ML19270G932

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Secondary Containment Leak Rate Test,90-Day Rept
ML19270G932
Person / Time
Site: Browns Ferry  
Issue date: 05/11/1979
From:
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML19270G931 List:
References
NUDOCS 7906210199
Download: ML19270G932 (26)
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s 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 Plcnt Unit 2 secondary containment pursuant to Technical Specification 4.7.C.1.b prior to each refueling 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 list the following test data:

(1) Standby gas treatment system flow rate: 8,800 SCFM (2) Reactor building differential pressures:

Unit 1 reactor zone:

-0.25" H O 2

Unit 2 reactor zone:

-0.30" H O 2

Unit 3 reactor zone:

-0.27" H O 2

Refueling zone average:

-0.28" H O 2

(3) Wind Speed: 8 mph (4) Wind Direction: South 79062101T1

. 5.0 Analysis and Interpretation 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 2 on April 28, 1979, the secondary contain-ment for the common refuel zone and the Unit 2 reactor zone were leak rate tested.

These two zones were isolated from the Units 1 and 3 reactor zones.

The results of this test are documented in the plant files. The SGT flow used on this date was 11,500 SCFM. Appendix A to S1 4.7.C gives the allowable inleakage per secondary containment zone documented during preoperational testing and based on a total allowable inleakage of 12,000 SCFM. Due to a personnel error, it was not understood that total inleakage for Unit 2 reactor zone and the combined refuel zones may not exceed 8,890 SCFM.

On 5/4/79, at about 12 m.,

it was discovered in normal surveillance review that the inleakage used in performing the test was greater than the allowable 8,890 SCFM. At this time, all fuel handling and work ever the Unit 2 reactor cavity were stopped and SI 4.7.C was performed again. The data obtained is that listed in this report. The retest data f rom SI 4.7.C is attached. The primary containment had been broken for about five days prior to the passage of SI 4.7.C and LER 50-260/79-8 was written as a result. The leak rate eas accept-able upon retest without aadification or repair to the secondary 2238 322

- 5.0 (Continued) containment. The retest shows that with an inleakage of 8,800 SCFM in the Unit 2 reactor core and the refuel zone, the secondary containment is capable of maintaining <

.25 inch of water pressure.

The results of the retest satisfy the requirements of technical specification 4.7.C.l.b.

The windspeed was not less than 5 mph as required by the technical specification. Ilowever, an analysis is attached to the SI 4.7.C-1 data sheet showing the validity of the data at a wind condition of 8 mph.

RCC:MB 6/5/79 Attachments 2238 323

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TENNESSEE VALLEY AUTHORITY BROWNS FFRRY NUCLEAR PIANT J

.SURVEILIANCE INSTRUCTION 4.7.C SECONDARY CONTAINMEfff UNIT 1, 2 OR 3 J

Approved:

pia [SLperintendent May 11, 1976 Date:

General Revision 2238 2 4

\\

Page 1 I

BF SI 4.7.C 11/7/78 SI 4.7.C

- Secondary containment Description This surveillance is used to comply with the requirements of portions of technical specification 4.7.C.

The following table lists the requirements satisfied by this instruction Tech. Spec.

Frequency Referenced Surveillance Requirements e

At each refueling out-4.7.C.l.c Demonstrate the capability of secondary con-age prior to refueling tainment to maintain - 1/4" water pressure with a system inleakage of not more than

? 2,000 cfm under calm wind conditions < 5 mph.

SI 4.7.C 1. will be used to satisfy this requirement.

Any time the integrity 4.7.C.2 Isolate the affected zone from the other zones 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 it broken up into four zones, each of which can be isolated independently. These zones are the unit 1 reactor zone (UlR2), the unit 2 Reactor zone (U2RZ), the unit 3 reactor zone (U3RZ), and the refueling zone (RFZ) which is common to all three units.

