ML20210K323
| ML20210K323 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 08/08/1997 |
| From: | Saunders R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 97-079A, 97-79A, NUDOCS 9708190225 | |
| Download: ML20210K323 (18) | |
Text
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Vikti Ni A Ei.iri nic ANi> l'<m i:n Cm PA N Y Ricimosis. Visuaisir 2mit August 8, 1997 1
i United States Nuclear Regulatory Commission Serial No. 97 079A Attention: Document Control Desk NL&OS/ETS Washington, D.C. 20555 Docket Nos. 50 338 50 339 l License Nos. NPF 4 NPF 7 4
Gentlemen:
YJBRINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION VHlTS 1 AND 2 RELIEF FROM ASME SECTION XI REQUIREMENTS In a February 24,1997 letter (Serial No. 97 079), Virginia Electric and Power Company requested relief from ASME Section XI paragraph IWA 5250. The relief would permit continued Service Water System operat!on for up to eighteen months from the date of discovery of each minor leak or indication of previous leakage attributed to microbiological influenced corrosion (MIC). In a telephone conference call, the NRC staff requested additional information (i.e., a more definitive scope statement) to complete the evaluation of the Code Relief Request. The enclosure to this letter provides the revised relief request (NDE-32), which includes the requested information and a proposed change to the Service Water System walkdown frequency.
The proposed frequency for conducting Service Water System walkdowns has been changed from monthly in the initial relief request to every six weeks. This walkdown frequency was chosen to coincide with our twelve week Maintenance Rule planning schedule for the Charging Pumps in order to limit the time equipment is out of service for testing and maintenance, consistent with the intent to improve availability.
Performing walkdowns on a six week frequency permits both proactive identification and repair of flaws as well as reducing the time safety-related equipment is out of service.
Until this relief is approved by the NRC staff, a routine monitoring program has been implemented for the Service Water System. The monitoring program includes walkde,,;ns of the accessible portions of the stainless steel Service Water System piping to identify, monitor and quantify any leakage. When a leak or evidence of previous leakage is identified, an evaluation of the Service Water System is performed ,
kD bb k ho 38 P PDR i
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, to the extent possible in accordance with Generic Letter (GL) 90 05, "Guldance for Pedorming Temporary Non Code Repair of ASME Code Class 1,2, and 3 Piping," to determine operability and continued safe operation of the units until tne necessary ASME Code repairs can be completed.
The revised relief request has been reviewed and approved by the Station Nuclear Safety and Operating Committee.
This letter does not establish any additional commitments. If you have any additional questions concerning this relief request, please contact us.
Very truly yours, R. F. Saunders, Vice President Nuclear Engineering and Services Enclosure cc: U. S. Nuclear Regulatory Commission Replon ll Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 A.tlanta, Georgia 30303 Mr. M. J. Morgan ,
NRC Senior Resident inspector North Anna Power Station
l ,
l ENCLOSURE Revised ASME Section XI Rollef Request NDE-32 MlC Monitoring Program Virginia Electric and Power Company North Anna Power Station Units 1 and 2
Virginia Electric & Power Company North Anna Power Station Unit 1 and Unit 2 Second 10 Year Interval Request for Rollef Number NDE 32 Revision 2
- 1. IDENT1FICATION OFCOMPONEtRS Drawina #
Ser@e Water System 11715 CBB-40D 2 SHTS.1 and 2 11715 CBM 78A 2 SHTS.1 and 4 11715-CBM 788 2 SHTS.1 and 3 11715-CBM-78C 2 SHT. 2 11715 CBM 78G 2 SHTS.1 and 2 11715 CBM 73H 2 SHT 1 Components within the scope of this Request for Relief include the welds and associated piping which comprise the moderate energy stainless steel piping of the Service Water System (SW). This piping system provides cooling water from the Service Water Reservlor to safety related equipment and return the Service Water back to the retum headers. Normal operating pressure it.100 PSIG. The design pressure is 150 PSIG and the design temperature is 150'F. This is an ASME,Section XI, Class 3 system.
