Text

Results & Analysis of 781127 Secondary Containment Leak Rate Test.Shows Secondary Containment Capability to Main 1/4 Inch Water Vacuum Under Calm Wind W/Sys in Leakage Rate of Not More That 12,000 Scfm Before Refueling
	ML19274D552
Person / Time
Site:	Browns Ferry
Issue date:	02/09/1979
From:	; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML19274D549	List: ML19274D548; ML19274D552;
References
	NUDOCS 7902130097
	Download: ML19274D552 (23)
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TENNESSEE VALLEY AUTHORITY Division of Power Production SECONDARY COIITAINMENT LEAK RATE TEST BROWNS FERRY NUCLEAR PLANT UNIT 1 CONDUCTED NOVEMBER 27, 1978 SUBMITTED TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION PURSUANT TO FACILITY OPERATING LICENSE NUMBER DPR-33 790213 0097

e 1.0 - Browns Ferry Nuclear Plant Unit 1 Secondary Cont ainment Leak Rate Test Report 2.0 Purpose This report describes the results and analysis of the test data taken during leak rate testing of the Browns Ferry Nuclear Plant unit 1 secondary containment pursuant to Technical Specification 4. 7.C.1.c before the first refueling outage.

o 3.0 Procedure The attached surveillance instruction (SI), S1 4.7.C-1, outlines the procedures followed during secondary containment Icak rate testing.

4.0 Data The attached surveillance instruction data sheets list the following test data:

(1) Standby gas treatment system flow rate: 9,000 scfm (2) Reactor building differential pressures:

Unit 1 reactor zone:

-0.33" H O 2

Unit 2 reactor zone:

-0.30" H O 2

Unit 3 reactor zone:

-0.29" H O 2

Refueling zone average:

-0.31" H O 2

(3) Wind Speed:

3.5 mph (4) Wind direction: southeast 5.0 Analysis and Interpretation Technical Specification 4.7.C.l.c requires that secondary containment capability to maintain 1/4-inch water vacuum under calm (<5 mph) wind conditions with a total system inleakage rate of not more than 12,000 ocfm shall be demonstrated at each refueling outage before refueling.

sllowing shutdoen of unit 1 on November 27, 1978, the secondary containment for the common refuel zone and the unit reactor zone were leak rate tested.

Browns Ferry Nuclear Plant Unit Secondary Containment Leak Rate Test Report (Continued) 5.0 Analysis and Interpretation (continued)

These two zones were isolated from the unit 2 and unit 3 reactor zones.

Appendix A to S1 4.7.C gives the allowable inleakage per secondary containment zone documented during preoperational testing. Assuming a total allowable inleakage of 12,000 scfm, it is shown in Appendix A that the allowable inlerkage for testing the refuel zone and unit I reactor zone in combination under calm wind conditions is 9,204 scfm. From the data taken during this test, it is shown that, assuming a total combined inleakage of 9,000 scfm in the unit reactor zone and the refuel zone, the secondary containment system is capable of maintaining greater than 0.25 inches of water vacuum.

These results fulfill the requirements of Technical Specification 4.7.C l.c.

LFB:SS 1/15/79

Page 1 BF S14.7.C

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5/11/76 II 4.7.C

- Secondary Contairment

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Descriprinn This curveillance 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 3

Under v.irlous wind 4.7.C.1.b Demonstrate the capability of secondary con-conditionn during the tainment to maintain - 1/4" water pressure first U-3 operating with a system inleakage of not more than cycic 12,000 cfm using the Standby Gas Treatment satisfythisre(q[uirement.fl~4.7.C{1willbeusedto System (SGTS).

At each refueling out-4.7.C.I.c Demonstrate the capability of secondary con-age prior to refueling tainment to maintain - 1/4" water pressure with a system inleakage of not more than 12,000 cfm under calm wind conditions < 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 zones

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and demonstrate secondary containment capabi-of onc zone has been viola c cil lity to maintain - 1/4" water pressure under calm wind conditions using the SGTS.

SI 4.7.C-1 will be used to satisfy the require-ments for the zones.

