ML19261C198
| ML19261C198 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/09/1978 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML19261C197 | List: |
| References | |
| NUDOCS 7903190341 | |
| Download: ML19261C198 (24) | |
Text
.
9 TENNESSEE VAI. LEY AUT110RITY Division of Power Production SECONDARY CONTAINMENT LEAK RATE TEST BROWNS FERRY hUCLEAR ~'LANT UNIT 3 CONDUCTED SEPTEMBER 9, 1978 SUBMITTED TO TiiE UNITED STATES NUCLEAR REGULATORY COMMISSION PURSUANT TO FACILITY OPERATING LICENSE NUMBER DPR-68 7903190341
Browns Ferry Nuclear Plant Unit 3 Secondary Containment Leak Rate Test Report (Continued) 5.0 Analysis and Interpretation (Continued) conditions with a total system inleakage rate of not more than 12,000 scfn shall be demonstrated at each refueling outage before refueling.
Following shutdown of unit 3 on September 9, 1978, the secondary con-tainment for the common refuel zone and the unit 3 reactor zone were leak rate tested. These two zones were isolated from the unit 1 and unit 2 reactor zones. Appendix A to SI 4.7.C gives the allowable inleakage per secondary containment zone documented during preoper-ational testing. Assuming a total allowable inleakage of 12,000 scfm, it is shown in Appendix A that the allowable inleakage for testing the refuel zone and unit 3 reactor zone in combination under calm wind conditions is 9168 sefm. From the data taken during this test, it is shown that, assuming a total combined inleakage of 9,000 scfm in the unit 3 reactor zone and the refuel zone, the secondary contain-ment system is capable of maintaining greater than 0.25 inch of water vacuum. These results fulfill the requirements of Technical Specification 4.7.C.l.c.
Page 1 BF SI 4.7.C SI 4.7.C - Secondary Containment Description This surveillance is used to comply with the requirements of portions of technical specification 4.7.C.
The following table lists the requirements satisfied by this instruction.
Tech. Spec Frequency Referenced
. Surveillance Requirements Under various wind 4.7.C.l.b Demonstrate the capability of secondary conditions during containment to maintain -1/4" water the first U-3 prer.sure with a system inleakage of not operating cycle.
more than 12,000 cfm using the Standby Gas Treatment System (SGTS). SI 4.7.C-1 will be used to satisfy this requirement.
At each ref ueling out-4.7.C.l.c Demonstrate the capability of secondary age prior to refueling containment to maintain -1/4" water pressure with a system inleakage of not more than 12,000 cfm under calm wind conditions 1 5 mph.
SI 4.7.C-1 will be used to satisfy this requirement.
Any time the integrity 4.7.C.2 Isolate the affected zone from the other of one zone has been zones and demonstrate secondary contain-violated ment capability to maintain -1/4" water pressure under calm wind conditions using the SGTS. SI 4.7.C-1 will be used to satisfy the requirements for the zones.
The reactor building is broken up into four zones, each of which can be iso-lated independently. These zones are the unit I reactor zone (UlRZ), the unit 2 reactor zone (U2RZ), the unit 3 reactor zone (U3RZ), and the refueling zone (RFZ), which is common to all three units.
This surveillance instruction is written to use the SGTS fans A and C, B and C, or A and B, or a single fan to demonstrate that at a flow of < 12,000 cfm the secondary containment zones can be maintained at a static pressure of
-1/4" water under calm wind conditions. Manual isolation of the zones will be used since it is fast and the steam line tunnel temperature increases, which may cause a unit trip.
Page 2 BF SI 4.7.C SI 4.7.C - Secondary Containment Description (Conti.tued)
SI 4.7.C-1 will be used to demonstrate secondary containment capability.
This is to be accomplished by isolating the secondary containment for the reactor building or the required zones, starting the standby gas treatment trains, adjusting the flow to Icss than the allowable flow and verifying the static pressure of the tested zone (s) is -1/4" H O or less. This procedure 2
will normally be used to test the secondary containment capability of the reactor building prior to refueling.
SI 4.7.C-1 testing should be limited to 30 minutes if at all possible since the main steam line tunnel temperatures may trip an operating unit.
SI 4.7.C - Secondary Containment capability 1.
PURPOSE This procedure is used to isolate the zones to be leak tested and to verify secondary containment capability to maintain -1/4" H O with a 2
system in-leakage of < 12,000 cfm without actually measuring the in-leakage.
