Text

Secondary Containment Leak Rate Test Conducted 780320 for 90-day Period.Concludes Secondary Containment Sys Is Capable of Maintaining Greater than 0.25 Inch of Water Vacuum
	ML20104A474
Person / Time
Site:	Browns Ferry
Issue date:	03/20/1978
From:	; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML20104A472	List: ML20104A467; ML20104A474;
References
	NUDOCS 7903190271
	Download: ML20104A474 (25)
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e TENNESSEE VALLEY AUTHORITY Division of Power Production SECONDARY CONTAINMENT

. LEAK RATE TEST BROWNS FERRY NUCLEAR PLANT UNIT 2 CONDUCTED MARCH 20, 1978 h

e SUBMITTED TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION PURSUANT TO FACILITY OPERATING LICENSE NUMBER DPR-52 '

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1.0 - Browns Ferry Nuclear Plant Unit 2 Secondary Containment 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 2 secondary containment pursuant to Technical Specification 4.7.C.1.c prior to the first refuelin. outage.

3.0 Procedure The attached surveillance instruction, SI 4.7.C-1, outlines the procedures followed during secondary containment leak rate testing.

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

1-(1) Standby gas treatment system flow rate: 8700 scfm (2) Reactor building differential pressure:

Unit 2 reactor zone:

-0.53" H O 2

Refueling zone average:

-0. E 8" H O 2

(3) Wind Speed: 17.1 mph (4) Wind direction: southwest 5.0 Analysis and Interpretation Technical Specification 4.7.C.1.c requires that seconda;y 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 12000 scfm shall be demonstrated at each refueling outage prior to refueling.

Following shutdown of Unit 2 on March 18, 1978, the secondary contain-ment for the common refuel zone and the Unit 2 reactor zone were leak rate tested.

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

These two zones were isolated frcm the Unit 1 and Unit 3 reactor zones.

Appendix A to SI 4.7.C gives the allowable inleakage per secondary containment zone documented during preoperational testing. Assuming a total allowable inleakage of 12000 sefs, it is shown in Appendix A that the allowable inleakage for testing the refuel zone and Unit 2 reactor zone in combination under calm vind conditions is 8988 scfm. From the data -taken during this test it is shown that assuming a total combined inleakage of 8700 scfm in the Unit 2 reactor zone and the refuel zone that the secondary containment system is capable of maintaining greater that 0.25 inches of water vacuum. These results fulfill the requirements of Technical Specification 4.7.C.l.c.

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Peg 2 1 BF SI 4.7.C l

11/7/78 1SI 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 Re f eren,c,a(_

Surveillance Requirements l

2 At each refueling out-4.7.C.l.c Demonstrate the capability of secondary con-i age prior to refueling tainment to maintain -1/4" water pressure with a system inleakage of not more than 12,000 cfm under caLa wind conditions 15 aph. SI 4.7.C-1 will be used to natisfy this requirement.

Any time the integrity 4.7.C.2 Isolate the affected zone from the other zones of one zone has been and demonstrate secondary containment capabi-violated 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 I

inde, pendently. These zones are the unit I reactor zone (UlRZ), the unit 2 Reactor zone (U2RZ), the unit 3 reactor zone (U3RZ), and the re' fueling 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, l

L.

or A and B, or a single fan to demonstrate that at a flow of i 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.

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Pega 2 BF SI 4.7.C 5/11/76 SI 4.7.C - Secondary Containe.ent Description (Continued)

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 less than the allowable flow and verifying the static pressure of the tested zone (s) is -1/4" H O or less. This procedure vill nor-2 mally be used to test the secondary containment capability of the reactor building prior to refueling.

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i 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.

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Page 3 BF SI 4.7.C 5/11/76 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 containannt capabili y to maintain -1/4" H O with a system in-leakage 2

of < 12,000 cfa.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

47W610-64 15 45N614-6 5

47W610-65 15 3.

PREREQUISITES 3.1~

Notify each unit operator and assistant shift engineer such that they may comenmicate and be aware of the ventilation and SGTS status during this test.

