ML18024B013

Secondary Containment Leak Rate Test

ML18024B013
Person / Time
Site:	Browns Ferry
Issue date:	08/22/1979
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18024B015	List: ML18024B013 ML19249D796
References
NUDOCS 7909250416
Download: ML18024B013 (67)

Text

TENNESSEE VALLEY AUTHORITY Division of Nuclear Operations SECONDARY CONTAINMENT LEAK RATE TEST BROMNS FERRY NUCLEAR PLANT UNIT 3 CONDUCTED AUGUST 22, 1979 DxhokP ~, <>~

Csutretd 7P> < ~>~~/8 BN~PNI RMNNQQY90CQlfjg Submitted to The United States Nuclear Regulatory Commission Pursuant to Facility Operating License Number DPR-68

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1.0 Browns Ferry Nuclear Plant, Unit 3 Secondary Containment Leak Rate Test Report 2.0

~Pue eee This report describes the results and analysis of the test data taken during leak rate testing of the Browns Ferry Nuclear Plant Unit 3 secondary containment pursuant'o Technical Specification

'4.7.C.l.b prior to each refueling outage.

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

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

(1)

Standby gas treatment system flow rate:

8,600 scfm (2)

Reactor building differential pressures:

Unit 3 reactor zone:

-0.25" H20 Refueling zone average:

-0.25" H20 (3)

Wind Speed:

4 mph (4)

Wind Direction:

South

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5.0 Anal sis and Inter retation Technical Specification. 4.7.C.l.b 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 scfm shall be demonstrated at each refueling outage prior to refueling.

Following shutdown of Unit 3 on August 20, 1979, the secondary contain-ment for the common refuel zone and the Unit 3 reactor zone were leak rate tested.

The results show that Unit 3 reactor zone and refuel I'ones are capable of maintaining <-.25" H 0 with less than the allowed 2

flow.

TENNESSEE VALLEY AUTHORITY BROWNS PERRY NUCLEAR PLANT SURVEILLANCE INSTRUCTION 4.7 AC SECONDARY CONTAINMENT UNIT 1, 2, OR 3

",Approved:

Date:

Plant Superintendent August 21, 1979 General Revision

l

P.".ge 1

B: SI 4.7.C 8/ 21/79

. -- ~ly with the requirements of portions of technical a =-

.'ng table lists the requirements satisfied by this

-pec.

ed Surveillance Requirements

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b Demonstrate the capability of secondary con-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.

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Isolate the affected zone from the other zones and demonstrate secondary containment capabi-lity to maintain 1/4" water pressure under calm wind conditions using the SGTS.

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

into four zone%,

each of which can be isolated

=:-=-=== =he unit 1 reactor zone (U1RZ), the unit 2 Reactor

-one (U3RZ), and the refueling zone(RFZ) which is

- written te nse the SGTS fans A and C,

S and C,

==-= = =mnonstrate that at a flow of < 12 000 cfm all

.-.==- =-= zones can be maintained at a static pressure "nditions.

Hanual isolation of the zones will be

=='p prevent steam line tunnel tempera=ure increases,

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Page 2

BF SI 4.7.C 8/21/79 SI 4.7.C Secondar Containment 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, adgust-ing the flow to less than the allowable flow and verifying the static pressure of the tested zone(s) is -1/4" H20 (or less as required by Table 1 for varying wind speeds).

This procedure will normally be used to test the secondary containment capability of the reactor building prior to refueling.

Note; Wind speed and direction measurements will be taken from the site meteorological tower instrumentation and will be assumed to be acceptably accurate representation for the conditions at the reactor building.

CAUTION:

This testing should be limited to 30 minutes if at all possible since the main steam line tunnel temperatures may trip an operating unit.

Page 3

BF SI 4.7.C 8/21/79 SI 4.7.C Secondar Containment Ca abilit PURPOSE This procedure is used to isolate the zones to be leak tested and to verify secondary containment capability to maintain -1/4" H20 with allowable system 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 45N614-5 5

45N614-6 5

Number 47W610-64 47W610-65 Revision 2.3 FSAR Volume 5, Section 12,2.2.9 3.

PRERE UISITES 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.

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'ain steam line tunnel temperature is not 0

above 150 3.5 Verify switch 16A-S34 is not in DRYHELL BYPASS or TORUS BYPASS on each unit or the unit that is to be tested.

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SI 4.7.C-l Secondar Containment Ca abilit Page 4

BF SI 4.7 AC 8/21/79 3.6 Station a man at the Reactor Building 480V Vent Board in case any breakers need to be reset duxing this test, and in the SGTS building to adjust manual dampers.

