ML20126J867
| ML20126J867 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 03/18/1981 |
| From: | Thickman H SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| Shared Package | |
| ML20126J865 | List: |
| References | |
| NUDOCS 8105050656 | |
| Download: ML20126J867 (300) | |
Text
{{#Wiki_filter:SO'JTH CAROLINA ' ELECTRIC 6 GAS COMPANY V.C. SUMMER NUCLEAR POWER STATION UNIT #1 JENKINSVILLE, SOUTH CAROLINA DOCKET #50-395 REACTOR BUILDING INTEGRATED LEAK RATE TEST (TYPE "A") FINAL TECHNICAL REPORT
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SOUTH CAROLINA ELECTRIC &. GAS COMPANY
.V.C. SUMMER-NUCLEAR POWER STATION i- UNIT'#1 f
JENKINSVILLE, SOUT11 CAROLIN A DOCKET # S0-395 , I 1 i ) i l
- i REACTOR BUILDING INTEGRATED' LEAK RATE TEST (TYPE A)
FINAL TECl!NICAL REPORT l 1 i
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l 4 i 1 i 1 1 j ! PREPARED BY: H.B. THICKMAN V.C. SUMMER START-UP MARCH 18, 1981 i j
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TABLE OF CONTENTS i 1.
Introduction:
1 :
- 2. Summary 2 l
- 3. Reactor Building Structure 3
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- 4. Instrument System Description 5- l
- a. Pressure Indicators (RB) 6 l l
- b. Temperature Indicators (RB) 6 'l i
- c. Dewpoint Indicators (RB) 6
- d. Atmospheric Indicators 7 .:
- e. Data Processor 7
- f. Instrument Location Drawing .8'
- g. Data Aquisition System Schematic 9 l
() h. Leak Rate Test Panel Schematic 10
- 5. Reactor Building Pressurization System 11 !
- 6. Description of the Computer Program used for V.C. Summer ILRT 13 f
i
- 7. Description of Events of the V.C. Summer ILRT 14
- 8. Description of Reactor Building Penetrations 17 j
- 9. LLRT-Type B & C Test Summary 25
- 10. Attachments - ,
I. Tabular Data for ILRT > II. Variable Plots for ILRT l III. Tabular Data for CLRT IV. Variable Plots for CLRT V. Copy of ILRT Procedure SUM-C146 1 10
l 1 {}- 1 - INTRODUCTION + i V.C. Summer Nuclear Power Station, Unit //1, of the South Carolina Electric & Gas Company, containment structure had i performed on it a Pre-operational Integrated Leak Rate Test i (Type A). This test was performed at the calculated-peak containment internal-pressure (Pa ) related to the Design i Basis ' Accident & specified in the Technical Specifications. , The method used to perform tnis test was the " Absolute Method." I
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This report describes & presents the results of the 7 Pre-operational Integrated Leak Rate Test performed in - h,). January 1981. , t h i i t i l l r t I t (2) i i i i (1) !
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SUMMARY
, During the1 month of January, 1981, the Integrated Leak Rate Test (Type A) was performediat a start pressure of 63 370 ,
psia. All Type "B" and "C" test were satisfactorily
. performed, with rework and retesta performed on all installed penetrations, as required. . For .tnis test all penetrations and' .
containment isolation valves were in their accident. position; exceptions during the test noted in Section-7 of this report. l The measured Total-Time Fitted Mass Point Leak Rate, @ the ' 95% confidence limit was 0.055% / day. A CLRT was' performed immediately af ter the ILRT as required by 10 CFR 50 > I the Ap%pendix J. The 95 confidence CLRT provided a leak rate of 0.168%/ day @ limit. () i 8 s
3-REACTOR BUI DING STRUCTURE , The-Reactor Building is a post tensioned, reinforced concrete ' structure with an integral steel liner. The reactor building consists of a cylindrical wall,~a shallow dome roof, and a foundation mat with a depressed incore instrument pit under , the ceactor vessel. The foundation mat bears. on fill concrete
.which extends to competent rock. At the foundation side of :
the reactor building foundation mat a tendon access gallery is formed into the top of the fill concrete. ; i
-The reactor building is lined on the inside face with a steel l plate liner which. forms a leak tight membrane. The liner is l not considered to provide structura1' reinforcement.
i i The reactor building foundation consists of a 12 foot thick . structural mat which supports the reactor building shell and l the concrete and steel internal structures. The structural , mat is supported by fill concrete which extends down to + competent rock. Thickness of the fill concrete varies from 27 l to 52 feet. t ('g The structural mat is circular in plan with a diameter of 154 '
\J feet and extends 10 feet beyond the reactor building shell ,
cylincrical wall. The incore instrument pit is located near-i the center of the mat and is " keyhole" in shape in plan. The base of the pit is 13 feet thick and the walls vary in thickness from 8 to 13 feet.
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A 6 foot wide by 8 foot high tendon access gallery is formed ! into the full concrete directly under the reactor building ! shell cylindrical wall. The gallery provides access to the i veritcal tendon anchorages. , The reactor building shell consists of concrete with a specified minimum compressive strength of 5000 psi and is t reinforced with reinforcing bars. The 4 foot thick cylindrical wall has an insice diameter of 126 feet and a height of 149 feet from the top of the structural mat (elev. ; 408 ft.) to the spring line (elev. 557 ft.). The 3 foot thick ! thallow dome roof has an inside central radius of 81 ft. 4 i 1/2 inches and a transition inside radius of 30 feet. S l I l (3) i
REACTOR BUILDING STRUCTURE CONT. , f'% : V The apex of the-outside face of the dome is located at elevation 602 ft. 0-1/4 inches. The shall is post tensioned by ungrouted tendons. Each tendon consirts of 170, 1/4 in. : diameter, stress relieved wires. The cylindrical wall *
. contains 115 vertical tendons and 150 hooptendons. The wall employs the three buttress - 240 degree hoop tendon concept. l The dome contains a total of 99 tendons arranged in a :
three-way system with 33 tendons per band. , t The reactor building shell is provided with a 16 foot ID i equipment hatch, a 9 foot OD personnel airlock and a 5 foot : OD personel emergency airlock. The wall is thickened to 7 feet 6 inches in the areas of the equipment hatch and , personnel airlock. Other major penetrations in the shell :' include 3 - 56 inch OD sleeves for main steam lines, 3 - 38 . irch in OD sleeves for feedwater lines and a 24 inch OD -i sleeve for the fuel transfer tube. Principal dimensions of the reactor building structure are as ; follows: f f's k/ Inside diameter 126 ft. 0 in. . Inside Height (to spring line) 149 ft. O in. Vertical Wall Thickness 4 ft. O in, i Dome Thickness 3 ft. + 1/4 in. i 0 - Foundation Slab Thickness 12 ft. 0 in. , Internal Free Volume 1.842 X 106 ft. 3 i l i i i
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-4 1 INSTRUMENT SYSTEM DESCRIPTION } i The reactor building was instrumented to permit the leakage rate determination by the " Absolute Method." The actual mass :
of dry air within the reactor building was calculated using ] the Perfect Gas Law: g i Q=PaV j RT where: Q = the actual mass of air , Pa = air partial pressure V = Reactor building volume (assumed to be constant , thru-out the test) ,_ ' R = gas constant , t T = reactor building temperature : i The " heart" of the data acquisition system is a Volumetrics Integrated Leak Rate System, Model 14640. This system , consists of: i
- 1. Reactor building temperature indicators (24) '
- 2. Reactor building dewpoint indicators (5)
- 3. Reactor building pressure indicators (3)
- 4. Verification test rotometers (2) '
/' 5. Atmospheric temperature indicator (1) ' _) - \ 6.-' Atmospheric pressure indicator (1) ;
- 7. Data processor (1)
This system uses both manual and automatic data acquisition. The following ILRT parameters are automatically scanned and recorded at preset intervals: ,
- 1. Reactor building temperatures ,
- 2. Reactor building dewpoint ,
- 3. Atmospheric temperature t
- 4. Atmospheric pressure Manually recorded data was taken at the same time intervals as the automatically recorded data. The manually recorded i data was: l
- 1. Reactor building pressure ;
- 2. Verification test rotometer flow ,
The manual and automatically recorded data were inputted to l the main test computer via a Texas Instrument Portable [ Computer Terminal. ; i i I o (5) { l
s L The computer used this data to compute the reactor building ; leak rate from the perfect gas law. (For a more detailed
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. ks'- computer program description-see Section-6). , A.. PRESSURE INDICATORS ( 3 )_ l The reactor building pressure was indicated by 3 independent pressure indicators. Two of these indicators were Mensor ; Percision Pressure Gauges, the third was a Heise Gauge. The j two Mensor Precision Gauges were considered " Test Gauges" ' with one (1) gauge being the primary instrument Land the other l an installed operating spare. The Heise Gauge was used only i for gross proosure indication and was not a " test gauge". ; Both Mennor Pressure Gauges were equiped with one-piece fused l quartz bourdon elements .with a range of 0-100 psia. 1
- 1. Monsor Precision Pressure Gauge - (Test Gauge) certified ;
accuracy 0.05% F.S. l resolution .001 ; capsule range 0-100 psia l maximum probable error .05 psia i
- 2. Mensor Precision Pressure Gauge (Spare) certified ;
accuracy' O.015%.F.S ! resolution . 001 l capsule range 0-100-psia ; maximum probable error .015 psia i fs km) 3. Heise Gauge (indication only) ; accuracy 0.1% ; resolution 0.1% psia i range 0-100 psi [ i B. Temperature RTD's (24) ,
- 1. Pyco 100 ohms ;
model accuracy 0.2 F resr'ution .001 l range 0-125 F , maximum probable error .2 F j I C. Dewpoint Transmitters (5) ;
- 1. General Eastern 1200 EPS i accuracy + 1% FS ;
resolution .001 i range 0-120 F ! maximum probable error 1.2, ;
!!OTE: See attached of Instrument Location Drawing. Data Aquisition l Schematic & Leak Rate Test Panel Schematic.
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D. Atmospheric' Indicators ;
- 1. Atmospheric temperature PYC0 ,
model 100 ohm accuracy 1% resolution' .001 range 0-125 : maximum probable error 1.2% ,
- 2. Atmospheric pressure ,
Rosemont
- model 1151AP5A22T0008PB accuracy 5% FS resolution .001 range 25 to 35 " .hg ,
maximum probable error .175" hg i E. Data Processor. Acurex . model Auto Date 9 () sol t on range b input -10 VDC to +10 VDC maximum probable error .5% FS 4 i v 1 I i P i P (7) .
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l l i . 'I' ) 5-REACTOR BUILDING PRESSURIZATION SYSTEM 4 i The reactor building was pressurized with clean, dry, oil free air. This air was supplied by the use of 10 oil free air ' compressors rated @ between 900 - 1500 SCFM. The 10 compressors were attached to an air compression header which directed the air thru air cooling and drying equipment to-the reactor building. i The air cooling and drying equipment consisted of:
- 1. Van Air System Inc. ,
Deliquescant Compressed Air Dryer
- 2. R.P. Adam Co. ,
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l t 6-Description of the Computer Program used for V.C. Summer ILRT q V ' The' computer and computer' program used during the V.C. Summer ILRT wasLaupplied thru Ebasco Company of N.Y.C., N.Y. This program has been used extensively and sucessfully both in the i U.S.A. and foreign countries. This program is highly sophisticated with many peripheral programs to assist in meeting the many aspects.of Type "A" testing; some'of these programs include: .
- 1. detection of Reactor building stabilization
- 2. automatic correction for instrument failure
- 3. automatic storage, retrieval and file handling
- 4. automatic correction for deleted sensor ,
- 5. instrument error.and 95% confidence limits. 1 Throughout the test, data was nanually entered via Texas Instrument 700 terminals. Temper ature, pressure and dewpoint '
were monitored at 15 minute intercals, entered into the computer and the first order linear regression leak rate was calculated using the perfect gas law. Raw data inputs were verified by requesting tabular or plotted computer output. This output was verified against raw data input. Each sensor was assigned a :
" volume fraction". Wieghted average temperature and partial pressure were computed according to the fraction of total free containment volume each was assigned. The computer program -
() automatically reassigned " volume fractions" for sensors deleted, if no spare was provided. A deleted sensor requires no further input. Throughout the progress of the test information ; was retrieved and listed in table or graph form. This ; information included such things as - l
- 1. raw data
- 2. simple leak rate ,
- 3. average temperature and dewpoint !
j
- 4. simple and total time statistical leak rate were evaluated to ensure completeness and accuracy of the j indicated test results. ;
Attachments I, II, III,& IV contain the tables, graphs, and i other major variables, including: l
- 1. vtatistical and simple leak rate
- 2. instrument errar analysis
- 3. tabular listings of raw data The information in Attachments I, II, III, & IV is for both the ILRT and CLRT. l l
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- 03) l l
a 1 I )- 7-Description of Events of V.C. Summor ILRT l The reactor building was .made ready for the start of j pressurization by first aligning all containment isolation 1 valves to.their accident position and then an independent valve verification was performed. Secondly a reactor building , inspection' was performed just prior to the start of- . pressurization. On January 9, 1981 0 1900 hours with the i dewpoint (MT-73064) deleted, the pressurization of the V.C. l Summer Station reactor building was started. Pressurization j was accomplished using 10 portable, oil free air compressors , of 900-1500 SCFM each. . t Between 2.6 and 4.1 psig the control room started recieving reactor building smoke alarms. At 4.0 psig reactor building ' pressurization was stopped, a reactor building entry and inspection was made. Upon the completion of the inspection with no unusual conditions found, and with concurrence of the shift supervisor reactor building repressurization was started. Reactor building pressurization was secured on 1/10/81, 0857 hours @ 50.25 psig. Reactor building stabilization was started ,
@ 0915 .
I) During the stabilization period it was noted that there was gross air leakage coming out of the main steam lines. It was a decided to reduce reactor building pressure to 10 psig and J inspect the steam generators. Depressurization started @ 1332 with reactor building pressure @ 49.7 psig. The reactor building was depressurized to 11.65 psig e 2129 and the building was entered @ 2144. This inspection revealed 3 vent - line pot valves open; no other leakage was apparent. The ; reactor building repressurization was started 82332 hours. The reactor building reached test pressure (50.25 psig) on [ 1/11/81 @ 0846. Reactor building stabilization was started @ 0900. Due to a high indicated leakage rate ' leak survey team : were sent to the field. A large leak was found on the Fuel Transfer Tube Blind Flange. This leak was stopped by placing i a blind flange on the Spent Fuel Bldg. side of the transfer tube, this was completed @ 2300 hours. On 1/12/81 e 0300 a leak was located on the mini-containment horizontal joint for penetration 327. QC was notified and the , bolts for the horizontal joint were retorqued; the leakage i was reduced to a small amount. RTD (TE-7307P) was deleted due to erratic readings 6 0550, 1 49.52 psis. i [') . (e : I 04)
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i I') Penetration 329, valve XVT 0029A-SI had water running out of , it, shut this valve @'0830. - On 1/13/81 @ 0002, 49 47 peig, it was. determined'that the , leakage - rate was still above V.C. Summer limits. The indication was that the steam generators were still leaking. To ensure-the leakage was from the steam generators, it was suggested that theysteam Generators be pressurized to 55 peig and see' - how this affected the indicated leak rate. The steam generators were pressurized with instrument air starting @ 0013 and completed @0345 At 0707' based on data evaluated during this time and the indicated reactor building leakage rate, it was determined that th'e steam generators (all 3) were still causing a leakage rate 4 greater than allowable. Reactor building depressurization was started @0730. At 2106 hrs the reactor building pressure was at i "0" psig and repair and leak survey teams entered. The steam generators, main-steam and feedwater lines, valve, instruments , etc were checked with snoop and repairs. vere made (see end of this section for a complete list of leakin6 equipment). - During this time already located leaks were also repaired; , this included the rep 3acement'of the Transfer Tube blind flange gaskets and the horizontal joint for the mini-containment of : penetration 327. Local leak test were performed on both the transfer tube blind flange (1) and the mini-containment: the ; transfer tube blind flange was tested satisfactorily, but the 7-)s (_ mini-containment still had a small amount of leakage and was isolated for the remainder of the test. l On 1/14/81 @ 0410 hrs. the reactor building access was secured and at 0514 hrs. pressurization of the reactor building commenced. At 1730 the reactor building presourization was stopped @ 49 45 - psig and stabilization period started.
- RTD (7307R) was deleted due to eratic indication @ 2345 ;
On 1/15/81 @ 0040, dewpoint (MT-7306D), was deleted due to erratic ' indication. l At 0345 @ 48.88 psig was the start of the 24 hour ILRT test i period. On 1/16/81 @ 0345 completed the 24 hour ILRT test period with l an indicated total time mass point leakage rate of 0.055% !
/ day @ 95% confidence limit. l This was within the acceptable cirteria for the V.C. Summer l Station. ;
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?[' ). At 0433 @ 48.88 ' psig af ter modifying the outlet tubing for FIL 7304'the CLRT was started. The flow rate used letedwas 8.14with SCFM. /
t At'1000 hours'@ satisfactory 48.60atpsig results the CLRT a leak was rate of comp % / day. At 1050-0.168 + reactor building depressurization was completed, .and followed by a
~
i reactor building inspection. The ILRT was satisfactorily completed ' ' on 1/16/81 @ 2133 . The following is a list of valves or equipment that was; _ repaired or adjusted during the unpressurized periods prior ; to the official start of the ILRT. ! r
- 1. Transfer tube blind flange - new gaskets installed and retested (LLRT) prior to start of.ILRT.
- 2. Pene. 327 Mini-Containment horizontal joint - repaired and retorqued hcrizontal joint - failed ILRT.(small amount of leakage) +
Blanked off for ILRT will require repair and LLRT after ILRT.
- 3. Valves requiring packing adjustments:
3103-SW 2912-SA ; 3107A-SW 3003A-SP 9606-CC 9568-CC ,
- 4. Leaks found during steam generators pressurization on l
( )' 1/13/81 and corrected prior to start of ILRT: ;
-- Main steam and steam generator transmitters (various) vent
- and drain valves.
-- Secondary hand hole covers on ISG 2A !
-- emergency feedwater check valves (XVC-1038A, 1039A) ,
-- secondary manway covers on XSG-2C
-- emergency feedwater check valves (XVC-10380, 10390)
-- swagelock fitting leaks on the following instruments: ;
LT-485 LT-497A LT-487A LT-497 LT-487 LT-477A j l f 1 i l () (16)
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'8'.' DESCRIPTION'OF-REACTOR BUILDING PENETRATIONS Page'l of 8 LINE 'i
-( N PENETRATION NUMBER SIZE -.- DESCRIPTION
%)
- 101 36"- Reactor Building Purge Exhaust .