3.2 Verify that the reactor building ventilation sy' stem is in a normal operational status per OI 30.

3.3 Verify that the SGTS is in standby readiness per 01 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 DRTWELL BYPASS or TORUS BYPASS on each unit or the unit that is to be tested.

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Peg 2 4 BF SI 4.7.C 5/11/76 SI 4.7.C Secondary Containment capability 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 SGTS building to adjust 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 within a current calibration period.

FI-65-50 1-PdIC-64-2 FI-65-71 2-PdIC-64-2 1-PdIC-64 3-PdIC-64-2 2-PdIC-64-1 3-PdIC-64-1 4

3.9 Verify the inboard equipment access lock doors closed with seals inflated.

3.10 Verify that a drywell or suppression chamber purge is not 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 Sheet SI 4.7.0-1) for all four zones.

4.

PRECAUTIONS 4.1 Do not allow the main steam line tunnel temperature on any unit in operation to exceed 160* F.

If this temperature is approached to within 10* F, stop the test and reestablish normal ventilation per OI 30 or provide another means for ventilating the main steam line tunnel to b

prevent a unit trip (trip point is 186* F).

4.2 Attempt to restrict testing time to 30 minutes.

5.

LIMITATIONS AND ACTIONS

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SI 4.7.C Secondary Containment Capabilities j-6.

PROCEDURE 6.1 Initial and perform the indicated sections on the configuration to e

be tested on Data Sheet SI 4.7.C-1 and perform steps indicated below.

6.1.1 U1RZ - Perform section 6.2 and section 6.4.

l 6.1.2 U2Rz - Perform section 6.2 and section 6.4.

i 6.1.3 U3RZ - Perform section 6.2 and section 6.4.

6.1.4 RFZ - Perform section 6.3 and section 6.4.

6.1.5 U1RZ 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 - Perform sections 6.2, 6.3 and section 6.4.

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

6.2 Manual Isolation of a Reactor Zone NOTE: HS-64-117. 8S-64-120, HS-64-119, & RS-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." (Inboard and common valves) 6.2.2 Place HS-64-120 (Panel 9-25) in the TEST position for the reactor zone to be isolat'd.

(Outboard valves) e 6.2.3 Start SGTS trains A and B in accordance with 0165 and verify actions and/or take data as indicated on Data Sheet SI 4.7.C-1 i

for the reactor zone that is being isolated.

NOTE: If a reactor zone is the only zone to be isolated, so to Section 6.4 and if the refuel zone is to be isolated complete Section 6.3 before going to 3

Section 6.4.

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l 6.3 Manual Isolation of the Plant Refueling Zone I~

6.3.1 Place HS-64-119 (Panel 9-25-1) in the TEST position.

(Inboard ~

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and common valves) 1 l

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Pag 2 6 BF SI 4.7.C 5/2/78 SI 4.7.C Secondary Containment Capabilities 6.

PROCEDURE (Continued) 6.3 Manual Isolation of the Plant Refueling Zone (Continued) 6.3.2 Place HS-64-122 (Panel 9-25-1) in the TEST position.

(Outboard valves) 6.3.3 Start SGTS trains A and B, if not already running, in accordance.

with OI 65 and verify actions and/or take data as indicated on Data Sheet SI 4.7.C-1 for the refueling zone.

6.4 Secondary Containment Capability NOTE: This section is to verify that the secondary containment is capable of maintaining a -1/4" E 1 with a system inleakage of $ 12,000 cfm for the entire reactor building or allowable in-leakage for one or more zones.

6.4.1 Adjust the total flow indicated on FI-65-50 and FI-65-71 (Panel 9-25-2) to 11,500 cfm for entire reactor building or less than allowable flow for one or more zones as shown in Appendix A by closing a SGTS fan 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 and the air temperatures at the differential pressure indicator locations.

