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 RMNNQQY 90CQl fjg 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 are capable of maintaining <-.25" with less than the allowed I'ones H 0 2

flow.

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

",Approved:

Plant Superintendent Date: 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

~ - 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.

~ ~ 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 Number Revision 45N614-5 5 47W610-64 45N614-6 5 47W610-65 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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Page 4 BF SI 4.7 AC 8/21/79 SI 4.7.C-l Secondar Containment Ca abilit 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 panels: 25-219-1 25-215-2 s

25-215-3 25-213-1 25-213-2 25-213-3 3.8 Verify the following process instruments to be within a cuxrent l

calibration period. FI-65-50 1-PdIC-64-2 FI-65-71 '-PdIC-64-2 1-PdIC-64-1 3-PdIC-64-2 fd 2-PdIC-64-1 l" 3-Pdlc-64-1 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 i

respective zones to s

be tested or the doors indicated by number~~'(dee Table 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 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 andd per form th e indicated n sections on the configuration to be tested on Data S h ee t SX 4 ~ 7.C-l

~ and perform steps indicated below. Sections 6 . 12 an 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 t'.8.

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

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

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

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 Xso at on o nual Xsolation Manual of a Reactor Zone - Perform only as req uired p er section 6.1.

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 reactor zone to* be isolated. (Outboard valves)

6. 2.3 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 f th e Pl an t Refueling Zone - Perform only as required per section 6.1.

6~341 Place HS-64-119 (Panel 9-25-1) in the TEST position. (In oar and common valves)

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Page 6 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 1-PdIC-64-2 1-25-213 U2RZ 2.-PdIC-64-2 2-25-213 U3RZ 3-PdIC-64-2 3-25-213 01RFZ 1" PdIC 1 1-25-219 U2RFZ 2-PdIC" 64- 1 2-'75-215 U3RFZ 3-PdIC 1 3-25-215 6.4. 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.

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

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Page 7 BF SX 4.7.C 8/21/79 SI 4.7.C Secondar

~ ~ Containment Ca abilities

6. PROCEDURE {Continued) 6.5 Secondary Containment Capability - U1RZ only NOTE: This section is to verify that the secondary containment is capable of maintaining a -1/4" H 0 2

with a system inleakage of

< 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

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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 building at ground level.

6.6 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 1,308 cfm by closing a fan dishcarge damper or if two L'ans C SGTS 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 i 21/79 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.

6.6.5 Verify static pressures are less than the value listed in Table 0, for wind velocity.

1 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 g 1,488 cfm for the"Unit 3 reactor zone.

6.7.1 Adjust the toal flow indicated on FI-65-50 and FX-65-71 (panel 9-25-2) to C 1,488 cfm by closing a SGTS fan discharge damper or if two L 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 Instrument Panel U3RZ 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 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 fans are running it may be necessary to shut one fan 'ofz.

4 NOTE: Let the flow stabilize for 5 minutes before the next step.

6.8.2 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 6.8.3 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 2

with a system inleakage 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 discharge damper or if two fans are running it may be necessary 4

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 1-PdIC-64-2 1-25-213 U1RFZ 1-PdlC-64-1 1-25-219 U2RFZ 2-PdIC-64-1 2-25-215 U3RFZ 3-PdIC-64-1 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 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.

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

Zone Ineeenmene panel U2RZ 2-PdIC-64-2 2-25-u3 ULRPZ 1-PdXC-64-1 1-25-219 U2RPZ 2-PdXC-64-1 2-25-215 U3RPZ 3-PdXC-64-1 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 building at ground Level.

6.10.5 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 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 3-PdIC-64-2 3-25-4 3 UlRFZ 1-PdIC-64-1 1-25-219 U2RFZ 2-PdIC-64-1 2-25-215 U3RFZ 3"PdIC-64-1 3-25-215 6,11.4 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 building at ground level.