The reactor building is broken up into four zones, each of which can be isolated independently. These zones are the unit I reactor zone (UlRZ), the unit 2 Reactor zor.e (U212Z), 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 SCTS fans A and C, B and C, ur A and B, or.a singic fan to demonstrate th'at at a flow of 5 12,000 cfm the secondary containment zones can be maintain,cd at a ntatic pressure of -1/4" water under calm wind conditions. Manual isolation of a

the zoner, ut il be used since it is fast and the steam line tunnel temperature

(,_

increascu,which may cause a unit trip.

.._ 2.

Page 2 BT SI 4.7.C

//11/76

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SI 4.7.C - Secondary containment Description (Continued)

SI 4.7.C-1 will be used to demonstrate secondary containment capability.

This is to be accomplished by isolating the secondary containdent for the reactor building or the required zones, starting the standby gas treatment trains, adjust-ing the flow to less than the allowable flow and verifying the static pressure of the tested zone (s) is -1/4" 110 or less. This procedure vill normally be used to 2

test the secondary containment capability of the reactor building prior to refueling.

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SI 4.7.C-1 testing should bc Ifmited to 30 minutes if at all possible since the main steam line tunnel temperatures may trip an operating unit.

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i Page 3 l

EF SI 4.7.C 5/11/76 e

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SI 4.7.C - Secondary containment Capability 0

UJ 1.

ERPOSE This procedure is used to isolate the zones to be leak tested and to verify secondary containment capability to taaintain -1/4" H O with a system in-leakage s

2 of f_ 12,000 cfm without actually measuring the in-leakage.

2.

REFERENCES 2.1 Technical specifications for units 1, 2, and :), Section 4.7.C.

2.2 The following drawings:

Number Revision Number Revision r,

45N614-5 5

47W610-64 15 45N614-6 5

47W610-65 15

[

3.

PREREQUISITES 3.1 Notify each unit operator and assistant shift engineer such that they may cocznunicate and be aware of the ventilation and SGTS status a

during this test.

l 3.2 Verify that the reactor building ventilation system is in a normal operational status per OI 30.

3.3 verify that the SGTS is in standby readiness per OI 65.

3.4 Verify that each units' main steam line tunnel temperature is not above 150 F.

3.5 Verify switch 16A-S34 is net in ORYWELL BYPASS or TORUS BYPASS on 9

each unit or the unit that is to be tested.

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Page 4 BF SI 4.7.C 5/11/76 SI 4.7.C-1 Secon<!ary Containcient Capability C

r.

3.

PREREQUISITES (Continued) 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 SCTS building to adjust m

manual dampers.

3.7 set up communication between panel 9-25-1 and 9-25-2 and the following 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 withir. a current calibration period.

F1-65-50 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 39 verify the inboard equipment access lock doors closed v8 seals inflated.

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3.10 Verify that a drywell or suppression chamber purge '-

. : in process or planned during this test.

3.11 Verify on Data Sheet SI 4.7.C-1 that each of the doors are closed for the respective zones to be tested or the doors indicated by number (See Table 3.11 of Data Sacct S14.7.C-1) for all four zones.

4.

PRECAUTIONS 4.1 De not allow the main steam line tunnel temperature on any unit in operation to execed 1600 F.

If this temperature is approached to within 100 F, stop the test and reestablish normal ventilation per 01 30 or,

I provide another means for ventilating the main steam line tunnel to prevent a unit trip (trip point is 1860 F).

4.2 Attempt to restrict testing time to 30 minutes.

s 5.0 _ LittITATIONS AND ACTT03

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5.1 None s

S Page 5 BF SI 4.7.C 5/11/76 SI 4.7.C Secondary containtnent Capabilities e

6.

PROCF' DURE 6.1 Initial and perform the indicated sections on the configuration to be tested on Data Shtet SI 4.7.C-1 and perform steps indicated below.