Zone Instrument Panel U1RZ 1-PdIC-64-2 1-25-213 U2RZ 2-PdIC-64-2 2-25-213 U3RZ 3-PdIC-64-2 3-25-213 U1RFZ 1-PdIC-64-1 1-25-219 U2RFZ 2-PdIC-64-1 2-25-215 U3RFZ 3-PdIC-64-1 3-25-215 6.4.4 Verify all four zones static pressures are 1 -1/4" H 0.

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Paga 7 BF SI 4.7.C 5/2/78 1

SI 4.7.C Secondary containment Capabilities 1

6.

PROCEDURE (Continued) 6.4 Secondary Containment Capability (Continued) 6.4.5 Record the wind direction and velocity from the 33 f t. level windspeed.

6.4.5.1 Record air temp. outside reactor building ac ground level indicator.

NOTE: If all four zones static pressures are ;E -1/4" H 0 7

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 2

requirements the following steps must be completed.

2 NOTE: Check to assure reactor building is isolated.

6.4.o Adjust the total flow indicated on FI-65-50 and FI-65-71 i

(Panel 9-25-2) to 12,000 cfm or allowable flow from Appendix A for one or more zones by opening the fan discharge damper or it may be necessary to start another fan and adjust its i

discharge damper.

t-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 followieg ststic pressures.

Zone Instrument Panel U1RZ 1-PdIC-64-2 1-25-213 U2RZ 2-PdIC-64-2 2-25-213 U3RZ 3-PdIC-64-2 3-25-213 U1RFZ 1-PdIC-64-1 1-25-219 U2RFZ 2-PdIC-64-1 2-25-215 U3RPZ 3-PdIC-64-1 3-25-215

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6.4.8 Verify all four zones static pressures are 1 -1/4" H 0.

2 NOTE: If all four zoner static pressures are j[ -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 0 static pressure requirement the following ste s 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 on 2

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 Flows.

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k P gs 8 BF SI 4.7.C 5/11/76 SI 4.7.C Secondary Containment capabilities 6.

PROCEDURE (Continued) 6.4 Secondary Containment Capability (Continued) l 6.4.10 (Continued)

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

6.4.11 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.

6.4.12 Record the following static pressures.

Zone Instrument Panel U1RZ 1-PdIC-64-2 1-25-213 U2RZ 2-PdIC-64-2 2-25-213 U3RZ 3-PdIC-64-2 3-25-213 U1RFZ 1-PdIC-64-1 1-25-219 U2RFZ 2-PdIC-64-1 2-25-215

)

U3RFZ 3-PdIC-64-1 25-2 15 6.4.13 Verify the remaining zones static pressures are ji-1/4" E 0.

2 NOTE: If these zones static pressures are j[ -1/4" H 0 9

this will 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 TE.9T position l

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.

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Pag 2 9 BF SI 4. 7. C 5/2/78 Appendix A t

Secondary Containment h ak Rate Test Criteria i

l During preoperational testing for unit 3 the following in-leakage rates at

-1/4" H O static pressure were documented.

2 Documented Inled.aae Percentame Common refuel floor (units 1, 2, & 3) 6250 641 i

Unit i reactor zone 1239

-12.7%

Unit 2 reactor zone 1064 10.9%

Unit 3 reactor zone 1211 12.4%

iotal secondary containment 9764 CFM 100%

Leak 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 being j

tested, the total allowable inleakage will be based on preoperational testing and will be based 3.1 the sum of the allowable.inleakages for the zones being tested. Af ter a secondary containment violation, the total inleakage must not be greater than the total of the allaeable inleakage for each individual zone as indicated below.

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The technical specifications require the total secondary containment inleakage t

l to be less than 12,000 cfm at -1/4" differential pressure. The following are,

I therefore established for surveillance testing various combinations of zenes when' secondary containment has been violated.

Zone Allowable Inleakane Cosuson refuel floor 7680 Unit i reactor zone 1524 Unit 2 reactor zone 1308 Unit 3 reactor zone 1488 Reactor Building f 12000 CFM

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Page 10 BF SI 4.7.C DATA COVER SHEET SI h.7.C-1 5/11/76 SECONDARY CONTAINMENT CAPAB'ILITY UNIT 1,h0K3 3/se[vr A m 9/.o 7 ems k Date l

Performed By Unit Operator

" yere criteria satisfied?

des No i

If no, notify shift engineer.