This surveillance instruction is written to use the SGTS fans A and C, B and C, or A and B, or a single fan to demonstrate i

I I

that at a flow of $ 12,000 cfm the secondary containment zones can be maintained at

}

a static pressure of -1/4" water under calm wind conditions. Manual isolation of

{!

the zones will be used since it is fast and the steam line tunnel temperature increases,which may cause a unit trip.}} j} 3

.a: ....-.. u.a.. Page 2 BF SI 4.7.C 5/11/76 SI 4.7.C - Secondary Containment Description (Continued) SI 4.7.C-1 will be used to demonstrate secondary containment capability. This is to be accomplished by isolating the secondary containment for the reactor trains, adjust-building or the required zones, starting the standby gas treatment ing the flow to less than the allowable flow and verifying the static pressure of the tested zons(s) is -1/4" H O or less. This procedure will normally be used to 2 test the secondary containment capability of the reactor building prior to ' refueling. ..a testing should be 1Laited to 30 minutes if at all possible SI 4.7.C-1 since the main steam line tunnel temperatures may trip an operating unit. L 2238 .526 O s 9

.... ~... ~... < Page 3 BF SI 4.7.C 5/11/76 Secondary containment capability SI 4.7.C 1. PURPOSE This procedure is used to isolate the zones to be leak tested and to verify secondary containment capability to maintain -1/4" H O with a system in-leakage w 2 of < 12,000 cfm without actually measuring the in-leakage. 2. REFERENCES 2.1 Technical specifications for units 1, 2, and 3, Section 4.7.C. 2.2 The following drawings: Number Revision Number Revision 45N614-5 5 47W610-64 15 45N614-6 5 47W610-65 15 3. PREREQUISITES 3.1 Notify each unit operator and assistant shift engineer such that they may communicate and be aware of the ventilation and SGTS status during this test. 3.2 Verify that the reactor building ventilation system is in a normal operational status per OI 30. 3.3 Verify that the SGTS is in standby readiness per OI 65. 3.4 Verify that each units' main steam line tunnel temperature is not above 150 F. 3.5 Verify switch 16A-S34 is not in DRYWELL BYPASS or TORUS BYPASS on each unit or the unit that is to be tested. 2238 27 e

~. Page 4 BF SI 4.7.C 5/11/76 SI 4.7.C-1 Secondary Containment Capability 3. PREREQ'11 SITES (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-64-1 3-PdIC-64-2 2-PdIC-64-1 3-PdIC-64-1 3.9 Verify tha 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 J respective zones to be tested or the doors indicated by number (See 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 1600 F. If this temperature is approached to within 100 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 1860 F ).. 4.2 Attempt to restrict testing time to 30 minutes. 2238 .28L 5.0 LIMITATIONS AND ACTIONS 5.1 None f,

I Page 5 BF SI 4.7.C 5/11/76 SI 4.7.C Secondary containment capabilities 6. PROCEDURE 6.1 Initial and perform the indicated sections on the configuration to 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. 6.1.2 U2RZ - Perform section 6.2 and section 6.4. 6.1.3 U3RZ - Perform section 6.2 and section 6.4. l 6.1.4 RFZ - Perform section 6.3 and section 6.4. 6.1.5 UlRZ 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, HS-64-120, HS-64-119, & HS-64-122 are spring. return to normal. 6.2.1 Place HS-64-il7 (Panel 9-25) in the TEST position for the reactor zone to be isolated. (Inboardand common valves) 2 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-1 for the reactor zone that is being isolated. NOTE: If a reactor zone is the only zone to be isolated, go to Section 6.4 and if the refuel zone is to be isolated complete Section 6.3 before going to Section 6.4. 6.3 Manual Isolation of the Plant Refueling Zone 6.3.1 Place 15-64-119 (Panel 9-25-1) in the TEST position. (Inboard and common valves) 2238 .529

Page 6 BF SI 4.7.C 5/2/78 SI 4.7.C Secondary containmnnt capabilitics 6. PROCEDUPC (Continued) 6.3 Manual Isolation of the Plant Refueling Zone (Continued) 6.3.2, Place 11S-64-122 (Panci 9-25-1) in the TCST 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 [ NOTP.: This section is to scrify that the secondary containment [ is capabic of maintaining a -1/4" !! 0 with a system 2 inicakage of < 12,000 cfm for the entire reactor building, or allowable, in-leakage for one or more zones,