102 16" Reactor' Building Cooling Unit B Return , ; 103' 6" Post Accident Hydrogen-Purge Line-104 -- Space a. 105A -3/8" H 2 Analyzer Supply , 105B- 3/8" H2. Analyzer Discharge 106 -- Spare 107 -- Fuel Transfer Tube , 108 -- Spare 201 2" Reactor Building Leak Rate Test Flow Test Line ; 202 32" Main Steam Loop C , 203 18" Feedwater Loop C !
.O 204 3" Component Cooling to Reactor Coolant [
Pumps l 205 4" Emergency Feedwater B , 206 18" Feedwater Loop B 207 32" Main Steam Loop B 208 -- Spare 209 -- Space ! 210 2" Reactor Building Leak Rate Test Pressure j Sensing Line j 211 8" Reactor Building Leak Rate Test Blowdown j 212 8" Reactor Building Leak Rate Test Blowdown ! 213 4" Emergency Feedwater C 214 -- Spare 215. -- Space t (17)
4 , . DESCRIPTION OF REACTOR BUILDING' PENETRATIONS , Page 2 of 8 j LINE . t J /~) - . PENETRATION ~ NUMBER- SIZE DESCRIPTION , b 216 8" Reactor Building Leak Rate Test-
. Pressurization Line {
217 1/4n Reactor Building Pressure' Sensing . (PT-953) i t Spare ! 218 __ 219 3" Steam Generator Blowdown Loop-C l r 220 3/8" Steam Generator. Blowdown Loop C Sampling l Line l
'I' 221 1-1/2" Seal-Injection to Reactor Coolant Pump Loop C 222 3" High Head Safety Injection to Reactor Coolant Loops j 223 3/8" Sampling Line'from Reactor Coolant Loop :
0 t 224 3" Steam Generator Blowdown Loop B ) 225 Steam Generator Blowdown Loop B Sampling
])' 3/'"
Line i 226 12" Residual Heat Removal Pump Suction from j Reactor Coolant Loop C , 227 10" Low Head Safety Injection to Reactor : Coolant Loops l 228 -- Spare 229 l-1/2" Seal Injection to Reactor Coolant Pump ! Loop B j l 230 -- Spare ; l 231 la Demineralized Water l l 232 __ Space l 301A: 3/8" H 2 Analyzer Supply 301B 3/gn H g Analyzer Discharge 302 6 Purge Pressure Blower Suction 303 10a Supply to Reactor Building Spray Nozzles i -(]) - Train B l i (18) ! t _- , o
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~ DESCRIPTION OF REACTIOR BUILDING' PENETRATIONS ,
- Page 3 of l' LINE O PENETRATION WUMBER' . SIZE- DESCRIPTION:
-A f j
.304 16" ; Service Water to Reactor Building Cooling j Unit A >
305- 16" Service Water from Reactor Building' Cool- l ing Unit A 3'06~ 18" Feedwater Loop A Emergency Feedwater'A 308 4" {
-309 10" Reactor Building High Range Area Monitor Capped Instrument Support ;
310 2" Reactor Building Station Service Air _
- t 311 2" Reactor Building Instrument Air -j 312 8" Component Cooling Water to Reactor ;
Coolant Pump Bearings ; 313 1" Nitrogen Supply to Feedwater Lines [ 314 3/8" Sampling Line From Reactor Coolant Loop B O 315 Space i 316- 12" Residual Heat Removal Pump Suction from :, Reactor Coolant Loop A ' 317 1" Fill Line to Accumulators 318 3" Reactor Coolant to Letdown Heat Exchanger 319 6" Reactor Building Instrument Air l Compressor Suction Line 320 1" Accumulator Nitrogen Supply l t 321 3/4" Accumulator Test Line ! 322 1C" Low Head Safety Injection to Reactor ; Coolant Loops ; 1 323 3/8" Accumulator Sampling Line 324 -- Spare 325 10" Low Head Safety Injection to Reactor i n Coolant Loop Hot Legs : U l l, i t i (19) I
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DESCRIPTION OF REACTOR' BUILDING PENETRATIONS ( .. 7 I Page 4 of 8
' PENETRATION NUMBER DESCRIPTION
.326 3" Steam Generator Elowdown Loop A 327 12" Spray Pump' A Suction.from Reactor Build-ing Recirculation. Sump
-328 -12". Spray Pump B Suction from Reactor Build-ing Recirculation Sump 329 14" . Safety Injection Pump A Suction from Reactor Building Recirculation Sump 330 su Component Cooling Water from. Reactor Coolant Pump Bearings 401 10" Supply to Reactor Building Spray Nozzles Train A 402 36" Reactor Building Cooling Supply 403 16" Reactor Building Cooling Unit B Supply 404 4a Fire Service Hose Reel Supply 405 3/8" Sampling Line from Pressurizer O.
'd
~
406A 1/8" Dead Weight Tester l 406B 1/4" Reactor Building Pressure Sensing Line (PT-952) , 3 407A la- Radiation Monitor Supply l 407B la Radiation Monitor Return ! 408 1-1/2" Seal Injection to Reactor Coolant Pump , Loop A 409 3" Charging Line to Regenerative Heat : Exchanger , 410 2" Reactor Coolant Pump Seal Water Return i 411 Steam Generator Blowdown Loop A Sampling ! 3/8" 412 3" High Head Safety Injection to Reactor Coolant Loops ; 413 -- Spare 414 __ Space O ! (20) !
-i l
f
gy cDESCRIPTION'0F REACTOR BUILDING PENETRATIONS
..Page 5'of 8
. ~. .
LINE PENETRATION NUMBER SIZE' DESCRIPTION'. , i .'v O' 1 415 3" 'High Head Safety Injection to Reactor ! Coolant Loop
.416 __.
Spare l
-417 Spare ,
'418 3/4" Reactor-Coolant Drain Tank!to Vent Header and H2 419 3" Refueling Cavity Drain Line i 420 1" Pressure Relief Tank 421 -3" Refueling Cavity Fill Line .
422 3" Pressure Relief Tank Makeup '! 423 3" Reactor Coolant Drain Tank 424 3" Reactor Building Sump Drain 425 14" Safety Injection Pump B Suction from Reactor Building Recirculation Sump ; O 426 3" Boron Injection to Reactor Coolant Loops 427 4" Fire Service Deluge 428 32" Main Steam Loop A i 500 1/4" Reactor Building Pressure Sensing
-(PT-951) ;
I 501 ELECT. Reactor Building Cooling Unit Fan j PENE. (Train."B") 502 Reactor Building Cooling Unit Fan (Train "B") l 503 Miscellaneous 480V. Power { 504 Reactor Coolant Pump "C" ; 505 Reactor Coolant Pump "C" 600 -- Spare 601 Reactor Coolant Pump B 602 Reactor Coolant Pump B :
-Q (21)
DESCRIPTION OF REACTOR BUILDING PENETRATIONS Page 6 of_8 i f~} v PENETRATION NUMBER. D_ESCRIPTION
' Protection. Inst. System Channel I I 603 ELECT.
.PENE. .
604. " Protection' Inst. System Channel III/ Train l "B" Inst. 605 Nuclear Inst. System Channel-I
'606 Nuclear Inst. System Channel III
.607 Miscellaneous Instrumentation 700
' control Rod Drive Power 701 control Rod Drive Power 702 Train A Inst.
703 1/4" Reactor Building Pressure Sensing (PT-950) t 704 -- Spare 705 control Train "A" Channel (Control) Q 706 Reactor Building Cooling Unit Fan (Train "A") 707 Control Rod Drive Power 1 l 708 Control Rod Drive Power [ 709
" Reactor Coolant Pump A .
710 " Reactor Coolant Pump A 711 Control Rod Position Indication & Incore i Temp. Theples i i 712 Movable Incore Detector Drive Control !
" Movable Incore Detector Drive Control 713 !
714 " Fixed Incore Detectors ! 715 " Process Inst. Oroup 3 & 4 ; 716 " T. V. and Communications & Movable Incore ! Detectors ; l 717
" Misc. 480V. Power .
O- !- (22) ,
. DESCRIPTION OF REACTOR BUILDING PENETRATIONS Page 7 of 8 PENETRATION NUMBER DESCRIPTION l
{) 718 ELECT. Leak Test and Dew Pt. Thermals PENE. 719 -- Spare - 720 " Protection Instrument Systen Channel II , 721 " Nuclear Instrument Systen Channel II 722 " Misc. 480V. Power 723 " control Train "B" Channel III (Control) 724 -- Spare
" Misc. Control 725 726 " Reactor Bldg. Cooling Unit Fan (Train "A")
727
" Reactor Bldg. Cooling Unit Fan (Train '
"A") -
728
" Reactor Bldg. Cooling Unit Fan (Train "A")
" Process Inst. Group 1 & 2 800 801 Radiation Monitoring 802 -- Spare 803 -- Spare 804 -- Space 805
" Reactor Bldg. Polar Crane & Reactor ;
Bldg. Power PNL. , i 807
" Reactor Building Cooling Unit Fan (Train "B") ;
F 808 " Reactor Building Cooling Unit Fan (Train :
"B")
809 Pressurizer Heaters 810 Pressurizar Heaters 811 -- Spare ; 812 Misc. Control ( )' [ I L (23)
l t t DESCRIPTION OF REACTOR BUILDING-PENETRATIONS 1-
. __ m_ _ ,
Page 8 of 8 ;
-i PENETRATION NUMBER DESCRIPTION ]. . .
813 ELECT. . Protection Instrument System Cha'nne.L IV j PENE." 814 Nuclear Iristrument System Channel . IV 815- - Pressurizer Heaters
--- Personnel Access Airlock [
--- - Personnel Escape Airlock
--- Equipment Access Hatch '
j
.t L
f i t t e s I j i i I i i I [ I i i f a f h O- ! f (24) :
i t I 9 LIRT ('lYPE B & C) TEST
SUMMARY
.I 1. ' TYPE B TEST . cc/ min. , Pene #' Description As Left Leak Rate 107 Fuel Transfer Tube . 0 - 201 L.R. System Blind Flanges (2) 0
- 210 L.R. -System Blind Flanges (2) 0 ,
211 L.R. System Blind Flanges (2) 0 ' 212 L.R.' System Blind Flanges (2) 0 216 L.R. System Blind Flanges (2) 0 6 327 SP Sys. Mini-Containment (valve enclouses) 0 l 328 SP Sys. Mini-Containment (valve , enclouses) 0 l 329 RH Sys. Mini-Contairunent (valve j enclouses) 0 425 RH Sys. Mini-Contairrnent (valve enclouses) 0 501. PT 951 0 , 502 Elect. Pene. 503 Elect. Pene. 0 504 Elect. Pene. 0 505 Space Pene. 600 Elect. Pene. 0 601 Elect. Pene. 0 602 Elect. Pene. O
\ 603 Elect. Pene. 0 ~
604 Elect. Pene. O 605 Elect. Pene. 0 606 Elect. Pene. 0 , 607 Elect. Pene. 0 700 Elect. Pene. 0 1 701 Elect. Pene. O 702 Elect. Pene. 703 PP 950 0 704 Elect. Pene. 0 705 Elect. Pene. 0 706 Elect. Pene. O ; 7 07 Elect. Pene. 0 708 Elect. Pene. O e 709 Elect. 'ene. 0 , O ! 710 Elect. rene. 711 Elect. Pene. O t 712 Elect. Pene. O j 713 Spare Pene. 714 Elect. Pene. 0 .i 715 Elect. Pene. 0 716 Elect. Pene. 0 l 717 Elecc. Pene. 0 718 Elect. Pene. O i O , 3 f (25) :
9 LUrr (TYPE B & C) TEST
SUMMARY
p, id- 1. TYPE B TEST-cc/ min. 1 Pene # Description As Lef't Leak Ibte , 719 Spare Pene. ' 720 Spare Pene. 721 Elect. Pene. 0 7.22 Elect. Pene. 0 723 Elect. Peno. 0 724 Spare Pene. Elect. Pene. 0 725 726 Elect. Pene. 0 727 Elect. Pene. O < 728 Elect. Pene. O i 800 ' Elect. Pene. 0 , 801 Spare Peno. 802 Elect. Pene. 0 803 Elect. Pene 0 ' 804~ Elect. Pene. 0 805 Elect. Pene. 0 806 Spare Pene. 807 Spare Pene. 808 Elect. Pene. T , 809 Elect. Pene. 0 810 Elect. Pene. 0 - 811 Spare Pene. Y]
/
812 Spare Pene. ! Elect. Pene. 813 0 614 Elect. Pene. 0 815 Elect. Pene. O Personel Air Lock T Bnergency Air Lock 40 Equipment Hatch 0 l P [ s I e (26)
I l -3 9 LLRT (TYPE B & C) TEST
SUMMARY
- 2. TYPE C TEST ,
ccAnin. Pene # l Description As Left Leak Rate 101 R.B. Purge Exhaust 300 102 R.B. Cool Unit "B" Return 25 103 Post Acc. H2 Purge Line 100 104 Spare 105A H2 Analyzer Supply 105B H2 Analyzer Return 106 Spare 108 Spare 204 C.C.W. to Reactor Cool Pumps 40 208 Spare 209 Spare 214 Spare 215 Spare 217 Pr 953 , 218 Spare 221 Seal Inj. to RCP-C 0 222 Hi.Hd. S.I. to RCS 70 223 Sample fran RCS-C 0 226 RHR Suction from RCS-C 0 227 Io. Ed. S.I. to RCS 162 n 228 Spare Pene. V. 229 Seal Inj. to RCP-B Space Pene. 25 230 231 Demin, Water 0 232 Spare Pene. 301A H2 Analyzer Supply 301B Analyzer Return 302 rge Press. Blower Suction 440 303 R.B. Spray Nozzles - Train "B" 240 304 S.W. to R.B. Cool Unit "A" 380 . l 305 S.W. From R.B. Cool Unit "A" 80 307 Spare Pene. . 309 R.B. Hi Range Area Monitor Support e 310 R.B. Station Air 440 311 R.B. Instrument Air 520 ; 312 CCW to RCP Bearirgs 0 313 N2 to F.W. Lines 460 ' 314 Sample from RCS-B 0 315 Spare Pene. ' 316 BHR Pump Suction RCS-A 60 317 Fill Line to Accumulator 0 RCS Intdown Heat Exchanger 420 : 318 319 R.B. Instrument Air Comp. Suction 320 320 N2 to Accumulator 255 i 321 Accumulator Test Line 0 322 Lo. Hd. S.I. to RCS - Hot Legs 0 0 ; (27)
1 l 9 LLRT (TYPE B & C) TEST SUbEARY
- 2. TYPE C TEST cc/ min.
Pene_# Description As Left Leak Rate 323 Accumulator Sample 0 324 Spare Pene. _ 325 Lo.Hd. S.I. to RCS - Hot Legs 222 327 Spray Pump "A" Suction From R.B. Sump 110 328 Spruy Pump "B" Suction From R.B. Sump *5664 329 S.l. Pp. A Suction Frcm R.B. Sump 0 330 CCW From RCP Bearings 800 , 401- Supply to RB Spray Nozzle - Train "A" 105 1 402 R.B. Cooling Supply 104 , 403 R.B. Cooling Unit B Supply 540 ! 404 Fire Service Hose Reel Supply 25 ) 405 Sample Line from Prez. 0 . 0 i 406A Dead Weight Tester 407A Radiation Monitor Supply 80 4078 Radiation Monoitor Return 135 408 Seal Inj. to RCP-A 0 409 Charging to Regen. Heat XR 70 - 410 RCP Seal Water Return 0 412 Hi. Bd. S.I. to RCS 235 413- Spare Pene. 414 Spare Pene. O 415 416 n1 na s 1 to aos Spare Pene. 7o 417 Spare Pene. 418 RCDP to Vent Edr. & Hp ~25 . 419 Refuel Cavity Dr. Line 90 : 420 Prez Relief Tk. 0 7 421 Refuel Cavity Fill Line 580 422 PRI Makeup 0 , 423 RCDP 40 424 R.B. Sump Dr. 480 425 S.I. Pp "B" frcm R.B. Sump 0 : 426 Boron Inj. to RCS 0 427 Fire Service Deluge 85 :
* '1'his penetration to be repaired arti retested after ILRT.
l The total local leakage rate for both Type B & C Test is: ) i 13,895 cc/ min. l
)
l t i
)
(28) l
. ,- ~ - . . . . . . . - . - . . . - . . . . . . -- .-. - . . . . . . ,
J e ; 1 i, i i i l 3
~
.i
.i i
.i f
ATTACID1DTI l,
'l
'l TABULAR DATA for ILitT {
I r f i f 9 l 4 Y f L i e t t L I i j O t,
.__---.-.--,--,...-...--.-....--..-...-.-.---...--..~,,..-,---.i
- . . _ . .~ _ ~ . . ._
- . _ . - - . , . - - . _ ~ _ .
( e SOUTH CAROLINA ELECTRIC.AND 3AS I VIRGIL C. SUMMERLSTATION i ILRT ! f
. LEAK RATE' COMPUTED USING MASS POINT METHOD l AS RECOMMENDED BY ANS N274 REVISION 2 i (CONTAINMENT SYSTEM LEAKAGE TESTING REQUIREMENTS) !
i TEST PERIOD STARTED AT '345 HOURS ON 15 JAN 1981 .!
.!e i
i A LEAST SQUARES FIRST ORDER FIT OF LEAK RATE TO TIME ! SHOULD, YIELD A SLOPE OF ZERO-AND AN INTERCEPT EQUAL , TO THE LEAK RATE AS COMPUTED AT THE INITIAL START TIME l THE EQUATION HAS THE FORM - L=ST+R j WHERE L - CORRELATED LEAK RATE l S - SLOPE OF CORREL?. TION' T - TIME IN HOURS l R - INTERCEPT LEAK RATE ! ( ! LEAK RATE = -0.002 HOURS + 0.091 PER CENT ! MEAN = 0.070 PER CENT f i l INITIAL CONTAINMENT AIR WEIGHT = 600051 LBS. FINAL CONTAINMENT AIR WEIGHT = 599743 LBS. ! FITTED MASS POINT LEAK RATE IS 0.054 PER CENT PER DAY l MASS POINT LEAK RATE AT UPPER 95% CONFIDENCE LIMIT l IS 0.055 PERCENT PER DAY l I i l MAXIMUM NRC LEAK RATE OF 0.150 PER CENT PER DAY j GIVEN FOR HIGH PRESSURE TEST AT 61.80 PSIA ! l 0
L f
/~% i k_[ >
~!