I 3.7 Set up communication between panel 9-25-1 and 9-25-2 and the following s

panels:

25-219-1 25-215-2 25-215-3 25-213-1 25-213-2 25-213-3 fdl" FI-65-50 FI-65-71 1-PdIC-64-1 2-PdIC-64-1 3-Pdlc-64-1 3.8 Verify the following process instruments to be within a cuxrent l

calibration period.

1-PdIC-64-2

'-PdIC-64-2 3-PdIC-64-2 3.9 Verify the inboard equipment access lock doors closed 3.10 Verify that a drywell or suppression chamber purge is planned during this test.

with seals inflated.

not in 'process or 3.11 Verify on Data Sheet SI 4.7.C-1 that each of the doors are closed, for the i

respective zones to be tested or the doors indicated by number~~'(dee Table s

3.11 of Data Sheet SI 4.7.C-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 prevent a unit trip (trip point is 186 F).

4.2 Attempt to restxict testing time to 30 minutes.

5.0 LIMITATIONS AND ACTIONS If this test is being performed prior to refueling, notify the Results Section Supervisor or Reactor Engineer to review results prior to y I,~

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BP SI 4.7 C

8/21/79 SI 4.7.C-l - Secondar Containment Ca abilities 6.

PROCEDURE 6,1 Initial and per orm e

n d

f th indicated sections on the configuration to be tested on Data S ee h t SX 4 7.C-l and perform steps indicated

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below.

Sections an 6 12 d 6 13 must be performed in addition to the sections listed below for the applicable zone.

6.1.1 UlRZ - Perform section 6.2 and section 6. 5.

6.1.2 U2RZ - Perform section 6.2 and section 6. 6.

6.1.3 U3RZ - Perform section 6.2 and section 6.7.

6.1.4 RFZ

- perform section 6.3 and sec iont'.8.

6.1.5 U1RZ and RFZ - Perform sections 6.2, 6.3 and sec d section 6.9.

6.1;6 U2RZ and RFZ - Perform sections 6.2, 6.3 and section 6.10.

6.1.7 6.1,8 U3RZ and RFZ >> Perform sections 6.2, 6.3 and section 6.11.

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

nual Xsolation of a Reactor Zone - Perform only as req p

uired er section 6.1.

6.2 Manual Xso at on o a

NOTE:

HS-64-117, HS-64-120, HS--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

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reactor zone to be isolated.

{Inboardand common valves) 6.2.2 Place HS-64-120

{Panel 9-25) in the TEST position for the

6. 2.3 reactor zone to* be isolated.

(Outboard valves)

Start SGTS 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-l for the reactor zone that is being isolated.

6. 3 Manual Isolation o t e an f

h Pl t Refueling Zone - Perform only as required per section 6.1.

6 3 1

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

(In oar

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4 and common valves)

H I,

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BF ST, 4.7 AC 8/21/79 SI 4.7.C Secondar Containment Capabilities 6.

PROCFDURE (Continued) 6.3 ltanual Isolation of the Plant Refueling Zone (Continued) 6.3.2 Place HS-64-122 (Panel 9-25-1) in the TFST 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-l for the refueling zone.

6.4 Secondary Containment Capability - Reactor Building (All Zones)

SMOTE:

This section is to verify that thc secondarv containment is capable of maintaining a -1/4" H20 with a system inleakage oi ~ 12,000 cfm,for the entire reactor buf.ldinp 6.4. 1 Adjust, the total flow indicated on FI-65-50 and FI-65-71.

(panel 9-25-2) to < 12,000 cfm for entire reactor building by closing a SGTS fan discharge damper or if two fans are running it may be necessary to shut one fan off.

NGTE:

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.

'.4.3 R cord the following sLatic pressures and the air temperatures at the differential pressure indicator locations.

Zone Instrument

'anel UlRZ U2RZ U3RZ 01RFZ U2RFZ U3RFZ 1-PdIC-64-2 2.-PdIC-64-2 3-PdIC-64-2 1"PdIC 1 2-PdIC" 64-1 3-PdIC 1 1-25-213 2-25-213 3-25-213 1-25-219 2-'75-215 3-25-215 6.4. 4 6.4.5 Record the wind direction (XR-90-102-2) and velocity (XR-90-102-1) at the 33 ft. level.

Instrumentation is located behind Unit 2 Panel 9-4.

Also, record the air temperature outside the reactor building at ground level.

Verify all zones static pre'ssures are less than the value listed in Table 1 for wind velocity.

J A

k I"

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BF SX 4.7.C 8/21/79 SI 4.7.C-1

- Secondar Containment Ca abilities

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6.