  • 6.4.1 Adjust the total flou indicated on FI-65-50 and FI-65-71 l

(panci 9-25-2) to 11,500 cfm for entire reactor building or less than allowable flow for one or more zones as shosm in Appendix. A by closing a SGTS f an discharge damper'or if two fans are running it may be necessary to shut'ene fan off. i NOTE. Let the flow stabilize for 5 minutes before the next ctcp. I 6.4.2 Record flows indicated on FI-65-50 and FI-65-71 (panci 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. Zona _ Instrument Panel 5 U1RZ 1-PdIC-64-2 1-25-213 U2RZ 2 - Pd IC - 6 'e - 2 2-25-2!3 U3R7. 3 - Pd IC 2 3-25-213 UlRFZ 1-Pd 1C 1 1-25-219 U2RFZ 2-Pd IC 1 2'25-215 U3RFZ' 3-Pd IC 1 3-25-215 6.4.4 verify all four ::ones rtatic pressuren are 2 -1/4" 11 0. 2 q(@D! 2238 330

  • Reviston

Page 7 BF SI 4.7.C 5/2/78 SI 4.7.C Secondary contalicnent C mabilit ics i 6. PROCEDURE (Continued) 6.4 secondary Contalunent Capability (Continued) 6.4.5 Record the vind direction and velocity friom the 33 ft. level windspeed

  • 6.4.5.1 Record air temp. outside reactor building at ground level indicator.

Norr,: If all four zones static pressurcs: arc $ -1/4" 1I 0 this 2 will satisfy 4.7.C.1.b and c. If ione or more zones do C not meet the -1/4" 1I20 static pres:sure requirements the following steps must be completed. 1 NUIE: Check to assure reactor building is isolated.

  • 6.4.6 Adjust the total flow indicated on FI-65-50 and FI-65-71 (pal 9-25-2) to 12,000 cfm or allowable flow from Appenclix A for one or more zones by opening the fan discharge damper or it nuay be necessary to start another fan and adjusi: its discharge da:nper.
  • NOTP.:

let the flow s tabilize for 5 minutes before the next stop. Record flows indicated on FI-65-50 and FI-65-71 (pal 9-25-2) cnd total on Data Sheet SI 4.7.C-1. 6.4.7 Record the following static pressures. Zone ,I_n a t rument Panel ' UlRZ 1-Pd IC 2 1-25-213 U2RZ 2-PdIC-64-2 2-25-213 fU3RZ 3 PdIC-64 2 3-25-213 k 1-PdIC-64 1 1-25-219 g /UlRFZ U2RFZ 2-PdIC-64 1 2-25-215 U3RFZ 3-PdIC-64 1 3-25-215 6.4.8 Verify all four zoncs static presourcs are s -1/4" !! 0. 2 N0hE: If all four zones static pressures arc < -1/4" 110 this 2 uill satis fy 4.7.C.1.b and c. If one or more zones do the -1/4" 110 static prcosure requirement the not ucet 2 following steps must be completed. 6.4.9 Isolate the zone (s) tha: have a static pressure of > -1/4" II 0 2 from the remaining zones and indicate zones isolated on Data sheet SI 4.7.C-1. 6.4.10 Adjust the total flow indicated on FI-65-50 and FI-65-71 (pn1 9-25-2) to the Allowable Flov of the remaining nones. See Appendix A for the Allowable Flous. 7 2238 .531 D'*

  • Revision

Page 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) 6.4.10 (Continued) NOTE: Let the flow stablize for 15 minutes before the next step. 6.4.11 Record flows indicated on FI-65-50 and FI-65-71 (pn1 9-25-2) and total on Data Sheet SI 4.7.C-1. 6.4.12 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 2-25-2L5 U3RFf 3-PdIC-64-1 3-25-215 6.4.13 Verify the remaining zones static pressures are 5 -1/4" H 0. 2 NOTE: If these zones static pressures are < -1/4" H O this will 2 satisfy 4.7.C-2. Maintenance must be performed on the isolated zone and should be indicated on Data Sheet SI 4.7.C-1 cover sheet under Remarks. 6.4.14 Check those switches that were put in the TEST position under sections 6.2 and/or 6.3 in their NORMAL position and verify on a Data Sheet SI 4.7.C-1. 6.4.15 Verify on Data Sheet SI 4.7.C-1 those actions listed under l RETURN TO NORMAL for the zones tested. L so o ?) e