Attachment 2 provides an identification of each piping segment within the scope of this Request for Relief. The p! ping segments are identified by their line numter designation 'hich is a unique identifier. The graphics represented on the associated draw. gs of each piping segment along with the associated line number designation provide a defining boundary for each pipe segment. The identification of piping segments as components is appropriate as both the welds and piping forming the piping segments are subject to developing through weil leaks.
II. IMPRACTICABLE CODE REQUIREMENTS The Service Water System has experienced through-wa'l leakage caused by Microbiological Influenced Corrosion (MIC). Chemical treatment of the Seivice Water System has not been effective in eliminating MIC. The Service Water System is being monitored for MIC. Identification of additional through wall leakage is anticipated. Through wall leakage must be located and evaluated in accordance with the requirements of IWA 5250 of the 1983 Edition and Summer 1983 Addenda for Unit 1 and 1986 Edition for Unit 2. The specific Code requirement for which relief is requested is IWA 5250(a)(2).
Relief Request NDE-32 Rev.2 Page 1 of 7
"lWA 5250 Conective Measures:
(a) The source of leakage detected during the conduct of a system pressure test shall be located and evaluated by the Owner for corrective measures as follows:...
(2) repairs or replacements of components shall be performed in accordance with IWA-4000 or lWA 7000, respectively."
Articles IWA 4000 and IWD-4000 of ASME Section XI Code repair requirements would require removal of the flaw and subsequent weld repair.
Code repairs for through wall leaks require the line to be isolated and drained.
Taking a train of service water out of service in some instances is a major evolution and requires entering a Technical Specification action statement.
Welds and piping with through wall flaws caused by MIC can typically be shown
, to have adequate structural integrity to remain in service. This type of through wall flaw is unpredictable but not normally subject to catastrophic failure, it is impractical to require a Code repair within the time specified by the Technical Specification Limiting Condition for Operation every time a l through wall flaw is identified.
l i
Generic Letter 90-05, "Guldance for Performing Temporary Non-Code Repair of ASME Code Class 1,2, and 3 Piping", provides guidaace for submitting relief requests to allow continued operation with a through wall flaw. Submitting a relief request for each instance of through-wall leakage caused by MIC is an .
administrative burden and causes additional unnecessary reviews for the NRC. '
Implementing GL 90-05 each time a through-wall flaw is identified is also impractical.
This relief request establishes a plan for continued operation with through wall flaws in stainless steel piping in the Service Water System based upon the guidance of GL 90-05 to the extent it is believed practical. This relief request will be implement.J upon receiving NRC approval. In the interim, GL 90-05 will be followed for through-wall flaws and relief requests will be submitted.
Ill. ISI BASIS FOR RELIEF REQUEST This relief request is submitted in a format laid out in NRC GL 90 05. The following information and justification is provided in accordance with the guidelines of Part B and C of Enclosure 1 to GL 90-05.
Relief Request NDE-32 Rev.2 Page2 of 7 j
Scone. Limitations and Specific Considerations Scope The scope consists of welds and stainless steel piping, pipe class 153A and 163, with evidence of possible through-wall leaks in the Service Water System at North Anna Power Station Units 1 and 2, 1, imitations Based on radiographic examinations and laborator/ examinations of removed portions of piping from replacements, North Anna Power Station is experiencing MlC in its stainless steel piping. The MIC caused flaws originate on the inner l diameter of the pipe. The Service Water System is common to both Units. As long as one Unit is in Mode 1,2,3, or 4 both trains of service water must bo operable, if both Units are in Mode 5 or 6 then one train of Service Water must
) be operable. The intent of this relief is to permit continued operation with the l
identified through-wall flaws until repairs are accomplished in a scheduled service water outage.
Specific Consklerations I
l System interactions, i.e. consequences of flooding and spray will be evaluated.
The flaws located on piping, such that potential through wall leakage could affect plant safety related equipment will be declared inoperable and the appropriate Technical Specification action statement entered.
Butt welds and piping accessible to radiography with through wall flaws will be evaluated for structural integrity within 14 days of identification for all design loading conditions, including dead weight, pressure, thermal expansion and seismic (DBE) loads. The methods used in the structural integrity analysis will consist of area reinforcement, fracture mechanics, and limit load analyses.
These methods are detailed in Attachment 1. The welds that aru found to be unacceptable will be declared inoperable and the appropriate Technical Specification action statement entered.
A 3/4" hole will be postulated for any location with a through wall flaw that can not be characterized volumetrically by ultrasonics or radiography, socket welds and welds that are inaccessible for radiography. Laboratory examination of cut sections of MIC degraded socket weld samples indicate that flaws are enveloped within the 3/4" size. A leaking socket weld location will be analyzed by treating the cross section as equivalent to the cross section of the attached pipe with a 3/4" hole. The methods used in the structural integrity analysis will consist of area reinforcement, fracture mechanics, and limit load analyses. These methods are detailed in Attachment 1. A through wall flaw size is postulated in order to Reisf Request NDE-32 Rev.2 Page 3of 7
perform a structural analysis. Additional monitoring is performed for a period of two (2) months on socket welds to assure the degradation mechanism is behaving in a manner expected for a MIC flaw.
The structural integrity for all welds identified with evidence of through-wall leakage will be monitored by the following methods:
. Weekly visual monitoring of through wall flaws from the time of identification until completion of structural integrity analysis. If the welds are determined to be structurally acceptable then the visual monitoring frequency will be decreased to once every six weeks.
. Weekly visual monitoring of through wall flaws in socket welds and butt welds inaccessible to radiography for a period of two (2) months, if there is no significant change in the lee': age rate the monitoring frequency will be decreased to once every six weeks until the welds are repaired.
A significant change is defined as a 0.5 gpm increase in the leakage rate from the initial observed leakage condition for each weld. Should any location reach the threshold of a significant change the weld will be reassessed for structural integrity and flood / spraying consequences.
- A total leakage rate limit of 1.0 gpm for a single supply or retum line to an Individual component will be established, if this total leakage rate limit is exceeded then an evaluation will be performed to determine if design service water flow is available to affected components. Inadequate service water supply will cause the associated service water lines and equipment to be declared inoperable and appropriate action will be taken according to Technical Specifications.
The temporary non code repair will be to leave the welds as they are found, subject to monitoring and meeting the criteria for consequences and for structural integrity as described above.
Evaluation Flaw Detection During Plant Ooeration and imoracticality Determination The Service Water System is a common system for both Units at North Anna Power Station. Both trains are ' required to be operational or the appropriate Technical Specification action statement be entered. The through-wall flaws on Service Water lines in service are anticipated based on the North Anna Power Station history of MIC. Virginia Electric and Power Company requests to evaluate the flaws and leave acceptable through-wall flaws in service in order to RelielRequest NDE 32 Rev.2 Page4 of 7
perform Code repairs in controlled conditions during scheduled service water outages.
Roo! Cause Determination and Flaw Characterization The Service Water System at North Anna Power Station has previously expoilenced MIC. Radiograph examinations of service water welds having evidence of through wall leakage revealed small voids surrounded by exfoliation, which is typical of MIC. No other type of inservice defects were identified by the radiographs near the areas with through wall leaks. Additionally, a visual examination performed by a Virginia Electric and Power Company staff metallurgist of a sample of piping segments removed to repair the leaking welds confirmed the presence of MIC.
l l Butt welds identified with through wall leakage and accessible for radiography will be radiographed and evaluated for structural integrity within 14 days of discovery.
Through-wall flaws that cannot be characterized by radiography, socket welds and inaccessible butt welds, will be characterized as a 3/4" hole for cach area of leakage.
Flaw Evaluation Flaw evaluation for welds with through-wall leakage will be performed as described in Attachment 1. The flaws in butt welds that can be characterized by radiography will be evaluated by three types of analyses, area reinforcement, limit load analyses, and fracture mechanics u;ing the guidance from NRC Generic Letter 90-05. The flaws in welds that cannot be characterized by radiography, i.e. socket welds and inaccessible butt welds, will be evaluated by the same analysis by assuming a 3/4" hole for each point of leakage within a weld with through wall leakage. Socket welds will be analyzed by treating the cross section at the socket weld as equivalent pipe cross section.
IV. AUGMENTED INSPECTION An augmented inspection program will monitor a sample of butt welds in the Service Water System using radiography. Radiography will be performed overy three (3) months. The frequency of radiography will be assessed after a year and may be adjusted for each location based on the results of the radiographs.
Relief Request NDE-32 Rev.2 Page 5of 7
V. ALTERNATE PROVISIONS As an attemative to performing Code repairs in accordance with IWA 5250(a)(2) to through wall flaws in the Service Water System the through-wall flaws will be left as is. The through wall flaws will be monitored for leakage and must meet the critoria for flooding and spraying consequences and for structuralintegrity as described to remain in service. Operation in this mode will continue until the subject welds are replaced. All welds identified with through-wall flaws will be replaced within 18 months from the time of discovery.
The structural integrity of the Service Water System will be monitored by the following methods until the repairs required by IWA 5250(a)(2) are completed.
Weekly visual monitoring of through-wall flaws from the time of identification until completion of structural integrity analysis. If the welds l
are determined to be structurally acceptable then the visual monitoring 1
frequency will be decreased to once every six weeks.
All welds identified as having a through wall flaw will be assessed for structural integrity within 14 days of detection. Butt welds will be radiographed, if accessible, to characterize the flaws. Socket welds and t
butt welds inaccessible to radiography will be assessed for structural integrity by assuming a conservative large hole. Wolds determined to be
! structurally adequate will be included in the above monitoring program.
! Identification of a structurally inadequate weld will result in the assoc,ated piping to be declared inoperable and the appropriate Technical Specification action statement to be taken.
4 Weekly visual monitoring of through wall flaws in socket welds and butt welds inaccessible to radiography for a period of two (2) months. If there is no significant change in the leakage rate the monitoring frequency will be decreased to once every six weeks until the welds are repaired.
A significant change is defined as a 0.5 gpm increase in the leakage rate from the initial observed leakage condition for each weld. Should any location reach the threshold of a significant change, the weld will be reassessed for structuralintegrity and flood / spraying consequences.
I A walkdown of the accessible stainless steel portions of the Service Water System will be performed every six weeks. This inspection frequency qas chosen to coincide with the existing 12 week Maintenance Rule schedule for Charging Pumps in order to limit the time equipment is out of service for testing and maintenance consistent with the intent of the Maintenance Rule. Two one week windows, six weeks apart, are available within this schedule to perform service water repairs. Performing inspections within Relief Request NDE 32 Rev.2 Page 6of 7 9
4 .
e this schedule will allow repairs to be made in a timely manner and reduce the time safety related equipment is out of service. The frequency of the q walkdowns will be assessed after a year and maybe adjusted based on -
the results of the inspections.
A total leakage rate limit of 1.0 gpm for a single supply or retum line for an Individual component will be established. If this total leakage rate limit is exceeded then an evaluation will be performed to determine if design service water flow is available to affected components. Inadequate service water supply will cause the associated service water lines and equipment to be declared inoperable and appropriate action will be taken according in Technical Specifications.
. - An augmented inspection program will monitor a sample of butt welds in the Service Water System using radiography. Radiography will be performed every three (3) months. The frequency of radiography will be assassed after a year and may be adjusted for each location based on the results of the radiographs.
The proposed attemative stated above will ensure that the overall level of plant quality and safety will not be compromised.
l VI IMPLEMENTATION SCHEDULE This altemative to Code requirements will be followed upon receiving NRC approval for the remainder of the second ten year inspection intervals. The Unit 1 second ten-year inspection interval will end on December 24,1998 and the Unit 2 second ten year interval will end on December 14,2000.
Attachments:
- 1. Flaw Evaluation Methods and Results
- 2. Drawing /Line Number Designations
References:
- 3. Nuclear Regulatory Commission Generic Letter 90-05 "Guldance for Performing Temporary Non-Code Repair of ASME Code Class 1,2, and 3 Piping" Relief RequestNDE 32 Rev.2 Page7 of 7
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i ATTACHMENT 1 Flaw Evaluation Methods and Results introduction Butt welds identified as having possible through wall leaks will be radiographed, if l accessible. Flaws in butt welds that are inaccessible for radiography will be postulated l
as a 3/4" hole for each area identified with a through wall flaw. All butt welds will be analyzed for structural integrity by three methods, area reinforcement, limit load analysis, and linear elastic fracture mechanics evaluation.
Flaw size in socket welds identified as having possible through-wall leaks cannot be characterized by nondestructive examination. A conservatively large hole,3/4", will be postulated for each area identified with a through wall flaw. The postulated flaw will be analyzed for structural integrity by treating the cross section as equivalent to the cross section of the attached pipe.
Atea Reinforcement Analysis The area reinforcement analysis is used to determine if adequate reinforcing exists such that ductile tearing would not occur. The guidelines of ANSI B31.1 paragraph 104.3.(d) 2 (reference 1) are used to detrmine the Code required reinforcing area.
The actual reinforcing area is calculated and is checked against the required reinforcement area.
The Code required reinforcement t ma in square inches is defined as:
1.07(tm)(d1)
Where im is the code minimum wall, and d1 is the outside diameter The Code reinforcement area required is provided by the availablo material around the flaw in the reinforcing zone.
Limit Load Analysis The structural integrity of the piping in the degraded condition will be established by calculating the minimum margin of safety based upon a Limit Load Analysis. These methods are documented in EPRI. report NP 6301-D,(Ductile Fracture Haidbook)
(reference 2).
AIR = 4Af}'+ AfZ'+ T' Relief Request NDE-32 Rev.2 Page 1 of 3 Attachment 1 i
p The' limit load analysis of the postulated flawed sections will
- 3 pedermed with a material flow stress representing the midpoint of the ultimate stre :gth and yield point stress. The flawed sections will be subjected to deadweight, thermal, and seismic DBE loading.
The allowable limit load is given by, Ma = 2 of Rm2 t-(2cos(p)-sin (e)) in-lbf I
of = flow stress = 0.5 (Sy + Su) psi
- Sy = yield stress psi l
~
Su = ultimate stress psi Rm = mean radius of the pipe f
p , e , n elR!* P)+F 2 J o o j
- R,, e t Ri = intemal radius of the pipe' P = pressure psig
. F = axialload in Ibs t = pipe thickness = inches D = Cutside diameter inches e = half angle of the crack (radians) = crack lenalb 2Rm MR = Resultar^ Nat MY = Bending Mo,', ent
,_ MZ = Bending Moment T = Torsion The calculated factor of safety is, FS = .Mg (MR)
The minimum factor of safety of 1.4 is required to be qualified for continued operation.
Fracture Mechanics Evaluation A linear elastic fracture mechanics analysis will be pedormed for circumferential through-wall crack using the guidance provided in NRC Generic Letter 90-05. The Relief Request NDE-32 Rev.2 Page2 of 3 Attachment 1
'4 structural integrity of the piping in the degraded t.oadition was _ established by calculating the minimum margin of safety based upon a Fracture Mechanics evaluation.
This method is documented in EPRI report NP-6301-D (Ductile Fracture Handbook)
(reference 2).
A through-wall circumferential crack will be postulated for every area containing MIC.
- The cracks will be subjected to a design pressure loading in addition to the deadweight, normal operating thermal and seismic DBE loadings. For the purpose of this evaluation a generic allowable stress intensity factor of KIC = 135 ksiDin will be used for the stainless steel material per NRC GL 90-05.
L The applied stress intensity factor for bending, KIB, is found by:
l KlB = [ab-(n Rm 0)0.5) Fb The applied stress intensity factor for intemal pressure, KIP, is found by:
KIP = am-(n Rm 0)0.5 Fm The applied stress intensity factor for axial tension, KIT is found by:
KIT = ct.(n Rm 0)0.5 Ft
{
The stress intensity factor for residual stresses, K'R is found by:
KIR = S-(n Rm 0)0.5 Ft Total applied stress intensity KT includes a 1.4 safety factor and is calculated by:
KT = 1.4-(KlB + KIP + KIT) + KIR The allowable stress intensity factor is taken from Generic Letter 90-05.
KALL = 135 ksirin Stress Intensity Factor Ratio is defined as:
SR = KI KALL The stress. intensity factor ratio shall be less than 1.0 for continued operation.
Relief Request NDE-32 Rev.2 Page3 of 3 Attachment 1 -
ATTACHMENT 2 List of drawings containing the Service Water System and the associated line number designations for pipe class 153A and 163.
DRAWING 11715-CBB-040D-2, SHEET 1 1-1/4*-WS-G37-153A-Q3 4" WS-G01-163-Q3 3/4*-WS-F83-163 4" WS-F99-163-03 3/4"-WS-F82163-03 DRAWING 11715-CBB-040D-2, SHEET 2 1-1/4"-WS-H78-153A-03 1-1/4"-WS-H81-153A-Q3 DRAWING 11715-CBM-078A-2, SHEET 1 l 3/4"-WS-G31 163-Q3 3/4"-WS-F67-163-03 3/4"-WS-H77-163-03 4"-WS-F64-163-03 4"-WS-H76-163-03 3/4"-WS-F80-163-03 3/4"-WS-G30-163-03 3/4" WS F68-163-03 3/4"-WS-339-163-03 4"-WS-F65-163-Q3 3/4"-WS G36-163-03 3/4"-WS F69163-Q3 3/4"-WS-930-163-Q3 8"-WS- 93-163-03 1/2" WS-F61-163-03 8"-WS- 94-163-03 2"-WS D72-163-03 4"-WS-F62-163-03 3/4"-WS F78-163-03 3/4"-WS-F66-163-03 4"-WS-F63-163-03 3/4"-WS-F79-163-03 DRAWING 11715-CBM-078A 2, SHEET 4 8" WS-515-163-03 8"-WS-516-163-Q3 8"-WS 513-163-03 8"-WS-514-163-03 4"-WS-H48-163-03 3/4"-WS-F64-163-03 3/4"-WS-H52-163-03 3/4"-WS-H53-163-Q3 4"-WS-H50-163-03 3/4"-WS-H66-163-03 3/4" WS-H54-163-Q3 4"-WS H51-163-Q3 3/4*-WS-H67-163-Q3 3/4"-WS H55-163-03 3/4"-WS-G32-163-03 3/4"-WS-G33-163-Q3 8"-WS-115-163-03 8"-WS 116-163-03 8"-WS-113-163-03 4"-WS- 46-163-03 4"-WS- 47-163-03 2"-WS 926-163-03 3/4"-WS H60-163-03 3/4"-WS-H61-163-Q3 3/4" WS-H62-163-03 3/4"-WS-H63-163-03 4"-WS- 56-163-03 4"-WS- 57-163-03 8"-WS-114-163-03
- . 4
- DRAWING 11715-CBM-0788-2, SHEET 1 -
1-1/2"-WS-346-163-03 1"-WS-347-163-03 1" WS-G06-163-03 1-1/2"_ WS-347163-03 1-1/2*-WS 348-163-03 1"-WS-349-163-03 1"-WS-G05-163-03 1 1/2"-WS 349-163-03 1 1/2"-WS-350-163 1"-WS-351-163-Q3
~ 1"-WS-G04-163-03 1-1/2"-WS-351-163-03 1-1/2"-WS-352163-03 1" WS-353-163-03 1"-WS-G03-163-03 1-1/2"-WS 353-163-03 3/4"-WS-347-163-03 3/4"-WS-349-163-Q3 3/4"-WS-351-163-03 3/4"-WS-353163-03 DRAWING 11715-CBM-078B-2, SHEET 3
- 1 1/2" WS-724-163-03 1"-WS 725-163-03 1"-WS-933-163-03 1-1/2"-WS-725-163-03 1-1/2"-WS-726-163-03 1"-WS-727-163-03 1"-WS-934-163-03 1-1/2*-WS-728-163-03 1"-WS-729-163-03 1"-WS-935163-03 1 1/2" WS-729-163-03 1-1/2"-WS-730-163-03 1"-WS 731-165-03 1"-WS-936-163-03
' 1 1/2"-WS-731-163-03 1-1/2"-WS-727-163-03 3/4"-WS-725-163 03 3/4"-WS-725-163-03 !
3/4"-WS-729-163-03 3/4"-WS-731-163-03 DRAWING 11715-CBM-078C-2, SHEET 2 !
4"-WS- 46-163-03 1"-WS 85-163-03 3/4"-WS-A47-163-03 1"-WS-485-163-03
- 1"-WS- 81-163-03 1"-WS-487-163-03 1"-WS- 77 163-03 1"-WS-489-163-03 1"-WS-477-163-03 1"-WS-491-163-03 1"-WS-481-163-03 3"-WS- 75-163-03 3"-WS- 73-163-03 3'-WS- 76 163 4"-WS- 47-163-03 3/4"-WS- 79-163-03 3/4"-WS-A49-163-03 3/4"-WS-381-163-03 1"-WS- 82-163 03 2"-WS- 80-163-03
- 1"-WS- 78-163-03 34'-WS- 83-163-03 1"-WS-478-163-O3 3/8"-WS-383-163-03
' 1"-WS-482-163-03 3/8*-WS-382-163-O3 i
' 3"-WS- 74-163-Q3 2"-WS-376-163-Q3
- 4"-WS- 56-163-03 3/8"-WS-397-163-O3 3/4"-WS-A48-163-Q3 3/8"-WS-398-163-03 '
11715-CBM-078C-2, SHEET 2 (Cont'd) j
.7 - ..
117i5-CBM 0780-2, SHEET 2 (Cont'd) 1" WS- 90-163-03 2*-WS-377163-03 !
3/4"-WS-C06163-03 3/8" WS-C01-163-03 1"-WS- 92 163-03 3/8"-WS-399-163-03 1"-WS- 86-163-03 3/4"-WS-378-163-03 3/4"-WS-C01 163-03 2"-WS- 84-163-03 1"-WS-488-163-Q3 3/4"-WS 379-163-Q3
. 3/4"-WS-913-163-03 1"-WS- 88 163-03 1"-WS-490-t 63-03 3/4"-WS-380-163-Q3 1"-WS- 78 163-03 3/4" WS- 83-163-Q3 1" WS-478-163-Q3 3/8"-WS-383-163-03 1" WS 492-163-03 3/4"-WS-A50-163-03 4" WS- 57-163-03 1"-WS 89-163-Q3 3/4"-WS-773-163-03 3/4"-WS-400-163 03 2*-WS-772-163-03 3/4"-WS-774-163-03 3/8"-WS-910-163-Q3 2"-WS-775-163-03 3/8"-WS-914163-03 3/8"-WS-913-163-Q3 2"-WS-776-163-03 3/8"-WS-915-163-03 3/8" WS-916-163-Q3 3/4"-WS-779-163-03 2"-WS-777-163-03 3/4"-WS 909-163-Q3 1"-WS 486-163-03 3/8"-WS-912-163-Q3 DRAWING 11715-CBM-078G-2, SHEET 1 '
2" WS-D46-153A-Q3 - 2"-WS-C88-153A 1"-WS-D50-153A-03 2"-WS-C81-153A-Q3 3/4"-WS-D39-153A-Q3 2"-WS-C87-153A-Q3 1"-WS-D30-153A-03 2"-WS- 63-163-03 3/4"-WS-D41-153A-03 3/4"-WS D61-163-03 3/4"-WS-D55-163-03 2"-WS- 62 163-Q3 1"-WS-D31-153A-Q3 2"-WC-C80-153A-Q3