I i DESCRIPTION OF VARIABLES. 'l
)
AVG. TEM. . VOLUMETRICALLY WEIGHTED TEMPERATURE. f AVG. PRE - AVERAGE PRESSURE.- ~
-VAP. PRE /.VOLUMETRICALLYWEIGHTEDVAPOURPRESSURE. l LEAK COM - LEAK RATE COMPUTED FROM FIRST ORDER REGRESSION.
LEAK MAS - LEAK RATE FROM MASS POINT FIRST ORDER REGRESSION. 3 LEAK SIM - LEAK RATE BASED ON TOTAL TIME CALCULATIONS. ;
. AIR. MAS - AIR MASS DATA. j i
1 f i NOTE FOR CURVES- . l
- 1. TOP ABSCISSA SCALE REPRESENTS SAMPLE NUMBERS. [
- 2. ALL LEAKAGE RATE CURVES ARE BASED ON " TOTAL TIME" ;
METHOD ANALYSIS. t t t
< 3 ;
(_/ ; e NOTE FOR TABULAR DATA - t TABLE VALUES OF ZERO SIGNIFY EITHER
- 1. DATA IS NOT APPLICABLE TO THE CALCULATION OR l !
- 2. SENSOR HAS BEEN DELETED FROM THE SCAN.
i I i h I h I i r L i I 8 4 . . - . _ .._, -m , ., .. . , . .
.1
, ,. ~ ,- - ,- . . _ ~ . . . . . - --
VARIABLE TABLE
SUMMARY
)
g# SAM DELT" AVG. TEM' AVG. PRE VAP.~ PRE LEAK COM LEAK SIM'. LEAK MAS AIR MASS 1 l
'NUM MINS DEG. F. PSIA PSIA. PER CENT PER CENT. PER CENT' 1000 LBS .
1- 0- 63.739 63.370 0.125 0.090' O.000 0'.000 600.051' ! 2- -15 63.723 63.366' O.124 'O.090 0.275 0.000 600.034 l 3 30~ 63.714. 63.363 0.124 0.089 0.258 0.258 600.019 !
.4 45 63.693 63.362. .0.124 0.089- 0.104- 0.118 600.031 *
,- '5 60 63.668 63.360 0.125 0.089 0.051 0.045 '600.038 l
6 75 63.650 63.358 0.124' O.088 0.016 -0.000 600.046 , 7 '90' 63.632 '63.355 0.124 0.088 0.036 -0.002 '600.037 l 8 105 63.615 63.352 0.124 0.087 0.050 0.013 600.026 9 120- 63.604, 63.350 0.125 0.087 0.070 0.030 600.016- ., 10 135- 63.592' 63.348- 0.124 0.086 0.062 _ 0.037~ 600.016 ; 11 150 63.582 63.'346 0.124 0.086 0.073 -0.046 600.006- l 12 165 63.567 63.343 ' 0.124. 0.086- 0.082 0.057 599.994 13 180- ~63.555 63.341 O.124 0.085 0.077 0.062 599.993 l
~ 14 195 63.546 63.339 0.124 0.085 0.074' O.065- 599.990 l
.15. 210 63.525 63.335 0.124 0.084 0.093 0.073 599.970 16 225 63.514 63.334 0.124 0.084 0.078 0.075 599.977-17 240 63.504 63.333 0.124- 0.084 0.077 0.075 599.974 ,
18 255 63.492 63.330 0.124 0.083 0.085 0.078 599.961 i 19 '270 63.478 63.329 0.124 0.083 0.072 0.076 599.970 l 20 285 63.468 63.327 0.124 0.082 0.076 0.076 599.961 ; 21 300 63.459 63.326 0.124 0.082 0.071 0.075 599.962 { 22 315 63.445 63.324 0.124 0.082 0.075 0.075 599.953- ! 23 330 63.430 63.322 0.124 0.081 0.070 0.073 599.955 [ 24 345 63.428 63.321 0.123 0.081 0.067 0.072 599.955 63.423 l 25 360 63.319 0.124 0.080 0.077 0.072 599.936 26 375 63.408- 63.317 0.124 0.080 0.073 0.072 599.936 I 27 390 63.397' 63.316 0.124 0.000 0.073 0.072 599.932 ! 28 405 63.388 63.314 0.124 0.079 0.074 0.072 599.926 l 29 420 63.372 63.313 0.123 0.079 0.062 0.070 599.942 l 30- 435 63.376 63.311 0.124 0.078 0.077 0.071 599.911 ! 31 .450 63.363 63.309 0.126 0.078 0.083 0.0.73 599.896 32 465 63.349 63.309 0.124 0.077 0.067 0.072 599.922 33 480 63.340 63.306 0.125 0.077 0.075 0.072 599.901 ! 34' 495 63.329 63.305 0.124 0.077 0.069 0.072 599.908 l 35 510 63.328 63.304 0.125 0.076 0.073 0.072 599.896 { 36 525 63.321 63.303 0.125 0.076 0.074 0.072 599.889 i 37 540 63.316 63.301 0.124 0.075 0.073 0.072 599.886 ! 38 555 63.300 63.300 0.125 0.075 0.070 0.072 599.890 } 39 570 63.292 63.298 0.124 0.075 0.070 0.071 599.885 i 40 585 63.282 63.297 0.124 0.074 0.066 0.070 599.889 ! 41 600 63.281 63.296 0.124 0.074 0.069 0.070 599.879 ! 42 615 63.271 63.294 0.125 0.073 0.071 0.070 599.868 l 43 630 63.266 63.293 0.124 0.073 0.071 0.070 599.864 ? 44 645 63.253 63.292 0.125 0.073 0.069 0.070 599.865 .} 45 660 .63.257 63.291 0.124 0.072 0.070 0.070 599.857 i
'46 675 63.245 63.290 0.124 0.072 0.067 0.069 599.861 j 47 690 63.240 63.288 0.124 0.071 0.071 0.069 599.846 I 48 705 63.230 63.287 0.125 0.071 0.069 0.069 599.847 !
;49 720 63.225 63.286 0.124 0.070 0.067 0.069 599.849 l 50 735 63.216 63.285 0.125 0.070 0.070 0.069 599.836 4
51 750' 63.215- 63.283 0.125 0.070 0.071 0.069 599.829 ! 52- 765 63.206 63.282 0.125 0.069 0.071 0.069 599.825 i __ _ _ _. ._._I
VARIABLE TABLE
SUMMARY
(CONTINUED) i q k-) 53 780 63.200 63.281 0.124 0.069 0.066 0.068 599.835 54 795 63.188 63.281 0.124 0.068 0.064 0.068 599.838 55 810 63.189 63.279 0.125 0.068 0.068 0.068 599.821 56 825 63.182 63.279 0.124 0.068 0.064 0.067 599.830 57 840 63.178 E3.278 0.125 0.067 0.066 0.067 599.819 58 855 63.189 63.277 0.125 0.067 0.070 0.067 599.801 59 870 63.172 63.276 0.125 0.066 0.068 0.067 599.805 , 60 885 63.165 63.275 0.125 0.066 0.068 0.067 599.800 [ 61 900 63.162 63.274 0.124 0.066 0.065 0.066 599.806 62 915 63.159 63.273 0.125 0.065 0.068 0.066 599.791 63 930 63.160 63.272 0.124 0.065 0.067 0.066 599.789 64 945 63.143 63.272 0.124 0.064 0.061 0.066 599.809 65 960 63.142 63.271 0.125 0.064 0.063 0.065 599.797 66 975 63.138 63.270 0.125 0.064 0.063 0.065 599.793 67 990 63.132 63.270 0.125 0.063 0.062 0.065 599.794 68 1005 63.132 63.269 0.125 0.063 0.063 0.064 599.787 69 1020 63.124 63.269 0.124 0.062 0.058 0.064 599.802 70 1035 63.114 63.267 0.125 0.062 0.060 0.063 599.794 71 1050 63.110 63.267 0.125 0.061 0.059 0.062 599.793 i 72 1065 63.105 63.266 0.125 0.061 0.059 0.062 599.790 i 73 1080 63.102 63.265 0.125 0.061 0.060 0.062 599.780 74 1095 63.100 63.264 0.125 0.060 0.060 0.061 599.779 75 1110 63.089 63.262 0.125 0.060 0.060 0.061 599.773 76 1125 63.090 63.261 0.125 0.059 0.062 0.061 599.758 77 1140 63.088 63.261 0.125 0.059 0.061 0.060 599.760 () 78 79 1155 1170 63.079 63.073 63.260 63.259 0.125 0.125 0.059 0.058 0.060 0.060 0.060 0.060 599.762 599.759 ~ 80 1185 63.074 63.258 0.125- 0.058 0.060 0.060 599.752 . 81 1200- 63.070 63.258 0.125 0.057 0.060 0.060 599.751 I 82 1215 63.069 63.257 0.125 0.057 0.059 0.059 599.752 83 1230 63.066 63.257 0.125 0.057 0.058 0.059 599.752 3 84 1245 63.066 63.256 0.125 0.056 0.059 0.059 599.742 85 1260 63.062 63.256 0.125 0.056 0.057 0.058 599.750 86 1275 63.059 63.256 0.125 0.055 0.057 0.058 599.746 . 87 1290 63.050 63.255 0.125 0.055 0.056 0.058 599.748 ' 88 1305 63.042 63.254 0.125 0.054 0.056 0.057 599.748 89 1320 63.035 63.253 0.126 0.054 0.056 0.057 599.744 90 1335 63.032 63.252 0.125 0.054 0.056 0.057 599.741 91 1350 63.029 63.252 0.126 0.053 0.055 0.056 599.739 92 1365 63.033 63.252 0.125 0.053 0.056 *0.056 599.732 93 1380 63.,020 63.251 0.125 0.052 0.052 0.056 599.751 94 1395 63.020 63.250 0.125 0.052 0.053 0.055 599.742 95 1410 63.010 63.249 0.125 0.052 0.053 0.055 599.741 ' 96 1425 63.007 63.249 0.125 0.051 0.052 0.054 599.740 97 1440 63.006 63.249 0.125 0.051 0.051 0.054 599.743 98 1455 63.002 63.249 0.125 0.050 0.051 0.053 599.742 99 1470 62.996 63.246 0.126 0.050 0.054 0.053 599.720 100 1485 62.996 63.245 0.126 0.050 0.054 0.053 599.715 101 1500 62.995 63.243 0.125 0.049 0.056 0.053 599.700 102 1515 62.986 63.242 0.125 0.049 0.056 0.053 599.699 /~s 103 1530 62.991. 63.241 0.125 0.048 0.059 0.053 599.678 END OF TABLE
1 i
.l VARIABLE TABLE
SUMMARY
' SAM ' DELT -TEMP 1- TEMP 2~ TEMP 3 TEMP 4 TEMP 5 TEMP 6
.NUM MINS DEG. _F DEG.- F DEG. F DEG. F DEG. F DEG. F
- i 1 0 63.040 62.960 63.290 63.250- 64.410 63.350 l 2- 15 63.030 62.900 63.300 63.220 64.430- 63.330 i L '3 30- 63.010 62.930 63.290 63.210 64.380 63.330
4 45 63.000 62.870' 63.270 .63.180 64.360 ~ 63.290- l 5- 60 62.970 62.800 63.240 63.160 64.350 63.270 ; 6' 75 62.960. 62.830 63.230 63.160 64.340 63.240' l 7- 90 62.930 62.800- 63.200 63.130 64.340 63.240 t 8 105 '62.920 62.810 63.170' 63.120 64.320 63.210 ! 9 120 62.890 62.770 63.200 63.100 64.300 63.190 I 10 135 62.910 '62.760 63.210' 63.080 64.280. 63.190 .. 11 150 62.890 62.780 63.160- 63.090 64.290 63.180 l 12 165 62.890 62.760 63.120 63.060 64.270 63.170 l 13 180- 62.850 62.760 63.120 63.020 64.200 63.150 ! 14 195 62.840 62.740 63.100 63.010 64.260 63.130 i 15 210 62.810 62.730 63.080 63.010 64.230 63.090 I 16 225 62.000 62.690 63.080 63.010 64.240 63.090 -l 17 240 62.800 62.700 63.070 62.980 64.230 63.080 j 18 255 62.790 62.690 63.040 62.980 64.220 63.060 j 19 270 62.790 62.660 63.040 62.960 64.190 63.060 ? 20 285 62.770 62.670 63.000 62.950 64.190 63.040 l 21 300 62.740 63.640 63.030 62.940 64.190 63.030 - 22 315 62.740 62.620 62.980 62.950 64.160 63.030 i 23' 330 62.730 62.620 63.010 62.910 64.170 63.000 i 24 345 62.740 62.610 62.990 62.920 64.160 62.990 l 25 360 62.720 62.590 62.990 62.900 64.150 62.970 i 26 375 62.700 62.600 62.960 62.910 64.140 62.940 ! 27 390 62.690 62.590 62.970 62.880 64.140 62.950 f 28 405 62.680 62.580 62.940 62.880 64.120 62.940 t 29 420 -62.670 62.590 62.920 62.860 64.100 62.930 ! 30 435 62.660 62.580 62.900 62.860 64.110 62.920 'f 31 450 62.640 62.570 62.920 62.850 64.070 62.910 i 32' 465 62.640 62.550 62.920 62.840 64.080 62.900 33 480 62.630 62.550 62.890 62.840 64.060 62.900 34 495 62.630 62.510 62.890 62.800 64.040 62.890 . 35 '510 62.610 62.500 62.890 62.810 64.050 62.860 I 36 525 62.620 62.540 62.900 62.800 64.050 62.850 i 37 540 62.610 62.500 62.880 62.800 64.050 62.860 l 38 555 62.620 62.510 62.850 62.780 64.030 62.840 j 39 570 62.580 62.480 62.870 62.770 64.010 62.820 l 40 585 62.570 62.460 62.840 62.780 64.030 62.830 ; 41 600 62.570 62.470 62.860 62.770 64.020 62.820 l 42 615 62.550 62.470 62.820 62.750 63.990 62.810 - I 43 630 62.560 62.450 62.830 62.740 63.980 62.810 ! 44 645 62.540 62.440 62.800 62.720 63.980 62.800 ! 45 660 62.550 62.450 62.830 62.740 63.980 62.810 l 46 675 62.550 62.450 62.790 62.720 63.960 62.780 l 47 690 62.520 62.420 62.780 62.730 63.970 62.790 ) 48 705 62.520 62.400 62.810 62.700 63.960 62.780 l 49 720 62.530 62.380 62.820 62.720 63.950 62.750
.O.- 50 735 62.500 62.400 62.780 62.710 63.940 62.750 1 51 750 62.490 62.390 62.770 62.680 63.950 62.740 !
52 765' 62.490 62.380 62.760 62.690 63.940 62.750 l l i
i-H
. VARIABLE TABLE
SUMMARY
(CONTINUED)
/~N k l: 53 780 62.490 62.400 62.750 '62.660 '63.920 62.740 54 1795 62.470 '62.380 62.730 62.680 63.920 62.740 155 810 ~62.490 62.400 62.760 62.680 63.910 62.720 56 -825 62.460- 62.360 62.740 62.660 63.900 62.700 57 840 62.470 62.370 62.730 62.670 63.910 62.700 58 855 62.490 62.390 62.760 62.670 63.910 62.720 59 870 62.450 62.350 62.720. 62.660 63.890 62.720 60 885 62.460 62.360 62.720 62.640 63.800 62.700 61 900 62.450 62.390 62.700 62.650 -63.880 ~62.700 62 915 62.450 62.360 62.710 62.650 63.870 62.690 63 930 62.430 62.370 62.730 62 630 63.860 62.680 64 945' 62.450 62.340 62.720 62.620 63.890 62.670 65 960 62.440 62.340 62.680 62.620 63.870 62.680 66 975 62.420 62.350 62.690 62.630 63.850 62.670 67 990 62.400 62.330 62.690 62.610 63.850 62.670 68 1005 62.420 62.330 62.710 62.620 63.860 62.680 69 1020 62.390 62.300 62.710 62.610 63.870 62.670 70 1035 -62.390 62.300 62.660 62.600 63.840 62.670 71 1050 62.410 62.300 62.660 62.600 63.830 62.660 72 1065 62.400 62.280 62.670 62.590 63.030 62.640 73 1080 62.390 62.280 62.650 62.580 63.830 62.640-74 1095 62.380 62.300 62.670 62.570 63.830 62.640 75 1110 62.390 62.300 62.640 62.560 63.820 62.620 76 1125 62.370 62.280 62.640 62.570 63.820 62.630 77 1140 62.360 62.300 62.640 62.570 63.810 62.620
() 78 1155 79~ 1170 62.370 62.360 62.240 62.260 62.640' 62.640 62.560 62.530 63.800 63.790 62.620 62.610 80 1385 62.370 62.290 62.620 62.530 63.810 62.610 81 1200" 62.380 62.270 62.640 62.530 63.800 62.610 82 1215 62.360 62.280 62.640 62.550 G3.790 62.610 83 1230 62.350 62.290 62.630 62.550 63.770 62.600 84 1245 62.360 62.290 62.650 62.560 63.790 62.590 85 1260 62.340 62.290 62.630 62.540 63.770 62.600 86 1275 62.370 62.270 62.620 62.560 63.770 62.600 87 1290 62.340 62.250 62.640 62.510 63.770 62.570 88 1305 62.350 62.230 62.620 62.500 63.760 62.580 89 1320 62.330 62.240 62.600 62.530 63.750 62.580 90 1335 62.330 62.250 62.600 62.530 63.760 62.580 91 1350 62.310 62.240 62.600 62.530 63.750 62.570 92 1365 62.330 62.230 62.640 62.510 63.740 62.560 93 1380 62.300 62.200 62.600 62.480 63.730 62.560 94 1395 62.300 62.230 62.610 62.500 63.720 62.560 95 1410 62.280 62.240 62.610 62.500 63.730 62.560 96 1425 62.300 62.190 62.600 62.400 63.720 62.550" 97 1440 62.280 62.200 62.590 62 470 63.720 62.560 98 1455 62.300 62.200 62.590 62.500 63.730 62.550 99 1470 62.290 62.220 62.580 62.480 63.690 62.550 100 1485 62.270 62.210 62.580 62.480 63.720 62.550 101 1500 62.300 62.190 62.550 62.450 63.700 62.540 102 1515 62.260 62.190 62.570 62.470 63.690 62.530 103 1530 62.290 62.200 62.590 62.470 63.690 62.530 0 END OF TABLE
l l i VARIABLE TABLE
SUMMARY
(~)
\ SAM 'DELT.-TEMP 7 TEMP 8 TEMP 9' TEMP 10 TEMP' 11 TEMP 12
-NUM MINS DEG. F DEG. F DEG. F DEG.' F DEG. F DEG. 'F '
1 0 63.590 63.050 63.280 63.410 63.460 64.490 ; 2 151 63.530 63.000- 63.280 63.410 63.490 64.500 ) 3 '30 63.500 63.020 63.340 63.380 63.480 64.490 4 45 63.490 62.950 63.310 63.380 63.520 64.460 , 5 60 63.450 62.870 63.230 63.380 63.430 64.430 l i 6' 75. 63.400 62.870 63.220 63.340 63.420 64.400 L7 90 63.440 62.880 63.220 63.300 63.370 64.390
- 8 105" 63.390' 62.910 63.270 63.280 63.340 64.380 l 9 120 63.360 62.850 63.150 63.280 63.400
'64.360 10 135 63.330- .62.780 63.180 63.290 63.350 64.350 11' 150 63.280 62.860 63.200 63.260 63.320 64.320 l 12 165 63.280 62.860. 63.160 63.240 63.310 64.320
'13- 180 63.310- 62.820 63.130 63.250 63.300 64.3.40 ;
14 195 63.280 62.770 63.210' 63.220 63.350 64.300 "
-15 210 63.290 62.780 63.130 63.180 63.330- 64.290 16 225 63.270 62.730 63.140 63.180 63.260 64.270 l 17 240 63.290~ 62.720 63.130 63.170 63.270 64.250 f 18 255 63.250. 62.730 63.100 63.150 '63.220 64.250 i 19 270 63.230 62.760 63.080 63.140 63.200 64.240 j
-20 285 63.220 62.730 63.100 63.120 63.180 64.230 !