Page 9 EF SI 4.7.C 5/2/78 g pendix A Secondary Containment 1.cak Rate Test Crit cria During preoperational testing for unit 3 the following i'n-leakage rates at -1/4" 110 static pressure were documented. Doe:umented 2 Inlaakape

  • Percent ar,e 6250 64%

Common refuel floor (units 1, 2, & 3) Unit 1 reactor zone 1239 12.7% Unit 2 reactor zone 1064 10.9% 1211 12.4% Unit 3 reactor zone 9764 CFM Total secondary containment 100% Leak rate testing will ncrmally be done with cil zones simultaneously lined up for testing; however, ple.nt operating conditions and the technical specification When less than four zones (3-unit plant) are being tested, do not always permit this. the total allowabic inleakage will be based on preoperational testing and vill be based After a on the sum of the...owab1c inlcakag es for the zones being tested. secondary containment violation, the total inleakage must not be greater than the total of the allowabic inleakage for cach individual zone as indicated below. The technical specifications reqdire the total secondary containment inicokage The following are to be less than 12,000 cfn at -1/4" diff erential pressure. therefore established for surveillance testing various combinations of zones when secondary containment has been violated. Allowabi c Inicakage Zone ( 7680 Common refuel floor 15'24 Unit 1 reacto zone Unit 2 reactor *.one 1308 Unit 3 reactor conc jags l Reactor Building ( 12000 CFM i ~ }}}} j}}

  • Revisjon

.t b lh /

r I Page 10 y '. BF SI 4.7.C 5/11/76 DATA COVER SILEET SI 4.7.C-1 $[ SEC0ta\\RY COMTAlm1ENT CAPABILITY UNIT 1, 2[OR 3 [ V 19 f Performed By k 7/ Yarl Date k Unit 4perator /Yes No [ Were criteria satisfied? i If no, notify shift engineer, Yes (explain in If no, was a Limiting Condition for Operation violated? remarks) r tL Ho (explain in remarks) e1 ,Date Verified by Shift Engineer x Reason for test: v Maintenance complete on ) inoperabic Another system ( 0 Required by schedule { (b >\\ e M a t, s t/ Plant condition (explain)_ Other (explain) [" "2h N/ /. Date Results reviewed Assistant Shift fngineer Results Review and Approval ' k"" 8 T Date-V rz (1). Cognizant Engineer -v vu pu !i i Rescheduled q 'O ~ fun Date QA Staf f_ 4 RDLW3 i (1) Notify Maintenance that inicakage is excessive if criteria are not satisfied. 2 2 3 8 .i 3'4

3 '. rage -- BF SI 4.7.C 5/11/76 Data Sheet SI 4.7.C-1 (Continued) f1 0 Verify and/or Record Initials /Date Component / Process variable g Normal Q*4 i/b/74

  1. 'j 3.2 Rx. Bldg. Ventilation System MJ Standby Readiness 3.3 SGTS 3.4 Main Steam Line Tunnel Temperature f.150 F Ts3 i"

for units being tested n Not in Drywell or 3 3.5 16A-S34 for units tested Torus Bypass Currently Calibrated CM 3.8 F1-65-50 Currently Calibrated #M FI-65-71 k PdIC-64-1 (All three units) Currently Calibrated i Currently Ca'ibrated*~~~' PdIC-64-2 (All three units) r Closed and Seals i 3.9 Inboard Equipment Access Lock Doors M Inflated f 3.10 Drywell or Suppression Chamber Purge Not Inprocess C[ 3.11 Doors in the following table for the f tested zone (s) or the number doors M kl Closed for all zones. 0 0 O 2238 335 0 l B D d i o .._'t mes.