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

0 8 S 4.7.C SI 4 ~ 7 ~ C-1 - 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

-.25 - 3.44 x (1)

QP ( 10 (V - 25)

Re uired dP in H 0 0-5 (mH) -.250

-.254

-.258

-.263

-.269 10 -.276

-.283 12 -.291 13 -.299 14 -.309 15 -.319 16 -.329

-.341 18 353 19 -.365 20 -.379 21 -.393 22 -.408 23 -.423 24 -.439 25 -.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. Documented 2

Inleaka~e Percentage Common refuel 'floor (units 1, 2, & 3) 64%

Unit 1 reactor zone 1239 12.7%

Unit 2 reactor zone 1064 10.9%

Unit 3 reactor zone 1211 12.4%

9764 CP:1 Total secondary containment 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 tasted, the total allowable inleakage will be based on preopcrational testing and will be on the sum of the allowable inleakages for the zones being tested. After a 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 7680 Unit 1 reacto one l524 Unit 2 reactor zone 1308 Unit 3 reactor zone 1488 Reactor. 8ui'ding 12000 CcH

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BF SI . .C DATA COVER SHEET SI 4.7.C 8 '21/79 SECONDARY CONTAINMENT CAPABILITY UNIT 1, 2 OR 3 Performed By Date Unit 0 ra or Were criteria satisfiedp ~Yes No 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 ( ) inoperable Required by schedule Plant condition (explai'n) P( (d I Other (explain)

Results reviewed ~ Ii C Date $ 2%- 79 Assistant Shi Engineer 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.

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

~Ste Com onent Process Variable Verif and/or Record Initials/Date 3.2 Rx. Bldg. Ventilation System Normal 3.3 . SGTS Standby Readiness 3.4 Main Steam Line Tunnel Temperature c 150o F for units being tested 3.5 16A-S34 for units tested Not in Drywell or Torus Bypass 3.8 FI"65>>50 Currently Calibrated FI-65-71 Currently Calibrated '

PdIC-64-1 (All three units) Currently Calibrated PdIC-64-2 (All three units) Currently Calibrated 3.9 Inboard Equipment Access Lock Doors Closed and Seals Inflated 3.10 Drywell or Suppression Chamber Purge Not Inprocess 3.11 Doors in the following table for the tested zone(s) or the number doors for all zones. Closed

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PaSe 18 BF SI 4.7.C Table 3. 11 8/21/79 Data Sheet SI 4.7.C- 1 Elevation U1RZ U2RZ U3RZ 519.0 30 34, 36 40 31 35, 37 41 541. 5 42 43, 44 45 565. 0 8'221 0'236, 0:241 8 249 255 0 231 8 237 8250 242 224 0 238 8251 226 9 229 240 255 231

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g'228 242 g 232 8230 8230a 583. 0 $E'298 fP 826, 0'827 593.0 8'538 497, 501 506 8'539 8 '540 8 '513 490 8 541 jP '514 621.25 7P 534 6400647 651 8 637 8 648 fP"657 635 8 649 $P658 639.0 670 672 675 673 664.0 704 700 713 717 724 715 700, 702, 724, 715~ 713 705 701 714 725 716 701, 703, 725, 716, 714 706 7 12 715 722 717 704, 720, 722, 706, 717 716 -723 705 721 723 708 707 7nn ~ ~

l t ~Ste 6.1 Com DATA SHEET onent Process Variable Initial only NOTE:

U1RZ only SI 4.7.C-1 (Continued)

Verif and/or

'

Page Record S

19 4.7.C Initials/Date the configuration(s) to be tested and perform the steps indicated.

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

Configuration - Perform sections 6.2, 6 '

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

- 6.4 Entire Reactor Building Configuration - Perform sections 6.2 6.2 Complete only for .the reactor zone(s) listed 6.2.1 1-HS-64-117 TEST Position 2-HS-64-117 TEST Position 3-HS-64-117 TEST Position

6. 2. 2 1-HS-64-120 TEST Position 2-HS-64>>120 TEST Position 3-HS-64-120 TEST Position 6.2.3 SGTS Train A START or SGTS Train B START or SGTS Train C START Unit 1 Reactor Zone U-1 Reactor Zone Ventilati'on Sys. Shutdown 1-FCO-64-13 Closed 1-FCO-64-14 Closed 1-FCO-64-42 Closed 1-FCO-64-43 Closed

Page 20 BF SI 4.7.C 8/21/79 DaLa Sheet Sl 4.7.C-l (Continued)