6.1.1 U1RZ - Perform section 6.2 and section 6.4.

6.1.2 U2RZ - Perform section 6.2 and section 6.4.

6.1.3 U3RZ - Perform section 6.2 and section 6.4.

6.1.4 PS2 - Perform section 6.3 and section 6.4.

6.1.5 U1R2 and RFZ - Perform sections 6.2, 6.3 and section 6.4.

6.1.6 U2RZ and RFZ - Perform sections 6.2, 6.3 and section 6.4.

6.1.7 U3RZ and RFZ - Perfom sections 6.2, 6.3 and section 6.4.

6.1.8 Reactor Building - Perfom section 6.2 for each RZ, and section 6.3 for the RFZ and section 6.4.

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6.2 Manual Isolation of a Reactor Zone NOTE:

MS-64-117, HS-64-120, HU 64-119, & HS-64-122 are spring. return to normal.

6.2.1 Place HS-64-117 (Panel 9-25) in the TEST position for the reactor zone to be isolated.

(Inboardand common valves) 6.2.2 Place HS-64-120 (Panel 9-25) in the TEST position for the reactor zone to be isolated.

(Outboard valves) i 6.2.3 Start SCTS trains A and B in accordance with OI 65 and verify actions and/or take data as indicated on Data Sheet SI 4.7.C-1 l

for the reactor zone that is being isolated.

NOTE: If a reactor zone is the only zone to be isolated, l

go to Section 6.4 and if the refuel zone is to be isolated complete Section 6.3 before going to

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l Section 6.4.

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6.3 Manual Isolation of the Plant Refueling Zone 6.3.1 Place HS-64-119 (Panci 9-25-1) in the TEST position. (Inboard and common valves)

= = - = * - -,.

.........w,-..e=====-

Pace 6 BF SI 4.7.C 8/4/77 SI 4.7.C Se condary containment Capabt11 tics 6.

PROCEntfrE (Continued) 6*3 Manual Isolation of the Plant Refueling 2one (Continued) 6.3.2 Place 11S-64-122 (Panci 9-25-1) in the TEST positio s.

)

,i

'(Outboard valves)

Start SGTS trains A and B, if not aircady runniig, in accordance 6.3.3 with 0165 and verify actions and/or take data as indicated on Data Sheet SI 4.7.C-1 for the refuelir, zone, a

i 6.4 Secondary Containment Capability i

NOTE: This ccction is to serify that the secondary containment l

l 1s capable of ciaintaining a -1/4" !(20 with a system inleakage of< 12,000 cfm for the entire reactor building,

6.4.1 Adjest the total flots indicated on FI-65-50 and FI-65 71 (panel 9-25-2) to 11,500 cfm er as allowable by -losing a f

SGTS f an discharge damper or if two fans are running it may a

be necessary to shut one fan of f.

110Tr.; Let the flow stabilize for 5 minutes before the next ::tep.

6.4.2 Eccord flows indicated on FI-65-50 and F1-65-71 (panci 9-25-2) and total on Data Sheet SI 4.7.C-1.

6.4.3 Record the following static pressures.

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Zone Instrument Panci 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-Pd 1C 1 1-25-219 U2RFZ 2-PdIC-64-1 2 "5-215 U3RFZ 3-Pd1C-64-1 3-25-215 6.4.4 verify all four zones static pressures arc e, -1/4" 110.

2

'14 v i r. I e,.i

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t Page 7 BF SI 4.7.C j

8/4/77 SI 4.7.C Secondary contain. ment Capabilitics I

6.

PnocatTE (Continued) 6.4 secondary containment capability (Continued) 6.4.5 Record the wind direction and velocity from XR-90-102 (panct 9-14-1)

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four zones static pressurcs are d -1/4" 112 0 this NorC: If 11 wi i satisfy 4.7.C.1.b and c.

If one or more zones do

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not meet t.

-1/4" H2O static pressure requirements the following.tcps must be completed.

NUTE: Check to assurc reactor building is isolated.

6.4.6 Adjust the total flow indicated on 71-65-50 and FI-65-71 (pal 9-25-2) 4, f,

to 12,000 cfm by opening the fan dischargo damper or it may be necessary to start another fan end adjust its discharge damper.

NLfE: Le ; the flow stabilize for 5 minutes before the next stop.