2.
REFERENCES 2.1 Technical specifications for units 1, 2, and 3, Section 4.7.C.
2.2 The following drawings:
Number Revision Number Revision 45N614-5 5
47W610-65 15 3.
PREREQUISITES 3.1 Notify each unit operator and assistant shift engineer such that they may communicate and be aware of the ventilation and SGTS status during this test.
Page 3 BF SI 4.7.C SI 4.7.C - Secondary Containment Capability 3.
PREAEQUISITES (Continued) 3.2 Verify that the reactor building ventilation system is in a normal operational status per 01 30.
3.3 Verify that the SGTS is in standby readiness pcr OI 65.
3.4 Verify that each unit's main steam line tunnel temperature is not above 150 F.
3.5 Verify switch 16A-S34 is not in DRYWELL BYPASS or TORUS BYPASS on each unit or the unit that is to be tested.
3.6 Station a man at the Reactor Building 480V Vent Board in case any breakers need to be reset during this test and in the SGTS building to adjust manual dampers.
3.7 Set up communication between panel 9-25-1 and 9-25-2 and the follow-ing panels:
25-219-1 25-215-2 25-215-3 25-213-1 25-213-2 25-213-3 3.8 Verify the following process instruments to be within a current calibration period.
FI-65-50 1-PdIC-64-2 FI-65-71 2-PdIC-64-2 1-PdIC-64-1 3-PdIC-64-2 2-PdIC-64-1 3-PdIC-64-1 3.9 Verify the inboard equipment access lock doors closed with seals inflated.
Page 6 BF SI 4.7.C SI 4.7.C Secondary Containment capabilities 6.
PROCEDURE (Continued) 6.4 Secondary Containment Capability NOTE: This section is to verify that the secondary containment is capable of maintaining a -1/4" H O with a system 2
inleakage of 1 12,000 cfm for the entire reactor building.
6.4.1 Adjust the total flow indicated on FI-65-50 and FI-65-71 (panel 9-25-2) to 11,500 cfm or as allowable by closing a SGTS f an discharge damper or if two fans are running it may be necessary to shut one fan off.
NOTE: Let the flow stabilize for 5 minutes before the next step.
6.4.2 Record flows indicated on FI-65-50 and FI-65-71 (panel 9-25-2) and total on Data Sheet SI 4.7.C-1, 6.4.3 Record the following static pressures.
Z o'r.e Instrument Panel UlRZ 1-PdIC-64-2 1-25-213 U2RZ 2-PdIC-64-2 2-25-213 U3R2 3-PdIC-64-2 3-25-213 UlRFZ 1-PdIC-64-1 1-25-219 U2RFZ 2-PdIC-64-1 2-25-215 U3RF2 3-PdIC-64-1 3-25-215 6.4.4 Verify all four zones static pressures are 1 -1/4" H 0.
2 6.4.5 Record the wind direction and velocity from XR-90-102 (panel 9-14-1)
NOTE: If all four zones static pressures are 1 -1/4" H O 2
this will satisfy 4.7.C.1.b and c.
If one or more zones do not meet the -1/4" H O static pressure re-2 quirements the following steps must be completed.
NOTE: Check to assure reactor building is isolated.
i l
l I
Page 7 BF SI 4.7.C SI 4.7.C Secondary Containment Capabilities 6.
PROCEDURE (Continued) 6.4 Secondary Containment Capability (Continued) 6.4.6 Adjust the total flow indicated on FI-65-50 and FI-65-71 (panel 9-25-2) to 12,000 cfm by opening the fan discharge damper or it may be necessary to start another fan and adjust its discharge damper.
NOTE: Let the flow stabilize for 5 minutes before the next stop. Record flows indicated on FI-65-50 and FI-65-71 (panel 9-25-2) and total on Data Sheet SI 4.7.C-1.
6.4.7 Record the following static pressures.
Zone Instrument Panel UlRZ 1-PdIC-64-2 1-25-213 U2RZ 2-PdIC-64-2 2-25-213 U3RZ 3-PdIC-64-2 3-25-213 UlRFZ 1-PdIC-64-1 1-25-219 U2RFZ 2-PdIC-64-1 2-25-215 U3RFZ 3-PdIC-64-1 3-25-215 6.4.8 Verify all four zones static pressures are fL-1/4" H 0.