PROCEDURE

{Continued) 6.5 Secondary Containment Capability - U1RZ only

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NOTE:

This section is to verify that the secondary containment is capable of maintaining a -1/4" H 0 with a system inleakage of 2

< 1,524 cfm for the unit 1 reactor zone.

6.5.1 Adjust the total flow indicated on FX-65-50 and FX-65-71 panel 9-25-2) to ( 1,524 cfm 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 befoxe the next step.

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

6.5.3 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

/

6.5.4 Record the wind direction (XR-90-1024) and velocity {XR-90-102-1) at the 33 ft. level.

Instrumentation is located behind Unit 2 Panel 9-4. Also, xecord the air temperature outside the reactor 6.6 building at ground level.

Secondary Containment Capability - U2RZ only NOTE:

This section is to vexify that the secondary containment is capable of maintaining a -1/4" H20 with a system inleakage of

( 1,308 cfm for the Unit 2 reactor zone.

6.6.1 Adjust the total flow indicated in FI-65-50 and FI-65-71 (panel 9-25-2) to C 1,308 cfm by closing a

SGTS fan dishcarge damper or if two L'ans are running it may be necessary to shut one fan off.

NOTE:

Let the flow stabilize for 5 minutes before the next step.

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V BF SI 4.7.C 8 i21/79 SX 4.7.C Seconda Containment Ca abilities 6.

PROCEDURE (Continued) 6.6 Secondary Containment Capability - U2RZ only (Continued) 6.6.2 Record flows indicated on FX-65-50 and FI-65-71 (panel 9-25-2) and total on Data Sheet SI 4.7.C-1.

6.6.3 Record the following static pressures and the air temperatures at the differential pressure indicator locations.

Zone Instrument Panel s

U2RZ 2-PdXC-64-2 2-25-213 6.6.4 Record the wind direction (XR-90-102-2) and velocity (XR-90-102-1) at the 33 ft. level.

Instrumentation is located behind Unit 2 Panel 9-4.

Also, record the air temperature outside the reactor building at ground level.

0, 6.6.5 Verify static pressures are less than the value listed in Table 1

for wind velocity.

6.7 Secondary Containment Capabilit'y - U3RZ only NOTE:

This section is to verify that the secondary containment is capable of maintaining a -1/4" H20 wWh a system inleakage of 6.7.1 g 1,488 cfm for the"Unit 3 reactor zone.

Adjust the toal flow indicated on FI-65-50 and FX-65-71 (panel 9-25-2)

L to C 1,488 cfm 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.

6.7.2 Record flows fndicated on FX-65-50 and FI-65-71 (panel 9-25-2) and total on Data Sheet SI 4.7.C-1.

6.7.3 Record the following static pressures and the air temperatures at the differential pressure indicator locations.

Zone U3RZ Instrument Panel 3-PdIC-64-2 3-25-213

Page 9

BF SI 4,7.C 8 i21/79 6.

PROCEDURE (Continued) 6.7 Secondary Containment Capability - U3RZ only (Continued) 6.7.4

.Record the wind direction (XR-90-102-2) and velocity (XR-90-102-1) at the 33 ft. level.

Instrumentation is located behind Unit 2 Panel 9-4.

Also, record the air temperature outside the reactor building at ground level.

6.7.5 Verify all static pressures are less than the value listed in Table 1 for wind velocity.

6,8 Secondary Containment Capability - Refule Zone only NOTE:

This section is to verify that the secondary containment is capable of maintaining. a -1/4" 820 with a system inleakage of

< 7,680 cfm for the Refuel Zone.

6.8 ~ 1 6.8.2 Adjust the total flow indicated on FI-65-50 and FI-65-71 (panel 9>>25-2) to ( 7,680 cfm by closing a SGTS fan discharge damper or if.two 4

fans are running it may be necessary to shut one fan 'ofz.

NOTE:

Let the flow stabilize for 5 minutes before the next step.

Record flows indicated on FI-65-50 and FI-65-71 (panel 9-25-2) 6.8.3 and total on Data Sheet SI 4.7.C-1.

4 Record the following static pressures and the air t'emper6tures at the 'differenti'al pressure indicator locations.

Zone Instrument Panel UlRFZ 1-PdlC-64-1 1-25-219

'U2RFZ 2-PdIC-64-1 2-25-215 U3RFZ 3-PdIC-64-1 3-25-215 6.8.4 Record the wind direction {XR-90-102-2) and velocity (XR-90-102-1) at the 33 ft. level.

Instrumentation is located behind Unit 2 Panel 9-4.

Also, record the air temperature outside the reactor building at ground level.