Record flows indicated on FI-65-50 and FI-65-71 (pn1 9-25-2) and total on Data Sheet El 4.7.C-1.

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6.4.7 Record the following static pressures.

}' Zone Initrument Panel

- U1RZ A-PdIC-64-2 1-25-213 U2RZ 2-PdIC-64-2 2-25-213 fU3RZ 3'-PdIC-64 2 3-25-213 UIRFZ 1-PdIC-64 1 1-25-219 l' U2RFZ 2-PdIC-64 1 2-25-215 I

U3RFZ 3-PdIC-64 1 3-25-215 6.4.8 Verify all four zoncs static pressures are $ -1/4" !! 0.

2 N o i:: If all four zones static pre.sures arc < -1/4" H O this 2

will satis fy 4.7.C.1.b and c.

af one or more zones do the -1/4" 110 static pressure requirement the not meet 2

following steps must be coap'.cted.

6.4.9 1solate the zone (s) tha: have a st atic pressure of > -1/4" !! 0 2

from the remaining zoncs and indicate zones isolated on Data Sheet SI 4.7.C-1.

6.4.10 Adjust the total flow indicated on F1-65-50 and FI-65-71 (pn1 9 W ?)

to the Allouable Flow of the remaining.ones.

See Appenlix A for tl.c Allowable Finws.

iwv i. n.n..d(

y.-..

Page 8 BF SI 4.7.C 5/11/76 SI 4.7.C Secondary Containment capabilities t'

6.

PROCEDURE _ (Continued)

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6.4 Secondary Containment Capability (Continued)

)

6.4.10 (Continued)

/

NOTE: Let the flow stablize for 15 minutes before the next step.

6.4.11 Record flows indicated on FI-65-50 and FI-65-71 (pn1 9-25-2) and total on Data Sheet SI 4.7.C-1.

6.4.12 P 3rd the following static pressures.

Zone Instrument Panel U1RZ 1-PdIC-64-2 1-25-213 U2RZ 2-PdIC-64-2 2-25-2L3 U3RZ 3-PdIC-64-2 3-25-2L3 U1RFZ 1-PdIC-64-1 1-25-219 U2RFZ 2-PdIC-64-1 2-25-2L5 U3RFt 3-PdIC-64-1 3-25-215 6.4.13 Verify the remaining zones static pressurec sce < -1/4" H 0.

2 NOTE: If these :enes atatic pressures are 1 -1/4" H O this will 2

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satisfy 4.7.C-2.

Maintenance must be performed 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.

9 0

Page 9 l

e

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BF S1 4.7.C g

8/4/77 Appendix A Secondary Containment 1.cak Rate Test Criterla During preoperational testing for unit 3 the following in-1cakage rates at

-1/41'il 0 static pressure were documented.

Documented y

Inicakave Pererntace i

6250 Later Common refuel floor (units 1, 2, & 3)

Unit I reactor zone 1239 Unit 2 reactor zone 1064 1211 Unit 3 reactor zone y

9764 Total secondary containment later Cnf 100%

u:ak rate testing will normally be done with all zones simultaneously lined up for testing; however, plant operating conditions and the technical specification do not always permit this. When less than four zones (3-unit plant) are beir;; tested, the total allowabic inicakage will be based on preoperational testing and vill be based i

en the sum of the allowable inleakages for the zones being tested. After a

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i secondary containment violation, the total inleakage must not be greater than the I

total of the allowable inicakage for cach individual zone as indicated below.

i I

j The technical specifications require the total secondary containment inicakage I

to bc Icss than 12,000 cfn at -1/6" differential pressure. The following are therefore established for surveillance test various combinations of zones when l'

secondary containment has been violated.

A11ovabic Inleakac.c 7.one Common refuel floor 7680 Unit i reacto zone 15'24 Unit 2 reactor'*.one 1308 Unit 3 reactor zone 14n8 Ecactor 1:u11 ding 12000 Cn!