21 300 63.230. 62.770 62.990 63.130 63.220 64.220 f 22 315 63.190 62.720 63.000 63.110 63.180 64.220 i 23' 330 63.190 62.670 63.000 63.080 63.130 64.220 () l 24 345 63.200 62.670 63.010 63.100 63.160 64.200 25 360 63.180 -62.670 63.020 63.100 63.200 64.190 26 375 63.170 62.650 63.020 63.060 63.160 64.170 ' 27 390 63.150 62.650 62.970 63.050- 63.160 64.170 ! 28 405 63.160 62.650 62.970 63.030 63.130 64.160 l 29 420 63.110 62.650 62.950 63.030 63.080 64.150 :
- 30 435 63,140 62.650 62.980 63.040 63.100 64.170 j 31 450 63.130 62.650 63.000 63.010 63.070 64.150 }
32 465 63.120 62.590 62.950 63.030 63.080 64.140 ! 33 480 63.090 62.640 62.960 63.010 63.070 64.130 ; 34 495 63.150 62.530 62.930 62.980 63.100 64.120 r 35 510 63.120 62.580 62.970 63.000 63.100 64.120 ; 36 525 63.090 62.560 62.880 63.000 63.100 64.120 t 37 540 63.070 62.510 62.950 62.990 63.100 64.090 ! 38 555 63.000 62.600 62.880 62.960 63.040 64.100 39 570- 63.070 62.540 62.910 62.970 63.060 64.100 ' 40 585 63.040 62.510 62.860 62.940 63.020 64.080 ! 41 600 63.000 62.510 62.870 62.940 63.050 64.070 42 615 63.020 62.510 62.880 62.960 63.020 64.080 f 43 630 62.970 62.570 62.880 62.920 62.980 64.070 !
. 44 645 62.970 62.550 62.840 62.910 63.000 64.060 l 45 660 63.040 62.490 62.850 62.930 62.980 64.060 j 46 675 62.980' 62.490 62.830 62.900 63.010 64.040 i 47 690 62.990 62.490 62.830 62.900 62.960 64.030 '
48 705 63.020 62.460 62.830 62.900 62.940 64.020 ,
/"' 49 720 62.930 62.450 62.830 62.890 62.980 64.000 !
50 735 62.940 62.410 62.800 62.860 62.980 64.010 I 51 750 62.970 62.480 62.830 62.880 62.940- 63.990 I 52- 765 62.940 62.490 62.800 62.000 62.920 64.010 i [ t
. j
. . . -- --. -. =
b
i, n VARIABLE TABLE
SUMMARY
~ (CONTINUED) . :
. '-pli 53 780- 62.920 62.430' 62.820 62.880 62.910 63.990 54, 795 62.910 62.450 62.740 62.840 62.860 64.000 55 810 62.910' 62.420 62.740~ 62.860 62.950 63.970 ! 56 -825- 62.950 62.430 62.770 62.840 62.920 63.980 . C7 840. 62.890- 62.450 62.770 62.840 62.900 63.970 [ 58 855 62.880 62.460 62.770 . 62.860 62.900. 63.980 l 59 870 62.890 62.430 62.780 62.830 62.900 63.970 : 60 885 I 62.900- 62.460 62.770 62.820 62.880 63.970 !
- 61. .900- 62.870 62.420 .62.760 62.820 62.920 63.970 62- 915 62.860 62.470 62.730: 62.850 62.880 63.960 ;
63 930 62.910 . 62.450 62.800 ' 62.810 62.900 63.980 ; 64 945 62.810 62.360 62.760 62.820 62.880 63.940 , 65 960 62.800 62.410 62.720 62.820 62.900 63.950 i
'66 975 62.860 52.400 62.700 62.820 62.900 63.930 i 67 :900 62.860 62.380 62.740 62.800 62.880 63.930 !
68 1005- 62.820 62.370 62.730 62.800 62.920 63.930 69 1020 62.830 62.350 62.700- 62.800 62.890 63.920 i 70' 1035 62.850 62.340 ~ 62.750 62.770 62.840 .63.920 l
'71 1050 62.810 62.370 62.670 62.760 62.860 63.910 :
72 1065 62.810 62.340 62.690 62.790 62.890 63.900 ! 73 L1080 62.780 62.380 62.680 62.780 62.840 63.900 l
-74 1095 62.790 62.360 62.690 62.780 62.860 63.880 :
- 75. 1110 62.770 62.350 62.690 62.750 62.850 63.890 I 76 1125- 62.770 62.380 62.710 62.770 62.840 63.870 '
77 1140 62.810 62.380 62.680 62.760 62.860 63.880 () 78 1155 79 .1170 62.810_ 62.760 62.330-62.340 62.660 62.670 62.770 62.750 62.880 62.830 63.880 63.870
~!
l 80 1185 62.760 62.350 62.680 62.750 62.870 63.860 l 81 1200 62.750 62.320 62.650 62.760 62.870- 63.880 ) 82 1215 62.770 62.370 62.620 62.720 62.870 63.890 83 1230 62.780 62.350 62.650 62.740 62.850 63.870 84 1245 62.760 62.360 62.670 62.750 62.830 63.870 . 85 1260 62.780 62.330 62.650 62.740 62.880 63.850 1 86 1275- 62.730 62.350 62.680- 62.720 62.880 63.850 l 87 1290 62.730 62.340 62.620 62.730 62.890 63.850 l 88 1305 62.680 62.340 62.670 62.730 62.860 63.820 j 89 1320 62.680- 62.330 62.660 62.720 62.840 63.830 ; 90 1335 62.680 62.300 62.640 62.720 62.810 63.820 l 91 '1350 62.690- 62.330 62.630 62.700 62.800 63.840 ! 92 1365 62.700 62.310 62.670 62.720 62.850 63.810 93 1380 62.700 62.320 62.640 62.720 62.820 63.810 : 94 1395 62.680 62.310 62.630 62.700 62.840 63.810 95 1410 62.690 62.260 62.640 62.680 62.800 63.800 96 1425 62.690 62.270 62.610 62.690 62.780 63.800' 'I 97 1440 62.650 62.260 62.650 62.690 62.840 63.800 l 98 1455 62.650 62.260 62.580 62.690 62.810 63.770 1 99 1470 '62.700 62.280 62.570 62.690 62.780 63.800 100 1485 62.680 62.300 62.570 62.670 62.790 63.770 1 101' 1500 61.690 62.300 62.640 62.660 62.800 63.780 ; 102 1515 62.700 62.260 62.610 62.680 62.730 63.770 62.650 62.300 62.660 62.680 62.730 63.770 103 1530 END OF TABLE a
)
. VARIABLE TABLE
SUMMARY
SAM 'DELT TEMP 13 TEMP 14 ' TEMP 15 TEMP ,16 TEMP 17 TEMP 18
- NUM MINS DEG.- F DEG. F DEG.- F DEG. F .DEG. F DEG. F 1 0- 64.000' 64.500 64.720 0.000 63.250 0.000 2 '15 63.980 64.490 64.690 0.000 63.240 0.000
-.3- .30 63.960 ,64.480 64.680 ' O.000 , 63.210 0.000
;; 4 ;45 :63.940 64.470 64.660 0.000 63.210 0.000 5 60 63.920 64.460- 64.640 0.000 63.170 0.000 6 75 63.880 64.470 '64.630 t 0.000 63.170 _0.000
'7 90 63.860 64.440 64.600- 0.000 63.140 0.000 105 63.840 '64.390 64.580 0.000' '63.120 0.000 9 '120- 63.860 64.400' 64.580 0.000 63.120 0.000 10 135- .63.840 64.400 64.550- 0.000 63.110 0.000
-11 150 63.820 '64.380 64.540 0.000 63.090 0.000 12 165 63.810 64.380 64.530 0.000 63.070 0.000 13 '180 63.800 64.350 64.520 :0.000 63.060 0.000 14 195 -63.810- 64.370- 64.500 0.000 63.050 0.000 15 210- 63.770 '64.310 64.500 0.000 63.050 0.000 16- 225 63.760 64.340 64.480 0.000 63.020 0.000 17 240 63.750- 64.320. 64.450 0.000- 63.010 0.000 18 255- 63.730 64.320 64.450 0.000 63.000 0.000 19 270 '63.730 64.280 64.460 62.980 0.000 0.000 20 285 63.730 64.290 64.450 0.000- 62.980 0.000 21 300 63.710 64.250 64.430 0.000 62.970 0.000 22 315 63.720 64.240 64.420 0.000. 62.940 0.000 23 330 63.670 64.220 64.400 0.000 62.930 0.000
( 24- 345 63.680 64.250 64.390 0.000 62.930 0.000-25 360 63.690 64.250 64.380 0 000 62.930 0.000 26 375 63.660 .64.200 64.390 62.910 27 0.000 0.000 390 63.650 64.200 64.360 0.000 62.900 0.000 28 405 63.650 64.170 64.350 0.000 62.900 29 0.000 420 63.630 64.160 64.340 0.000 62.890 0.000 30 '435 63.640 64.170 64.340 0 000 62.860 31-0.000 450 63.630 64.150 64.310 0 000 62.870 32 0.000 465. 63.610 64.150 64.270 0.000 62.860 0.000 33 480 63.590 64.120 64.240 0.000 62.850 0.000 34 495 63.600 64.120 64.220 0 000 62.860 0.000 1 35 510 63.600 64.140 64.200 0.000 62.840 0.000 36- 525 63.600 64.130. 64.200 0.000 62.840 0.000 37 540 63.580 64.150 64.190 0.000 62.840 0.000 38 555 63.580 64.100 64,170 0.000 62.810 0.000 39 570 63.540 64.070 64.170 0.000 62.800 0.000 40 585 63.530 64.100' 64.170 0.000 62.800 0.000 i 41 600 63.530 64.120 64.140 0.000 62.800 0.000 42 615 63.510 64.080 64.150 43 0.000 62.790 0.000 ' 630 63.510 64.080 64.130 0.000 44 62.770 0.000 645 63.480 64.040 64.120 0.000 45 62.760 0.000 660 63.500 64.060 64.110 0.000 46- 675 63.500, 62.760 0.000 64.060 64.100 0.000 62.770 0.000 47 690, 63.490 64.040 64.090 0.000 62.760 0.000 48 705' 63.460 64.030 64.080 0.000 62.750 0.000 ! f"g- '49 720- 63.460 64.060 64.090 0.000 62.750 0.000 V 50 .735 63.480 64.030 64.070 0.000 62.730 51 750 63.460 0.000 i
.64.030 64.070 0.000 62.740 0.000 52 765 63.430 64.000 64.070 0.000 62.720 0.000
?
i VARIABLE TABLE
SUMMARY
(CONTINUED) b q(/ ' L- ~ 53' 780 63.460 64.010 64.060 0.000 62.720 0.000 54- .795' 63.440 '63.980 64.040 0.000 62.710 0.000 ; 55 810 63.420 63.990 64.030 'O.000- 62.710 0.000 l 56- 825 63.440- 63.970 64.030 0.000 62.710 0.000 ; 57- .840. 63.440 63.960 64.020 0.000 62.700 0.000 l 58 . 855 .63.440 63.980 64.020 0.000 62.700 0.000 59 870 63.410 63.960 64.020 0.000 '62.690 0.000 t 60' 885 63.420 63.950 63.990 0.000 62.670 0.000
'61 900 63.390 63.960 64.000 0.000 62.670 0.000 l 62 915 63.420 63.940 63.990 0.000 62.660 0.000 >
63; 930 63.380 63.940' 63.980 0.000. 62.670 0.000 ! 64 945- 63.380 63.970 63.960 0.000 62.650 .0.000 65 !960l -63.400 63.960 63.960 0.000 62.640 0.000 } 66 975 63.380 63.920 63.960 0.000 62.660 0.000 67 990 63.380 63.940 63.950 0.000 62.630 0.000 l 68 1005 .63.390 63.920 63.950 0.000 62.640 0.000 i 69: 1020 63.380- '63.940 63.940 0.000 62.630 0.000 i 70 1035- 63.350. 63.910 63.950 0.000 62.620 0.000 { 71 1050 63.380 63.900 63.920 0.000 62.630 0.000 ! 72 1065 63.340 63.900 63.920 0.000 62.620 0.000 [ 73 1080 63.370 63.900 63.920 0.000 62.610 0.000 - 74 1095' 63.320 63.940 63.920 0.000 62.620 0.000 l 75 1110' 63.320 63.870 63.920 0.000 62.610 0.000 !
.76 1125 63.320 63.880 63.920 0.000 62.590 0.000 ,
77 1140 63.320 63.860 63.910 0.000 62.590 0.000 () 78 1155 79- 1170 63.330 63.340 63.860 63.860 63.890 63.880 0.000 0.000 62.590 62.590 0.000 0.000 l'
'80 1185 63.290 63.880 63.880 0.000 62.590 0.000 81 1200 63.320 63.860 63.870 0.000 62.600 0.000 82- 1215 63.310 63.840 63.870 0.000 62.560 0.000 83 1230 63.310 63.850 63.870 0.000 62.560 0.000 i 84 1245 63.300 63.840 63.860 0.000 62.570 0.000 l 85 1260 63.290 63.820 63.860 0.000 62.570 0.000 !
86 1275 63.290 63.850 63.850 0.000 62.560 0.000 87 1290 63.310 63.840 63.840 0.000 62.550 0.000 j 88 1305 63.300 63.840 63.850 0.000 62.550 0.000 > 89 1320 63.270 63.820 63.830 0.000 62.540 0.000 l 90 1335 63.290 63.830 63.830 0.000 62.550 0.000 1 91 1350 63.260 63.810 63.830 0.000 62.520 0.000 l 92 1365 63.270 63.820 63.830 0.000 62.550 0.000 ) 93 1380 63.270 63.810 63.820 0.000 62.520 0.000 l 94 1395 63.270 63.800 63.810 0.000 62.530 0.000 ) 63.240 63.790 63.820 0.000 95 1410 0.000 62.510 96 1425 63.270 63.780 63.810 0.000 62.520 0.000 97 1440 63.260 63.770 63.800 0.000 62.520 0.000 98 1455 63.240 63.800 63.790 0.000 62.520 0.000 99 1470 63.260 63.760 63.800 0.000 62.500 0.000 ) 100 1485 63.240 63.780 63.780 0.000 62.520 0.000 1 101 1500 63.250 63.760 63.800 0.000 62.520 0.000 l 102' 1515- 63.230 63.770 63.790 0.000 62.510 0.000 103 1530 63.200 63.740 63.790 0.000 62.510 0.000 END OF TABLE
- -- ,, , . . - - - - . . . - -. 1
I 1
, VARIABLE TABLE
SUMMARY
)
. SAM DELT TEMP ' 19 TEMP 20 ' TEMP 21 TEMP 22 TEMP 23 TEMP' 24 NUM--MINS DEG. F DEG. F DEG. .F DEG. F DEG. F DEG. F l 1 0 64.510 64.550 63.840 .63.080 64.130 64.100 s 2 15 '64.470 64.530 63.840' 63.060 64.110. 64.070 3 30 64.460. 64.520 63.900 63.050. 64.100 63.980 l 4 45 64.450 .64.490 63.810 63.030 64.090 64.020 5 60 64.430 64.480 63.780 63.040 64.110 64.010 6 '75 64.410 '64.470 63.770 63.000 64.090 63.990
'7 90 64.420 ~64.440 63.760 62.960 64.070 63.970' 8 105 64.390 64.420 63.740 62.940 64.030 63.960 -)
9' 120 64.380 64.410 63.740 62.950 64.050 63.950 i
. 10 135 .64.370 64.410 63.720 62.930- 64.050 63.930 ,
11 150 64.370 64.390 63.710 62.910 64.050 63.910 12 165 64.340 64.380 .63.690 62.890- 64.040 63.900, ; 13 180 64.320 64.370 63.680 62.870 64.010 63.890 ' 14 195 64.300 64.350 63.680 62.870 64.010 63.870 15' 210 64.290 64.350 63.660 62.840 63.980 63.860 16 225 64.280 64.330 63.640 62.860 64.000 63.840 : 17 240 64.270 64.310 63.680 62.830 63.980 63.800 " 18 255 64.270 64.310 63.690 62.820 63.980 63.780 19 270 64.250 64.290 63.660 62.790 63.960 63.770 20 285 64.230 64.280 63.650 62.790 63.930 63.7Co 21 300 64.220 64.290 63.670 62.780 63.920' 63.730 l 22 .315 64.230 64.270 63.640 62.780 63.910 63.740 23 330 64.220 64.260 63.630 62.760 63.890 63.740 ! () -24 25 345 360 64.200 64.200 64.250 64.230 63.610 63.600 62.750 62.750 63.880 63.890 63.730 63.710 26 375 64.190 64.240 63.610 62.720 63.870 63.700 27 390 64.170 64.210 63.590 62.720 63.890 63.680 l 28 405 64.180 64.210 63.600 62.700 63.850 63.680 29 420 64.150 64.210 63.580 62.690 63.830 63.670 30 435 64.160 64.220 63.590 62.690 63.820 6?.670 31 450 64.120 64.190 63.580 62.680 63.820 63.660 l
- 32' 465 64.080 64.150 63.570 62.680 63.810 63.660 i 33 480 64.070 64.130 63.550 62.550 63.800 63.710 34 495 64.070 64.110 63.550 62.640 63.790 63.700 35 510 64.050 64.100 63.560 62.620 63.800 63.690 1 36 525 64.030 64.100 63.530 62.620 63.800 63.710 I
'; " l. I':l' 5
'::; :: ':" "':*' :; l 39 570 fa.030 64.060 63.510 62,' 63.780 63.700 !