BF SI 4.7.C Table 3.11 5/11/76 Data Sheet S1 4.7.C-2 (Continued) t RFZ U3RZ U2RZ UIRZ ' _ Elevation 519.0 30 34, 36 40 31 35, 37 41 42 43, 44 45 541.5 255 l 565.0

  1. 221
  2. 236, # 241
  3. 249 242
  4. 231
  5. 237
  6. 250

.) 226 224

  1. 238
  2. 251 255 231
  3. 229 240
  4. 228 242
  5. 232 ec
  6. 230
  7. 230a w
  8. S26, # B27 583.0
  9. 298 593.0
  10. 538 497, 501 506
  11. 539
  12. 540
  13. 513 490
  14. 541
  15. 514 621.25
  16. 534 640, 647 651
  17. 637
  18. 648
  19. ~-657 635
  20. 649
  21. -658

} 675 639.0 670 67 2 673 1-704 700 713 7 17 724 715 700, 702, 724, 715, 713 664.0 705 701 714 225 716 701, 703, 725, 716, 714 717 712 715 /22 717 104; 720, 722, 165, 706 705, 721, 723, 708, 707 23 712 707 708 -w ~' 4moems

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Q' Page 13 D., BF SI 4.7.C DATA SIIEET SI 4.7.C-1 (Continued) 5/11/76 Step Component / Process variabic Verify and/or Record Initials /Date /t /8 9 6.1.1 U1RZ Configuration

  • / 71 6.1.2 U2RZ Configuration F'N

/ 6.1.3 U3RZ Configuration &M 6.1.4 RFZ Configuration 6/M ~ 6.1.5 U1RZ and RFZ Configuration 2NT j6.1.6 U2RZ and RFZ Configuration A'/N 6.1.7 U3BZ and RFZ Configuration /N 6.1.8 Reactor Building Configuration '6.2.1 1-11S-64-117 TEST Position

  1. //7 2-1G-64-117 TEST Position oN/A 3-IIS-64-117 TEST Position q

J 6.2.2 1-IIS-64-120 TEST Position /P /M 2-11S-64-120 TEST Position ~

  1. [/I 3-lis 120 TEST Position h hD 6.2.?

SGTS Train A START or SGTS Train B START I e or SGTS Train C START Unit 1 Reactor Zone k U-1 Reactor Zone Ventilation Sys. Shutdown f 1-FCo-64-13 Closed ,57 1-FCO-64-14 Closed A/// F!$ i 1-FCO-64-42 Closed V![ / U 1-FCO-64-43 Closed / Q l 2238.537 s -~

.a.. Page 14 BF SI 4.7.C 5/11/76 Data Sheet SI 4.7.C-1 ' Continued) Verify and/or Record Initials /Date Comoonent/ Process Variable _ h 6.2.3 (Continued) 4'/ M Y9/~Ff Open 1-FCO-64-15 C// Open 1-FCo-64-40 tk/8 Open / 1-FCO-64-41 O'M Closed 1-FCo-64-60A N/// Closed / 1-FCO-64-60B /7'/[. -[ Closed 1-FCO-64-60C N Closed 1-FCO-64-60D A;[/f Shutdown U-1 Stair Hall Supply Fan 9 Unit 2 Reactor Zone Shutdown. [ U-2 Reactor Zor,e Ventilation Sys Closed 2-FCO-64-13 V Closed 2-FCo-64-14 Closed 2-FCO-64-42 Closed 2-FCO-64-43 M/ Open 2-FCO-64-15 Open 2-FCo-64-40 Open 2-FCo-64-41 r f Unit 3 Reactor Zone 6/h? Shutdown U-3 Reactor Zone Ventilation Sys t W//' Closed 3-FCO-64-13 Oh Closed 3-FCo-64-14 W/ /1 f Closed 3-FCO-64-42 SI// Closed 3-FCO-64-43 /l?' N Open 3-FCO-64-15 _ 4;/ N $/ Open 3-FCo-64-40 2238 338

d Fage 13 BF SI 4.7.C Data Sheet SI 4.7.C-1 (Continued) 5/11/76 e, Step Component / Process Variabic_ Verify and/or Record Initials /Date b 6.2.3 (Continued) Unit 3 Reactor Zone (Continued) A'//d Of79 3-FCo-64-41 Open [ f ~ 3-FCO-64-60A Closed