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ltevi n ion

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BF $T)4.7.C DATA COVER SilEET SI 4.7.C-1 5/J.1/76

[86 SECONDARY C0dTAINMENT CAPABILITY JOW UNIT h 2 OR 3

7_

Date

// 2 Performed By

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Un perpt No Were criteria satisf' ed?

es If no, notify shift engineer.

Yes (explain in If no, was a Limiting Condition for Operation violated?

remarks)

(

No (explain in

[

remarks)

D Verified by Shift Engineer

, Date Reason for test:

Maintenance complete on

) inoperable Another system (

Rgquired by schedule h6 W-!

/

lant condition (explain)-

F5/FL/ M,c-Other (explain)

//- 2 7-N I///

//r, -

Date Results revieweddssist[ ant Shif t Engineer Results Revicu and Aporoyd o"

(1, Cognizant Engineer

/

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Date

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Rescheduled

.Date _ lE -l~ ]Cf ld M QA Staff _

REauu:s I

I inle-kage is excessive if criteria are not satis fied.

(1) Notify Maintenance that t

a

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Page 11 BF SI 4.7.C 5/11/',6 1

Data Stsect SI 4.7.C-1 (Continued)

I Verify and/or Record Initials /Date Component / Process Variabic g

//d2 Normal 3.2 Rx. Bldg. Ventilation System

//-[/-2[

Standby Readiness 3.3 SGTS

'/-3 2-7f 3.4 Main Steam Line Tunnel Temperaturc

$ 150' F yg for units being tested Not in Drywell or 3.5 16A-S34 for units tested Torus Bypass

// D 7

< / 27-)I Currently Calibrated 3.8 FI-65-50 Currently Calibrated

/l 27-7 FI-65-71 PdIC-64-1 (All three units)

Currently Calibrated

//-)'7-

//r27-7I PdIC-64-2 (All three units)

Currently Calibrated O

//

/

Closed and Seals

. [//-MM 3.9 Inboard Equipment Access Lock Doors Inflated

[/47-2 Purge Not Inprocess 3.10 Drywell or Suppression Chamber 3.11 Doors in the following table for the

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tested zone (s) or the number doors hD/) ((",27 /d Closed for all zones.

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l Page 12 BF SI 4.7.C Table 3.11 5/11/76 Data Sheet SI 4.7.C-2 (continued)

Elevation U1RZ U2RZ U3RZ RFz i~

519.0 30 34, 36 40 31 35, 37 41 t

j 541.5 42 43, 44 45 565.0

221

236, # 241

249 255

231

237

250 242 224

238

251 226

229 240 255 231

228 242

232

230 r'

230a L.

$26, # 827

. 583.0

298 593.0

538 497, 501 506

539

540

513 490

541

514 621.25

534 640, 647 651

637

648 d'457 635

649

458 6'9.0 670 672 675 673 664.0 704 700 713 717 724 715 700, 702, 724, 715, 713 705 701 714 725 716 701, 703, 725, 716, 714 712 715 722 7 17 704, 720, 722, 706, 717 706 g, m, m, 70e, m 71e 723 20,

Page 13 BF SI 4.7.C DATA SIEET SI 4.7.C-1 (Continued) 5/11/76 Step Component / Process Variable Verify and/or Record Initials /Date 6.1.1 U1RZ Configuration 6.1.2 U2RZ Configuratioa 6.1.3 U3RZ Configuration Mb 6.1.4 RFZ Configuration 6.1.5 U1RZ a J RFZ Configuration

/[37 7[

0 10 6.1.6 U2RZ and RFZ Configuration

/d M

6.1.7 U3RZ and RFZ Configuration 6.1.8 Reactor Building Configuration N

D,

//-27-7[

6.2.1 1-15 117, TEST Position 2-15-64-117 TEST Position N

3-15 117 TEST Position 14 p

6.2.2 1-HS-64-120 TEST Position

//-27 75/

Q

!V 2-1G-64-120 TEST Position dN M

3-15 120 TEST Position 6.2.3 SGTS Train A START C

/ / "M-8 or SGTS Train B START 7 J' N A

or SGTS Train C START Unit 1 Reactor Zone U-1 Reactor Zone Ventilation Sys.