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Page 10 BF SI 4.7.C 8/21/79 SI 4.7.C-l - Secondary Containment Ca abilities 6.

PROCEDURE (Continued) 6.8 Secondary Containment Capability - Refuel Zone only (Continued) 6.8.5 Verify all static pressures are less than the values listed in Table 1 for wind velocity.

6.9 Secondary Containment Capability - U1RZ and Refuel Zone only NOTE:

This section is to verify that the secondary containment is capable of maintaining a -1/4" H 0 with a system inleakage 2

of < 9,204 cfm for the Unit 1 Reactor Zone and Refuel Zone..-.

6.9,1 Adjust the total flow indicated on FI-65-50 and FI-65-71 (panel 9-25-2) to ( 9,204 cfm for entire reactor building by closing a

SGTS fan 4

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.

6.9.2 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.

6.9,3 Record the following static pressures and the air temperatures at the zone differential pressure indicator locations.

Zone Instrument Panel U1RZ U1RFZ U2RFZ U3RFZ 1-PdIC-64-2 1-PdlC-64-1 2-PdIC-64-1 3-PdIC-64-1 1-25-213 1-25-219 2-25-215 3-25-215 6.9.4 Record the wind direction (XR-90<<102-2) and velocity (XR-90-102-1) at the 33 ft. level.

Instrumentation is located behind Unit 2 Panel 9-4.

Also, record the air temperature outside the reactor building at ground level.

6.9.5 Verify all static pressures are less than the value listed in Table 1

for wind velocity.

Page 11 BF SX 4.7.C 8/21/79 SX 4.7.C Secondar Containment Ca abilities 6.

PROCEDURE (Continued) 6.10 Secondary Containment Capability - UZRZ and Refuel Zone onLy NOTE:

This section is to verify that the secondary containment is capable of maintaining a -1/4" 820 with a system inleakage of < 8,988 cfm for the Unit 2 Reactor Zone and Refuel Zone.

6.10.1 Adjust the total flow indicated on FI-65-50 and PI-65-71 (panel 9-25-2) to e 8,988 cfm by closing a SGTS fan discharge damper or if two fans are running it may be necessary to shut one fan off.

1 NOTE:

Let the flow stabilize for 5 minutes before the next step.

6.10.2 6.10.3 Record flows-indicated on PI-65-50 and FI>>65-71 (panel 9-25-2) and total on Data Sheet SI 4.7.C-L.

Record the following static pressures and the air temperatures at the differential pressure indicator locations.

Zone Ineeenmene panel U2RZ ULRPZ U2RPZ U3RPZ 2-PdIC-64-2 1-PdXC-64-1 2-PdXC-64-1 3-PdXC-64-1 2-25-u3 1-25-219 2-25-215 3-25-215 6.10.4 Record the wind direction (XR-90-102-2) and velocity (XR-90-102-1) at the 33 ft. level.

Instrumentation is located behind Unit 2 Panel 9-4.

Also, record the air temperature outside the reactor 6.10.5 building at ground Level.

Verify all st'atic pressures are less than the value listed in Table 1 for wind velocity.

Page 12 F/h./A" SI 4.7.C-1

- Secondar Containment Ca abilities 6.

PROCEDURE (Continued) 6.11 Secondary Containment Capability - U3RZ and Refuel Zone NOTE:

This section is to verify that the secondary containment is capable of maintaining a -1/4" H20 with a system inleakage of

< 9,168 cfm for the Unit 3 Reactor Zone and Refuel Zone.

6.11.1 Adjust the total flow indicated on FI-65-50 and FI-65-71 (panel 9-25 2) to (9,168 cfm 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 befoxe the next step.

e 6.11.2 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.

6.11.3 Record the following static pressures and the air temperatures at the differential pressure indicator locations.

rona Instrument Panel U3RZ UlRFZ U2RFZ U3RFZ 3-PdIC-64-2 1-PdIC-64-1 2-PdIC-64-1 3"PdIC-64-1 3-25-4 3 1-25-219 2-25-215 3-25-215 6,11.4 Record the wind direction (XR-90-102-2) and velocity (ZR-90-102-1) at the 33 ft. level.

Instrumentation is located behind Unit 2 Panel 9-4.

Also, record the air temperature outside the reactor 6.11.5 building at ground level.

Verify all static pressures are less than the value listed in Table 1 for wind velocity.

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4.7.C SI 4 ~ 7 ~ C Seconder Containment Ca abilities 6.

PROCEDURE (Continued) 6.12 Check those switches that were put in the TEST position under sections 6.2 and/or 6.3 in their NORliAL position and verify on Data Sheet SI 4.7.C-1.