If no, was a Limiting Condition for Operation violated?

Yes (explain in remarks)

No (explain in j

remarks) 1 Verified by Shift Engineer

, Date Reason for test:

Maintenance complete on

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Another system (

) inoperable Required by schedule Plant condition (explain) 1 l

Other (explain)

I 3 - d0 ~ 7 Results reviewed' tb [

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Date

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1stant Shift Enginae Results Review and Approval f ^'

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B.f '1 b

. (1) Cognizant Engineer Date l

Rescheduled 3-7[

QA Staff l/)W\\

Date REHARKS Aerr

LJ,no see.ec) 12.1 m pH i-s t

i (1) Notify Maintenance that inlaskage is excessive if criteria are not satisfied.

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Pag 3 11 BF Si 4.7.C 5/11/76 Data Sheet SI 4.7.C-1 (Continued)

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Verify and/or Record _ Initials /Dste

' Component / Process Variable jteg

_t,e

< ~.J

-Tv7'/t Normal 3.2

, Rx. Bldg. Ventilation System

/.7/7-7f Standby Readiness 3.3 SGTS

!8'/f27 3.4 Main Steam Line Tunnel Temperature 4[150'F

/

for units being tested

/

Not in Drywell or M N / f-/7. Jg 3.5 16A-S34 for units tested Torus Bypass 3.8 FI-65-50 U2. 9-u ct-

. Currently Calibrated [cc.

340 /1r FI-65-71

02. 4-7.5 C E-Currently Calibrated 3//9 /3 s' ou :G 2*9

[0 f//9 /1/_

PdIC-64-1 (All three units) RFF g,pf Currently Calibrated a,

f//9/72' PdIC-64-2 (All three units) 25-Is"b Currently Calibrated

<x,

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16 (h)

Closed and Seals-

.f 3.9 Inboard Equipment Access Lock Doors

/t/ W

Ipflated, 3 /9-7 3.10 Drywell or Suppression Cham'er Purge Not Inprocess b

3.11 Doors in the following table for the tested zone (s) or the number doors N

J f/g Clos'ed for all zones.

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Page 12 BF SI 4.7.C Table 3.11 5/11/76

,7 Data Sheet SI 4.7.C-2 (continued) ylu Y

i Elevation U1RZ U2RZ U3RZ RFZ 34,!36 /

40 519.0 '.

30 31 35;

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41 s.*s.~F er n

i 42 3

45 i

e 541.5 i

WW, I

(*

249 255 [

h 565.0

221

231

/ # 237 vYA

250 24 2 /

U 3,v I

251 226 i/

.e # 238diff "b 224

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40 240' 9 # '

255 231./

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229 v

i f228

/ 242 95 W l%

0% W 9232 tw

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230 g,{ tec A

230s 583.0

298

,fondl iS26,f827

/ k 46 5

593.0

538

f. 7497,'* 50173.

506

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539

540 /

513

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I 0

490

541 p.314 621.25

$34 46f d

651

637

648 /

. f'657 g

2., 64) h

458 635

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72 95 675 g\\'

639.0 670 673 /6 700[702[724[715 664.0 7049 700 713 717 724 715 713 701 [ 703 725[716 714' 705 701/

714 725 716

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s 706 712 715 722-717 704, 720, 722,'$706, 717

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, 721, 723, 708, 707 707 7og j

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t Page 13 Br SI 4.7.C DATA SHEET SI 4.7.C-1 (Continued) 5/11/76 Steg,

component / Process Variable verifv and/or Record

Initials /Date

/*/4 6.1.1 U1RZ Configuration N4 6.1.2 U2RZ Configuration

A

~6.1.3 U3RZ Configuration g4 6.1.4 RFZ Configuration r

A/M 6.1.5 51RZ and RFZ Configuration 8

3 #7[jfg-6.1.6 U2RZ and RFZ Configuration dA 6.1.7 U3RZ.and RFZ Configuration

//4 6.1.8 Reactor. Building Configuration TbSTPosition

4 6.2.1 1-HS-% -117.