2 NOTE: If all four zones static pressures are jL-1/4" H 0 this will satisfy 4.7.C l.b and c.
If one or 9
m5re zones do not meet the -1/4" H 0 static pressure 2
requirement the following steps must be completed.
6.4.9 Isolate the zone (s) that have a static pressure of > -1/4" H O from the remaining zones and indicate zones isolated 2
on Data Sheet SI 4.7.C-1.
6.4.10 Adjust the total flow indicated on FI-65-50 and FI-65-71 (panel 9-25-2) to the Allowable Flow of the remaining zones.
See Appendix A for the Allowable Flcws.
Page 8 BF SI 4.7.C SI 4.7.C Secondary Containment Capabilities 6.
PROCEDURE (Continued) 6.4 Secondary Containment Capability (Continued) 6.4.10 (Continued)
NOTE: Let :he flow stabilize for 15 minutes before the nexo step.
6.4.11 Record flows indicated on F1-65-50 and FI-65-71 (panel 9-25-2) and total on Data Sheet SI 4.7.C-1.
6.4.12 Record the following static pressures.
Zone Instrument Panel UlRZ 1-PdIC-64-2 1-25-213 U2RZ 2-PdIC-64-2 2-25-213 U3RZ 3-PdIC-64-2 3-25-213 UlRFZ 1-PdIC-64-1 1-25-219 U2RFZ 2-PdIC-64-1 2-25-215 U3RFZ 3-PdIC-64-1 3-25-215 6.4.13 Verify the remaining zones static pressures are jL -1/4" H 0.
2 NOTE: If these zones static pressures are jL-1/4" H,0 this will satisfy 4.7.C-2.
Maintenance must Be per-formed on the isolated zone and should be indicated on Data Sheet SI 4.7.C-1 cover sheet under Remarks.
6.4.14 Check those switches that were put in the TEST position under sections 6.2 and/or 6.3 in their NORMAL position and verify on Data Sheet SI 4.7.C-1.
6.4.15 Verify on Data Sheet SI 4.7.C-1 those actions listed under RETURN TO NORMAL for the zones tested.
Page 9 BF SI 4.7.C Appendii ji Secondary Containment Leak Rate Test Criteria During preoperational testing for unit 3 the following in-leakage rates at
-1/4" !! 0 static pressure were documented.
2 Documented Inleakage Percentage Common refuel floor (units 1, 2, & 3) 6250 Later Unit 1 reactor zone 1239 Unit 2 reactor zone 1064 Unit 3 reactor zone 1211 9764 Total secondary containment later CFM 100%
Leak rate testing will normally be done with all zones simultaneously lined up for testing; however, plant operating conditions anc the technical specification do not always permit this. When less than four zones (3-utit plant) are being tested, the total allowable inleakage will be based on pre-operational testing and will be based on the sum of the allowable inleakages for the zones being tested. After a secondary containment violation, the total inleakage must not be greater than the total of the allowable inleakage for each individual zone as indicated below.
The technical specifications require the total secondary containment inleak-age to be less than 12,000 cfm at -1/4" differential pressure. The following are therefore established for survcillance testing various combinations of zones when secondary containment has been violated.
Zone Allowable Inleakage Common refuel floor 7680 Unit I reactor zone 1524 Unit 2 reactor zone 1308 Unft 3 reactor zone 1488 Reactor Building
< 12000 CFM
In 0
Page 1 BF SI 4 DATA COVER ".T.ET SI 4.7.C-1 5/11/
SECONDARY CO:ITAIhMENT CAPAEILITY UtIIT1,2Oh bd O Date 9-9-76 Performed By _,
Uait~Operato(
/
4 O
Were criteria satisfied?
Yes No
'l
.If no, notify shift engint.cr.
,j If no, was a Limiting Condition for Operation violated?
Yes (explain in remarks)
No (explain in remarks)
I I
Verified by Shift Engineer
, Date
?.cason for test:
Maintenance complete on i.