  1. //7 3-FCO-64-60B Closed

//V//I 3-FCo-64-60C Closed ~ /)'[!I- 'I 3-FCO-64-60D Closed J ,-F//8 U-3 Stair Hall Supply Fan Shutdown 6.3.1 1-HS-64-119 TEST Positian (ff 6.3.2 1-HS-64-122 TEST Position 6.3.3 SGTS Train A START or SGTS Train B START or SGTS Train C START s/' 9 Refueling Zonc U-1 Area Refueling Zone Vent Sys Shutdown ~~ U-2 Area Refueling Zone Vent Sys Shutdown c/ U-3 Area Refueling Zone Vent Sys Shutdown 1-FCO-64-6 Close 2-FCo-64-6 Close 1 0 V i 3-FCo-64-6 Cloce N '/6/ 1-FCo-64-5 Close V/ LV. 2-FCo-64-5 Close WJ b# D I 3-FCO-64-5 Close Of I 1-FCO-64 Close 2-FCO-64-10 Close u ___, \\ 3-FCO-64-10 Closc Df'I'7 l s b h// A&ct&f' a) P 1 2238.339 8 w- = ..wo--

3 Pacc 16 DF SI 4.7 C , Continued) 5/2/78 ; ( g Data Sheet SI 4.7.C-1 [] Verify.and/or itecord_ Initials /nnte_ ,cg.ponent/Procer. Variabl_c g 6.3.3 (Cou'.inued) nornelin'* 7aan (Continued) 4/7' Close 1-rCo-64-9 Close 2-l'CO-64-9 '/ /~7 r Close 0-FCO-6'+ - 9 Open 1-FCO-64-63 Open 1-FCO-64-7 Close W 1-FCO-64-65A L 1-r'CO-64-65B Clcsc 1-FCO-64-65C cio,c l-FCo-64-65D Close N 1-FCo-64-44 Open a Open L ~1-FCO-64-45 Shutdoun Equipment Access Lock Er.haust Fan T1 Shutdoun U-l Stair IIall Supply Fan Shutdown .U-3 Stair Hall Supply Fan g gth e

  • U
i..

l L. g 200 sfem 6.4.9 F1-65-50 3 BOO --sfem j FI-65-71 DO sfem ^ O T..I L. ) h

  • P,cv i c ion

\\ 2738 .540 - - - - ~ ~ - - - _

  • ' "*-*ee,,,.,

0 , CW l Pnge 17 />' "*g BF SI 4.7.C 4 ' },.k.c Data Sheet SI 4.7.C-1 (cont inued) 5/2/78 seco component /Procens variabic Verify.ond/or Record Initialn/Date , 2 5' "11g0 Of YU!'77/ 6.43 1-PdIC Rx Zone

  • Thermometer Rc Zone 7F F

%'f 'f PdIC Rx Zone . Ye " 11 0 d 3 "* Thermometer Rx Zonc '7 9" F cyf "11g0 ve,4 g ?' 3-PdIC Rx Zone , ;t 7 b

  • Thermometer Rx Zonc f& '

F Tf PdIC Refueling Zone , tQ " 11 0 L414 2 t/' G d Pd IC Refueling Zone , 'l f "H O A/ 2 PdIC Refueling Zonc ~, dei "H O M 2 q Ne d ~

  • Thermometer Refueling Zonc

'/ f ' F 6.4. 4 All zones _$ -1/4" 110 2 r fvd 5 ([V ' Directio 'l

  • 6.4 5 33 ft. level / Uindspeed

,L 2Ph J 46.4.5.1 Thermometer / Outside temp. bts-- F f ' //[ ^ G A/. ,j 6.4. 6, FI-65-50 scfm / FI-65-71 scfm N/N q J. Total scfm +//iP s / O 6.4. 7 1-PdIC-64-2 Rx Zonc "1120 ry//4 U 2-PdIC-64-2 Rx Zone "}I 0 /t/// 2 3-PdIC-64-1 Rx Zonc " 11 0 Y[ 2 1-PdIC-64-1 Refueling Zone " 11 20 2-PdIC-64-1 Refueling Zone "It 0