40 585 64.000 64.060 63.520 62.bJO 63.760 63.730 ! 41 600 64.000 64.050 63.520 62.580 63.790 63.700 ) 42 615 63.990 64.040 63.560 62.560 63.750 63.680 1 43 630 64.000 64.040 63.550 62.560 63.750 63.700 ) 44 645 63.970 64.040 63.530 62.550 63.740 63.730 1 45 660 63.980 64.020 63.510 62.550 63.730 63.720 46 675 63.970 64.010 63.540 62.520 63.720 63.690 47 690 63.970 64.020 63.500 62.530 63.720 63.740 48 705 63.950 64.010 63.460 62.530 63.710 63.750 (~4 49 720 63.930 64.010 63.460 62.510 63.720 63.730 57 50 735 63.940 63.990 63.460 62.510 63.710 63.740 ' 51- 750 63.950 63.990 63.450 62.500 63.690 63.750 52 765 63.930 63.980 63.440 62.490 63.690 63.730
. . - - - , - ,+- ,m. --.w,- - ,-n, - - - - - - - - - - ,
VARIABLE TABLE'
SUMMARY
(CONTINUED)
' 53 ' 7'80 63.920 63.980 63.450 .62.490 63.680 63.720 54' 795' 163.930. 63.980 ~ 63.450 62.480 s63.670 63.730 55 810 63.920' 63.990 63.430 62.470 63.670 63.720 56- 825: ~63.910 63.970 63.410 62.470 63.650 63.740 57 .840' 63.890 63.980 63.410 62.460 63.640 63.750
. 58. 855 63.900 63.980 63.430 62.490 63.690 63.740
- 59. 1870 63.890 63.970 63.390 62.450 63.660 63.750
'60 885 63.890 63.970 63.370 62.440 63.630 63.750
- 61 900' 63.870- '63.950 63.370 62.450 63.640 63.740 62' 915 63.880' 63.940' '63.350 62.440 63.640 63.760-63' 930 63.850 63.950 '63.340 62.430 63.640 63.780 ;
.64 945 '63.840 63.950 63.330 -62.420- 63.630 63.760 65' 960 63.870 63.940 63.340 62.420 63.630 63.740-66 975 63.850 63.930 63.330 62.420' 63.620 63.740
- 1 67 990 63.840 03,930 63.330 62.410 63.620 63.740 68 1005 63.830- 63.900 63.330 62.400 63.600 63.750 69 1020 '63.830 63.890 13.320 62.390 E3.610 63.750 70 1035 63.820 63.880 03.310 62.390 63.600 63.750 1 71 .1050 63.820 63.900 63.310 62.390 63.600 63.720-72 ~1065 53.810 63.890 63.320 62.380 63.610 63.700 73 1080 63.810 63.890 63.320 62.380 -63.600 63.720 74 1095 63.800 63.870 63.290 62.370 63.600 63.710
.75 1110 63.780. 63.880 63.280 62.380 63.590 63.700 76 1125- '63.790 63.880 63.300 62.350 63.580 63.710 77 1140 63.790 63.870 63.290 62.370 63.570 63.690
()- 78 1155 79 . 1170 63.780 63.790 63.860 63.860 63.280 63.280 62.330 63.560 63.690 3 62.350 63.560 63.680 1 80 1185 63.770, ~63.850 63.280 62.330 63.560 63.690 81 1200 63.760 63.850 63.260 62.340 63.560 63.670
- 82 1215 63.760. 63.860 63.240 62.350 63.560 63.700 .
83 1230 63 750 63.860 63.230 62.330 63.560 63.710 84 1245 63.750 63.850 63.220 62.330 63.550 63.700 85 1260 63.740 63.850 63.230 62.330 63.560 63.720 ) 86 1275 63.730 63.820 63.210 -62.330 63.540 63.710 87 1290 63.730 63.830 63.210 62.310 63.540 63.710 BB 1305 63.720 63.820 63.210 62.310 63.520 63.660 89 1320 63.730 63.810 63.190 62.310 63.530 63.660 90 1335 63.710 63.810 63.190 62.290 63.520 63.670 91 1350 63.710 63.810 63.200 62.300- 63.510 63.690 92 '1365 63.730 63.800 63.190 62.280 63.510 63.680 l 93 1380 63.690 63.810 63.180 62.280 63.500 63.680 94 1395 63.710 63.790 63.180 62.290 63.510 63.660 I 95 1410 63.680 63.790 63.190 62.200 63.490 63.650 96 1425 63.700 63.790 63.190 62.270 63.500 63.650 97 1440 63.690 63.780 63.170 62.280 63.490 63.660 98 1455 63.690~ 63.790 63.190 62.270 63.500 63.630 99 1470 63.670 63.770 63.200 62.260 63.480 63.590 100 1485 63.680 63.780' 63.200 62.250 63.490 63.600 101 1500 63.680 63.760 63.200 62.250 63.480 63.600 102 1515 63.670 63.770 63.170 62.250 63.460 63.610 103 1530 63.660 63.770
-( } 63.200 62.280 63.480 63.610 END OF TABLE
.-w.--w,
.h r
i VARIABLE TABLE
SUMMARY
f SAM DELTI PRES 1 HUM .1 HUM .2 HUM t 3_ HUM 4 HUM 5 NUM: MINS' PSIA FRACTION FRACTION FRACTION. FRACTION- FRACTION ! 11 0 63.370 0.000 0.000 .0.428 0.000 0.424 ;
- 2. 15 63.366 0.000 0.000 0.428 0.000 0.423 t
'3 30 63.363 0.000 0.000 0.426 0.000 0.423 j 4 45 63.362 0.000 0.000 0.428 0.000 0.423 i 5 60 63.360 0.000 0.000 0.429 0.000 0.424 ,
6 75 63.358 0.000 0.000 0.427- 0.000 0.423 7 90 63.355 0.000 0.000 0.428 0.000 0.423 I 8 105 63.352 0.000 0.000 0.428 ~0.000 0.425 [ 9 120- 63.350 0.000 0.000 0.429- 0.000 0.427 i 10 135 63.348 0.000 0.000 0.429 0.000 0.424 . 11 '150 63.346 0.000 0.000 0.431 0.000 0.424 l 12 165' 63.343 0.000 0.000 0.430 0.000 0.426 i 13 -180 63.341 0.000 0.000 0.430 0.000 0.425 ' 14 195 63.339 'O.000 0.000 0.428 0.000 0.424 f 15 210 63.335 ' 0.000 0.000 0.429 0.000 0.425 I 16 '225 63.334 O.000 0.000 0.429 0.000 0.423 $ 17 240 63.333 0.000 0.000 0.429 0.000 0.427 j 18 , 255 63.330 0.000 0.000 0.429 0.000 0.425 l 19 270 63.329 0.000 0.000 0.429 0.000 0.424 ! 20 285 63.327 0.000 0.000 0.431 0.000 0.423- l
- 21. 300 63.326 0.000 0.000 0.428 0.000 0.426 ;
22 315 63.324 0.000 0.000 0.432 0.000 0.427 -! 23 330 63.322 0.000 0.000 0.430 0.000 0.427 j O 24 25 345 360 63.321 63.319 0.000 0.000 0.000 0.000 0.430 0.430 0.000 0.000 0.422 0.426 j f 26 375 63.317 0.000 0.000 0.431 0.000 0.428 i 27 390 63.316 0.000 0.000 0.432 0.000 0.428 ! 28 405 63.314 0.000 0.000 0.431 0.000 0.428 29 420 63.313 0.000 0.000 0.429 0.000 0.424 t 30 435 63.311 0.000 0.000 0.433 0.000 0 426 i 31 450 63.309 0.000 0.000 0.431 0.000 0.429 l 32 465 63.309 0.000 0.000 0.432 0.000 0.429 l 33 480 63.306 0.000 0.000 0.433 0.000 0.430 ' 34 495 63.305 0.000 0.000 0.431 0.000 0.431 l 35 510 63.304 0.000 0.000 0.432 0.000 0.432 ; 36 525 63.303 0.000 0.000 0.434 0 000 0.434 i 37 540 63.301 0.000 0.000 0.430 0.000 0.430 $ 38 555 63.300 0.000 0.000 0.432 0.000 0.433 i 39 570 63.298 0.000 0.000 0.433 0.000 0.432 l 40 585 63.297 0.000 0.000 0.434 0.000 0.429 j 41 600 63.296 0.000 0.000 0.434 0.000 0.431 42 615 63.294 0.000 0.000 0.434 0.000 0.433 43 630 63.293 0.000 0.000 0.433 0.000 0.431 44 645 63.292 0.000 0.:000 0.434 0.000 0.434 45 660- 63.291 0.000 0.000 0.432 0.000 0.432 46- 675 63.290 0.000 0.000 0.433 0.000 0.431
- 47. 690 63.288 0.000 0.000 0.434 0.000 0.432 48 705 63.287 0.000 0.000 0.436 0.000 0.433
- 49 720 63.286 0.000 0.000 0.436 0.000 0.430 O 50 51 735 750 63.285 63.283 0.000 0.000 0.000 0.000 0.436 0.436 0.000 0.000 0.435 0.432 52 765 63.282 0.000 0.000 0.436 0.000 0.433
g g. ' e :- i
- a. '
VARIABLE TABLE
SUMMARY
'(CONTINUED) .
- \
f_ 53 780; 63.2811 0.000' O.000 0.430- 0.000 0.432 54_~ '795. '63.281 l0.000 0.000 l0.434 0.000 0.433 55 810. 63.279 0.000 0.000 0.435 0.000 0.433
~56 825 63.279 0.000 .0.000 ,0.434 'O.000 0.430- j 57 .840 63.278 0.000 0.000 0.437' O.000 0.432 ; :
- 58. 855 ,63.277 0.000 0.000T 0.435- 0.000 0.434~ ,
59 870 63.276 0.000 .0.000 0.436 0.000 0.435' ' 60' 885 63.275 0.000. 0.000 0 437 0.000 0.436 ! l61 900' 63.274 'O.000 0.000 0.433 0.000 0.431 [
- 62 915L 63.273 0.000 0.000; 0.436 0.000 0.435 i d
63 930' 63.272 0.000 0.000 0.435 0.000 0.433 j 64 945 63.272 0.000 0.000 0.437 0.000 0.432 j 65 960 63.271' O.000 .0.000 0.437 0.000 0.437 ; 66: 975 63.270 0.000 0.000 0.437- 0.000 0.434- !
.67- 990: 63.270 0.000 0.000 0.437 0.000 0.435 68 1005 63.269 0.000 0.000 0.438 0.000 0.435 j 69 1020- 63.269 10.000 O.000 0.434 0.000 0.435 ;;
70 1035 63.267 0.000 ~0.000 0.436 0.000 0.434 71 1050 63.267 0.000 0.000 0.436 -0.000 0.435 72 1065 63.266 0.000 0.000 0.436 0.000 0.437 *
.73 1080 63.265- 0.000 0.000 0.437 0.000' O.436 i 74 1095' '63.264 0.000 'O.000 0.436 0.000 0.436 )
75 1110 63.262 0.000 0.000 0.438 0.000 0.435 >
,76 1125 63.261 0.000 0.000 0.438 0.000 0.437 77 1140 63.261 0.000 0.000 0.436 0.000 0.437 63.260 0.436 O- 78 79 1155 1170 63.259 0.000 0.000 0.000 0.000 0.437-0.439 0.000 0.000 0.437 I 80 1185 63.258 0.000 0.000 0.437 0.000 0.436 31 1200 63.258 0.000 0.000 0.438 0.000 0.436 82 1215 63.257 0.000 0.000 0.438 0.000 0.436 l 83 1230 63.257 0.000 0.000 0.435 0.000 0.438 )
84 1245 63.256 0.000 0.000 0.437 0.000 0.439 85 1260 63.256 0.000 0.000 0.436 0.000 0.437 ., 86 1275 63.256 0.000 0.000 0.437 0.000 0.436 87- 1290 63.255 0.000 0.000 0.438 0.000 0.437 88 1305 63.254 0.000 0.000 0.439 0.000 0.437 89 1320 63.253 0.000 0.000 0.439 0.000 0.441 90 1335 63.252 0.000 0.000 0.440 0.000 0.438 91 1350 63.252 0.000 0.000 0.440 0.000 0.440 92i 1365 63.252 0.000 0.000 0.440 0.000 0.438 93 1380 63.251 0.000 0.000 0.436 0.000 0.438 j 94 1395 63.250 0.000 0.000 0.439 0.000 0.436 1 95 1410 63.249 0.000 0.000 0.439 0.000 0.438 1 96 1425. 63.249 0.000 0.000 0.440 0.000 0.439 -l 97- 1440 63.249 0.000 0.000 0.440 0.000 0.438 98 -1455 63.249 0.000 0.000 0.441 0.000 0.439 l
-99 1470 63.246 0.000 0.000 0.442 0.000 0.439 !
100 1485 63.245 0.000 0.000 0.442 0.000 0.438 ) 101 1500 63.243 0.000 0.000 0.441 0.000 0.438 102 1515' '63.242 0.000 0.000 0.4+0 0.000 0.438 l 103 1530 63.241 0.000 0.000 0.440 0.000 0.439 O- , END OF TABLE i
f l i l 1 i i P E
~
s i l ATTAC191DIT. ; i VARIABLE PLOTS for ILRT
- i l
l l 1 e
?
O \ L i l i 1 e
EBASCO SERVICES INCORPORRTED-0 1 17 33 0 49 65 81 0
- 97. . .113
, i . i . t , i . i . . 1 0 4000 COMPUTED LEAK RATES RELATIVE TO LIMITS x x SIMPLE NRSS POINT LERK RRTE h NRC TECHNICAL SPECIFICATION LIMIT 3
'h ---
Y Y CONTAINMENT DESIGN LERK RATE
' REGRESSED MASS POINT LERK-RATE j
w - 3: 0.3200
>- 5 to E xx n
b x .j T . O l 0.2400
~
x = w _ _ _ _ _ _ _ _ _ - - _ , _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - - - _ _ _ _ _ _ _ - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - g L c a
& b Z -
- 0.1600 w ._.
U t x w x 0.0800
% *vvV x x x x(ryvy% T< *x'74pg x
x x *
*****WW g x
x 0.0000 ' ' ' ' ' ' ' 0 240 480 720 960. l200. l440 l68@i TIME IN MINUTES
E8ASCO SERVICES INCORPORATED 0 O
~
0 1 17. 33 49 65 81 97 113 i
. i , i , i , i . i . .
12 0000 - COMPUTED FIT x xRELATIVE TO CRITICAL LIMIT STATISTICRL MRSS POINT LERK RRTE , v v REGRESSION LINE FOR STRTISTICRL M9SS POINT LERK RRTE g y CD i ~ E bJ l Z 8 0000 E E to t i >- t C O - 4.0000 g Oc bJ g ct 8 m H __ _ owwwvv"v""" 5 ] 0.0000 ,,,yyyoyw wvn " ' " O , ,,,,,,,[vowvv""""""""" of a LLI e n_ m
-4.0000 - -8.0000 i i i i i i i 0 240 480 720. 960. 1200 1440 1680 TIME IN MINUTES
EBASCO SERVICES INCORPORATED O O O 1. 17 , 33 , 49 , 65 , 81 ,
- 97. ,
1,13-64.8000 - VOLUMETRICALLY WEIGHTED CONTAINMENT TEMPERATURE H - w 2: I Z j W 5 64.4000 - [ r l-E e W U co I: m 64.0000 - CD ,, W ! z !-'
- 63.6000 -
W r 3 F-- T - oc 63 2000 - - W O_
- E-W t-l 62.8000 ' ' ' ' ' '
0'. 240 480 7'20 960 l200. l440 l680 TIME IN MINUTES --
m EBASCO SERVICES INCORPORATED - /, l O. Q, _U 1 17. i e 33 i . 49. i , 65 i . 81 i . 97 i , 113 i l 63.4400 - AVERAGE CONTAINMENT PRESSURE - l 4 cc E: ,s
- 63.4000 - !'
y e
'z m g; -
e-4
= s .w .oc 63.3600 - \y @ . _-) "a
- to "". ;
.CD === l a
w 3 oc 8'
;o_ 63.3200 -
63.2800 - . [ i i i i i 63 2400 n- i 480 960 1200 1440 i 240 720. 1680 TIME IN MINUTES
EBASCO' SERVICES INCORPORATED .._ O O O 1 17. 1 33 49 65 81 97 -113
. . . i . i , i , i ,- i 0.1272 VOLUMETRICALLY WEIGHTED VAPOR PRESSURE T 9 H
E V) E o_ - I 0.1264 E z : -.
.- E e
LU 3 at a k g s-u3 0.1256 u m m, U) E to , oc = == =" ", L " m , m a i m a a a g' E m a m N , a a " {c 0.1248
" =
,= ,. ,a m m, mm
=
> m m "a ma m
a m
- m u "
. , , m m a " E * = ,
a g , a *
=
0 1240 = =
= m.
= ,
- a l "m
= "
0.1232 i i i i i e i 0 240 480 720 960. 1200. 1440 1680 TIME IN MINUTES
, , . . . . ~n.n-.,n,,n -n~ n a.--e...m. - ..~ ~ - -n.,_.- .-
- a. .a m - - - - a a.a u n..-s r-J
- - h
. 1 I
k, . .. ,. ,, . I i .. .
. t i:
- t l ;.
I. l e a i-II ' ATTAC1EENT E h TABULAR DATA for CLRT [ a I I-l[ i t-1 IO 1 1 4 !. l i 1 l
- l. I J l n i 8
1 i .I !. i 6 l l l ! ' i I i I l. l \ l i E i. 1 . 1 I I l l \
SOUTH CAROLINA ELECTRIC AND GAS VIRGIL C. SUMMER STATION l q ')
~.