Another system (
) inoperabic Required by schedule t>
Plant condition (explain) s/ Other (explain)
RE Ft>E t t A.)6 AOTM(-
!l I'
b// ~7 [
dod t/
Date Results reviewed
~<w Ass'istant Shif t Engineer i?
i Results Revicu and Approval Date
- // - 8 j
(1) Cognizant Engineer M
.'B 1 'l Rescheduled
~~l 3 ~ W QA Staff h)}n Date REMARKS k
1 (1) Notify Maintenance that inicakage is excessive if criteria are not satisfied.
a
.J' Page 11 SF SI 4.7.C D
5/11/76 L(
Data '5hcet SI 4.7.C-1 (Continued) f!U Verify and/or Record Initials /Date_
Component / Process Variable Normal 3.2 Rx. Bldg. Ventilation System Standby Readiness 3.3 SGTS 0
3.4 Main Steam Line Tunnel Temperaturc
$ 150 F for units being tested Not in Drywell or 3.5 16A-SM for units tested Torus Bypass Currently Calibrated J2B f 3.8 FI-65-50 Currently Calibrated 7&Of At FI-65-71 Currently Calibrated M[
I' Pd1C-64-1 (All three units)
Currently Calibrated M[
PdIC-64-2 (All three units)
Closed and Seals Inboard Equipment Access Lock Doors f) J #
(
3.9 Inflated l
j M [-
y Purge Not Inprocess
'.s 3.10 Drywell bg Suppression Chamber
.l 3.11 Doors in the following table for the tested zone (s) or the number doors M ['
Closed for all zones.
i f
d ji O
I I
e e
a
c..,
3.-
Page 12 BF SI 4.7.C Table 3.11 5/11/76 1(
Data Sheet S1 4.7.C-2 (Continued)
Elevation UlRZ U2RZ U3RZ RFZ 519.0 30 34, 36 40 31 35, 37 41 a
4 541.5 42 43, 44 45' 3
565.0
- 221 0-236, # 241
- 249 255
- 231
- 237
- 250 242 fl 224
- 238
- 251 226 a
- 229 240 255 231
- 228 24 2 i
- 232 t
- 230
{
- 230a
-l 583.0
- 298
- S26,#-827 t
593.0
- 538 497, 501 506
- 539
- 540
- 513 1
490
- 541
- 514 621.25
- 534 640, 647 651 3
- 637
- 648
- #'457 635
- 649
- 458 639.0 670 672 675 673
\\
664.0 704 700 713 717 724 715 700, 702, 724, 715, 713 705 701 714 725 7 16 701, 703, 725, 716, 71.,
706 712 715 722 717 704, 720, 722, 706, 717 723 705, 721, 723, 708, 7N 707 708 712
Page 15 BF SI 4.7.C q
Data Sheet SI 4.7.C-1 (Continued) 5/11/76 Step Component / Process Variable Verify and/or Record Initials /Pate 6.2.3 (Continued)
Unit 3 Reactor Zone (Continued) 3-FCO-64-41 Open M FCO-64-60A Closed
% FCo-64-60B Closed
-FCO-64-60C Closed M FCO-64-60D Closed U-3 Stair Hall Supply Fan Shutdown
}'
6.3.1 1-HS-64-119 TEST Position CAF 6.3.2 1-HS-64-122 TEST Position 6.3.3 SGTS Train A START or SGTS Train B START Mg or SGTS Train C START
[
Refueling Zone U-1 Area Refueling Zone Vent Sys Shutdown U-2' Area Refueling Zone Vent Sys Shutdown U-3 Area Refueling Zone Vent Sys Shutdown 1-FCo-64-6 Close 2-FCO-64-6 Close 3-FCO-64-6 Close 1-FCO-64-5 Close 2-FCO-64-5 Close 3-FCO-64-5 Close 1-FCO-64-10 Close 2-FCO-64-10 Close 3-FCO-64-10 close e
Page 17' BF SI 4.7.C Data Shcet SI 4.7.C-1 (Conttinued) 5/2/78 C-Component / Process variable _
_ Verify nnd/or Record Initials /Date h
M/
. 3 2_
"Ilg0 6.43 1-PdIC Rx Zone 64-F
' Md'
- Thermometer Rx Zone
-.M "Il 0
'EO g
2-PdIC Rx Zone 64-F Mid
- Thermomet.cr Rx Zone
.3 W "lig0 A
3-PdIC Rx Zone 64-F
~_ M4
- Thermometer Rx Zone 1-Pd1C Refueling Zone
. ;'y %~
" 11 0 XA 2
~
s
.33
" 11 0 pd 2
2-PdIC Refuellng Zone 3 5~
" 11 0
_84 2
3-PdIC Refueling Zonc 64-F IM
- Thermoneter Refueling Zone 6.4. 4 All zones < -1/4" 110 g
2 A'
M Directic.n d4 2.~ 1 mph
- 6.4 5 33 ft. ~1 cycl / Windspeed k
~
(o[o F
- 6.4.5.1 Thermometer / Outside temp.
