems are physically inaccessible for volumetric examination. They cannot be examined because of interference from a structural steel guide as shown on figure 3.
(4) The design of this Reactor Clean up branch pipe connection weld calls for the use of reinforcement saddle. This saddle is fillet welded over the actual pressure retaining branch pipe to main pipe weld, completely incasing it as illustrated on figure 4. Relief from Inservice Inspection requirement for this weld has been granted by the NRC staff.
(5) In the Recirculation system there are two (02) elbow to recirculation pump casing welds (suction side). The elbow and pump casing material is
-type CF8M cast austenitic stainless steel which has been demonstrated to be highly resistant to oxygen-assisted stress corrosien in the as-installed condition per NUREG-0313, Rev. 1. The high ultrasonic beam attenuation of the cast stainless steel base material inhibits meaningful examination of the two subject welds by ultrasonic method. The examination requirement
- is thus impractical for these two welds because of material structure.
The safety implications of these exemptions are minimal due to the fact that'the safety margins in the subject welds are typical of those in all welds in the applicable systems. Since the exempted welds represent only a small fraction of the total number of welds examined per IGSCC Inspection Order (12 out of 237), the statistical significance of exempting these welds is expected to be negligible.
O II-l
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- " I I INACtES$1BLE WELD
(?RE55U1E-RETAINING) l I l \' f: RX CAVITY l W%
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l Figure 1 lleid Obstruction Details s
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l CONTAINNENT DRYWELL SHELL l .
EXPANSION TEIPLE
. EELL0ss F LUED e .* HEA CENTERING LUC 5 - -_
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&x x x x x x x x x x x xx x x, Y
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11' TO
IMACCESSIELE uELD
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PENETEATION *[ .
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Figure 2 Typical Design of Primary Containment Penetration ,
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PO EritATION
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l .su!DE INACCES$!BLE wtLD (PRESSURE-RETAINING) l' I
Figure 3 Weld Obstruction Details I
NACCES$13LE WELD PRESSURE-RETAINING) f
, e SRANCM,P!PE RUN l .
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\ REINPORCEMENT PLATE l MAIN PIPE RUN Figure 4 Reinforced Branch Pipe Connection i
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e f Attachment 6 0
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Table 1
. Quad Cities Unit 2 - Steady" State Stresses for IHSI Treated o Welds With Flaw Indications Total Weld ID a Pressure a Deadweight a Thermal Applied Stress N- 'I '
' 02D-s3 '5800 [ ,} 643 1710 8153
- og l
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02M-S3 6811 ,
1132 349 8293
.c . g-02M-S4 6811 +
f, 289. ,
134 7234 s<.
02AS-S4 3
.6692 s
' ' '\ 1C6f f 1,. ' 203 7051 02AS-S6 6692 .- -74 404' ~
7022 s i 02AS-S12 6692 ', J ~58 453 s 7203
.,.s ,
02AS-F14 [6692 62 >
418 7172 1
02AD-F12 , ,
6439N. 35 ,
241 6680 02BS-S12 6692 101" 896 7689 c
02BS-F14 6692 ,
90 J .4 1037 7819 02A-S10 6290 'O* ,
0 6290 02B-S9 6290 'O O 6290 10S-F5 . 6510 ., -561 ,
10993 18064 1
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Note: All stress values a're in psi. ,
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Attachment 7 Table 2 Quad Cities Unit 2 - Weld Overlay Induced Shrinkage Stresses
! 02AS-S12 46 02AS-S4 72 02AD-F12 224 02A-S10 0
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02B-S9 0 02BS-S12 108 02BS-F14 105 10S-F5 56
- Due to weld overlays in the piping system for welds with flaw indications that were treated by IHSI.
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Attachment 8 Table 3 Quad Cities Unit 2 -- Weld Overlay As-Built Information q
Overlay Iingth Overlay Shrinkage t Upstream /{hickness AL Wald I.D. L Downstream
- 02D-F6 3.875" */.391" .140" E02F-F6 4.5" .270"/.313" .230" l
02G-S3 4.5"' .314"/.276" .230"
- 02J-F6 3.75" .309"/.339" .176" 02AS-S9 2.80" NA/.348" .020" 02BS-S3 4.62" .285"/.362" .041" 02BS-F7 5.54" NA/.287" .019" 02BD-S6 6.56" .462"/.550" .031" 10S-F1 3.625" NA/.329" .045"
- Raadings could not be taken due to geometry.
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .)