ML19209C194
| ML19209C194 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 07/30/1979 |
| From: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| NUDOCS 7910120181 | |
| Download: ML19209C194 (25) | |
Text
,g'
[b j
SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 s Street, Box 15830, sacramento, California 95813; (916) 452-3211 July 30,1979 h
f? '
- /h '3\\
Nuclear Regulatory Commission ei - f yp,3 'GT Attention. Mr. R. H. Engelken, Director N
t$b Q> i]
Region V Office of Inspection &
\\'% g {[ 6 XA Enforcement M
1990 North California Boulevard Walnut Creek Plaza, Suite 202
'Qlt g.
Walnut Creek, California 94596 Docket No. 50.312 Rancho Seco Nuclear Guierating Station, Unit No.1 I. E.Bulletin 79-14
Dear Mr. Engelken:
The District has received I. E.Bulletin 79-14 dated July 2, 1979 and has prepared a response to Phase 1.
The attached response addresses all items identified as required within 30 days.
The require-ments of Phases 2 and 3 will subsequently be satisfied by field and engineering verification.
Recognizing that the intent of the bulletin is to verify the validity of seismic analysis of the safety systems, the District feels that an in-depth review of the pertinent drawings, calculations, and other identified documents is appropriate and will be accomplished in a timely manner.
It may not be necessary to shut down the operating unit to do physical measurements and visual checks, in light of the many extensive earlier verifications and existing "as built" drawings.
The District is confident that a review and verification of consistency between design / analysis packages and "as built" documents is a viable alternative to shutting down to examine inaccessible areas.
Upon completion of the document review and verification, a physical inspection of accessible piping and supports will form the basis for acceptance of the inaccessible piping systems. Additional physical checks could also be made in January or February during the scheduled refueling outage.
Should you have any questions please contact Larry Smith at (916) 452-3211.
Sincerely yours, b[
9>t<-
John J. Mattimoe Assistant General Manager and Chief Engineer i
}
}g4 4
7910120 7'743 titcreic mr >
r, t re i n ner on c a c.c a c in int n u.1 oe cuiron.u
r PHASE I RESPONSE TO NRC BULLETIN I.E. 79-14
~
The identification of design and constructed plant system documents in compliance with Phase 1 of I.E.Bulletin 79-14 is contained herein.
These documents and plant physical examinations will be utilized to demonstrate the adequacy and validity of the seismic analysis.
Attachment A lists sources of input information for the seismic analysis of safety-related piping. This attachment identifies the safety-related lines of concern and the specific design documents used for the analyses.
Attachment B shows lines to be inspected per Item 2 of I. E.Bulletin 79-14.
This attachment indicates the system names and line numbers of those safety-related lines which are normally accessible and represent one system in each set of redundant systems.
Attachment C shows lines to be inspected per Item 3 of I.E.Bulletin 79-14.
This attachment indicates the system names and line numbers of all other normally accessible safety-related systems and all normally inaccessible safety-related systems.
Elements to be utilized as part of the field inspection program will con-sist of as-built isometrics and pipe support detail drawings.
For each line inspected, routing will be checked against the isometric, supports and components will be located and marked on the isometric (supports being checked against support detail drawings). The marked up isometric, appli-cable available valve and component vendor documents (certified design drawings, quality documents included with shipments, etc.) will then be evaluated against the seismic analysis to determine any nonconformance.
}
2b
Sheet 1 of 17 Attachment A Sources of Input Information for Seismic Analysis of Safety Related Systems Document Information 1.
"Line Designation List Dwg. No. M-853" Pipe Diameter Pipe wall schedule or thickness Thermal insulation thickness Temoerature 2.
" Specifications for Piping Design Pipe Material No. M-870" 3.
" Design Earthquake Horizontal and Plot of acceleration response Vertical Acceleration Response versus the natural period Spectrum" of the system 4.
"P&I Diagram" Pipe class change Jocation 5.
" Piping Drawings" Source for development of
" Stress Isometrics" which show t'he geometry of the line.
1 ?86 4
\\
/
~
~
~
ATTACHMENT A s
Sol"tCES OF INPUI INFORMATION FOR SEISMIC ANALYSIS OF SAFETY-REI.ATED SYSTEMS otes 2,3 System Limits Line Nos.
Stress Prob Design Documents Note 1, BNote 1, CN l' I AuxilaryBldg.Elev.O',-g"1 High Pressure 7250 to P238B 23801-6"-HD 9
A Injection to Penet. 22 & 23 23628-6"-CD 9
No. SK-6292-S-85-Rev. 0 7/13/70 1/2% damping. D 23802-6"-CD 9
Auxiliary Bldg Elev. O'-0" No. SK-6292-S-86 Rev. 0 7/13/70 3
23522-6"-CD 9
1/2% damping. P&1 Dingram " Decay Heat Removal System" 23629-6"-CD 9
M-522 and " Makeup and Purification 23572-4"-CD 9
System" M-521. Stress iso.
" Prob. #9 Area 3 "hetions V235 to P236, T250 to P238B,
& Bypasses" Rev. 2 4/5/71 23822-4"-CA 8
A
,BNote 1 CNote 1 AuxiliaryBldg.elev.g';0"g 23822-2-\\"-CA 8
No. SK-6292-S-85 Rev. 0 7/13/70 1/2% damping. D 23627-4"-CA 8
Auxiliary Bldg. Elev. O'-0" No. SK-6292-S-86 Rev. 0 7/13/70 23620-4"-CA 8
1/2% damping. P&I Diagrams, "Deay Heat Removal System" M-522 and " Makeup and Purification System" M-521.
Stress Iso. " Prob. #8 Area 3 - H.P. Injection Pump P238B and Hakeup Pump P236 Discharge to V200" Rev. 3 10/15/72 23822-25"-CA 106 A *
- I, BNote 1 Note 1 C
Auxiliary Bldg. Elev. ggg"g 23823-24" A 106 No. SK-6292-S-85 Rev. 0 7/13/70 1/2% damping. D Auxiliary Bldg. Elev. O'-0" No. SK-6292-S-86 Rev. 0 7/13/70 1/2% daning. P&I Diagrams " Decay Heat Removal System" M-522 ano " Makeup and Purification System" M-521.
Stress Iso. " Calc. No. 106 Area 4 - HP Injection Pump P238B to Reactor hssel" Rev.16/6/73 8r+
T-250 to P238A to 23800-6"-HD 81 A te 1, BNote 1 Note 1 N
C AuxiliaryBldgElev.Ogg"y Penet. 20 & 21 23803-6"-GD 81 No. SK-6292-S-85 Rev. 0 7/13/70 1/2% damping. D o
23629-6"-GD 81 Auxiliary Bldg. Elev. O'-0" No. SK-6292-S-86 Rev. 0 7/13/70
~
1/2% damping. P&I diagram " Decay Heat Removal System" M522 N
and " Makeup and Purification System," M-521. Stress Iso.
" Makeup and Purification System" dated 11/2/72 N
?n
I o es 2,3 System Limits Line Nos.
Stress Prob fjesign Documents Note 1, gNote 1 Note 1 C
AuxiliaryBldg.Elev.Q;0"3 23629-6"-CD 2B A
26024-4"-GD 2B No. SK-6292-S-85 Rev. 0 7/13/70 1/2% damping. D Auxiliary Bldg. Elev. O'-0" No. SK-6292-S-86 Rev. 0 7/13/70 1/2% damping. P&1 diattams " Decay Heat Removal System" M522 and " Makeup ar.d Purification System" M521. Stress Iso
" Prob. 2B Area 4 Decay I! cat Removal System Outside R.D."
Rev. 2 12/2/71 Note 1 Reactor Bldg. Conta'inment Structura 23626-4"-CA 1A ANote 1, BNote 1, C Elev. 16'-0" No. SK-6292-S-65 Rev. 0 7/13/70 1/2% damping (vertical accel. =.75 x horiz. accel.). P&I diagram " Makeup and Purification Systen" M-521. Stress. Iso. " Prob.
lA Area 4 Makeup and Purification System" dated 2/3/72 2 pages.
23626-4"-CA 83 A
,BN te 1, C
, Reactor Bldg. Interior Structure 23626-2\\"-CA 83 Elev. l'-6" No. SK-6292-S-77 Rev. 1 7/13/70 1/2% damping 23633-2h"-CA 83 (vertical accel. =.75 x horiz. accel). P&I Diagram " Makeup and Purification Systen" H-521. Stress Iso. " Prob.
83 Area 5&4 23626-4"-CA, 23820-4"-CA, 23633-3"-CA" dated 7/21/71 Inside Containment 23822-2 "-CA 43 ANote 1, BNote 1, CNote 1 Reactor Bldg. Interior Structure Elev. 40'-0" No. SK-6292-S-81 Rev. 1 7/13/70 1/2% damping and 23824-2)"-CA Elev. I'-6" No. SK-6292-S-77 Rev. 1 7/13/70 1/2% damping v3 (vertical accel. =.75 x horiz. accel). P&I diagram " Makeup j[
and Purification System" M-521.P&I Diag " Reactor ny r*
Coolant System" M-520. Stress 1so.
"HP Injection Pump Discharge to Reactor Vessel V-200" Rev. 1 6/29/71 to o
a N
M V 3 C3
)
C'C) 9-
'8 System Limite_
Line Nos.
Stress Prob Design Documents te 1 21503-2)"-CA 60A, B, C A te 1, B te 1, C Reactor Pldg. Interior Structure Elev. 40'-0" No. SK-6292-S-81 Rev. 1 7/13/70 1/2% damping (vertical accel. =.7.', x horiz. accel). P&I Diagram " Makeup and Purification Systen" M-521.
Stress Iso. " Prob.
f60A, B, C Area #1, Pressurizer Spray Line Stress Analysis" Rev. 2 9/12//2 23823-2%"-CA 42 ANote 1, B te 1, C
- I Reactor Bldg. Interior Structure 23825-2\\"-CA Elev. 40'-0" No. SK-6292-S-81 Rev. 1 7/13/70 1/2% damping and Elev l'-6" No. SK-6292-5-77 Rev. 1 7/13/70 1/2% damping (vertical accel. =.75 y horiz. accel). P&I Diagram " Makeup and Purification Systein" M-521. P&I Diagram
" Reactor Coolant System" M520. Stress' Iso. "23825-2\\-CA, HP Injection Pump Discharge to Reactor Vessel" Rev. 3 11/12/71 23626-2)-CA 57 A te 1, B l' 1, CNot e 1 Reactor Bldg. Interior Structure 20003-25-CA Elev. 40'-0" No. SK-6292-S-81 Rev. 1 7/13/70 1/2% damping and Elev. I'-6" Fo. SK-6292-S-77 Rev. 1 7/13/70 1/2% damping (vertical accel. =.75 x horiz. accel.) P&1 Diagram " Makeup and furification System" M-521.
P&I Diagram
" Reactor Coolant Syst e m" M-520.
Stress Iso. "#57 Area 1 High Pressure injection Line R. B. Pen. #20 to RV200" Rev 3 3/28/72 23620-2h"-CA 56 A
,BNote 1, C "t' Reactor Bldg Interior Structure on N te 1 Elev. 1-6" No. SK-6292-5-77 Rev. 1 7/13/70 1/2% damping
@[
20004-2 "-CA and Elev. 40'-0" No. SK-6292-S-81 Rev. 1 7/13/70 1/2% damping n) c' (vertical accel. =.75 x horiz. accel.)
P&ID Diagram " Makeup and Purification System" M-521. P&I Diagram " Reactor 4s Coolant System" M-520.
Stress Iso " Prob. #56 Area #1 c3 High Pressure Injection Line" a
~N A
i I
C73 s c) m f
d
'k
tes 2,3 System Limits I.ine Nos.
Stress Prob Design Documents Decay Heat T250 & Penet 31 25021-16"-HD 14 AN te 1, BN te 1, CNot e 1 Reactor Bldg Containment Removal System to P261-B &
26101-18"-GD 14 Structure Elev. 16'-0" No. SK-6292-S-65 Rev. 0 7/13/70 P291-B to 26101-12"-GD 14 1/2% damping (vertical =.75 x horiz. accel) P&I Penet. 27 29101-10"-CD 14 Diagram " Decay Heat Penoval System" M-522. Stress Isos. " Prob. 14A Areau 3, 4, & 5 RBS 3 rain and Decay Heat Removal System" Iev. 6 1/4/72 4 pages. P&I Diagram " Reactor Bldg. Spray System" M-524.
- 1, B
,C'
,AuxiliaryBldg.Elevy'-g",
26121-18"-CD 13 A
damping, D 26121-10"-GD 13 No. SK-6292-5-85 Rev. 0 7/13/70 1/2%
Auxiliary Bldg. Elev. O'-0" No. SK-6292-S-86 Rev. 0 7/13/70 1/2% damping. PT.1 Diagram " Decay Heat Removal System" M-522 Stress Iso. " Prob. 13 26121-10"-GD and 26121-18"-GD" dated 2-L1-71 26123-6"-CD 119 A
,BNote 1, Statle Seismic analysis 5/10/74, P&I Diagram " Decay Heat Removal System'.'
Stress Iso.
" Area 4, Decay Heat Ennoval Bypass from Pump P-261B to Reactor Vessel V200" dated 4/23/74 26021-10"-CD 2A ANote 1, BNote 1, CNote 1 Reactor Bldg Containment Structure 26021-10"-CA 2A Elev. (-)11'-0" No. SK-6292-S-63 Rev. 0 7/13/70 1/2% damping 26030-8"-CD 2A (vertical accel. =.75 x horiz, accel). Pfil Diagram " Decay 26022-8"-CD 2A Heat Removal System" M-522.
Stress Iso. " Prob. 2A Area 4.
Decay Heat Removal System Outside R. B."
Rev. 2 12/2/71 Sp co*c+
tn 26032-4"-CD 2D A
,BNote 1, CNote 1 Auxiliary Bldg. Elev. Q "y No. SK-6292-S-85 Rev. 0 7/13/70 1/2% damping. D w
N Auxiliary Bldg. Elev. O'-0" No SK-6292-S-86 Rev. 0 7/13/70 1/2% damping. P&I Diagram " Decay Heat Removal System" M-522
~
Stress Iso. " Prob. 2D Area 4 Decay Heat Removal System Outside R. B." Rev. I 1/4/71 s
y' b
1 I
C3 i
V
Notes 2,3 System Limits Line Nos.
Stress Prob Design Documents Note 1, BNote 1 Not e 1 C
Reactor Bldg. Containment Structure T-250 & Penet 30 26100-18"-CD 14 A
to P-261-A &
29100-10"-GD 14 Elev. 16'-0" No. SK-6292-S-65 Rev. 0 7/13/70 1/2% damping P-291-A to 26100-21"-CD 14 (vertical accel =.75 x horiz. accel). P&1 Diagram " Decay Penet. 28 25020-16"-HD 14 Heat Removal System"11-522. Stress Iso. " Prob. 14A Areas 3, 4 & 5 RBS Drain and Decay Heat Removal System" Pg i of 4 Rev. 6 1/4/72. P&lD Diagram " Reactor Bldg. Spray System" H-524.
Note 1, B
,C Auxiliary Bldg. Elev. Og-g" g 26120-10"-CD 12 A
26120-18"-GD 12 No. SK-6292-S-85 Rev. 0 7/13/70 1/2% damping. D Auxiliary Bldg. Elev. O'-0" No. SK-6292-S-86 Rev. 0 7/13/70 1/2% damping. P&I Diagram " Decay Heat Removal System" M-522.
Stress Iso. "I' rob.12 Line 26120-10-GD and 26120-18-GD" dated 8/4/71 26024-4"-GD 2B ANote 1, BNote 1,gNot e 1 Aux 1'ary Bldg. Elev. Oy-g" g No. SK-6292-S-b3 tev. 0 7/13/70 1/2% damping. D Auxiliary Bldg. Elev. D'-0" No. SK-6292-S-86 Rev. O J/13/70 1/2% damping. P&1 Diagram " Decay Heat Removal System" M-522.
Stress Iso. " Prob. 2B Area 4 Decay Heat Removal System Outside R. B." Rev. 2 12/2/71 N te 1, BNote 1 C
Reactor Bldg. Interior Structure 26020-10-CD 3A A
Elev. I'-6" No. SK-6292-S-77 Rev. 1 7/13/70 1/2% damping (vertical accel. =.75 x horiz. accel). P&I diagram " Decay Heat Removal System" H-522. Stess Iso. Problem 3A v3 Area 4 Decay Heat Removal Cooler E260A to V200" dated j[
2/23/71.
n>r+
Ch O
{
W
}
a f
s
' -i
otes 2,3 System Limits Line Nos.
Goress Prob Design Documents Inside 26021-10"-CA 31 A
,B te 1,C te 1 Reactor Bldg Interior Structure Containment 26529-10"-CA Elev. l'-6" No. SK-6292-S-77 Rev. 1 7/13/70 1/2% damping 26528-14"-CA (vertical accel. =.75 x horiz. accel. PSI Diagram " Decay 26521-14"-CA Heat Removal System" M 522. Stress Iso. " East Decay Heat System" Res. 1 5/3/74 Note 1 Note 1 Note 1 26020-10"-CA 33 A
B C
Reactor Bldg Interior Structure 26524-14"-CA Elev. l'-6" No. SK-6292-5-77 Rev. 1 7/13/70 1/2% damping 26520-14"-ED (vertical accel. =.75 x horiz. accel) P&I Diagram " Decay l{ cat Removal System" M-522.
Stress Iso. " Prob 33 West Decay Heat Systes." Rev. D 4/28/74
1
- 1, B
' I, C Reactor Bldg. Containment Structure Reactor Building P2918 to 29123-8"-GD 10 A
Spray System Penet. 26 29123-8"-HD Elev. (-)11'-0" No. SK-6292-S-63 Rev. 0 7/13/70 1/2% damping 29193-6"-GD (vertical accel. =.75 x horiz. accel.) P&I Diagram " Reactor Bldg Spray System" M-524.
Stress Iso. " Prob. 10 Area 4 - 29123-8-GD & 29199-6"-HD & CD" dated 9/14/71 P291A to 29120-8"-GD 15 ANote 1, BNote 1, C
'"1 Reactor Bldg. Containment Structure Penet. 25 29198-6"-CD Elev. (-)11'-0" No. S1:-6292-S-O Rev. 0 7/13/70 1/21 damping 29120-8"- HD (vertical accel =.75 x horiz. accel.). P&1 Diagram " Reactor Bldg Spray System" M-524 Stress Iso. " Prob. 15 Area 4 Line 29120-8"-GD" Rev. 3 7/25/72 rp r
CD Inside 29123-8"-HD 51 A ** 1, BNote 1, CNote 1 r+
Reactor Bldg. Containment Structure Elev. 135'-0" No. SK-6' 2-S-73 Rev. 0 7/13/70 1/2% damping N
o Containment 29131-8"-HD and Reactor Bldg. Interior Structure Elev. 40'-0" o
No. SK-6292-S-81 Rev. 1 7/13/70 1/2% damping (vertical accel.
m
=.75 x horiz accel.) P&I Diagram " Reactor Bldg. Spray a
System" M-524. Stress Iso. " Prob. 51 Area #1 N
~
29131-8"-HD Spray Water Piping" Rev. I 1/4/72 M
b wO
}
N 4 ~>
otes 2,3 System Limits Line Nos.
Stress Prob p glan Documents 29131-6"-KD ANote 1, BN l' I, f te 1 assumed conservative 29131-4"-HD acceleration load. P&I diagram " Reactor Bldg. Spray System" M-524.
Piping l)<g. M-116.
29124-3"-10 52 ANote 1, 3 Note 1, CNote 1 Reactor Bldg. Interior Structure Elev. l'-6" No. SK-6292-S-77 Rev. 1 7/13/70 1/2% damping (vettical accel. =.75 m horir. accel.) P&ID Diagram
" Reactor Bldg. Spray Syntem" M-524. Stress Iso.
" Prob. 52 Area #129124-3-10 Spray Water Piping" Rev. 1 4/28/72 29123-6"-HD 26A ANote 1, BNote 1 Note 1 C
Reactor Bldg Interior Structure Elev. 40'-0" No. SK-6292-5-81 Rev.1 7/13/701/2% damping (vertical accel. =.75 x horiz. accel). P&I diagram
" Reactor Bldg Spray Syst em" M-524. Stress Iso. " Prob
- 26A 29125-6"-10) Spray Water at El. i0'-0" dated 6/28/71 Note 1, gNote 1 Note 1 C
Reactor Bldg. Interior Structure 29125-3"-HD 26B AElmv. 40'-0" No. SK-6292-S-81 Rev. 1 7/13/70 1/2% damping (vertical accel. =.75 horiz. accel). P&I Diagram " Reactor m
Bldg. Spraf "ystem" M-524.
Stress Iso. " Prob. 26B g
29125-3"-1m Spray Water at Elev. 40'-0"" Rev. I rp re 3/31/7" co o
29120-8"-HD 50 A te 1, 3 Note 1, CNote 1 Reactor Bldg Containment Structure 29130-8"-10 elev. 135'-0" No. SK-6292-S-73 Rev. 0 7/13/70 1/2% damping and Reactor Bldg. Interior Structure Elev. 40'-0" No. SK-6292-S-81 Rev. 1 7/13/70 1/2% damping (vertical accel. =.75 horiz.
N accel.) P&I Diagram "iteactor Bldg Spray System" M-524 w
Stress Iso " Problem #50 29130-8"-ilD Spray Water g
Piping" Rev. 1 9/21/71 1
otes 2,3 System Limits I.ine Nos.
Stress Prob Design Documents Note 1 Note 1 Note 1 29130-6"-IID A
B C
assumed conservative 29130-4"-llD acceleration load. Pl.I diag. " Reactor Bldg Spray System" M-524. Piping Dwg. M-116.
ote 1, b 't' I, C ot e 1 7-actor Bldg Interior Structure 29130-6"-HD 27 A
29122-6' HD Elev. 40'-0" No. SK-6792-1 Rev. 1 7/13/70 1/2% damping 29122-4"-HD (vertical accel. =.75 x riz. accel). P&1 Diagram
" Reactor Bldg Spray Sjat o M-524. Stress Iso.
" Prob. #27 29122-6"/4" ILL aray Water Piping" dated 6/24/71 Note 1, BNote 1, CNote 1 Reactor Bldg Interior Structure 29121-3"-HD 53 AElev. l'-6" No. SK-6292-S-77 Rev.1 7/13/70 1/2% damping (vertical accel. =.75 x horiz. accel). P&I Diagram " Reactor Bldg. Spray System" M-524. Stress Iso. " Prob #53, Area #1 29121-3"-HD S ray Water Piping" dated 10/6/70 t
Nuclear Service E480B to E260B &
48061-24"-lE 235 A
,B
- I, C AuxiliaryBldg.Elev.g'-0"1 Cooling Vater Penets. 7, 8, 11, 12 No. SK-6292-S-85 Rev. 0 7/13/70 1/2% damping. D Auxiliary Bldg. Elev. O'-0" No. SK-6292-S-86 Rev. 0 System 7/13/70 1/2% damping. P&I Diagram " Nuclear Service Cooling Water System" M-545.
Stress Iso. " Prob. #234
- 235-48060-18-lE Nuclear Service Cooling Water" dated w
7/1/74 g
?+
to O
48223-18"-lE 6
ANote 1, BNote 1, CNote 1 AuxiliaryBldg.elev.gg0"g 50056-10"-IE No. SK-6292-S-85 Rev. 0 7/13/70 1/2% damping. D N
50057-10"-HE Auxiliary Bldg. Elev. O'-0" No. SK-6292-S-86 Rev. 0 7/13/70 48223-12"-lE 1/2% damping. P&I Diagram " Nuclear Service Cooling Water System" M-545. Stress Iso. " Prob #6 Lines 48223-18-lE 50056-10-lE 50057-10-lE" Rev. 210/22/70 r)
.W-t,
Design Documents ' " ' #'#
System Limits Line Nos.
S_t ess Prob 26061-12"-HE 7
A te 1, BNote 1. CN 1 dampingD'f-g" Auxiliary Bldg. Elev 50066-10"-E No. SK-6292-S-85 Rev. 0 7/13/70 1/2%
50067-10"-E Auxiliary Bldg. Elev. O'-0" No. SK-6292-S-86 Rev. 0 7/13/70 26061-18"-E 1/2% damping. P&I Diagram "Nucicar Service Cooling Water System" M-545.
Stress Iso. " Prob. #7 Lines 26061-18-E 50Cf 6-10-E 50067-10-E" dated 10/26/70 48401-6"-1E 103 A te 1, BNote 1 Not e 1 C
Auxiliary Bldg. Elevg0'7 "
0 No. SK-6292-S-87 Rev. 0 7/13/70 1/2% damping D Auxiliary Bldg. Elev. 60'-0" No. SK-6292-S-88 Rev. 0 7/13/70 1/2% damping P&1 diag. " Nuclear Service Cooling Water System "M-545.
Stress Iso. " Prob. #103 Area 3&4 Line 48401-6-1E C. W. Surge Tank V484B to Mix Exchanger E-480B" dated 1/18/72 E480A to E260A &
48060-24"-E 234 ANote 1, B# ** 1 CNote 1 Auxiliary Bldg. Elev. go"y No. SK-6292-S-85 Rev. 0 7/13/70 1/2% damping. D Penets. 5, 6, 9, 10 Auxiliary Bldg. Elev.
O'-0" No. SK-6292-S-86 Rev. 0 7/13/70 1/2% damping. P&I Diagram " Nuclear Service Cooling Water System" M-545.
Strera Iso. " Prob. #234, 235 48060-18-E Nuclear !krvice Cooling Water" dated 7/1/74 48222-18"-E 3B A
t' I, BNote 1, CNote 1 Reactor Bldg. Interior structure Elev. I'-6" No. SK-6292-S-77 Rev. 1 7/13/70 1/2% damping (vertical accel =.75 x horiz accel). P&1 Diagram " Nuclear v3 7
Service Co~ ting Water System" H-545. Stress Iso.
" Prob. 33 Area 5, 7, & 8 Line 48222 Pump P-482A to Cooler E-260A" dated 4/13/71 ao O
-b Note 1
- I 48222-13"-E 3C A
e 1, 3
,C vesic Ground Spectra E g g'Basie
-0" damping. D do. SK-6292-S-59 Rev. 0 7 13/70 1/2%
48222-12"-E Ground Spectra Elev. O' 0" No. SK-6292-S-60 Rev. 0 7/13/70 50054-10"-E 50055-10"-E 1/2% damping. PSI Dia; ram " Nuclear Service Cooling Vater System" M-545. Stres. Iso. " Prob. 3C Area 4&5 Line 48222 - Pump P '.82-A to Cooler E-260-A" dated 3/24/71
~D 9,
LJ1
tes 2,3 System Limits Line Nos.
Stress Prob Design Documents 26060-12"-HE 4A A
BN te 1, CNote 1 Note 1 Reactor Bldg. Containment Structure 26060-18"-HE Elev. (-)11'-0" No. SK-6292-S-63 Rev. 0 7/13/70 1/2% damping 50064-10"-HE (vertical accel. =.75 s horiz. accel). P&I Diagram " Nuclear 50065-10"-HE Service Cooling Wster System" M-545. Stress Iso. " Prob. 4A Area 4T.i Decay H.R.C. E-260-A to Nuclear Ser. Cool. Unter H.E. E480-A" Rev. 3 3/29/73 ot e 1 26060-18"-HE 4B A
,B
,C Ares #7 Pipe Rack (see iso referenced below). P&I Diagram "tiuclear Service Cooling Water System" M-545.
Stress Iso. "Irob. 4B Area 5, 7, & 8 Cooler E260A to Exchar ger E480A" dated 11/17/71 Note 1 Note 1 4340*-6"-E 101 ANote 1, B C
Auxiliary Bldg Elev. -
1"1 No. SK-6292-S-87 Rev. 0 7/13/70 1/2% damping. t
~
Auxiliary Bldg. elev.
(,0'-0" No. SK-6292-5-88 Rev. 0 7/13/70 1/2% damping. P&I Diagram " Nuclear Service Cooling Water System" H-545.
Stres t: Iso. " Prob. #101 Area 5 Line 48400-6"-11E, Tant V-484-A to Exchanger E-480 A" dated 12/1/71 te 1 Inside Containment 50052-10"-RE 29 A
,B C
Reactor Bldg. Interior Structure Elev. 40'-0" No. SK-6N2-S-81 Rev.1 7/13/70 1/2% damping (vertical accel. =.75 x horiz accel). P&I Diagram
" Nuclear Service Cooling Water System" H545. Stress Iso. " Prob. #29 Area 1 50052-10"-HE from Exchanger E-480B" dated 7/31/70 eo et 50053-10"-RE 34 AN te 1, 3 Note 1, C '
- Reactor Bldg Interior Structure Elev.
j 40'-0" No. SK-6292-S-81 i'ev.1 7/13/10 1/21 damping (vertical O
accel. =.75 x horiz. accel.). P&I Diagram " Nuclear Service Cooling Water System" M-545. Stress Iso. " Prob G3*
Area 150053-10"-HE chromated Water Fr. E-480B" dated y
7/31/70 7'
so w
es 2,3 System Limits Line Nos.
Stress Prob pesign Documents Note 1, 3 Note 1, CNote 1 Reactor Bldg. Interior Structure 50062-10"-E 36 A
Elev. 60'-0" No. SK-6292-S-83 Rev. 1 7/13/70 1/2% dampir.g (vertical accel. =.75 m horiz. accel). P&1 Diagram " Nuclear Service Cooling Wter System" M-545.
Stress Iso.
" Prob. #36 Area 1 RBS l'mergency Cooling System -
Line 50062" Rev. 2 1/2n/72
' I, BNote 1 Note 1, Reactor Bldg. Interior Structure
,C 50063-10"HE 35 A
(Maximum earthquake) elev. 40'-0" No. SK-6292-S-82 Rev. 1 7/13/70 1/2% damping (vertical accel. =.75 horiz. accel.).
.&I Diagram " Nuclear Service Cooling Water System" M-545 Stress Iso. "#35 Area i 50063-10"-E to Cooling Water Pump P-482B" dated 7/31/70 50050-10"-HE 41 A
- I, B
' 1, C *" 1 Reactor Bldg. Inte.:!or Structure Elev. 40'-0" No. SK-6212.S-81 Rev. 1 7/13/70 1/2% damping (vertical accel. =.75 t horiz accel.) P&1 Diagram " Nuclear Service Cooling Water Syqtem" H-545. Stress Iso.
" Cool Water Pump P-482 to R. B. Emergency Cnol Unit A-500A" dited 10/30/73 50051-10"-E 39 A ** 1, B l' I, C Reactor Bldg Interior Structure
- l Elev. 15'-0" No. SK-6292 S-79 Rev. I 7/13/70 1/2% damping (vertical accel =.75 x horiz accel). P&I Diagram " Nuclear Service Cooling Water System" H-545. Stress Iso.
!:Q
" Emergency Nuclear Service Cooling Water Systems -
to Line 50051-10"-E" dated 1/10/73 (3 pages)
',D a
N
~+i 50060-10"-E 32A ANote 1, BNote 1, CNote 1 Reactor Bldg Interior Structure
[
Elev. 40'-0" No. SK-6292-S-81 Rev. 1 7/13/70 1/2% damping
~
(vertical accel. =.75 x boriz. accel.) P&1 Diagram " Nuclear Service Cooling Water System" H-545.
Stress 1 sos.
" Prob. 32A Area 1 Line 50050-10"-E R.B.E. Cool Unit A-500A to Heat Exrh. E-480A dated 9/1/70 (3 pages) 1 N
%9 N
s 2,3 System Limits Line Nos.
Stress Prob pesign Documents Note 1 Note L Reactor Bldg. Interior Structure N te 1, 3 C
50061-10"-!E 40 AElev. 40'-0" No. SK-629 bS-81 Rev. 1 7/13/70 1/2% damping (vertical accel. =.75 m horiz. acec1) P&I Diagram " Nuclear Service Cooling Water S/ item" M-545. Stress Iso.
" Prob. 40 Area 1 RBS En'rgency Cooling System Line 50061-10"-HE dated 7/15/71.
N te 1 Auxiliary T-358 to 31900-8"-HC 76 A
- 1, B te 1, C GroundSpectraElev.Og",y Feedwater Penet. 39 31920-6"-DB2 76 No. SK-6292-S-59 Rev. 0 7/13/70 1/2% damping'. D Ground Spectra Elev. O'-0" No. SK-6292-S-60 Rev. 0 7/13/70 System 1/2% damping. P&I Diapam "High Pressure Feedwater I! cater System" H-533.
Stress Iso. " Calc 76 High Pressure Feedwater lleater Systeni" dated 9/12/73'2 pages Note 1, B
,C conservative values in place of 31826-6"-DB2 92 AReector Bldg. Containma at Structure E1.16'-0" No. SK-6292-S-65 31821-6"-DB2 Rev. 0 7/13/70 1/2% dan. ping (vertical =.75 horizontal) P&I Diagram " Steam Generator System" M-532. Stress Iso.
" Problem 92 Area 5/7 Steam Generator System" dated 3/13/72 Note 1 Note 1 Basic Ground Spectra Eg g' Basic
-0" T-358 to 31800-8"-HC 76 ANote 1, 3 C
damping. D No. SK-6292-S-59 Rev. 0 7/13/70 1/2%
Penet. 38 31823-6"-DB2 Ground Spectra Elev. O'-0" No. SK-6292-5-60 Rev. 0 7/13/70 31891-6"-DB2 1/2% damping. P&I Diagram "High f ressure Feedwater IIcater us System" M-533. Stress Iso. "High Pressure Feedwater
[
Heater System" dated 9/12/73 2 pages co et a
w Note 1 31823-6"-DB2 80A ANote 1, BNote 1, C Reactor Bldg Containment Structure Elev. 16'-0" No. SK-6292-S-65 Rev. 0 7/13/70 1/2% damping 31820-6"-DB2 (vertical accel. =.75 x horiz. accel.) P&I Diagram " Steam Generator System" M-532. Stress Iso. " Aux.
Feedwater System" dated 6/11/73 t'J sO I,
CC A
Notes 2,3 System Limits Lise Nos.
Stress Prob pesign Documents Note 1, BNote 1, CNote 1 Inside 31821-6"-DB2 58 A
P&I Diagram " Steam Generator System" M-532.
Containment Stress Iso "#58 Auxitiary Feedwater to Steam Generator E-205-B" Rev. 1 5/15/11 Note 1 te 1 31820-6"-DB2 59 ANote 1, B C
Reactor Bldg Interior Structure Elev. 40'-0" No SK-6292-5-81 Rev. 1 7/13/70 1/2% damping (vertical accel =.75 x horiz accel). P&I Diagram " Steam Generator System" H-532.
Stress Isc. "#59 Area 1 Auxiliary Feedwater to Steam Generator E-205A" dated 11/18/70 Note 1:
A.
"Line Designation List" B.
" Specifications for Piping Design" C.
" Design Earthquake Horizontal Acceleration Response Spectrum" D.
" Design Earthquake Vertical Acceleration Response Spectrum" Note 2: For documents w3 hout a revision number and date the most current revision at the time of analysis was used.
Note 3: Valve weights were estimated using vendor cat 11og information.
m 27 (D
(D rt e
O O
-h md N
b 9
M sf3 j
}
s C)
%)
SOURCES OF INPUT INFORMATION FOR SEISMIC ANALYSIS OF SAFETY-RELATED SYSTER7 Notes 2,3 System Limits Line Nos.
Stress Prob.
ppsignDocuments Nuclear To and from T474B, 47351-10"-HE2 87 ANote 1,BNote 1,CII I" IMaximum accel.from Auxiliary Bldg.
elev. 20'-0" No. SK0292-s-42 Rev. 1 7/13/70 1/2% damping Service E-4738,E-2390, for horiz. and vertical. P&l diag. " Nuclear Service Raw Raw A529C,P261B,P291B, Water System" M-544. Stress Iso." Prob #87 Area 5 47351-10" Water A529E
-HE2 Nuclear Service Raw Water" dated 8/4/71.
System 47452-3"-HE2 88 ANote 1,Briote 1,C"U IAuxiliary Bldg. elev. O'-0" No.
47462-3"-HE2 SK-6292-5-85 Rev. 0 //13/70 1/2% damping. Pal diag.
" Nuclear Service Rau Water System" M-544. Stress Iso.
" Prob. #88 Area B 4 /351-10" HE2,47462-3"-HE2 & 47452-3".
HE2" Rev.19/8/72 I/ lote 1 Auxiliary Bldg. elev. O'-0" No. SK-6292-586 Rev. 0 7/13/701/2% damping.
47361-10"-HE2 77 All te 1,gNote 1,CNote 1 Maximum accel. from Auxiliary Bldg. elev. 20'-0" ilo. SK-6292-S-42 Rev.17/13/701/2%
damping for horiz. and vert. P&l diag. " Nuclear Service Raw Water System" M-544. Stress Iso. " Prob. #77 Area 5 47361-10"-HE2" datc<l 8/6/71.
48751-4"-HE2 48751-3"-HE2 52954-2-1/2"-HE2 23953-3"-HE2 52953-2-1/2"-HE2 48761-4"-HE2 si ANote 1,Briote 1 CNote 1 Auxiliary Bldg. elev O'-0" No.
SK-6292-S-85 Rev. 0 7/13/701/2% dampiag. D ote 1 Auxiliary N
48761-3"-HE2 Bldg. elev. O'-0" No. SK-6292-5-86 Rev. 0 7/13/70 1/2 52963-2-1/2"-HE2 co 29161-3"-HE2 damping.
Stress Iso. " Prob #91 Area 3,4,5 48761-4"/3"-HE2, 52964-48752-3"-HE2 52964-2-1/2"-HE2 2-1/2"-HE2,23963-3"-HE2,& 52963-2-1/2"-HE2" dated 8/13/71.
m 23963-3"-HE2 S
0 O
.M C)
CD
SOURCES OF INPUT INFORMATION TOR SEISMIC ANALYSIS OF SAFETY-RELATED SYSTEMS flotes 2,3 System Limits Line Nos.
Stress Prob..
Design Documents To and from T474A, 47350-10"-HE2 74 ANote 1,BNote I Note 1
.C Basic Ground Spectra elev O' 0" N6te 1 Basic E-473A,E2378,A-5298, 47451-3"-HE2 No. SK-6292-S-59 Rev. 0 7/13/70 1/2% damping. O E-239C A-529A.A-529D, 47461-3"-HE2 Ground Spectra elev. O'-0" No. SK-6292-5-60Rev.G 7/13/70 1/2% damping. P&l diag. " Nuclear Service Raw Water System" P-291A,P-261-A M-544. Stress Iso. " Nuclear Service Raw Water" dated 9/28/73 A ote 1,gNote 1 Note 1 N
Basic Ground Spectra e 0'-0" No.
damping.DOgy) Basic
.C 47360-10"-HE2 73 N
SK-6292-S-59 Rev. 0 7/13/70 1/2%
Ground Spectra elev. O'0" No. SK-6292-5-60 Rev. 0 7/13/70 1/2% damping. P&1 diag " Nuclear Service Raw Water System" M-544. Stress Iso. " Nuclear Service Raw Water" dated 9/28/7 48750-4"-HE2 85 AN te 1,BNote 1.C ote 1 Auxiliary Bldg. elev.20'-0" No.
il 23952-3"-hE2 SK-6292-S-42 Rev.1 7/13/701/2% damping. D ote 1 N
52950-2-1/2"-HE2 Auxiliary Bldg. elev. 20'-0" No. SK-6292-S-43 Rev.1 7/13/7 52951-2-1/2"-HE2 1/2% damping. P&l diag. " Nuclear Service Raw Water System" 48750-3"-HE2 M-544. Stress Iso. " Prob. 85 Area 5 Nuclear Service Raw Water System" dated 7/6/71.
48760-4"-HE2 86 ANote 1,BNote 1 Note 1
.C Auxiliary Bldg. elev 20' 0" No.
23962-3"-HE2 SK-6292-S-42 Pev.1 7/13/701/2% damping.DoteiAuxiliary R
52961-2-1/2%-HE2 Bldg. elev. 20'0" No. SK-6292-S-43 Rev. 1 7/13/70 1/2% damp 52960-2-1/2"-HE2 P&1 diag. " Nuclear Service Raw Water System" M-544. Stress 48760-3"-HE2 Iso. " Prob. #86 Area 5 Nuclear Service Raw Water System" dated 7/6/71.
A ote 1,BN te 1.CNote 1 N
0'0" No.
Auxiliary Bldg. elev$ damping. D ote Make-Up Penet. 15 to 22020-2-1/2"-CA 107 and PL5032 PLS036, 22024-2-1/2"-CA SK-6292-S-85 Rev. 0 7/13/701/2%
Purification and HV22011 Bldg. elev. O'-0" No. SK-6292-S-86 Rev. 0 7/13/701/2%
damping. P&l diag. "Make-Up and Purification System" M-521 System Stress Iso. " Cooler Outlet to Drain Orifice" dated 7/2/73.
22023-2-1/2"-CA 22022-2-1/2"-CA e
g i.J i
e
SOURCES OF INPUT INF0Pf4ATION FOR SEISMIC ANALYSIS OF SAFETY-RELATED SYSTEMS Notes 2,3 System Limits Line Nos.
Stress Prob.
Desion Documents _
A ote 1,B ote 1,CN te 1 N
N Auxilia Nte fg elev.0'-0" No. SK-6292-5 B1 Penet 18 to 21020-4"-CA 109 D
Auxiliary Bldg. elev. O'-0 SFV 24013 Rev. 0 7/13/70 1/2% damping.
No. SK-6292-5-86 Rce. 0 7/13/70 1/2% damping. P&I diag. "Make-and Purification System" M-521. Stress Iso. RC Pump Seal Water Return" A ote 1,B ote 1,C ote 1 Reactor Bldg. Interior Structure elev.~
N N
N Inside 60017-2-1/2-CA 55 Containment 22000-2-1/2"-CA l'-6" No. SK-6292-S-77 Rev.1 7/13/701/2% damping. (vert.
22001-2-1/2"-CA accel. =.75 x horli, accel.) P&I diag. " Reactor Coolant 22052-2-1/2"-CA System" M-520 and " flake-Up and Purification System" M-521.
22053-2-1/2"-CA Stress Iso. " Prob. #55 Area 1 Reactor Coolant Letdown System" dated 9/8/72 pgs. 1 and 2 A ote 1,B ote 1,C ote 1 Reactor Bldg. Interior Stru::ture elev.
N N
N 22020-2-1/2"-CA 72 22021-2-1/2"-CA l'-6" No. SK-6292-S-77 Rev. 1 7/13/70 1/2% damping. (vert.
22020-12"-CA accel. =.75 x hori z. accel.) P&I diag. "Make-Up and Puri-fication system" M-521. Stress Iso. " Prob. #72 Area 1 Make-Up and Purification System" dated 6/12/71.
A ote 1,B ote 1,C Reactor Bldg. Interior Structure elev.
N N
K t' 1 21023-2-1/2"-CA 540 21023-4"-CA l'-6" No. SK-6292-5-77 Rev.1 7/13/701/2% damping. (vert.
21024-4"-CA accel. =.75 x horiz. accel.) P&I diag. "Make-Up and Puri-21020-4"-CA fication System" H-b21. Stress Iso. "RC Pumps to Seal Return Coolers" 2 pgs.
Note 1:
A.
"Line Designation List' B.
" Specifications for Pioing Design" C.
" Design Earthquake Horizontal Acceleration Response Spectra" D.
" Design Earthquake Vertical Acceleration Response Spectra" Note 2: For documents without a re/ision number and date the most current revision at the time of analysis was used.
Note 3: Valve weights were estimated using vendor catalog infomation.
[
~
-91 M
LN C
rk N
- Q
Sheet 1 of 3 Attachment B Lines to be inspected per Item 2 of IE Bulletin 79-14.
System Limits Line Nos.
High Pressure T250 to P238B 23801-6"-HD Injection System to Penets. 22 & 23 23628-6"-GD 23802-6"-GD 23522-6"-GD 23629-6"-GD 23522-4"-GD 13822-4"-CA 23822-2 "-CA 23627-4"-CA 23620-4"-CA 23822-2 "-CA 23823-2 "-CA Decay Heat Removal T250 & Penet. 31 to 25021-16"-HD System P261-B & P291-B to 26101-18"-GD Penet. 27 26101-12"-GD 29101-10"-GD 26121-18"-GD 26121-10"-GD 26123-6"-GD 26021-10"-GD 26.21-10"-CA 26030-8"-GD 26022-8"-GD 26032-4"-GD Reactor Bldg.
P291B to Penet. 26 29123-8"-GD Spray System 29123-8"-HD 29196-6"-GD i'
1 303
Sheet 2 of T System Limits Line Nos.
B Nuclear Service E480B to E260g &
48061-24"-lE Cooling Water Penets. 7, 8, 11, 12 48223-18"-lE System 50056-10"-lE 50057-10"-lE 48223-12"-lE 26061-12"-IE 50066-10"-lE 50067-10"-lE 26061-18"-lE 48401-6"-HE Auxiliary Feedwater T-358 to Penet. 39 31900-8"-HC System 31920-6"-DB2 31826-6"-DB2 31821-6"-DB2 Nuclear To and From T474B, 47351-10"-HE2 Service E-473B, E-239D, A529C 47452-3"-HE2 Raw Water P261B, P2918, A529E 47462-3"-HE2 System 47361-10"-HE2 48751-4"-HE2 43751-3"-HE2 52954-2 1/2"-HE2 23953-3"-HE2 52953-2 1/2"-HE2 48761-4"-HE2 48761-3"-HE2 52963-2 1/2"-HE2 29161-3"-HE2 48752-3"-HE2 52964-2 1/2"-HE2 23963-3"-HE2 1
304 i
...w. ~
eet of System Limits Line flos.
Make-Up &
Outside 22020-2 1/2"-CA Purification Containment 22024-2 1/2"-CA System 22023-2 1/2"-CA 22022-2 1/2"-CA 21020-4"-CA e
1 305 i
.n.n.
Sheet 1 of 4 e
Attachment C Items to be Inspected per Item 3 of IE Bulletin 79-14.
System Limits Line Nos.
liigh Pressure T250 to P238A 23800-6"-HD Inje.ction System to Penets. 20 & 21 23803-6"-GD 23629-6"-GD 26024-4"-GD 23626-4"-CA 23626-4"-CA 23626-2 "-CA 23633-2 "-CA Inside Containment 23822-2 "-CA 23824-2 "-CA 21503-2 "-CA 23823-2\\"-CA 23825-2 "-CA 23626-2 "-CA 20003-2 "-CA 23620-2\\"-CA 20004-2$"-CA Decay IIeat Removal T250 & Penet. 30 26100-18"-GD System to P261A & P291A 29100-10"-GD to Penet. 28 26100-12"-GD 25020-16"-HD 26120-10"-GD 26120-18"-GD 26024-4"-GD 26020-10"-GD 26122-6"-GD i
1 306
Sheet 2 of 4 System Limits Line Nos.
~
Decay Heat Removal Inside Containment 26021-10"-CA System 26529-10"-CA 26528-14"-CA 4
26521-14"-CA 26020-10"-CA 26524-14"-CA 26520-14"-ED
?.eact:r 21 ;. Spray
?291A to Penet. 25 29120-8"-GD System 29198-6"-GD 29120-8"-HD Inside Containment 29123-8"-HD 29131-8"-hD 29131-6"-HD 29131-4"-HD 29124-3"-HD 29125-6"-HD 29125-3"-HD 29120-8"-HD 29130-8"-HD 29130-6"-HD 29130-4"-HD 29122-6"-HD 29122-4"-HD 29121-3"-HD Nuclear Service E480A to E260A &
48060-24"-HE Cooling Water Penets. 5, 6, 9, 10 48222-18"-HE System 48222-12"-HE 50054-10"-HE 50055-10"-HE 26060-12"-HE 3hh.i) hwh illk] (l J
26060-18"-ME n
UUll Ujt (3lgtj-l 50064-10"-HE I
50065-10"-HE 26060-lP"-HE 48400-6"-HE 1 307 i
Sheet 3 of 4 System Limits Line Nos.
Inside Containment 50052-10"-HE 50053-10"-HE 50062-10"-EE 50063-10"-HE 50050-10"-HE 50051-10"-HE 50060-10"-HE' 50061-10"-HE Auxiliary Feedwater T358 to Penet. 38 31800-8"-HC 31823-6"-DB2 System 31891-6"-DB2 31823-6"-DB2 31820-6"-DB2 Inside Containment 31821-6"-DB2 31820-6"-DB2 Nuclear
.To and From T474A, 47350-10"-HE2 Service E473A, E-237B, A-529B, 47451-3"-HE2 Raw Water E-239C, A-529-A, A-5290, 47461-3"-HE2 System P-291 A, P-261 A 47360-10"-HE2 48750- 4"-HE2 23952-3"-HE2 52950-2 1/2"-HE2 52951-2 1/2"-HE2 48750- 3"-HE2 48760- 4"-HE2 23962-3"-HE2
~
52961-2 1/2"-HE2 52960-2 1/2"-HE2 48750- 3"-HE2 e
9 7 'U' O 1
i 1
' ' ' 1;We
Sheet 4 of 4 System _
Limits Line tios.
Make-Up Inside 60017-2 1/2"-CA and Containment 22000-2 1/2"-CA 22001-2 1/2"-CA Purification 22052-2 1/2"-CA System 22053-2 1/2"-CA 22020-2 1/2"-CA 22021-2 1/2"-CA 22020 -12"-CA 21023-2 1/2"-CA 21023-4"-CA 21024-4"-CA 21020- 4"-CA O
D i
- T 4 8 9. Kv