  1. h 2

['/[, ~ 3-PdIC-64-1 Refueling Zone " 11 0 2 6.4.8 All zones < -1/4"It 0 [/% [

6. 4.9 Zones Isolated List

/P//[ /u//? e / -//N f

  • Revicion 3N/

kW nd#'j/ 1 /> 3 2238 .541

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Ugrr Z S 1 4. l. C. I s/4/7c) drTAcH F4EM r 1 ky 6f4f79 ( l. Poepose of To a nal3 e.e the effect of toindspeed in. excess a on the. test resu lt s 5 mph 2. CA t.c u t. A rio M L a. kJindspeed at 4he. time of eke. test coas 8 up%. b. Anai sis is cer o. red. for 4ke. efteas of s mph (s-s) 3 on 4 ke. -Les -)- results c. Per FS AR. i z. 2. z. 9. I 4.h e. d namic pressure s's 3 Ib 2 O.002.558 V. {tz. le hh'es ih S kanc e Ehts b e C o m.e 5 y oo2.s58 (33. lbp u. 4 ii, g ( i z ylF '4so 14o 2 . 00 44 'in gg ,3. 4NAt.9 sis. Assuming i n. e.v.ces s oM ne. a llo wa bl e that an$ uiend 5 mph has a detrimen Ea i e ffec.t clicec.-E l a pplica b l e ko khe. demo vis t rat.ed V AcoO m M k h e. 8 hecked E O n e. j s o b tract the. caicu late d ya to e. from the.. observe d Value as s ho u.)n bel oto. . S o - 6. oo 4 4) = -. 2.c) 5 G .Reac+or tone. = . ZB - (. co 44) = . 2 7 5 6 Re. foe.1 Eone = Siace. both utse valu e.s d e m o n s +ra t e. the regu,'re a Vacoom (. 2.s) and the. measu re d flee of 8800 cfm is b e.lo w h e. a no wa b le maximu% (8c)88 c5m.) it is d emo n stra ted hat th ere. is s u fficie n.t co n se rva tis % -Lo satnf 3 the h ecknica l s peciPiea-tm regui r'emest s - S$k ....2238 342~ ~ = u

- Step Component / Process Variable Verify and/or Record Initials /Date Return to Normal 6.411 FI-65-50 scfm NN / FI-65-71 scfm A//I Total scfm 6.4 J2 1-PdIC-64-2 Rx Zone "H2O 2-PdIC-64-2 Rx Zone "H2O k 3-PdIC-64-2 Rx Zone "H2O 4'/ 1-PdIC-64-1 Refueling Zone "H O // 2 a .2-PdIC-64-1 Refueling Zone "H O A'h 2 3-PdIC-64-1 Refueling Zone "H O [ 2 /7-[/N 6.413 Remaining zones < -1/4"HZO 7 r o 6.4.14 1-HS-64-117 NORMAL A' /N/ 2-1G-64-117 NORMAL / ' /V/N 3-1G 117 NORMAL r L ,(/N 1-HS-64-120 NORMAL n 2-1G-64-120 NORMAL N/ /k V/[ 3-1G-64-120 NORMAL 1-15 119 NORMAL /Nb 1-11s-64-122 NORMAL A'/h l ~~ 2238 343 h r ,.-,,.~.,.,- ry.,y, 3.,,., , g,, N ^.Q f.t.KQ3:'&:}7 ^ * ', ~ g;;;9;3l.g'7yy.w. 4,ypz.y;yy., ggp y ... ~.. -~~