d[A-scfm Al/A 6.4. 6,
FI-65-50
/,
scfm FI-65-71 lI-.
scfm Total 6.4. 7 1-PdiC-64-2RxZone
" 11 20 "11 0 2
2-PdIC-64-2 Rx Zone
" 11 0 2
3-PdIC-64-1 Rx Zone
" 11 20 1-PdIC-64-1 Refueling Zone
" 11 0 2
2-PdIC-64-1 Refueling Zonc g/
" 11 0 2
3-PdIC-64-1 Refueling Zone g/
6.4.8 All zones < -1/4"11 0 A\\/A-
- 6. 4.9 Zones Isolated List f
- Ecvision v/
y/
wA
(
4
Page 18 Data sheet SI 4.7.C-1 BF SI 4.7.C 5/11/76 Step domponent/ Process Variable Verify and/or Record Initials /Date Return to Mormal 3
td[A-6.411 FI-65-50 scfm A
/
/
FI-65-71 sc fm Total scfm 6.4J2 1-rdIC-64-2 Rx Zone "1I20 2-PdIC-64-2 Rx Zone "H2O 3-PdIC-64-2 Rx Zone
" 11 20
.I l-PdIC-64-1 Refueling Zone "II 0 2
1 2-PdIC-64-1 Refueling Zone
" 11 0 2
I 3-PdIC-64-1 Refueling Zone sf "H O 2
6.4.13 Remaining zones < -1/4"110 2
6.4.14 1-HS-64-117 NORMAL d
2-HS-64-117 HORMAL
[
3-11S-64-117 NORMAL M
l A
i 1-US-64-120 NORMAL NA\\
s 2-US-64-120 NORMAL 4
3-US-64-120
- NORMAT, h
1-US-64-119 NORMAL 5
1-HS-64-122 NORMAL A
?
e 1
o I
k e
Page 19 d
BF SI 4.7.C 5/11/76 Data Sheet SI 4.7.C-1 Verify and/or Record Initials /Date Compone nt/Proce s:: Variable g
Return to trormal dM, 0FF 6.4. 15 SGTS Fan A N/
Closed
' 8tM; FCO-65-3
.J OFF A-SGTS humidity control heater t
ON A-SGTS charcoal heater
/A OFF SCTS Fan B 3
1 Closed i
FCO-65-25 OFF E-SGTS humidity control heater
(
ON B-SGTS charcoal heater 0FF SGTS Fan C '
Closed FCO-65-51 OFF C-SGTS humidity control heater
\\[
ON C-SGTS charcoal heater
]1 Unit 1 Reactor Zone In op'eration as required U-1 Reactor Zone Ventilation System Al!A-OPEN
'I 1-FCO-64-13
('
OPEN 1-FCO-64-14 OPEN 1H.0-64-42 t
OPEN 1-FCO-64-43 Closed 1-FCo-64-15 d
Closed 1-FCO-64-40 I'
i Closed 1-FCo-64-41 Open l'
1-FCO-64-60A
~
Open 1-FCO-64-60B I
Open u
i 1-FCO-64-60C Open 1-FCO-64-60D In operat' ion as required U-1 Stair Hall Supply Fan
Page 20 BF SI 4.7.C Data Sheet SI 4.7.C-1 (Continued) 5/11/75 I
pg Component / Process Variable Verify and/or Record Initials /Date 6.4 15 (Continued)
Unit 2 Reactor Zone U-2 Reactor Zoac Ventilation System In operation as required 9
j 2-FCO-64-13 Open kA Y
2-FCO-64-14 Open 2-FCo-64-42 Open l
2-FCO-64-43 Open 2-FQO-64-15 Closed 2-FCO-64-40 Closed 2-7CO-64-41 Closed N
Unit 3 Reactor Zone U-3 Reactor Zone Ventilation System In operation as required t +
NM 3-FCo-64-13 Open
.l.
s LM 3-FCO-64-14 Open 8L 3-FCO-64-42 open d
3-FCO-64-43 Open
\\
t' 3-FCo-64-15 Closed t.