2-HS-64-117.

TEST Position M

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3-RS-64-117 TEST Position er/4 6.2.2 1-HS-64-120

. TEST Position s4 2-HS-64-120 TEST Position 3-RS-64-120.

TEST Position

4-e 6.2.3 SGTS Train A START A/d or S'GTS Train B START

4

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AD or SGTS Train C START-I' nit 1 Reactor Zone U-1 Reactor Zone Ventilation Sys.

Shutdown

4 1-FCO-64-13 Closed f

1-FCo-64-14 Closed 1-FC0-64 42 Closed 1-FCo-64-43 Closed

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BF'SI 4.7.C 5/11/76 Date Sheet SI 4.7.C-1

' Continued)

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Initials /Date_

j Step,

Component / Process Variable i

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6.2.3 (Continued)

A/d 1-FCO-64-15 open i

1-FCO-64-40 open-

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1-FCO-64-41 I

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1-FCO-64-60A

. Closed i

Closed i

1-FCO-64-60B 1-FCo-64-60C

, Closed i

t Closed 1-FCO-64-60D U-1 Stair Hall Supply Fan Shutdown 4

Unit 2 Reactor Zone l

D U-2 Reactor Zone Ventilation Sys Shutdown,

Closed ~

C6-2-FCo-64-13 M

-Closed 2-FCO-64-14 Closed "M

4 2-FCO-64-42

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Closed F_

7 4#C 2-FCo-64-43 G 84 at.C.

i Open i

2-FCO-64-15 2-FCO-64-40 Open g

AKJ2-l TA 2-FCO-64-41 Open i

Unit 3 Reactor Zone i

/f/4 l

U-3 Reactor Zone Ventilation Sys

- Shutdown f

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Closed 3-FCO-64-13 Closed 3-FCO-64-14 Closed 3-FCO-64-42 Closed 3-TCo-64-43 Y

3-FCo-64-15 Open t

3-FCO-64-40 Open

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l Page 15 BF SI 4.7.C 5/11/76 Data Sheet SI 4.7.C-1 (Continued)

Verify and/or Record Ynitials/Date g. Component / Process variable _

6.2.3 (dontinued)

, Unit 3 Reactor Zone _ (Continued) 8

//4 Open -

3-FCO-64-41 t

i

[

Closed 3-FCO-64-60A Closed

]

3-FCO-64-60B Closed 3-FCo-64-60C

. Closed 3-FCO-64-60D

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n Shutdown U-3 Stair Hall Supply Fan M

TEST Position 3

6.3.1 1-HS-64-119 TEST Position 6.3.2 1-BS-64-122' (g*$ _ MCs START 6.3.3 SGTS Train A

'// A START or SGTS Train B

-/M

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START or SGTS Train C.

6 Refuelimt Zone

~

Shutdown

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U-1 Area Refueling Zone Vent Sys -

M Shutdown U-2 Area Refueling Zone Vent Sys Shutdown U-3 Area Refueling Zone Vent Sys M

Close 1-FCO-64-6 Close I

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2-PCO-64-6 Close 3-FCO-64-6 f

Close 1-FCO-64-5 Close i

I 2-FCO-64-5

{

CM i

Close w

3-FCo-64-5 Close 1-PCO-64-10 i

Close 2-FCO-64-10 Close 3-FCO-64-10

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Page 16 BF SI 4.7.C Data Sheet SI 4.7.C-1 (Continued) 5/11/76 Step Comoonent/ Process Variable Verify and/or Record Initials /Date 6.3.3 (Continued)

Refueling Zone (Continued)

Close!

if M 1-FCO-64-9 4

bN.

2-FCO-64-9 Close f

W 3-FCO-64-9 Close 1-FCO-64-63 open F

{ hC-D-MC -

M 1-FCO-64-7 open p 3& 1-FCO-64-65A Close TC.