~Ste Com onent/Process Variable Verif and or Record 1nitials/Date 6.2.3 (Continued) 1"FCO-64-15 Open 1-FCO-64-40 Open 1-FCO-64-41 Open 1-FCO-64-60A Closed 1-FCO-64-60B Closed 1-FC0<<64-60C Closed 1"FCO-64-60D Closed U-1 Stair Hall Supply Fan Shutdown Unit 2 Reactor Zone U-2 Reactor Zone Ventilation Sys Shutdown 2"FCO-64-13 Closed 2"FCO"64"14 Closed 2-FCO-64-42 Closed 2"FCO-64-43 Closed 2"FCO-64-15 Open 2-FCO-64-40 Open 2-FCO-64-41 Open Unit 3 Reactor Zone U-3 Reactor Zone Ventilation, Sys Shutdown 3-FCO-64-13 Closed 3"FCO-64-14 Closed 3"FCO-64-42 Closed 3-FC0>>64-43 Closed 3-FCO-64-15 Open 3-FCO-64-40 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 Com onent Process Variable Verif and or Record Initials Date 6.4.2 FI-65-50 sfcm FI-65-71 s fcm Total (must be ( 12,000) 6.4.3 . 1-PdIC Rx Zone "H20 Thermometer Rx Zone 2-PdIC Rx Zone ffH 0 Thermometer Rx Zone 3-PdIC Rx Zone 'H20 Thermometer Rx Zone 1-PdIC Refueling Zone "H20 2-PdIC Refueling Zone 'H20 3-PdIC Refueling Zone >sH 0 Thermometer Refueling Zone Fo 6.4.4 Wind direction (behind Unit 2 pnl 9-4)

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

Thermometer/Outside temp. F 6.4.5 All zones ~P ( appropriate value in Table 1 hP req'd

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 Com onent Process Variable 6.5 ' FX-65-50 s lcm FI-65-71 Total (must be ( 1,524) 6.5.3 1-PdlC Rx Zone 'H20 Thermometer Rx Zone Fo 6.5.4 Wind direction (behind Unit 2 pnl 9-4)

Direction 33 ft. level/Windspeed (behind Unit 2 pnl 9-4) mph Thermometer/Outside temperature Fo 6.5.5 Zone QP < Value in Table 1 hP req'd

Page 24 'F SI 4.7.C 8/21/79 Data Sheet SI 4.7.C-4 NOTE: Complete this sheet if the Unit 2 Rx Zone only is to be tested.

~

t

~Ste C onent Process Variable Verif and or Record Initials Date 6.6.2 FI-65-50 Fl-65-71 s fcm Total (must be g 1,308) 6.6.3 2-PdIC Rx Zone 'H20 Thermometer Rx Zone F 6.6.4 Mind direction (behind Unit 2 pnl 9-4)

Direction 33 ft. level/Windspeed (behind Unit 2

..pnl 9-4) mph Thermometer/Outside temperature 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 Co onent Process Variable 6.7.2 Fl"65-50 sfcm FI-65-71 sfcm Total (must be ( 1,488) s fcm 6.7.3 3-PdIC Rx Zone 'H20 Thermometer Rx Zone F 6 '.4 Wind direction (behind Unit 2 pnl 9-4)

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

Thermometer/Outside temperature F 6.7.5 Zone LP < Value in Table 1 DP req'd

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Page 26 BF SI 4.7.C 8/21/79

'

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

~Ste Co onent/Process Variable Verif and or Record Initials/Date 6.8.2 FI-65<<50 sfcm FI-65"71 Total (must be C 7,680) 6.8.3 1-PdIC Refueling Zone 2-PdIC Refueling Zone 'H2O 3-PdIC Refueling Zone 'H20 Thermometer Refueling Zone 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 F 6.8.5 A11 zones 5P < Value in Table 1 AP req'd

0 Page 27

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3 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 only are to be tested.

P

'Z,

~Ste Com onent Process Variable Veri f and or Record Initials Date 6.9.2 FI-65-50 sfcm

~ FI-65-71 sfcm Total (must be < 9,204) 6.9.3 1-PdIC Rx.Zone 'H20 Thermometer Rx Zone F 1-PdIC Refueling Zone 'H2O 2-PdIC Refueling Zone 'H2O

. ~ PdIC Refueling'Zone 'H20 Thermometer Refueling Zone, Fo Wind direction (behind Unit 2 pnl 9-4)

Direction 33 ft. level/Windspeed (behind Unit 2 pnl 9-4) mph Thermometer/Outside temperature F 6.9.5 A11 zones +P < Value in Table 1 hP req'd

Page 28 .

BF SX 4.7.C 8/21/79 Data Sheet SI 4.7.C-8 NOTE: Complete this sheet if the U2 Rx and Refuel Zones only are to be tested.