Shutdown

//,27 Id 1-FCO-64-13 Closed

//-2 7-N 1-Fco-64-14 Closed h //~27-7f.

W/[

//-A7-N 1-FCo-64-42 Closed 1-FCO-64-43 Closed vl///-M-Y l

u9 l

l s

a.r

.4....

l Page 14 BF SI 4.7.C 5/11/76 Data. Sheet S1 4.7.C-1

' Continued)

Verify and/or Record Initials /Date_

Component / Process Varif A b

Step 6.2.3 (Continued)

//J7-$

Open 1-FCO-64-15

// 27 78 Open 1-FCO-64-40 v y M

//-17 76 Open 1-FCO-64-41

/7 / /-17 7f Closed I l-FCO-64-60A

,i 27 77 Closed 1-FCo-64-60B

/ /-2 7-N Closed 1-FCO-64-60C

//-27 7[

Closed 1-FCO-64-60D

//-2 7-7[

Shutdown U-1 Stair Hall Supply Fan

,y Unit 2 Reactor Zone M

Shutdown U-2 Reactor Zone Ventilation Sys f

Closed 2-FCO-64-13 Closed 2-FCo-64-14 Closed 2-FCO-64-42 Closed 2-FCo-64-43 Open 2-FCO-64-15 Open 2-FCO-64-40 W

Open 2-FCO-64-41 Unit 3 Reactor Zone

/M Shutdown U-3 Reactor Zone Ventilation Sys Closed i

3-FCO-64-13 3

f Closed 3-FCO-64-14 I

Closed 3-FCo-64-42 Closed 3-FCO-64-43 I

Open 3-FCO-64-15 Open 3-FCO-64-40 s

g Page 15 BF SI 4.7.C Data saeet SI 4.7.C-1 (Continued) 5/11/76 Step Component / Process Variable Verify and/or Record Initials /Date 6.2.3 (Continued)

Unit 3 Reactor Zone (Continued) 3-FCO-64-41 Open M

-FCO-64-60A Closed 3-FCO-64-60B Closed 3-FCo-64-60C Closed 3-FCO-64-60D Closed I

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' U-3 Stair Hall Supply Fan Shutdown

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6.3.1 1-HS-64-119 TEST Position

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//-27 ?I

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6.3.2 1-HS-64-122 TEST Position

//-177d If 6.3.3 SGTS Train A START or SGTS Train B START

//-)7-7f I

/ cf L

or SGTS Train C START

'M T

Refueling Zone U-1 Area Refueling Zone Vent Sys Shutdown

//~')7 78 G

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g U-2 Area Refueling Zone Vent Sys Shutdown

/ /-17 -7T U-3 Area Refueling Zone Vent Sys Shutdown

/I-37-7 1-FCO'-64-6 Close

//-)737 2-FCO-64-6 Close

//J7 77 3-FCO-64-6 e'ose

//-.27 7I 1-FCO-64-5 Close

//-7~/7[

h 2-FCO-64-5 Close

//-277/l 3-FCO-64-5 Close

/ I-27-7[

1-FCO-64-10 Close

//-d7 7Y 2-FCO-64-10 Close

//-O-7 3-FCO-64-10 Close

//-2)-7[I ep

'I i

or at.....

, Continued) 5/2/78

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Data Shect SI 4.7.C-1 Verify.and/or itecord_ In i ti a l s /n.,t e __

,Cg:tmonent/1'rocens Variabic g

(Cott.inued) f

6.3.3 nefuelin

7. nan (Continued)

W

//-17 7I Close 1-FCO-64-9

/ / _27 ) $

f Close 2-l'CO-64-9

//-377[

Close 3-PCO-64-9 n.2 ~7 7 f Open l-FCO-64-63

//-27-8 Open 1-FCO-64-7

//-)7-78 Close 1-FCo-64-65A

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// ~27-l-FCO-64-65B Clese

//M 7[

1-FCO-64-65C cio,,

/IS)")

l-FCO-64-65D Close

//47 7[

1-FCo-64-44 Open

//-?7-7 8 '

Open 1

- - FCO 54-45'

//J7-7[

Shutdown Equipment Access Lock Exhaust Fan

//-D-7 f il Shutdoun U-l Stair 11all Supply ran

//-l~7-7 [

Shutdown

.U-3 Stair Itall Supply Fan v

i g

i

~ //-)7-7 $

Md sfem 6.4 2 F1-65-50

//-97-7[

Nond sfem h

FI-65-71

[I )] ~]$

Q bD,D _s[cm yy Tt1 g

Revi::fon f

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.v rwr;m.-,[ -.