6.13 Verify on Data Sheet SI 4.7.C-1 those actions listed under RETURN TO NOIU1AL for the zones tested.

6.14 Notify the unit operators and assistant shift engineers that the test is complete and systems returned to normal.

6.15 If this test was performed for a refueling outage, notify the cognizant engineer to review the results prior to breaking primary containment.

Page 14 BP SX 4.7.C 8/21/79 TABLE 1 Zone Static Pressure Requirements for Given Hind Velocity at 33 feet QP ( -.25 - 3.44 x 10 (V - 25)

(1)

Re uired dP in H 0 0-5 (mH) 10 12 13 14 15 16 18 19 20 21 22 23 24 25

-.250

-.254

-.258

-.263

-.269

-.276

-.283

-.291

-.299

-.309

-.319

-.329

-.341 353

-.365

-.379

-.393

-.408

-.423

-.439

-.456

)25 Calculate using the formula above (1)

Equation developed from reference 2.3

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Page 15 BF ST 4.7.C 8/21/79 A

endix A Secondary Containment Leak Rate Test Criteria During prcoperational testing for unit 3 the following in-leakage rates at

-1/4" H 0 static pressure were documented.

2 Unit 2 reactor zone Unit 3 reactor zone 1064 1211 Documented Inleaka~e Common refuel 'floor (units 1, 2,

& 3)

Unit 1 reactor zone 1239 Percentage 64%

12.7%

10.9%

12.4%

Total secondary containment 9764 CP:1 100%

Leak rate testing will normally be done with all zones simultaneously lined up for testing; however, plant operating conditions and the technical specificatxon do not always permit this.

Hhen less than four zones (3-unit plane) are being the total allowable inleakage will be based on preopcrational testing and will on the sum of the allowable inleakages for the zones being tested.

After a

tasted, be base'econdary 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 secpndagy containment inleakage to be less than 12,000 cfm at -1/4" differential pressure.

The following are therefoxe established for surveillance'estirg various combinations oi zones when secondary containment has been violated.

7one A11ovable.Xnleakage Common refuel floor Unit 1 reacto one Unit 2 reactor zone Unit 3 reactor zone Reactor. 8ui'ding 7680 l524 1308 1488 12000 CcH

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DATA COVER SHEET SI 4.7.C Page

].6 BF SI

.C 8 '21/79 SECONDARY CONTAINMENT CAPABILITY UNIT 1, 2

OR 3 Performed By Unit 0 ra or Were criteria satisfiedp

~Yes No Date If no, notify shift engineer.

If no, was a Limiting Condition for Operation vioiatedi Yes (explain in remarks)

No (explain in remarks)

Verified by Shift Engineer

, Date Reason for test:

Maintenance complete on Another system

(

Required by schedule Plant condition (explai'n)

P(

(d I Other (explain)

) inoperable C

Results reviewed

~ Ii Assistant Shi Engineer Date 2%- 7 9 Results Review and A

rov 1 (1) Cognizant Engineer Date

~ 7 Rescheduled QA Staff Date (1) Notify Maintenance that inleakage is excessive if criteria are not satisfied.

Data Sheet SI 4.7.C"1 Page 17 BF SI 4.7.C 8/21/79

~Ste 3.2 Com onent Process Variable Rx. Bldg. Ventilation System Verif and/or Record Initials/Date Normal 3.3 3.4 SGTS Main Steam Line Tunnel Temperature for units being tested Standby Readiness c 150o F

3.5 16A-S34 for units tested Not in Drywell or Torus Bypass 3.8 3.9 FI"65>>50 FI-65-71 PdIC-64-1 (All three units)

PdIC-64-2 (All three units)

Inboard Equipment Access Lock Doors Currently Calibrated Currently Calibrated Currently Calibrated Currently Calibrated Closed and Seals Inflated 3.10 Drywell or Suppression Chamber 3.11 Doors in the following table for the tested zone(s) or the number doors for all zones.

Purge Not Inprocess Closed

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Table 3. 11 Data Sheet SI 4.7.C-1 PaSe 18 BF SI 4.7.C 8/21/79 Elevation 519.0 U1RZ 30 31 U2RZ 34, 36 35, 37 U3RZ 40 41 541. 5 42 43, 44 45 565. 0

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8'221 0 231 224 9 229 g'228 g 232 8230 8230a 0'236, 0:241 8 237 0 238 240 242 8 249 8250 8251 255 255 242 226 231 583. 0

$E'298 fP 826, 0'827 593.0 8'538 8'539 490

497, 501 8 '540 8 541 506 8 '513 jP '514 621.25 7P 534 8 637 635 6400647 8 648 8 649 651 fP"657

$P658 639.0 664.0 670 704 700 705 701 706 7 12 7nn 672 673 713 717 714 715 716 675 724 715 725 716 722 717

-723

701, 703,

704, 720,

725, 716, 714

722, 706, 717 705 721 723 ~

708 ~

707

700, 702,

724, 715~

713

l

Page 19 S

4.7.C t

DATA SHEET SI 4.7.C-1 (Continued)

~Ste Com onent Process Variable Verif and/or Record Initials/Date 6.1 Initial only the configuration(s) to be tested and perform the steps indicated.

NOTE:

Steps 6.12 and 6.13 are to be performed for all configurations.

U1RZ only Configuration - Perform sections 6.2, 6'

Entire 6.2 U2RZ only Configuration - Perform sections 6.2, 6.6 U3RZ only Configuration>> Perform sections 6.2, 6.7 RFZ only Configuration-Perform sections 6.3, 6.8 UlRZ and RFZ Configuration - Perform sections 6.2, 6.3, 6.9 only U2RZ and RFZ Configuration-Perform sections 6.2, 6.3, 6.10 only U3RZ agd RFZ Configuration - Perform sections 6.2, 6.3, 6.11 only Reactor Building Configuration - Perform sections 6.2 - 6.4 Complete only for.the reactor zone(s) listed 6.2.1 1-HS-64-117 2-HS-64-117 3-HS-64-117 2-HS-64>>120 3-HS-64-120

6. 2. 2 1-HS-64-120 TEST Position TEST Position TEST Position TEST Position TEST Position TEST Position 6.2.3 SGTS Train A or SGTS Train B or SGTS Train C

START START START Unit 1 Reactor Zone U-1 Reactor Zone Ventilati'on Sys.

1-FCO-64-13 1-FCO-64-14 1-FCO-64-42 1-FCO-64-43 Shutdown Closed Closed Closed Closed

DaLa Sheet Sl 4.7.C-l (Continued)

Page 20 BF SI 4.7.C 8/21/79

~Ste Com onent/Process Variable 6.2.3 (Continued) 1"FCO-64-15 1-FCO-64-40 1-FCO-64-41 1-FCO-64-60A 1-FCO-64-60B 1-FC0<<64-60C 1"FCO-64-60D U-1 Stair Hall Supply Fan Verif and or Record 1nitials/Date Open Open Open Closed Closed Closed Closed Shutdown Unit 2 Reactor Zone U-2 Reactor Zone Ventilation Sys 2"FCO-64-13 2"FCO"64"14 2-FCO-64-42 2"FCO-64-43 Shutdown Closed Closed Closed Closed 2"FCO-64-15 2-FCO-64-40 2-FCO-64-41 Unit 3 Reactor Zone U-3 Reactor Zone Ventilation, Sys 3-FCO-64-13 3"FCO-64-14 3"FCO-64-42 3-FC0>>64-43 3-FCO-64-15 3-FCO-64-40 Open Open Open Shutdown Closed Closed Closed Closed Open Open

I

Page 22'F SI 4.7.C 8/21/79 Data Sheet SI 4.7.C>>2 NOTE:

Complete this sheet only if entire reactor zone is to be tested.

~Ste 6.4.2 6.4.3 6.4.4 Com onent Process Variable FI-65-50 FI-65-71 Total (must be ( 12,000)

. 1-PdIC Rx Zone Thermometer Rx Zone 2-PdIC Rx Zone Thermometer Rx Zone 3-PdIC Rx Zone Thermometer Rx Zone 1-PdIC Refueling Zone 2-PdIC Refueling Zone 3-PdIC Refueling Zone Thermometer Refueling Zone Wind direction (behind Unit 2 pnl 9-4) 33 ft. level/Windspeed (behind Unit 2 pnl 9-4)

Verif and or Record Initials Date sfcm s fcm "H20 ffH 0

'H20 "H20

'H20

>sH 0 Fo Direction 6.4.5 Thermometer/Outside temp.

All zones ~ P ( appropriate value in Table 1

hP req'd F

I'

~

Page 23 BF SX 4.7.C 8/21/79 Data Sheet SX 4.7.C-3 Complete this sheet if the Unit' Rx Zone only is to be tested.