3/11/ to Data Sheet SI 4.7.C-1 Verify and/or Record Initials /Dato Component / Process Variable g Return to Normal b /c// j A OFF 6.4. 15 SGTS Fan A v .O r Closed FCo-65-3 Yl+t OFF A-SCTS humidity control heater tw1 OR 0 ~N A-SGTS charcoal heater A/ OFF SGTS Fan B +/[ Closed FCO-65-25 AN OFF B-SGTS humidity control heater F ON B-SGTS charepal heater /f/M OFF SGTS Fan C - r//1 Closed FCO-65-51 A/// l OFF C-SGTS humidity control heater ON C-SGTS charcoal heater 1 i Unit 1 Reactor Zone _ In operation as required 1 U-1 Reactor Zone Ventilation System v// OPEN 1-FCO-64-13 /4/M \\ OPEN 1-FCo 14

  1. /[

OPEN 1-FCO-64-42 A' /M OPEN 1-FCO-64-43

  1. /2 Closed 1-FCO-64-15 c//

Closed 1-FCO-64-40 i A'//d i Closed k 1-FCO-64-41 /Y // Open 1-FCO-64-60A ? 4 '/ l Open 1-FCO-64-60B A/N Open ? 1-FCO-64-60C ( A7[ Open 1-FCO-64-60D U-1 Stair lla11 Supply Fan In operation a22T5 red 344 y r t - ~~~ ~~ ~n ,1 yspan,..,1.-.,;..-- y, 4 .n..

Data Sheet SI 4.7.C-1 (Continued) 5/11//b c i s, Step Component / Process Variabic Verify and/or Record Initials /Date 6.4 15 (Continued) Unit 2 Reactor 7,one U-2 Reactor Zone Ventilation System In operation as required b f. 2-FCO-64-13 Open yM 2-FCO-64-14 Open but 2-FCO-64-42 Open 2-FCO-64-43 Open 2-FCO-64-15 Closed v I 2-FCO-64-40 Closed L 2-FCO-64-41 Closed b V L Unit 3 Reactor Zone n U-3 Reactor Zone Ventilation System In operation as required o M/N 3-FCO-64-13 Open y A'/ M b 3-FCO-64-14 Open A'/N 3-FCo-64-42 open 4'/N 3-FCO-64-43 Open A/N 3-FCo-64-15 Closed 3-FCo-64-40 closed o'/8 N //f~ 3-FCO-64-41 Closed t

  1. /

3-FCO-64-60A Open 4/ l 3-FCO-64-60B open 4N h 3-FCO-64-60C open NO 3-FCO-64-600 open j

0 u-3 Stair nail Supply Fan In Operation as Required h

I 2238 345 g .l N w w a2x w a m e n, m y ;y m..g.4y;%.%g

.it ti s o Data Sheet SI 4.7.C-1(Conticaucd) verify.,nd/or necord Tnitialn/ nite. variable coy onent/yrocenn g,. n 6,4. 15 (Continued) Refueling Zone _ In Operation as required U-1 Area Refueling Zone Vent Sys In Operation as required Y U-2 Arca Refueling 7.onc Vent Sys t L In Operation as required U-3 Area Refueling Zone Vent Sys '7 q M Open v 1-FCO-64-6 b Open p 2-FCO-64-6 D] Open ,b 3-FCo-65-6 k Open u 1-FCo-64-5 Open ,L.. 2-FCO-64-5 b,f n Open 3-FCO-64-5 uha Open l-FCO-64-10 Open 2-FCO-64-10 ~ Open 3-FCO-64-10 Vb open 1-FCo-64-9 {3 b Open 2-FCO-64-9 Open 3-FCO-64-9 V \\ h I Close V \\ 1-FCO-64-63 h [ G Close V U 1-FCO-64-7 M .* l-FCo-64-65A Open P b' Ope'n

  • 1-FCO-64-65B Om
  • 1-FCO-64 65C Open

~ vb I Open .'}

  • 1-FCo-64-65D Close 1-FCO-64-44 V

t st l h '.' Close ~ / Q3 1-FCO-64-45 In Operation as required b g Equipment Access I.ock Ddianst Fan ? In Operation an required U-1 Stair 1[all Supply Fan in Operation as required U-3 St air Itall Supply ran L ..[., .~ t ~ ~ ~ ~ ~

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