CLRT LEAK RATE COMPUTED USING MASS POINT METHOD AS RECOMMENDED BY ANS N274 REVISION 2 (CONTAINMENT SYSTEM LEAKAGE TESTING REQUIREMENTS) TEST PERIOD OTARTED AT 445 HOURS ON 16 JAN 1981 A LEAST SQUARES FIRST ORDER FIT OF LEAK RATE TO TIME SHOULD YIELD A SLOPE OF ZERO AND AN INTERCEPT EQUAL TO THE LEAK RATE AS COMPUTED AT THE INITIAL START TIME THE EQUATION HAS THE FORM - L=ST+R WHERE L - CORRELATED LEAR RATE i S - SLOPE OF CORRELATION T - TIME IN HOURS R - INTERCEPT LEAK RATE , U 0.015 HOURS + 0.084 PER CENT LEAK RATE = MEAN = 0.129 PER CENT INITIAL CONTAINMENT AIR WEIGHT = 599671 LBS. FINAL CONTAINMENT AIR WEIGHT = 599473 LBS. FITTED MASS POINT LEAK RATE IS 0.159 PER CENT PER DAY MASS POINT LEAK RATE AT UPPER 95% CONFIDENCE LIMIT , IS 0.168 PERCENT PER DAY , MAXIMUM NRC LEAK RATE OF 0.150 PER CENT PER DAY GIVEN FOR HIGH PRESSURE TEST AT 61.80 PSIA
^
LEAKAGE OF .150 % PER DAY AT 61.796 PSIA IS EQUIVALENT TO 8.14 SCFM. l SUPPLEMENTAL TEST (CLRT) DATA AND PREVIOUS ILRT RESULTS PLUS INJECTED LEAKAGE MUST BE WITHIN 25% OF LA (2.71 SCFM) FOR VERIFICATION t i
~
Nj DESCRIPTION OF VARIABLES AVG. TEM - VOLUMETRICALLY WEIGHTED TEMPERATURE. AVG. PRE - AVERAGE PRESSURE. VAP. PRE - VOLUMETRICALLY WEIGHTED VAPOUR PRESSURE. LEAK COM - LEAK RATE COMPUTED FROM FIRST ORDER REGRESSION. LEAK MAS - LEAK RATE FROM MASS POINT FIRST ORDER REGRESSION. LEAK SIM - LEAK RATE BASED ON TOTAL TIME CALCULATIONS. AIR MAS - AIR MASS DATA. NOIS FOR CURVES-
- 1. TOP ABSCISSA SCALE REPRESENTS SAMPLE NUMBERS. I
- 2. LEAKAGE RATE CURVES ARE BASED ON " TOTAL TIME" '
AND " MASS POINT" METHOD ANALYSFS. / 1 NOTE FOR TABULAR DATA - TABLE VALUES OF ZERO SIGNIFY EITHER
- 1. DATA IS NOT APPLICABLE TO THE CALCULATION OR
- 2. SENSOR HAS BEEN DELETED FROM THE SCAN.
D l f i k i 1
l fl u VARIABLE TABLE
SUMMARY
SAM DELT AVG. TEM AVG. PRE VAP. PRE LEAK COM LEAK SIM LEAK MAS AIR MASS NUM MINS DEG. F PSIA PSIA PER CENT PER CENT PER CENT 1000 LBS 1 0 62.979 63.239 0.125 0.152 0.152 0.170 599.671 2 15 62.981 63.237 0.126 0.154 0.188 0.194 599.653 3 30 62.975 63.236 0.125 0.156 0.157 0.178 599.651 4 45 62.977 63.234 0.125 0.158 0.180 . 0.185 599.632 5 60 62.975 63.232 0.125 0.159 0.193 0.195 599.616 6 75 62.981 63.231 0.125 0.161 0.197 0.201 599.601 7 90- 62.975 63.231 0.125 0.163 0.167 0 190 599.606 8 105 62.976 63.229 0.125 0.165 0.177 0.187 599.589 9 120 62.973 63.228 0.126 0.166 0.184 0.188 599.573 10 135 62.973 63.227 0.126 0.168 0.173 0.184 599.570 11 150 62.964 63.225 0.126 0.170 0.173 0.181 599.560 12 165 62.964 63.224 0.126 0.172 0.172 0.179 599.550 13 180 62.961 63.223 0.125 0.174 0.168 0.176 599.542 14 195 62.948 63.220 0.125 0.175 0.164 0.172 599.536 15 210 62.946 63.219 0.125 0.177 0.164 0.170 599.525 16 225 62.950 63.218 0.125 0.179 0.167 0.169 599.512 17 240 62.946 63.216 0.126 0.131 0.172 0.169 599.496 62.945 0.126 0.182 0.179 ('} k-18 19 255 270 62.939 63.214 63.213 0.126 0.184 0.173 0.171 0.172 599.476 599.473 END 0 TABLE l l l 1 l O 9 w
l F I' - - ,d g-VARIABLE TABLE
SUMMARY
SAM DELT TEMP -1 . TEMP 2 TEMP 3~ TEMP 4 TEMP 5 TEMP. 6 NUM -MINS' DEG. . F DEG. F DEG. F DEG. F DEG. F DEG. F 1 0 62.270' 62.200' 62.550 -62.460' 63.690 62.530 12 15- 62.270 62.180 62.550 62.460 63.660 62.530 3 30 '62.270 62.170 62.550 62.450 63.690 62.520
- 4. 45 62.280 62.200 62.540 62.470 63.690 62.530 5 60 62.260 62.240 62.560 62.480 63.670 62.510 6 75 62.280 62.230 62.550 62.470 63.670 62.510 7- 90 62.270 '62.220 62.540 62.450 63.690 62.530-8 105 62.300 62.210 62.576 62.450 63.680 62.510 9 120 62.270 62.220- 62.56C 62.490 63.690 62.510 10 135 62.290 62.200 62.590 62.460' 63.670 62.520 11 150~ 62.260 62.200 62.540 62.450 63.650 62.500 12 165 62.280 62.210 62.550 62.480 63.660 62.500 13 180 62.260 62.200 62.540 62.480 63.660 62~490 14 195 62.250 62.180' 62.530 62.440 63.640 62.500 15 210 62.240 62.160 62.520 62.420 63.650 62.490 16 225 62.240 62.190 62.520 62.440 63.640 62.500-17 240 62.210 62.160- 62.530 62.450 63.650 62.500 0 18 19 255 270 62.220 62.240 62.180 62.160 62.530 62.530 62.420 62.440 63.630 63.620
~62.490 62.490 END OF TABLE O.
~ __ , .
i i l i i VARIABLE TABLE
SUMMARY
[
' SAM DELT TEMP -7' TEMP 8 TEMP 9 TEMP 10' TEMP' 11 TEMP 12 NUM MINS DEG. . F DEG. F DEG. :F DEG. F DEG. F DEG. F i 1 0: 62.660 62.270 62.640 62.650 62.730 63.770 ;
2- 15 62.710 62.280 62.610- 62.670- 62.760 63.800 i 3 30 62.740 62.300 62.600 62.660 62.710 63.760 ! 4 45. 62.660 62.300 62.600 62.640 62.730 63.750 + 5 60. 62.670 62.340 62.550 62.630 62.750 63.760 ' 6 75 -62.660- 62.320 62.630- 62.670- 62.750 63.770 r 7 90 _62.640 62.290 62.590 62.650 62.740 63.750 f
'8 105 _62.650 62.270 62.580 62.670 62.780 63.750 )
9 120 62.660 62.300 62.570 62.660 62.790 63.740 > 10 135 62.620 62.270 62.590 62.670 62.790 63.760 I 11- 150 62.660 62.260 62.610 62.650 62.780 63.740 I 12 165' 62.650 62.230 62.620 62.670 62.750 63.740 i 13' 180 62.660 62.270 62.620 62.650 62.730 63.730 1 14 195 '62.660 62.300 62.550 62.630 62.700 63.750 15 210 62.610 62.250 62.610 62.640 62.710 63.740 l 16 225 62.660 62.280 62.610 62.620 62.720 63.730' j 17 240 62.680 .62.260- 62.580 62.620 62.690 63.740' i O 18 19 255 270 62.690 62.670-62.300 62.230 62.510 62.520 62.610 62.630 62.730 62.710 63.720 63.730 END OF TABLE I t
?
i I i l i i O D 1 4 -. + r -n., , , - - . , r ev e
I 1 l i
/^\ '%sl VARIABLE TABLE
SUMMARY
SAM DELT TEMP 13 TEMP 34 TEMP 15 TEMP 16 TEMP 17 TEMP 18 NUM MINS DEG. F DEG. F DEG. F DEG. F DEG. F DEG. F 1 0 63.220 63.730 63.770 0.000 62.490 0.000 2 15 63.220 63.730 63.770 0.000 62.500 0.000 3 30 63.190 63.750 63.770 0.000 62.480 0.000 4 45 63.200 63.750 63.760 0.000 62.490 0.000 5 60 63.190 63.760 63.760 0.000 62.460 0.000 6 75 63.210 63.730 63.740 0.000 62.470 0.000 , 7 90 63.240 63.730 63.750 0.000 G2.480 0.000 > f 8 105 63.220 63.740 63.750 0.000 62.490 0.000 9 120 63.200 63.710 63.750 0.000 62.480 0.000 10 135 63.220 63.720 63.740 0.000 62.480 0.000 11 150 63.210 63.710 63.750 0.000 62.470 0.000 12 165 63.190 63.710 63.740 0.000 62.460 0.000 13 180 63.180 63.690 63.730 0.000 62.470 0.000 14 195 63.170 63.690 63.730 0.000 62.460 0.000 - 15 210 63.190 63.720 63.720 0.000 62.470 0.000 l 16 225 63.170 63.710 63.720 0.000 62.460 0.000 , 17 240 63.160 63.720 63.720 0.000 62.460 0.000 () 18 19 255 270 63.180 63.180 63.720 63.700 63.720 63.710 0.000 0.000 62.470 62.460 0.000 0.000 , END OF TABLE , P 9 I O
{ i VARIABLE TABLE
SUMMARY
SAM DELT TEMP 19 TEMP 20 TEMP- 21. TEMP 22 TEMP 23 TEMP 24 . NUM MINS DEG. F DEG. F DEG. F DEG. 'F DEG. F DEG. F l 1 0 63.650 63.760 63.190 62.240 63.460 63.610 l 2 15 63.660 63.760 63.170 62.240- 63.460 63.600
.3 30 63.670 63.760 63.160 62.220 63.450 63.590 ;
4 45 63.660 63.770 63.170 62.240 63.460 63.610 ; 5 60 63.640 63.770 63.170 62.230 63.440 63.610 . 6 75 63.660 63.760 63.170 62.240 63.460' 63.630 l 7 90 63.670. 63.760 63.150 62.220 63.460 63.640 l 8 105 63.640 63.750 63.140 62.230 63.460 63.630 j 9 120 63.640 63.730 63.130 62.240 63.450 63.610 j 10 135 63.640 63.740 63.130 62.240 63.450 63.610 ; 11 150- 63.640 63.740 63.130 62.220 63.440 63.600 ! 12 '165 '63.630 63.730 63.140 62.220 63.420 63.620 1 13 180 63.640 63.730 63.130 62.230 63.430 63.620 . 14 195 63.640 63.720 63.110- 62.210 63.420 63.580 [
'15 210 63.620 '63.720 63.120 62.200 63.410 63.610 l 16 63.630. 63.740 63.120 62.190 63.410 63.590 225 17 240 63.630 63.730 63.120 62.220 63.410 63.570 .j 18' '255 63.620 63.730 63.110 62.210 63.400 63.610 j L( }: 19 270 63.620 63.720 63.120 62.200 63.410 63.560 l END OF TABLE i
3 t l f i l t 1 l
1 i LO VARIABLE TABLE
SUMMARY
~
SAM DELT' PRES 11 HUM 1 HUM 2 HUM 3 HUM 4 HUM 5 NUM . MINS PSIA. FRACTION FRACTION FRACTION FRACTION FRACTION-
- 1. 0 63.239' 0.000 0.000 0.441 0.000 0.440 !
2 15 63.237 0.000 0.000 0.443 0.000 0.440 ' 3- 30 63.236 0.000 0.000 0.441 0.000 0.439 ; 4 45- 63.234 0.000 0.000- 0.441 0.000 0.440 , 5 60 63.232 0.000 0.000 0.442 0.000 0.440 6 75 .63.231 0.000 0.000 0.440 0.000 0.440 7 90 '63.231 0.000 0.000 0.441 0.000 0.437 8' 105 63.229. 0.000 0.000 0.441 0.000 0.438 9' 120 63.228 0.000 0.000 0.443 0.000 0.440 10 135 63.227 0.000 0.000 0.441 0.000 0.441 11 150 63.225 0.000 0.000 0.440 0.000 0.443 12 '165 63.224 0.000 0.000 0.442 0.000 0.442
- 13 180 63.223 0.000 0.000 0.443 'O.000 0.439 14 195 63.220 0.000 0.000 0.440 0.000 0.440
.15. 210 63.219 0.000 0.000 0.442 0.000 0.440 16 225 63.218 0.000 0.000 0.443 0.000 0.439 17 240 63.216 0.000 0.000 0.443 0.000 0.440 18 255 63.214 0.442
( )' 19 270- 63.213 0.000 0.000 0.000 0.000 0.442 0.444 0.000 0.000 0.441 END OF TABLE t l END OF REPORT ON CONTAINMENT LEAK RATE TEST TO NRC I l 1 O
I
' ATTACHMENT 1-VARIABLE PLOTS for CLRT 4
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EBASCO SERVICES INCORPORRTE
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ATTACIU4ENT II 1 PHASE II TEST REPORT O. g-7: d. 1
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' PROCEDURE NAME so . tTE.DCef8CldY\A ) -M:6d(Pr'ed ,L6A L 2 Tie e4 PROCEDURE NUMBER - LR h /
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INDEX , i REACTOR-BUILDING PRE-OPERATIONAL INTEGRATED LEAK RATE TEST . ,,7 2 <
# 1.0 PURPOSE
2.0 REFERENCES
AND ENCLOSURES 30 PREREQUISITES 4.0 SPECIAL TEST-EQUIPMENT 50 LIMITATIONS AND PRICAUTIONS
'6.0 TEST METHOD i
70 DATA REQUIREMINTS r 8.0 ACCEPTANCE CRITERIA : ATTACEMENTS ATTACEMENT I . Contain=ent Building Integrated Leak Rate Test 7alve Line-Up , t ATTACEMENO II - Pressurization /Depreseurization Data i ATTACEMENT III - Te:perature Data
' A00ACEMIN IV - Moisture Data i r
ATTACEMINT V - Atmospheric Conditions .t ATTACEMINT VI - Flow Data ATTACEMIN ?!I - Require =ents for Personnel Entry of Reactor 3uilding ;
@ 12 psig. ;
ATTACEMINT VI:I - ILRT Staff Personnel i A :ACEMINT :X - Data Acquisition Syste Cutput ;
,, - i a,,. m.
n u ne,. ;i m. .t - ron.ro3.
. noo: ,og A :ACEMINT X: - Reactor 3uilding Equip:ent 7enting l r
ATTACEMIli? XI: - Safety Exclusion Areas ! A27ACEMINT II I - General Otservation i i
. ATTACEMENT XIV - Verification of Relief Valve -
e i ATT AC E.'iEN: XV - Deco:presion Tables and I ergency Infor:ation , A :ACEMI:~2 XV: - In s t rum e nt Insta11atior. Location > i
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1.0 PURPOSE-
. 1.1 To verify that the leakage rate of the Reactor Building
("i is within the acceptable limits as specified in Appendix J, of' KJ 10 CFR 50, " Primary Reactor Containment Leakage Testing for Water-Cooled Fower Reactors". 1.2 The test will be conducted by pressurizing the Reactor Building structure to 47 1 psig (+10.0, -0.0) with air and after conditions have stabiliced. for a minimum of four hours, data vill be gathered for a period cf twenty-four hours or longer.*
*It is the intent of this procedure to perform the. leakage rate test over a minimum of a 24 hour period. However, references 2 3, 2.d and 2.6 permit a shorter test period, the requirements are met allowing a shorter test period and it becomes impractical to continue the test for a full 24 hour period, then a shorter period may be established.
13 Upen completion of the 'ILRT a " Verification Test" will be conducted at 47 1 psig (+10.0, -1.0) . A superimposed known leakage will be started and maintained for a minimum of 4 hours to verify the accuracy of the test instrumentation. 1.4 Definitions 1.4.1 Integrated Leakage Rate Test (ILRT) The leakage test (Type A Test) performed on the primary Reactor Contain=ent 3uilding by pressurizing the 2uilding (~T to Pa and determining the overall integrated leakage \-) rate. 1.4.2 Type A Tests Tests intended to measure the primary Reactor Tontain=ent 2nilding overall integrated leakage rate (1) af ter the pri=ary reactor containment syste: has been ecc=pleted and is ready for operation, and (2) at periodic intervals thereafter. 1.J.3 T7;e 3 Tests Tests intended to detect loc ~al leak 3 and to =easure leakage across each pressure containing or leakage li=iting boundary, other than valves, such as resilient seals, gaskets, expansion bellows or electircal i penetrations. 1.4.4 Type C Tests Tests intended to =eacure pri ary reactor contain=ent syste: isica icn valve leakage rates. ,_-) w e"' 126-3 RET.
1.4 5 Verification Tests
~- Test intended to confir= the capability of the Type A Test I,s_3) method'and equipment used to determine-the containment leakage rate'(Lam)-
1.4.6 Leakage Rate The rate at which the contained fluid escapes from the test volume at a specified test pressure. 1.4 7= Primary Reactor Containment System The design feature, which acts as the principal barrier, after the Reactor Coolant Pressure Boundary, to_ prevent the release under all conditions of design, of quantities of radioactive material that would have unique , radiological effect on the health of the public. It includes: (a) the containment structure, including access opening, i penetrations, and appurtenances. (b) those valves, pipes, closed syste=s and other i components used to effect isolation of the contaiment ' at=osphere from the outside environs. (c) those systems Or portione of systems that by their , functions, extend the containment structure boundary to include their system boundary. This ces not (]) include the " secondary containment", " containment enclosure building" or " reactor building" surrounding i so=e Contain=ent Systems, whose function is to control Containment Syste leakage. , 1.4.3 Cverall Integrated leakare Eate l The total leakage through all lea 2 age paths including , containment welds , valves , fittings and components which penetrate the pri=ary reactor containment system, , expressed in weight percent of contained air = ass per i day. , t e 1.4.0 Pa The calculated peak containment internal pressure related to the design basis accident (ICCA). Generally specified i in the technical specifications or associated basis. i i i
)
i h i W c . .; , i 126-4 EF.~ . i i
l a 1.4.10 La (Weight Percent / Day)
~ ' ,- The maximum allowable leakage rate at pressure Pn stated
(_). as percent of containment free volume /24 hours. La=0.2% of the. containment mass per day. i
- 1. 4.11 Lam (Weight Percent / Day) l The measured containment leakage rate at pressure Far obtained from testing the primary reactor containment '
system in the state as close as practical (e.g., vented, ; drained, flooded or in operation) to that which would exist following a loss of coolant accident (LOCA) which results in Pa- l
-1.4.12:La (Weight Percent / Day) !