~Ste 6.5 '

6.5.3 Com onent Process Variable FX-65-50 FI-65-71 Total (must be ( 1,524) 1-PdlC Rx Zone Thermometer Rx Zone s lcm

'H20 Fo 6.5.4 6.5.5 Wind direction (behind Unit 2 pnl 9-4) 33 ft. level/Windspeed (behind Unit 2 pnl 9-4)

Thermometer/Outside temperature Zone QP < Value in Table 1

Direction hP req'd mph Fo

Page 24

'F SI 4.7.C 8/21/79 Data Sheet SI 4.7.C-4

~Ste 6.6.2 6.6.3 6.6.4 C

onent Process Variable FI-65-50 Fl-65-71 Total (must be g 1,308) 2-PdIC Rx Zone Thermometer Rx Zone Mind direction (behind Unit 2 pnl 9-4)

Verif NOTE:

Complete this sheet if the Unit 2 Rx Zone only is to be tested.

~t and or Record s fcm

'H20 F

Initials Date Direction 33 ft. level/Windspeed (behind Unit 2

..pnl 9-4)

Thermometer/Outside temperature mph F

Zone aP < Value in Table 1

hP req d

0

Page 25 BF SI 4.7.C 8/21/79 Data Sheet SI 4.7.C-5 NOTE:

Complete this sheet if the Unit 3 Rx Zone only is to be tested.

~Ste 6.7.2 6.7.3 6'.4 6.7.5 Co onent Process Variable Fl"65-50 FI-65-71 Total (must be ( 1,488) 3-PdIC Rx Zone Thermometer Rx Zone Wind direction (behind Unit 2 pnl 9-4) 33 ft. level/Windspeed (behind Unit 2 pnl 9-4)

Thermometer/Outside temperature Zone LP < Value in Table 1

Direction DP req'd sfcm sfcm s fcm

'H20 F

F

~

~

~

~

~

~

~

NOTE:

~Ste Data Sheet SI 4.7.C-6 Complete this sheet if the Refuel Zone only is to be tested.

Co onent/Process Variable Verif and or Record Page 26 BF SI 4.7.C 8/21/79 Initials/Date 6.8.2 6.8.3 FI-65<<50 FI-65"71 Total (must be C 7,680) 1-PdIC Refueling Zone 2-PdIC Refueling Zone 3-PdIC Refueling Zone Thermometer Refueling Zone sfcm

'H2O

'H20 F

6.8.4 Wind direction (behind. Unit 2 pnl 9-4)

Direction 33 ft. level/Windspeed (behind Unit 2 pnl 9-4)

Thermometer/Outside temperature 6.8.5 A11 zones 5P < Value in Table 1

AP req'd F

0

~

~

3 Page 27 BF SI 4.7.C 8/21/79 Data Sheet SI 4.7.C-7 NOTE:

Complete this sheet if the U1Rx and Refuel Zones

~Ste Com onent Process Variable Verif 6.9.2 FI-65-50

~ FI-65-71 Total (must be < 9,204) only are to be P

'Z, and or Record sfcm sfcm tested.

Initials Date 6.9.3 1-PdIC Rx.Zone Thermometer Rx Zone 1-PdIC Refueling Zone 2-PdIC Refueling Zone

~ PdIC Refueling'Zone Thermometer Refueling

Zone,

'H20 F

'H2O

'H2O

'H20 Fo Wind direction (behind Unit 2 pnl 9-4) 33 ft. level/Windspeed (behind Unit 2 pnl 9-4)

Thermometer/Outside temperature 6.9.5 A11 zones +P < Value in Table 1

Direction hP req'd mph F

Page 28 BF SX 4.7.C 8/21/79

~Ste Co onent Process Variable 6 ~ 10. 2 FI-65>>50 FI-65-71 Total (must be g 8,988)

/

6.10.3 2-PdIC Rx Zone Verif Thermometer Rx Zone r

1-PdIC '.Refueling Zone 2-PdIC Refueling Zone

..3-PdIC Refueling Zone thermometer Refueling Zone Data Sheet SI 4.7.C-8 NOTE:

Complete this sheet if the U2 Rx and Refuel Zones only are to be and or Record s fcm s fcm "H20 Fo "H20 "H20 "H20 F

tested.

Initials Date I

6.10.4 Wind direction (behind Unit 2 pnl 9-4) 33 ft. level/Windspeed

{behind Unit 2 pnl 9-4)

Thermometer/Outside temperature 6.10.5 All zones DP g Value in Table 1

Direction AP red'd mph Fo

~ ~

Page 29 BF SI 4.7.C 8/21/79 Data Sheet SI 4.7.C-9 NOTE:

Complete this sheet if the U3 Rx and Refuel Zones only are to be tested.