> 3/4"-WS-043-153A 03 3/4"-WS-C67-153A ' 3" WS- 73-163-03 3/4"-WS-C73-153A-03 2"-WS- 54-163-Q3 3/4"-WS-C76-153A-03 2" WS- 52-163-Q3 3/4"-WS-C70-153A-Q3 3/4"-WS-D67-163-03 2"-WS-C86-153A O3 2"-WS- 50-163-03 2"-WS- 79-153A-Q3 3'-WS- 74-163-Q3 2"-WS-C85-153A-03 2"-WS- 55-163 3/4"-WS-D62-163-03 3/4"-WS-D54-163-03 2"-WS- 60-163-03 2"-WS- 53-163 3"-WS- 75-163-03 3/4"-WS-D68-163 3/4"-WS-D69-163-03 2" WS- 51-163-Q3 2"-WS- 61-163-03 11715-CBM-078G-2, SHEET 1 (Cont'd)
e 9
11715-CBM-078G 2, SHEET 1 (Cont'd) 3/4'-WS-D56-163-03 3/4"-WS D701E3-Q3 2"-WS C83153A-Q3 3"-WS- 76-163 53 2"-WS-C89-153A 03 2"-WS-C78-153A-03 3/4" WS-D60-163-03 3/4"-WS C66153A-03 2"-WS- 64-163 03 3/4"-WS-C72153A 03 2" WS- 65-163-03 3/4" WS-C75-153A 03 2"-WS-C82-153A-03 3/4"-WS-C69-153A-03 3/4"-WS-C68153A 03 2"-WS-C84153A-Q3 3/4"-WS-C74 153A-03 3/4" WS-C77153A-03 3/4"-WS-C71 153A-03 DRAWING 11715-CBM-078G-2, SHEET 2 2* WS-D46-153A-03 3/4"-WS D65-163-03 3/4"-WS D71-153A-03 3/4"-WS-D66-163-03 1"-WS-D47-153A-03 3/4"-WS 934-153A-03 3/4"-WS-D33-153A-03 2"-WS-948-153A-03 3/4"-WS-D51 163-Q3 3/4"-WS-940153A-Q3 1" WS-D48-153A-03 1-1/2"-WS 976-153A-Q3 3/4"-WS-D35-153A-Q3 1-1/2"-WS-982-153A-Q3 3/4"-WS-D52-163-03 3/4"-WS-943-153A-03 1"-WS-D49-153A-03 3/4"-WS-937153A-Q3 3/4"-WS-D37-153A-03 2"-WS-954-153A-03 3/4"-WS-D53-163-03 2"-WS-947-153A-O3 3"-WS- 73-163-03 1-1/2"-WS-977-153A-O3 3/4"-WS-D63-163-Q3 1 1/2"-WS-963-153A-Q3 3"-WS- 74-163 03 2"-WS-953-153A-03 2"-WS-454-163-03 3/4"-WS-D58163-Q3 2"-WS-455-163-Q3 2"-WS-462 163-03 2"-WS-452-163-Q3 2" WS-463 163-Q3 2"-WS-453-163-03 2" WS-946-153A-03 2"-WS-450-163-Q3 1-1/2"-WS-979-153A 03 2"-WS-451-163-03 1-1/2"-WS-978 153A-O3 2"-WS 949-153A-03 2"-WS-952-153A-03 1-1/2" WS-981-153A-03 2"-WS-945153A-03 1-1/2"-WS-965-153A-Q3 1-1/2"-WS-980-153A-03 2"-WS-955-153A-Q3 1-1/2"-WS-961-153A-Q3 3/4"-WS-D57-163-Q3 2"-WS-460-163-Q3 2"-WS-464-163-03 2"-WS-945-153A-03 2"-WS-465-163-Q3 2"-WS-944-153A-03 3"-WS- 75-163-03 1-1/2"-WS-975-153A 03 3"-WS- 76-163-03 1-1/2"-WS-971-153A-03 3/4"-WS-D59-163-03 2"-WS-950-153A-Q3 2"-WS-461-163-03
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