The composite leaka6e rate measured using the ILRT : instruments 'af ter Lo is superi= posed. ! 1.4.13 Lo (Weight Percent / Day) !
'The known leakage rate superimposed on the containment during verification tests. ,
I i i i r
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)
SlJM- l 146-5 ?.ri. t ,
2.0 REFERENCES
1 2.1 SUM-3-2, " Preparation of Phase II Start Up Procedures". < fs t t
2.2' V. C.Sumner Final Safety Analysis Report, Section 6.2 and.
Table 14 1.6. ANSI Standard N45 4-1972, " Leakage - Rate Testing of Containment 2.3 Structures for Nuclear Reactors". 2.4 Code of Federal Regulations,. Title 10, Part 50, Appendix J,
" Primary Reactor. Containment Leakage Testing for Water Cooled Power Reactors".
25 GAI Final System Design Description, "Reictor Building Integrated-Leak Rate Test System". ANS-N274, Containser.t Leakage Testing Requirements, Revision 3 - 2.6 November 15, 1978. 2.7 GAI Specifications: 2.7.1. S-206, " Reactor Building Liner and Penetration Sleeves". 2.7 2 SP-207, " Fabrication and Installation of Reactor Building , Post Tensioning Systec". 2.7 3 S?-525, " Personnel Access Airlock, Personnel Escape Airlock, and Iquipment Access Ratch". e 2.7 4 SF-614, " Specification for Isolation valve Containers" . (]) 2.7 5 SP-473, " Leak Rate Test Fanel". , 2.7.6 S?-606, " Reactor Building Piping Penet.a icns". 3 i 2.7.7 SP-529, " Electrical Penetrations". . 2.S Instruction Manuals: ; 2.5.1 IMS-942- , " Operating Instructions for Autodata-Nine ! Digital Acquisition Systen". ; i 2.3.2 IMS-943- , " Operating Instructions for Mense. ^uar:: ! Manore:er", i 2.9 3 IMS-943- , " Operating Instructions for leak Rate Test : Panel, 7.?N6LR". , i 29 Code of Federal Regulations, Title 29, Part 1926.5:4, Apteniix A,
' l
" Safety and Realth Regulations for Construction".
2.10 Westinghouse Me:c, CGWG-1516, de.:ed August 4, 1975, "Iquipment ! and Instrumentation Protection during Integ.ated Leakage Rata 203:". j 5 i
%) ;
t ' =.,e 4 he "V 146-6 RI'.' . ; j r P
E + l 1 1 2.11 Drawings:
)
~ 2.11.1 B-814-101, Rev. 2, Containment Pressure PT-951 l
\/ 2.11.2 b-814-102, Rev. 2, Containment Pressure PT-952 2.11 3 B-814-203, Rev. 2, Containment Pressure PT-950 ,
r 2.11.4 B-814-204, Rev. 2, Containment Pressure PT-953 2.11 5- D-302-011, Rev. 7, Main Stea=-Nuclear ; 2.11.6 D-302-083, Rev. 9, Feedwater-Nuclear i 2.11.7 D-302-221, Rev. 5, Service Water Cooling System 2.11.8 D-302-222, Rev. 8, Service Water Cooling Systes t 2.11 9 D-302-231, Rev. 6, Fire Service 2.11.10 D-302-241, Rev. 9, Station Service Air ; 2.11.11 D-302-273, Rev. 3, Reactor Zuilding and 3ackup ! Instrument Air Services ; 2.11.12 D-302-311, Rev. 3, Nitrogen 31anketing . 2.11.13 D-302-612, Rev. 7, Cc=ponent Cooling Syste: Inside l Reactor 3uildin e ,
, ~ .
2.11.11 D-302-651, Rev. 11, Spent Fuel Cooling ; (]) i 2.11.15 D-302-661, Rev. 9, Reactor 3uilding Spray Syste ; 2.11.16 D-302-715, Rev. 4, De:ineralized Water Nuclear Services I i 2.11.17 D-302-771, Rev. 4, Nuclear Sa pling l l 2.11.18 D C2-731, Rev. 5, Steas Generator 3 lowdown j 2.11.19 D-302-791, Rev. 7, Reactor Makeup
- dater Syste: ;
l 2.11.20 D-302-211, Rev. 3, Reactor ?uilding leak Rate Testing ; Syste: l 2.11.21 D-302-812, Rev. 2, 2005 Check "alve Testing ; 2.11.22 D-302-021, Rev. 6, 2.eactor and Auxiliary Building Su=p rumps 2.11.23 D-302-951, Rev. 7, Industrial Cooling Water Syste ; i 2.11.24 D-302-S61, Rev. 10, Post Accident Rydrogen Re: oval I Syste: l 2.11.25 D-206-CO*, Rev. 1, Reactor 3uiliing Air Radiati:n !
'4: n i t o .- RX A2 3.3.;.- , _ c, 4, _: _ r. n.w o , : ... u. . i , e..: .,c,4.,-...e -s...-.-
i 1 . :. -!S"M , i 1 i
2.11.27 D-912-103, Rev. 9, R3 Purge Supply and Purge Exhaust' Syste: t
, ,I 2.11.28 E-511-104, Rev. 7, Reactor Building Liner Plate v Stretchout 2.11.29 E-511 -105, Rev. 8, Reactor Building Liner Plate Stretchout 2.11 30 E-511-106, Rev. 2, Reactor Building Liner Plate Penetration Details 2.11 31 E-511-107, Rev. 12, Reactor Building Liner Plate Penetration Details 2.11 32 C-811-002, Rev. 1, Instrument Location Layout Integrated Leak Rate Test Sensor Locations 2.11 33 SS-422-101, Rev. O, Reactor Building ?enetration List -
Quadrant I 2.11 34 SS-422-201, Rev. O, Reactor Building ?enetration List - Quadrant II 2.11.35 SS-422-202, Rev. O, Reactor Building Penetration List - Quadrant II 2.11 36 SS-422-301, Rev. 2, Reactor Building Penetration List - 7-s Quadrant III d 2.11 37 SS-422-302, Rev. 1, Reactor Building Penetration List - Quadrant III , 2.11 38 SS-422-401, Rev. O, Reactor 3uilding ?enetration List - Quadrant IV 2.11 39 SS-422-402, Rev. O, Reactor 3uilding ?enetration Lis - Quadran I7 r 2.11.40 1MS-07-002-1, Rev. 7, Reactor C0 clan: Syste 2.11.41 1MS-07-002-2, Rev. 7, Reactor Coolant Syste: 2.11.42 1MS-OS-C02-1, Rev. 7, Chemical and Volume Centr:1 Syste: ; 2.11.43 1MS-05-002-3, Rev. 7, Chemical and Volu:e Centrol ' Syste: 2.11.44 IMS-09-003-1, Rev. 7, Waste Processing Syste: l i 2.11.45 1MS-12-002-1, Rev. 7, Safety Injection Syste: ; 2.11.46 1MS-12-002-2, Rev. 7, Safety Injection Syste: 7, 2 1".4~ 1MS *2-2 2-3. Rev. 5, Safet;- Infe:-ion 27 s;e: ;
\- ,
ww..gv ; 146-S RI7. _I i f
2.11.48 1MS-13-002-5, Rev. 7, Residual Heat Removal System (~N 2.11.49 1MS-05-76, Rev. 6, Equipment Access Hatch-General \I Arrangement : 2.11 50 1MS-05-77, Rev. 4, Equipment Access Hatch-Double 0-Ring Seal 2.11 51 1MS-05-78, Rev. 4, Equipment Access Hatch-Double 0-Ring Seal Test Connection IMS-05-388, Rev. 1, Personnel Access Airlock-Plan View I 2.11 52 2.11 53 1MS-05-386, Rev. 1, Personnel Access Airlock-Atmos- . pheric Bulkhead 2.11 54 IMS-05-387, Rev. 1, Personnel Access Airlock-Contain-ment Bulkhead 2.11 55 1MS-05-198, Rev. 3, Personnel Access Airlock-Seal Test Panel - i 2.11 56 1MS-05-182, Rev. 2, Personnel Access Airlock-Tes: - Clamps j 2.11.57 1MS-05-239, Rev. 1, Personnel Access Airlock-operating Procedure 2.11 58 1MS-05-474, Rev. O, Personnel Access Airlock-seylock Procedure ; (]) 2.11 59 13S-05-151, Rev. 4, Personnel 2 scape Airlock-Plan Viev i 2.11.60 1 M S-0 5 -14 2, Rev. 5, Personnel Escape Airlock-Bulkheads ., 2.11.61 1MS-05-143, Rev. 4, Personnel Iscape Airlock-3ulkheads ! 2.11.62 1MS-05-150, Rev. 4, Personnel Iscape Airlock-Seal ?est ; Panel i 2.11.63 1MS-05-140, Rev. 3, ?ersonnel Escape Airlock-Operating l Procedu.. 2.11.64 1M5-05-476, Rev. C, Personnel Iscape Airlock-Keylock l Procedure i l 2.11.65 D-302-242, Rev. O, Supply Air to Personnel Access and Imergency Air Locks. l () )i S"M-0 l
;4f-? ==" -
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, , - , - , . v,.a-. - . , , .-- , . - .. ,,-
i 30 PREREQUISITES INITIAL /DATE
~
l
,d,~ 31 General L 31.1 The Reactor Building Structural Acceptance Test (LR2) i has been sucessfully completed. (SAT). < c /A j'/v-g/
!
- NOTE These steps are part of the Structural Acceptance Test (LR-2). If the Integrated Lenk Rate Test (LR-3) immediately follows the Structural Acceptance Test (LR-2) these steps do not have to be repeated.
r-I +3 1.2 The tendons of the.RB shall be inctalled and tensioned per SP-207, the Shop and Field Quality Assurance Program of Inland-Ryerson, and shall be reviewed by the Test Coordinator prior to the start of the ILRT.
- 5. A ff MlA l'C0 #( *3 1 3 The Personnel Access Airlock has been installed and tested per LR-5 s, a.7 MlA
+3 1.4 The Personnel 2 scape Airlock has been installed and tested per LR-5 sA7 d)A
+3 1 5 The Equipment Access Eatch has been installed and tested per LR-4. g O/A
+3 1.6 A general visual inspection of the exterior and interior fg of the Reactor Building shall be completed prior to the i_j s start of the ILRT. Particular attention should be given to all penetration areas. T r /.c /- / u. g f
+3 1.? A review of all structures and equip =ent within the R3 that can be da= aged by external preseures of 47.1 psig shall be conducted prior to this test. Iquipmen; and instrumentation within the R3 =ust be protected in acco.-dance with the instructions of Attach =en: XI.
n"l 4L i-j>&gi
*3.t.3 A weather check for extre=e or radical ven;her changes will be ade p.~ior to the start of the ILRT by checking with either of the following: l l
3.t.9.1 SCI &G icad dispatchers office 903-799-123a/Ex . i 2264 or 799-5243 - 3 1.8.2 .'iational Weather Service, 503-794-2409 ; fa y r we.e 4.* a an/ refr-*/ h t> edo 7g ,,,,,,g, i n.mbe r /~ 3 H; v e/x [10:I: The 'lRT shall not be cor. ducted under expected extre e weather conditions such as snow stor s, heavy rains, s;rrns winds or radical enanges such a hign or 1:v pressure area. O 3 C.'1- :
'46-10 RI'.. _*
v
INITIAL /DATE
,3 a
i The inside air te:perature of the R3 will be monitored
'3 1 9 for at least 72 hours prior to start of the ILRT so that TCY a\ it reaches a steady-state condition and is held constant within + 5'F. An ambient te=perature of between 55 to 85'F
[_ is satisfactory. AJMr 31.10 A representative of GAI resident engineering and SCE&G Tcd2L Nuclear Engineering is available for consultation during the conduct of the ILRT. ulA 3 1.11 ILRT Staff Personnel per shif t are available as follows:
** '-Containment Test Coordinator Tr je /-/a-g/
** 1-Test Supervisor '7~u/- /- p/-p,/
ptgat ** 1-Resident Engineer M/A
** 1-SCE&G Nuclear Engineer < rec /-/xcg/
++ 2-Plant Operators 3rz # / u- e/
+* 6-General Observation and Safety --T~r a /-/2/-#/
++ 2-Data Reduction Operators -rcA- / uu gj 1-Co: pressor Operator and Maintenance v e /e /- /v- sy (V3
*+ 1-Data Acquisition Syste: Operator ---/- /- /u- e/
2-I & C Technicians -r u /- /v- e/ ! 2-Ilectricians re a. /-/u-pr 4-Pipe Fitters or "echanics -r e // / - /w // 2-Welders -r c 44 /-i%42/ t 6-Laborers 9tu >-su.g
++50 I: These I;RO staff personnel will be required to be available for the entire test. A Leak Survey Team of 6 to 8 people will be cade up of the staff re:bers r.ot recuired for the entire test. The remainder may be released once ?g is reached and an acceptable lea 2 rate is apparent.
"0TI: All ~;R2 Staff Personnel shall be faciliar with A;:aa'--aa' VIII and have si6ned appropriate blanks, if required.
t
\-) 1 b 'w e$ " s 4
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i INITIAL /DATE V, , 3 1.12 Install temporary lighting for shelters and other required locations, as field determined. rep /-/A+g- l 3 1.13 Locate necessary equipment for access to the measuring points,'as field determined. 72A /-/w-pg 3 1.14 All non-escential electrical loads, located within the Reactor Building not required for the ILRT thall be de-ener61 :ed: 3 1.14.1 Temporary Construction Li6ht StrinEs.
f2// /~/N(
3 1.14.2 Construction Fans or Eeaters. T f 44 /~/wg , 3 1.14 3 Welding Machines. 7e# /-/+ // 3 1.15 Verify that the interior of the RB is as dry and clean as practical. All flammable fluids or gasses are removed. ,
'rus t-/V-9f ,
3 1.16 Provide temporary communications as field determined. 77 h- /- /H of : 3 1.17 Locate tables, chairs, workbenches, table lamps and desk calculators as field determined. -r- / // Auf jf n () 3 1.18 All exclusion areas shall be roped off, posted, and monitored by Safety Inspectors. The Safety Inspectors shall be on the site at all times during the ILRT. ( Re fe r to Attachment III). u- /-/w-/g l t 3 1.19 Reactor Building Penetrations are installed and penetration leak tests are completed.A Centainment gJ*3{ Isolation Valve and Penetration Local Leak Rate Test !
" Type 3 and C" , LR-4, and " Access Airlock Leak Test", '
LP.-5) 4 4. de p irect b 7.u r- r2p /.fw.// j t h (n.) m -: !
!46 '2 ?Il . ', l
.~
INITIAL /DATE 3 1.20 The following instruments have been calibrated within the [)
' last thirty (30) days:
3 1.20.1 PI-7311-LR (ICP-240.025) 7gp j- /.g/ 3 1.20.2 TI-7312-LR 1"2 At t 3 1.20.3 PI-7315-LR (ICP-240.025) 77 > // 3 1.20.4 PC-7318-LR 7'/' /c 3 1.20 5 TI-7316-LR , - <rAl-3 1.20.6 FI-7304-LR 707 42 _l_ . 3 1.20.7 PI-7313-LR (ICP-240.025) 7"?-4/ l 3 1.20.8 TI-7314-LR 7C/// 3 1.20 9 FI-7305-LR -{? A4 3 1.20.10 PI-7301-LR (ICP-240.025) 3CP /A 3 1.20.11 PI-7302-LR (ICP-240.025) 1'?A4 3 1.20.12 PI-7303-LR (ICP-240.025) '725// ! (~} 3 1.20.13 TI-7317-LR -r'/, //- ! v 3 1.20.1.1 PC-73CS-LR 75(//- 1 3 1.20.15 Data Aquisition Syste: 7'6Ar 3 1.20.16 ROD's (x 24) , / /d' 7 ' 3 1.20.17 RED's (x 5) /~ l
,/ /i s ,/
3,1.21 The Test Superviser shall keep a tes; leg ^' a activities including valve leakage repairs during the .
-- I ILR0usingAttachen;XIII,GeneralObserva'bl $ // ))
/ j 3 1.22 Secondary system instrucer.ts shall be in thei. normal cperating line up, except the equilizing va g" =
enal open to prevent instr ent datage. In // h8e/ 32 Che following syste:s are available for operation: 3 2.1 Reacter Euilding lignting Systecs: 3.2.1.1 Normal T//2 /-/^/ e/ r; V S U. *- 0
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~
1 l
i INITIAL /DATE ;
,.s NOTE: Some light bulbs will be removed that are not required for '
j 'i i the test or may not withstand the pressure. Some may be
'~#
inoperative due to breakage from SAT. Refer to Attachment ! XI. 3 2.2 Reactor Building Sump Level indication is operable and is recorded at hourly intervals on Attachment X. 323 Airlocks are operable: , 3231 Personnel Access Airlock 77 44 / 3232 Personnel Escape Airlock 7-(Ar" !/' 3 2.4 Verify with the appropriate System Test Supervisor that , actuation of Engineered Safety Features Actuation Systems by Reactor Building pressure has been defeated. , 1~6 A /- /u- s/ ;- 325 Reactor Building cooling Units. 7 e /,c 1 M o- epaab,$ 3 2.6 Service ' dater system. 77? /#. , 3 2.7 Industrial Cooling System. 5Ce 4- .F i 3 2.8 Fire Protection System or temporary fire protection equipment available. 77? /r J-h/-f/ 3 2.9 Leak Rate Test System. , ( 3 2.9 1 Air Compressors are available for operation. t 7?/r /- /4- e / j i 3292 Diesel Fuel available for compressors Operation l C 16 gal./hr/ compressor, e-r/+ S /tA f f l 3293 Temporary cooling water is available for lea 2 Rate Oest System aftercooler. r-n /-/ v-@ : 3294 The Air Dryer for the leak Rate System is 1:aded : with Dry-0-Lite deliquescent air dryer tablets or i' equivalent. 7~r ca /-/v.fy t 3295 Test sensors for ILE are pre-located as per C-811-002. -r? u /. /W- ! ( - ; P A.0 SPECIAL CEST EOUIPMENT ; 4.1 Auxiliary Tes: Equi, men & Instruments ; 4 .1 .1 RCD's ! Cuantity : 21 !