~Ste 6.11.2 6.11.3 Com onent/Process Variable FI-65-50 FI-65-71 Total (must be <9168) 3-PdIC Rx Zone Thermometer Rx Zone 1-PdIC Refueling Zone 2-PdIC Refueling Zone 3-PdIC Refueling Zone Verif and/or Record

3) >0 sfcm 55nO sfcm t4 o 0 sfcm H 0 2

g Fo

-.1 5 H20

.15 20 0

Initials/Date 6.11.4 Thermometer Refueling Zone Mind direction (behind Unit 2 pnl 9-4) 33 ft level/windspeed (behind Unit 2 pnl 9-4)

Thermometer/Outside temp.

5f<f'irection F'.11.5 Al.l zones AP

< value in table EP req'd

Eg

~

~

Data Sheet SI 4.7.C-10 Page 30 BF SI 4.7.C 8/21/79 Complete the appropriate portions of this sheet (for zones tested).

I ate Com onent/Process Variable Verif and/or Record Initials/Date 6.12 1-HS-64"117 2-HS-64-117 3-HS-64-117 NORMAL NORMAL NORMAL 1-HS-64-120 2-HS-64-120 3"HS"64-120 NORMAL NORMAL

" NORMAL 1-as-64-119 1-as-64-122 NORMAL NORMAL

i

Data Sheet SI 4.7.c-l 0 (Continued)

Page 31 BF S) 4'.C ate Com onent/Process Variable Verif and/or Record Initials/Date

.Return to Normal Complete the appropriate portions of this sheet (for zones tested).

6. p SGTS Fan A OFF Fco-65-3 A"SGTS humidity control heater A"SGTS charcoal heater SGTS Fan B

Fco-65-25 B-SGTS humidity control heater B-SGTS charcoal heater SGTS Fan C

Fco-65<<51 C-SGTS humidity control heater C-SGTS charcoal heater Closed OFF ON OFF Closed OFF ON OFF

'losed OFF ON Unit 1 Reactor Zone U-1 Reactor Zone Ventilation System 1<<FC0>>64-13 In operation as required OPEN 1-FCO-64-14 1-FCO-64-42 1-FCO-64-43 1-FCO-64-15 1-FCO-64-4O 1-FCO-64-41 1"FCO-64-60A 1-FCO-64-60B 1-FCO-64-60C 1-FCO-64-60D OPEN OPEN OPEN Closed Closed Closed Open Open Open Open U-1 Stair Hall Supply Fan In operation as required

~

~

~Ste Data Sheet SI 4.7.C-10 (Continued) page 32 BF SI 4.7.C 8/21/79 Com onent/Process Variable Verif and/or Record Initials/Date 6.k3 (Continued)

Unit 2 Reactor Zone U-2 Reactor Zone Ventilation System 2-FCO-64-13 2-FCO-64-14 2-FCO-64-42 2-FCO-64-43 2<<FCO-64-15 2-FCO-64-40 2-FCO-64-41 In operation as required Open.

Open Open Open Closed Closed Closed Unit 3 Reactor Zone U-3 Reactor Zone Ventilation System 3-PCO-64-13 3-PCO-64-14 3-PCO-64-42 3-FC0>>64-43 3-FCO-64-15 3-FCO-64-40 3-FCO-64-41 3-PCO-64-60A 3-FCO-64-60B 3-FC0>>64"60C 3-FCO-64-60D U-3 Stair Hall Supply Fan In operation as required Open Open Open Open Closed Closed Closed Open Open Open Open In Operation as Required

1

I

~

~

Data Sheet SI 4.7.c-+continued)

Page BF SI 4.7.C 8/21/79 Stan Component/Process Variable 6.13 (Continued)

Refuelin Zone Verif and/or Record Initials/Date U-l Area. Refueling Zone Vent $ys U-2 Area Refueling Zone Vent Sys In Operation as required In Op ration as required U-3 Area Refueling Zone Vent $ys 1-Fco-64-6 2<<FCO"64-6

. 3-FCO-65-6 1-Fco-64-5 2-Fco-64-5

~

3-FCO-64-5 1-Fco-64-1o 2-Fco-64-10 3"FCO"64-10 1-Fco-64-9 2-FCO-64-9.

3-Fco-64-9 1-FCO-64-63

, 1-Fco-64-7 1-FCO-64-65A 1-FCO-64-65B 1-FCO-64-65C 1-FCO-64-65D 1-Fco-64-44 1-Fco-64-45 Equipmcnt Access Lock Exhaust Fan U-1 Stair 1fall Supply Fan

~ ~ 1,

~

~

~ ~ ta,,

1 In Operation as required Open Open Open Open Open

, Open Open Open Open Open Open Open Close Close Open Open Open Open Close Close In Operation as required In Operation as required Tn h~nr~t (nn no rnnl) Irnd

4 I 0