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L'a CC L/

BF SI 4.7.C Data Shcot SI 4.7.C-1 (Cont inued) 5/2/78 Step Component / Process variable verify.and/or Record Initials /Date 6.43 1-PdIC Rx Zone

_ M "H90

//-D.76 O

Thermometer Rx Zone A4 F f/8/])

//-277f 2-PdIC Rx Zone

, To "H 0

/h

,f)yy g

/ 9Q L /-217 T

Thermometer Rx Zonc 4'A F 4

D 3-PdIC Rx Zoac

,cN "Hg0 Kyy/A

, f-> >. n

Thermoccter Rx Zone

-Ah4DF SWM n_27-7g 1-PdIC Refucling Zone

,3/ "H O &J#//

n.n_W 2

2-PdIC Refueling Zone

-30 "H O

/ /-77 7 I 2

3-PdIC Refueling Zone

%3 / "H O

//-)7.7[

2 r-L

Thermometer Refueling Zone d/A F

//-)2 7[

6.4. 4 All zones 3 -1/4" H O gM h Q fj,7 7,7 7 2

L SE W/).i n.K Direction 1

r

6.4 5 33 ft. level / Windspeed

/ 6N.ph

//47Y

6.4.5.1 Thermometer / Outside temp.

86 F

//,.2 7-T 6.4. 6,

FI-65-50 scfm k

FI-65-71 scfm r

f L

~.

Total scfm i

s Il 6.4. 7 1-PdIC-64-2 Rx Zone t

"H2O U

2-PdIC-64-2 Rx Zone "H O 2

3-PdIC-64-1 Rx Zone "H O 2

l-PdIC-64-1 Refueling Zone "H2O 2-PdIC-64-1 Refueling Zot.c "H O 2

3-PdIC-64-1 Refueling Zone "H O 2

6.4.8 All zones < -1/4"H O

\\/

2

~

6. 4.9 Zones Isolated List

/A 44

[d

Revision 1/

a g

O

-h e

U.

Page 18 Data Sheet SI 4.7.C-1 BF SI 4.7.C 5/11/76 Step component / Process variable verify and/or Record Initials /Date Return to Normal 6.4.11 FI-65-50 scfm FI-65-71 se fm Total scfm 6.4 J2 1-PdIC-64-2 Rx Zone "H2O 2-PdIC-64-2 Rx Zone "H2O a

3-PdIC-64-2 Rx Zone "H2O

[

1-PdIC-64-1 Refueling Zone "H O 2

.2-PdIC-64-1 Refueling Zone "H O 2

e 3-PdIC-64-1 Refueling Zone

" 11 0 2

6.4.13 Remaining zones 5 -1/4"1120

\\ /

i 6.4.14 1-HS-64-117 NORMAL

//-373((

r ff

[

2-IIS-64-117 NORMAL hM 3-11S-64-117 NORMAL

/M

//iD-h 1-IIS-64-120 NORMAL 2-11S-64-120 NORMAL N

3-ils-64-120 NORMAL bh l

-N 1-HS-64-119 NORMAL 1-11S-64-122 NORMAL f[~ ~

H g

~

1 B

[.-

Page 19 BF SI 4.7.C Data Sheet SI 4.7.C-1 5/11/76 l

i Step component / Process Variable Verify and/or Record Initials /Date Return to Normal 6.4. 15 SGTS Fan A 0FF N