3& 1-FCo-64-65B Close

3& 1-FCO-64-65C Close

3& 1-FCO-64-65D Close k k_

Open 1-FC0 64-44

-l-FCo-64 open

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Equipment Access Lock Exhaust Fan Shutdown D

, U-1 Stair Hall Supply Fan Shutdown NC U-3 Stair Hall Supply Fan Shutdown Ne kuipmed SS c.:<-<

ou I

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f*2 do efem 6.4 2 FI-65-50 3/tlW 3 $~OD stem F1-65-71

&.9fftl W OY DO sica Total

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P.sge 17' BF SI 4.7.C Data Sheet SI 4.7.C-1,(Continued) 5/11/76 t

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Verify and/or Record,Ittitials/Date

. Component / Process variable M

b Nb "H O 2

6.43 1-PdIC Rx Zona j[d /!/T[7

- O, S3 "H O 2

'2-PdIC Rx Zone Mk "H O 2

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3-PdIC Rx Zone

/!/9[g

- O.48 "H O 2

" ' - PdIC Refueling Zone

O.4i "H O M J ff 2

2-PdIC Refueling Zone M I//9/[

- 0, h "H O 2

3-PdIC Refueling Zone gg

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6.4. 4 All zones < -1/4" B 0 2

.SW

.4e Direetion M.,...

/ "#. I aph 6.4 5 IR-90-102 sefm Mh 6.4. 6.

FI-65-50 scfm I

FI-65-71 scfm Total "H2O 6.4. 7 1-PdIC-64-2 Rx Zone 0

"H2.

'~

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

3-Pd';C-64-1 Rx Zone

"H2O i

1-PdI".-64-1 Refueling Zone t

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2.PdIC-64-1 Refueling Zone

~

"H O 2

3-PdIC-64.1 Refueling Zone 6.4.8 1.11 zones,< -1/4"H 0 2

List 6.4.9 Zones Is: lated

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c'

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L c

P g3 18 Data Sheet SI 4.7.C-1 BF SI 4.7.C 5/11/76 Step Component / Process variable verify and/or Record Init'ials/Date Return to Normal 6.4 11

"'FI-65-50 scfm

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FI-65-71 scfm Total scfm

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6.412 1-PdIC-64-2 Rx Zone "H2O 2-PdIC-64-2 Rx Zone "H2O 3-PdIC-64-2 Rx Zone "HgG 1-PdIC-64-1 Refueling Zone "H O 2

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

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

Y 6.413 Remaining zo'nes < -1/4"H2O

~

Mb 6.4.14 1-HS-64-117 Natu%L 2-HS-64-117 NORMAL h

kC Mb 3-HS-64-117 NORMAL d4 1-HS-64-120 NORMAL M N E C--

2-BS-64-120 NORMAL M

3-RS-64-120 NO3 MAL 1-ES-64-119 NORMAL P kk6 1-HS-64-122 NORMAL M A-f O*

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., g,,,.

4.,,, u m,,..g,.,,,, g,...g,

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BF SI 4.7.C Data Sheet SI 4.7.C-1 5/11/7,6 Step Component / Process Variable Verify and/or Record. Initials /Date Return to Normal kC 6.4. 15 SGTSFank 0FF FCo-65-3 Closed A4.C A-SGTS humidity control heater dFF

/lllC.

A-SGTS charcoal heater CN i

i)1./LC -

d.h SGTS Fan B 0FF FCo-65-25

, Closed

/>ti Ad

/

B-SGTS. humidity control heater OFF

.B-SGTS charcoal. heater CN A/84-SGTS Fan _C l,,,,_,

OFF 6/h FCO-65-51 Closed' S.) /4-C-SGTS humidity control heater OFf A/#4-C-SGTS charcoal heater.