Closed 3-FCO-64-40
[
3-FCO-64-41 Closed
[pd f'
3-FCO-64-60A Open g
- s 3-FCO-64-60B Open Mt, d
3-FCO-64-60C Open y
/b 3-FCO-64-60D Open U-3 Stair Ital 1 Supply Fan In Operation as Required i
i L.
l' age 21 s
BF SI 4.7.C
?
5/2/78 Data Sheet SI 4.7.C-1(Contimucd)
(
Veri fy.nnel_/nr Reenrd Inftials/n,te variabic Cn;nponent / Procc a n sp, 6.4. 15 (Continued)
Refueling Zone _
i In Oper.ation as required U-1 Arca Refueling Zone vent Sys In Oper:ation as required U-2 Area Refueling Zone Vent Sys U-3 Area Refueling Zonc dont Sys In Oper.ation as required 1
_M Open 1-FCO-64-6 M
Open 2-FCO-64-6 MM s
Open
\\
3-FCO-65-6
,#j g
Open 1-FCO-64-5 IM Open 2-FCo-64 5 dd Open s
3-FCO-64-5 M/
(
Open 1-FCO-64-10 i
Open 2-FCO-64-10 MA Open
\\
3-FCO-6'4 - 10
/d open 1-FCO-64-9 k
r Open
!I 2-FCO-64-9 Open 3
.3-FCO-64-9 iM
.\\
Close 1-FCO-64-63 Mc2\\
close
~
\\
1-FCO-64-7' M6 l* 1-FCO-64-65A Open y
0pe'n M4 I*
- l-FCO-64-65B
\\
M4 Open
- l-FCO-64-65C Open
- l-FCo-64-65D Close 1-FCO-64-44 x
&d
(
Close
~
\\
3 1-FCO-64-45' In Operation as required i
g Equipment Access Lock' Exhaust Fan l
7 5
In Operation as required
.U-1 Stair lla11 Supply Fan In Operation as required
.1
...4-u it c: nniv Fan
Page 14 BF SI 4.7.C 5/11/76 Data Sheet SI 4.7.C-l'
' Continued)
Step component / Process variable Verify and/or Record Initials /C,tg 6.2.3 (Continued) 1-FCO-64-15 Open MA 1-FCo-64-40 Open 1-FCO-64-41 Open i
1-FCO-64-60A Closed 1-FCO-64-60B Closed 1-FCO-54-60C Closed 1-FCO-64-60D Closed l'.-
\\[
U-1 Stair Hall Supply Fan Shutdown Unit 2 Reactor Zone U-2 Reactor Zone Ventilatica Sys Shutdown A)[
l 2-FCO-64-13 Closed i
2-FCO-64-14 Closed i
2-FCO-64-42 Closed 2-FCD-64-43 Closed 2-FCO-64-15 Open 2-FCo-64-40 open 2-FCO-64-41 open V
J Unit 3 Reactor tone U-3 Reactor Zone Ventilation Sys Shutdown 3-FCo-64-13 Closed 3-FCO-64-14 Closed s
1 3-FCO-64-42 Closed 3-FCo-64-43 Closed 3-FCO-64-15 Open 3-FCO-64-40 Open
.s.
e e
.. i e
Face 16 DF SI 4.7.C 5/2/78 Data Shec:: SI 4.7.C-1,(Conti nued)
Initials /Date_
ycri fy.mnd/or Record _
Cgtponent/ Process variabic_
g 6.3.3 (Coatinued)
,gfueli nr. 7.nac_
(Continued)
P Closc 1-FCO-64-9
~
Close 2-FCO-64-9 Close 3-FCO-64-9 Open 1-FCO-64-63 Open
, 1-FCO-64-7 Close
~
- b FCo-64-65A
- gics,
- h FCO-64-65B Close h FCO-64-65C w
Close
\\ FCO-64-65D 4
Open 1-FCO-64-44 a
.Open
" FCO-64,,
Shutdown Equipment Access Lock Er.haust Fan Shutdoun U-1 Stair Itall Supply Fan Shutdown U-3 Stair Itall Supply Fan a
~
s Xmo cien
_N s
a i
6.4 2 F1-65-50
_ /d h()
_s fem F1-65-71 M
.Smo afem x
T.t. 1
')
.[
- Revision s
(-
<