~Ste Co onent Process Variable Verif and or Record Initials Date 6 ~ 10. 2 FI-65>>50 FI-65-71 s fcm Total (must be g 8,988) s fcm

/

6.10.3 2-PdIC Rx Zone "H20 Thermometer Rx Zone Fo r

1-PdIC '.Refueling Zone "H20 2-PdIC Refueling Zone "H20

..3-PdIC Refueling Zone "H20 I 6.10.4 thermometer Wind 33 ft.

pnl 9-4)

Refueling Zone direction (behind Unit 2 pnl 9-4) level/Windspeed {behind Unit Thermometer/Outside temperature 2

Direction F

mph Fo 6.10.5 All zones DP g Value in Table 1 AP red'd

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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 Com onent/Process Variable Verif and/or Record Initials/Date 6.11.2 FI-65-50 3) >0 sfcm FI-65-71 55nO sfcm Total (must be <9168) t4 o 0 sfcm 6.11.3 3-PdIC Rx Zone H 0 2

Thermometer Rx Zone g Fo 1-PdIC Refueling Zone -.1 5 H20 2-PdIC Refueling Zone .15 20 3-PdIC Refueling Zone 0 Thermometer Refueling Zone 6.11.4 Mind direction (behind Unit 2 pnl 9-4) 5f<f'irection 33 ft level/windspeed (behind Unit 2 pnl 9-4)

Thermometer/Outside temp.

Al.l zones value in table F'.11.5 AP <

EP req'd

Eg

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Page 30 BF SI 4.7.C 8/21/79 Data Sheet SI 4.7.C-10 Complete the appropriate I

portions of this sheet (for zones tested) .

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

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

i Page 31 BF S) 4 '.C Data Sheet SI 4.7.c-l 0 (Continued) 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 Closed A"SGTS humidity control heater OFF A"SGTS charcoal heater ON SGTS Fan B OFF Fco-65-25 Closed B-SGTS humidity control heater OFF B-SGTS charcoal heater ON SGTS Fan C OFF Fco-65<<51 'losed C-SGTS humidity control heater OFF C-SGTS charcoal heater ON Unit 1 Reactor Zone U-1 Reactor Zone Ventilation System In operation as required 1<<FC0>>64-13 OPEN 1-FCO-64-14 OPEN 1-FCO-64-42 OPEN 1-FCO-64-43 OPEN 1-FCO-64-15 Closed 1-FCO-64-4O Closed 1-FCO-64-41 Closed 1"FCO-64-60A Open 1-FCO-64-60B Open 1-FCO-64-60C Open 1-FCO-64-60D Open U-1 Stair Hall Supply Fan In operation as required

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page 32 BF SI 4.7.C Data Sheet SI 4.7.C-10 (Continued) 8/21/79

~Ste Com onent/Process Variable Verif and/or Record Initials/Date 6.k3 (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 2-FCO-64-42 Open 2-FCO-64-43 Open 2<<FCO-64-15 Closed 2-FCO-64-40 Closed 2-FCO-64-41 Closed .

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

1 I

~

Page

~

BF SI 4.7.C Data Sheet SI 4.7.c-+continued) 8/21/79 Stan Component/Process Variable Veri f and/or Record Initials/Date 6.13 (Continued)

Refuelin Zone U-l Area. Refueling Zone Vent $ ys In Operation as required U-2 Area Refueling Zone Vent Sys In Op ration as required U-3 Area Refueling Zone Vent $ ys In Operation as required 1-Fco-64-6 Open 2<<FCO"64-6 Open

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

Open 3-FCO-64-5 , Open 1-Fco-64-1o Open 2-Fco-64-10 Open 3"FCO"64-10 Open 1-Fco-64-9 Open 2-FCO-64-9. Open 3-Fco-64-9 Open 1-FCO-64-63 Close

,

1-Fco-64-7 Close 1-FCO-64-65A Open 1-FCO-64-65B Open 1-FCO-64-65C Open 1-FCO-64-65D Open 1-Fco-64-44 Close 1-Fco-64-45 Close Equipmcnt Access Lock Exhaust Fan In Operation as required U-1 Stair 1fall Supply Fan In Operation as required

~~ 1, ~ ~ ~ ~ ta,, 1 Tn h~nr~t (nn no rnnl) Irnd

4 I 0