ON Alb

~

Unit 1 Reactor Zone U-1 Reactor Zone Ventilation System In operation as required

'Nb 1-PCO-64-13 OPEN i

1-FCO-64-14 CFEN 1-FCO-64-42 OPEN 1-FCO-64-43 OPEN 1-FCO-64-15 Closed 1-FCO-64-40 Closed 1-FCO-64-41 Cissed 1-FCO-64-60A Open 1-FCO-64-60B Open 1-FCO-64-60C Open p-1-FC 64-60D Open U-1 Stair Hall Supply Fan In operation as required

J Srr: ..ma t.,q.:,.e y.-n;.g.;.7p.;7;gn_ td,,gg. 7.y,g,3.;..g.gg.-gg,ggggg.,g.a y,

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=-

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

verify and/or Record Initials /Date Component / Process Variabla_

M,

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6.4 15 (Continued) i i

Unit 2 Reactor Zone U-2 Reactor Zone Ventilation System In operation as required I

MC -

Open 2-FCO-64-13 ATL C /

l 2-FCO-64-14' Open MC/

.Open 2-FCO-64-42 W

0 pen 2-FCO-64-43

/L/LC' Closed 2-FCo-64-15 N(l U Closed 2-FCO-64-40 d/d _

Closed 2-FCO-64-4i l

Unit 3 Reactor Zone _

5 3 Reactor Zone Ventilation Systcc In operation as' required h4 Open 1

3-FCo-64-13 I

open 3-FCO-64-14 1

3-FCO-64-42'

}

Open 3-FCO-64-43, Open

~

Closed 3-FCO-64-15 F

closed 3-FCo-64-40 Closed 3-FCO-64-41 I

Open 3-FCO-64.-60A.

Open 3-FCO-64-60B.

Open 3-FCO-64-60C r

open 3-FCO-64-60D In Operation as Required U-3 Stair Hall Supply Fan m.

'N O

(.,.

1, z-Page 21 BF SI 4.7.C l

Data Sheet SI 4.7.C-1(Continued) 5/11/76 I

l Steo Component / Process Variable Verify and/or Record Initials /Date 98 -

6.4.15 '.(Continued) i Refuelina Zone U-1 Area Refueling Zone Vent Sys In Operation as required Mb

' ~

U-2 Area Refueling Zone Vent Sys In Operation as required _ bh,,, _

' '1F3 Area Refueling Zone Vent Sys In Operation as required

-b M

1-FCO-64-6 Open 2-FCO-64-6 Open

~bpen 4(LC, 3-FCo-65-6 Mfl.6 1-FCO-64-5 Open Open Art C

' ~

2-FCO-64-5.

M6.--.

Open 3-FCO-64 --

Aff_.C 1-FCo-64-10 Open

.e-h 2-FCo-64-19.-

.Open MC 3-FCO-64-10 Open -

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re.

~

1-FCo 64-9 Open 2-FCO-64-9 Open

,, M_ O, l%8 C--

3-FCO-64-9 Open D

q Close 1-FCo-64-63 h

Close 1-FCo-64-7 l

'3& 1-FCO-64-65A Open E

b i

36 1-FCO-64-65B

.Open b

3& 1-FCo-64-65C open b

3& 1-FCO-64-65D Open MC-Close 1-PCO-64-44 b

Close 1-FCo-64-45' Equipment Access Lock Exhaust F,an In Operation as required _

In Operation as required s#/ C U-1 Stair Hall Supply Fan U-3 Stair Hall Supply Fan In Operation as required

UT/ Ell. LANCE INSTRUCTION DATA SliEET

. TOLLOWUP DATA REQUEST FOR INCOM,PL.E..,

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LF8 i

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- DATE

L St 2 O 4 7 has deficiencies o the data sheet (s) as described below.

/' N dd Date

~

Followup data reviewed and approved,-

('

Cognizant Engineer I (

Corrective Action Item No..

Deficiency 1

l G.a. 4 u L.4.c L

with cA..

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$ (1) Corrective ' action canst be filied o tt cy.plicitly, additici. 3.' tie r s or c:.r. : t., YJ may be attached, or references to locuincuts, such as nulintensnee historj records er troubic reports, that contain explicit inforwition so that cos:::en-motic failur s. cza [. - be evaluated end quality ass'.'rance,2sta'21it.hed. (2) Signature and dstc of persen resol /in:; deficiency required for cach itett. ~ \\ j 2.

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