FCO-65-3 Closed

~

A-SGTS humidity control heater OFF hk M

r A-SGTS charcoal heater On

//d7lf

~

SGTS Fan B 0FF FCO-65-25 Closed

// J)-7f B-SGTS humidity control heater OFF

/ / 97 '2[

B-SGTS charepal heater ON

[/ 97-)[

l' I

r SGTS Fan C -

OFF V

FCO-65-51 Closed

((

[

C-SGTS humidity control heater OFF M

C-SGTS charcoal heater ON N

L Unit 1 Reactor Zone U-1 Reactor Zone Ventilation System In operation as required 1-FCO-64-13 OPEN

//-M 7[

1-FCO-64-14 OPEN

//-))J$

1-FCO-64-42 OPEN

//-)73[

1-FCC-54 '.3 OPEN

//273[

1-FCO-64-15 Closed

//-)7-7[

1-FCO-64-40 Closed

// D7[

1-FCo-64-41 Closed

// J7]I

//-I7-7!

1-FCO-64-60A Open I

1-FCO-64-60B Open

//1773 [

1-FCC-64-60C Open

//-)) 7

//d77I 1-FCO-64-600 Open U-1 Stair Hall Supply Fan In operatio'n as requir

~,

Page 20 BF S1 4.7.C Data Sheet SI 4.7.C-1 (Continued) 5/11/76 1

Step Component / Process Variable

' Verify and/or Record Initicis/Date 6.4 15 (Continued)

Unit 2 Reactor Zone U-2 Reactor Zone Ventilation System In operation as required 2-FCO-64-13 Open 2-FCo-64-14 open r

2-FCO-64-42 Open r

2-FCO-64-43 Open i'

2-FCO-64-15 Closed 2-FCO-64-40 closed 2-FCO-64-41 Closed k /

I' L

Unit 3 Reactor Zone r

i U-3 Reactor Zone Ventilation System In operation as required N

3-FCO-64-13 Open

~

J 3-FCO-64-14 Open 3-FCo-64-42 Open r

3-FCO-64-43 Open 3-FCO-64-15 Closed 3-FCo-64-40 Closed 3-FCo-64-41 Closed l

3-FCO-64-60A Open 0

3-FCO-64-60B Open 3-FCo-64-60C Open l

3-FCo-64-6'0D Open U-3 Stair 11all Supply Fan In Operation as Required B

O

Page 21 BF SI 4.7.,C Data Sheet SI 4.7.C-1(Continued) 5/2/78 Sten Component /proccc*: Variabic Vet.fy mnd/or itecord Tnitials/n,te 6.4. 15 (Continued)

Itofueling Zone U-l Arca Refueling Zone Vent Sys In Operation as required U-2 Area Refueling Zcnc Vent Sys In Operation as required U-3 Area Refueling Zone Vent Sys In Operation as required N //-27 7f p

b 1-FCO-64-6 Open I I

/ / 2h?[

f 2-FCO-64-6 Open

+c b

/ / / @-)['

3-FCO-05-6 Open

//_J7J[

1-FCO-64-5 Open

//-3)77 2-FCO-64-5 Open r

Open

//J7JI 3-FCO-64-5

/ / -)~/-)/

l-FCO-64-10 Open

// N /[

2-FCo-64-10 Open

/

//W) 7I ~

~

en 3-FCo-64-10 Open 1-FCO-64-9 Open

/ / 07 '7[

//50-7I 2-FCO-64-9 Open

//J/ 7[

3-FCO-64-9 Open 1-FCO-64-63 Close

// 7M

//-8 Y l-FCO-64-7 Close v

//-27)[

.* 1-FCO-64-65A Open

1-FCo-64-65B 0 pin

//. 7.7j/

//-7/ ?[

l-FCo-64-65C Open MS-Y Open

- l-FCO-64-65D

//-17-I Cloco l-FCO-64-44

//-7/-7[

Close 03 vv 1-iCO-04-45 7

Equipment Access T.ock Exhaust Fan In Operation as required U

U-1 Stair lla11 supply Fan In operation as required U-3 Stair llall Supply Fan In Operation an required

.,

ML19274D552

Text

6.3.3 nefuelin

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