'dod el : 4 wire
?ange: 3 *5C'? T/// J- //A&/ j Accura:y , te p ', ,
r f'~~ \ < S UM- l 146 14 RI',* . i i
INITIAL /DATE ,q 4.1.2 RHD'S l (V) Accuracq t . 48 % ES. Ii Quanitity: 5 ' Model: 1344T Range : 0-100% relative hus:dity -l[ 14-gl l 4.1 3 PI Mensor Accuracy c.mS(S/n-ic9 o.os (WO-LsSQ _k /-14 O t 4.2 Miscellaneous Equipment ll t 4.2.1 Flashlights of the 6 volt type or stronger. l (As field required.) ! fr // /-/M// 4.2.2 One (1) desk calculator capable of multiplication and division to five (5) decimal places. -r/ p /-/e-pg 4.2 3 Platforms, ladders, and scaffolds (as field , determined.) ~17# /'-/M //' i 4.2.4 Te=porary waterproof shelters (as field determined.) WH /~/h*9/ ; 4.2 5 Te=porary lighting (as field determined.) -77 // /- /v-gf , 4.2.6 Tables, chairs, workbenches and table la:ps (as field determined.) 77 4 / /N gf 4.2.7 Te=porary ec=.::unications (as field determined. ) ,
)
Tf // /-/H-9/ Ten (10) air compressers capable of supplying a total of I 4.2.8 at least 6CCO SCFM of oil free air at 100 psig discharge l pressure. -rT y- /- su.ej l 4.2.9 Squee::e bottles of Snoop Leak Detection Solution or equivalent. -n g /- af-N
- 1. 2.10 Ultrasonic Leak Detector, or ecuivalent, f-- i detecting leaks.
~
Yfh ./-/&-B/ 4.2.11 Safety tape, signs, and barricade za erials for j establishing :he Ix lusion Areas per Attachmen: ZI*. < 7~/ b /~/H df
\
4.2.12 Containment Te:perary Circulation fans are We installed. /~/ ) l l S U?.-C 146-15 RI'i . 1-
INITIAL /DATE ! t f'S V ( 50 LIMITS AND PRECAUTIONS ; 5 1- All personnel not assigned to the ILRT staff shall remain outside the safety exclusion areas during the ILRT. All. personnel assigned to the ILRT staff chall re=ain in the safety designated area during the ILRT until the Test Supervisor ; deter =ines it is safe te perfor: the assigned duties or directs ! the IL.TT staff personnel otherwise. The exclusion areas and safety area are shown on Attachment XII. . TC /> He t / ; NOTE: The Contain=ent Test Coordinator is the only person that can order the start or restart of the test. Any.of the . following: ILRT Test Supervisor, Resident Engineers Tea =, ; Safety Coordinator or the Shift Supervisor can order the ; test stopped. All cust be in agreement for the test to start. . i 5 2. Work activities within the exclusion area while this test is ! being conducted will be stopped for the duration of the test. Access to the exclusion area during the test will be approved i by the Test Supervisor only. n /- /-/AA// ; 53 The ILRT shall not te conducted under extreme weather conditions such as snow stor:s, heavy rains, strcng vinds, or radical changes in barometric pressure. 5' < /,- /-/ v-p/ i r" 51 A general inspection of the accessible interior and exterior \ surfaces of the contain=ent structure (Reactor Su11 ding) and ! cc=ponents shall be perfor:ed prior to the Type A Test (ILRT) to uncover any evidence of structural deterioration ; which say affect either the containment structure integrity l or leak-tightness. If there is evidence of structural : deterication, the Type A Test shall not be perf0rted until { corrective action is taken in accordance vi;h repair ; procedures, non-destrue:1ve examinations and tests as l specified in the applicable code. 7'/Ze s'a,s // j 55 All pessible interferences between the R3 and pipes, cable i trays, and other buildings er any similar object shall be ; noted on A::ach:en: IIII, General Observations, and brough: to the attention of the Test Ocordinator 1 :ediately f:r : iispositten, prier to or during the ILRT. r& A /u pg ; 5.6 Reac cr 2uilding pressure is to be increased or decreased only I with the authorization of the Test Coordinator. HW- 6/ i E r f
..,.-s,
=
i
*:.,42 ,
F i-
INITIAL /DATE s gcgi 5 7 The Reactor Building will be pressurized, depressurized and
,y stabilized at pressure plateaus of 0, 413'47.1, and 0 psig.
(' ') Pressurization =ay proceed within the reasonable limits of the equip =ent, but depressurization should be controlled to 5 psi per hour unless a highter rate is authorized by the Test Coordinator / Resident Engineers Team. 12 p A/w pf 58 If the test pressure drops, for unexpected reasons, the ILRT - shall be stopped, and the situation evaluated by the Test Coordinator for test continuation or abortion. Sc% p /-/g n
- NOTE: These steps are part of the Structural Acceptance Test (LR-2).
If the Integrated Leak Rate Test i= ediately follows the Structural Acceptance Test (LR-2)(LR-3) these steps do not have to be ; repeated. 6 7cg g 'f*59 The Reactor Building pressure will be held att12 psig during pressurization for an internal and external inspect 4cn of the g ' building and equipment. (Attachment VII). M,/A !
+5 10 Personnel as determined by the Test Supervisor who are to enter the Reactor Building for the 12 peig inspection =ust eet requirements of Attachment VII. -r & /-/4/.N
+5 11 Air within the Reactor Building is to be sa: pled and analysis is to be posted at personnel access points to the R3 Containment c prior to the 12 psig entry. Sampling to be done in accordanca l with EPP-123, HPP-125, and Attachment VII. --r m A/a p/
('-,#1 5 12 If any significant odifications or repairs, as determined by the ; Test Coordinator and Resident Ingineers, are =ade to the R3 follcwing the ~LRT, the IIRT shall be repeated or the repair [' local leak rate tested and the results added to the ILRT results (L g=). re. nr , ft M- /-m-e/ 5 13 ILRT leakage rates shall be calculated using the Absolute Method corrected for instru ent error. ( Attach:ent X7:!) . -~ue /-m. e/ 5 1a The sequence Of test activities shall be as follows: Times indicated are esti:ates only based on a pressurizatien and r depressurization rate of 3 psi per hour: 7'r # /-/u-d/ ! t 30TI: If the ILRT is to 1 :ediately follow the S AT (SUM-C-147), ; building inspection at 12 psig is not required i aa. m m t. ,t i_ m y __ m. .T .M.T_ 1 Pressurice Reactor Building to 12 psig 4.0 l Inspection of Reacto.- Iu11 ding Interior and Exterior 1.0 l Freasurice Reactor 3u11 ding to !!.1 peig '2.0 ! I j f )\ \- j C ) s 's. *.R s-;=. e'a
- V m-f*. 4 56 _
l l.
i I 1 1
~
otabilize Reactor Building Pressure at 47.1 7s 4.0 (,) psig (minimum) Record and Check data at 47 1 psig 24.0 Verification Test at 47 1 psig 6.0 Reduce Reactor Building Pressure in 0 psig 15 0 , TOTAL 66.0 Hours
' INITIAL /DATE 5 15 Air Lock Operation is to be in accordance with ,
Attachment VII. Pressurization and depressurization . rate of 3 psi per minute should not be exceeded in order to prevent personnel injury. 11//r /-/v vr , 5 16 Containment Temporary Circulation Fans are installed and operating- - ~7~& AAN
- 5 17 Insure L.R. Penetration and other penetrations in use or tested af ter the ILRT, will be add to Las ar.d the f{ .
UCL. 7'(h' /- / Ave : 5 1S Secondary system instruments shall be in their nor:al operating line up, except the equilizing valve shall be I open to prevent instrument damage. 7~/// A A.p / \ 6.0 TIST METECD 6.1 Pretest j 1 6.1.1 All prerequisites in See:1cn 3.0 of this pracedure have been cet. 7~~( N /-/W-tf , 6.1.2 All Li its ar.d Precautier.s in Section 3 0 of this ! procedure have been reviewed. 7-(/r /- /v d / 6.1 3
~
nstruments installed per Drawing CS* t-CC2. ;
-7~> /A- / - /+9/ :
6.1.4 Valves aligned per Attach en I of -his crocedure. I w s-e as
- ar, ' ! ter
- nur r'* J A 7 ; c,n ,.pi. p, i'
6.1 5 All equip =er.t vented as described in Attachsen: ZI. 7"? n >~ /+n ty 6.1.6 Verify that the tempora.y circulating are operating. i re J. - i.iu.pf TC9
- 1 ' 6.'.' Eeac: r luillir.g te:;erature har t een :Or.it:rei f:r ~2
- heure ar.1 har stablitei 5 *.' ( Re f e r to 5: ep 3 1 9 ) .
u e W led '" .5..*-
INITIAL /DATE NOTE: If the ILRT follows immediately the SAT this requirement
/~^) '
may be waived by the Test Supervisor.
%_e .
Temperature 4/.477 'F tJA 6.1.8 Clear the Reactor Building of all personnel. Tc /J /-/y-8 / f NOTE: At this time the test director should verify that all ;l personnel are out of the Reactor Building. 6.1 9 Close and lock inner and outer doors of the Personnel Access Airlock. yPA /-/+-// 6.1.10 Close and lock inner and outer door of the ?ersonnel , Escape Airlock. n // A /v-#/
+ 6.1.11 Verif lift pressure of Relief Valve 918 per Attachment
'TC Og(
XIV.f' NOTE: SAT cay)be
. valved if ILRT i=cediately follows Lif are psig blk 6.2 Pre-Pressurization Di : 0 PSIG: ,
+6.2.1 Review of possible interferences between the interior and exterior of the R3 and pipes, cable trays and other buildings shows that all items have been dispositioned by ;
A the SAT Test Coordinator. 7'g 4 /-/u./e
\_/ l 6.2.2 Start recording the ILRT Data as required in Attachments II, III, IV, 7, X. 7g p j jp p ;
i NOTE: If any data is anually taken, the data taker shall sign his na:e, date, ti=e and test pressure and see hat the data reaches the Tes Supervisor as soon as possible , after data is recorded. T r /s /-/v-?/ 1 I 6.2 3 All safety barriers and signs, etc, are in-place and the exclusion areas are being monitored by the Safety Inspec: Ors. v>4 /- / tA p r ! 6.2.4 Secondary syste: instruments shall be in their nor:al eteratin: line up, exce:t the seuili:ing~ valve shall be i open to prevent inst rument datade. 7~' /A /- > V-a t < 1 TCd > \ 6.3 Pressurization to 12 psig: 1 I i l j t N,s .m. . .. _ . -
* , .e l
4
I 4 4 INITIAL /DATE i
' NOTE: . If the Integrated Leak Rate Test (LR-3) is immediately
() fx
' following the Structrual Acceptance Test (LR-2) the inspection at the 12 psig pleateau may be omitted. This inspection was performed as part of LR-2. A review of ,
work done on the inside of the R.B. during the time between LR-2 and LR-3 may warrent another inspection at ' the 12 psig pleateau. This will be at the discretion of the Containment Test Coordinator. 631 Announce the start of the Test over the Plant Gaitronics System. 7'd 4' /- /4/ fy NOTE: All ILRT Staff Personnel on duty shall be in the , Test Control Center except those directed otherwise by . the Test Supervisor. All other persons shall be directed to stay out of the exclusion areas. The Safety Inscectors are responsible to enforce safety regulations and keep all unauthorized persons out of the exclusion areas during the Test. 632 During the ILRT Test monitor the followings at the same f requency: 6.3 2.1 Rourly (Attachment V & I) Atmospheric '41ndspeed and Direction Relative Rumidity 3arometric Pressure Average Air Te=perature (]) Control Roos Log WA /- a . sg , 6 3 2.2 Quarter Rourly (Attachment II, III, IV). R.3. Air Te=perature R.B. Mois tur e , R.3. Pressure 7fu f -/ u.p/ NOTE: R.3. Data will be provided through the data acquisition syste: in the ILRT Panel 436' elevation : Inter:ediate 3uilding. A: ospheric Data vill be recorded on Attachment V. In case of Cata acquisitan ; syste: f ailure data sheets are previded in Attachments II, III, I7 for Reactor Suilding Data. 633 Throttle open valve 938-LR to initiate cooling water t flow to the Leak Rate Test Aftercooler. WN /- / 4/-fr ! NOTI: Tc assure that water does not ecliect in the ; af tercooler, =ake periodic blowdowns by opening tha afterecoler drain valve at approxicately 15 =in. l intervals. 1 9 . W ee d 6e & . /~\ G s SUM-C 'i 126-20 ?.I7. _t
_.__m_. . _ J i x INITIAL /DATE I i 6 3 5 9 Throttle open Leak Rate-Test Air Dryer' drain valve 1
;h -]m
~ 911-LR.to establish a continous blowdown. Ty A- /-/u.// l 636 Throttle open' valve'914-LR and let' pressure control:
valve IPV-7318-LR throttle.as necessary to maintain upstream pressure,-indicated by PI-7315, at.80-psig. ygg ,_g 6 3 7- Open' valve 914-LR to th'e full'open position.LMaintaint upstream' pressure at 80 psig with pressure control valve ', IPV-7318-LR as necessary , mey / -/y.s?/
' 6 .~ 3 8 ' When valve 914-LR.is lfu'ly open, adjust pressure l controller PC-7318 for 80- psig with pressure control j valve'IPV-7318-LR to operate automatically. . !
9"(/,s /-/Vrdf ! 639 Observe pressure indicator PI-7301 and verify that' )
~ Reactor--Building pressure is increasing. .
Tf// s-/N-d t' - 6 3 10 Adjust- pressure controller PC-7318. as necessary to j
=aintain a steady pressurization rate. 7fu f. / v. 0 7
The rate of pressurization is. dependent only on the
~
NOTE: l capacity of the pressurication equipment and good udg=ent, but should be maintained a' < engineering approx. 5 psij/hr. ! j ~'"6.3 11 Increase the Reactor 3uilding pressure until PI-7301-LR I indicates 12 psig (+1.0, - 0.0) and then: {}) ') ! 6 3 11.1 Close'17T-914-LR. kjk i 6 3 11.2 Close 17T-919A-LR. AJ Mr yL 6.3 11 3 Stop the Air Co=preosors. k) hW ]
-(to '6.4 Reactor-Suilding Inspection at 12 psig. ,
NOCI: The ?eactor Building Inspection is conducted as a part of the Structural Acepetance Test (LR-2). If the Integrated l Leak Test (LR-})-immediately follows LR-2, this inspection say be o itted. Consideration.should be given any repair , or construction work done between LR-2 and IR-3 before " inspection is c=itted. , NOTE: Personnel en'tering t're Reactor 3uilding cust meet the requirements of Atta h=ent VII. ; 6.1.1 Air.Ouality Check , U003: Self contair$d air' breathing apparatus is to be available for personnel entering the Reactor 2uilding-for air quality sampling. LO sca-: 146-21 R I '." . _*
,- >-,n ---. . . , , . - . - -. - - . . -
INITIAL /DATE
-~~
rw , 6.4.1.1 Unlock outer door of Reactor Building Personnel (_) Access Airlock and enter Airlock. W A-6.4.1.2 Close outer door and slowly equalize air pressure in the Airlock with the RB pressurelMr ( Attachment VII) . 6 NOTE: Do not exceed Pressurization Rate of 3 PSI per minute. NOTE: The pressure shall be held at 3 psig and again at 7 psig sufficiently long to determine if anyone is experiencing discomfort.
\ 6.4.1 3 Perform air quality check per Atta ent VII.
-{Cy3 NOTE: If air quality limits are not =et, depressurize airlock and report results to Test Supervisor for resolution.
6.4.1.4 When airlock pressure has equalized, open the , inner door and perform air qualit- "eck per Attachment VII. 6.4.1 5 When air quality check is complete, enter the
~s Airlock and close the inner door. '
O k NOTS: Air Quality check is to be done in accordance with E??-123, EPP-125 and A::achmen: 7II. 6.4.1.6 Slowly depressurice the airlock and equalice the airlock pressure to at:cs:heric tre sure. I N NOTE: Do not exceed Depressurization Rate of ? ?SI per rinute. , o (_)
?
S L'7.- I
-:: :.. .3 .
4
INITIAL /DATE
^
c 6.4.1.7 Open outer door and post air quality sample
s -',
results on outer door and report to the Test k/ Supervisor. 6.4.1.7.1 Results Posted AJ d 6.4.1.7 2 Health Physics _ Aj k 6.4.1.7 3 0xygen (>19 5%)
~% Abk 6.4 1 7 4 FlamableGasses(<15%))k
~
% A 6.4.1.7 5 carboa Monoxide (< 100 p;m)
~
ppm AI R 6 Y\ NOTE: A copy of the results as recorded by Chemistry
.f(U and Health Physics is to be maintained by Test Supervisor for test records.
6.4.2 Internal Inspection 6.A.2.1 Gather personnel designated to perform inspection and ensure all have =et the requirements and are fa=iliar with the instructions cf Attachment VII.
^
\ )
- Lh v ,g 6.4.2.2 Nu=ber of Personnel entering. NW 6.4.2 3 Unlock Reactor 3uilding Personnel Access Airlock outer door and assemble group inside the Personnel Access Airlock.
AJA NOTI: Do not exceed Pressu.-1:ation !
?. ate of ? IS: per inute.
6.4.2.4 'elhen Airicek pressure has equalized, open the inner door and leave inner door of airlock open. - A1A 6.4.2 5 Inter the Reacter Building and chech equipner. , c0nditions as specified in Attach:en: 7:I. ;
-- r
\ ,
(m 0...'~.
*~C=;; .
~. L .7 f
INITIAL /DATE
%~ NOTE: Record all observations on Attachment * '
(~T VII, Su :ary of Inspection. 'J
,. ({'
6.4.2.6 Upon completion of inspection, enter Personnel Access Airlock. AJA :t 6.4.2.7 Number of Personnel Exiting .. (Compare with 6.4.2.2) /(jft i 6.4 2.8 Close inner door. Albr ! h 6.4.2 9 Slowly decrease air pressure to atmospheric pressure in accordance with Attach. nt VII. f NOTE: Do not exceed Depressurization Rate of 3
'[C4ag PSI per minute.
i 6.4.2.10 Open outer door and exit Personnel Accesa i Airlock. k l 6.4.2.11 Close and lock outer door, bdfk 6.4.2.12 Inform the Test Supervisor of any problems , (~T discovered within the Reactor Building and hand (/ in all observations recorded on Attachment VII, Su :ary of Inspection. 6.J.2.13 " Summary of Reacter Building Inspection at 12 PSIG", Attach ent VII, is co:plete. All i problems as noted on General Observations l Attach ent XIII, have been resolved A k __ 6.a.2.11 Review all information data and resolve any ; problems. If all is satisf actory, i proceed with pressurization to 47.1 psig. . (Cest Coordir.ator) hjk , 8 6 0 s r:-c 1af-24
- EI'l . -
E b I
INITIAL /DATE 6.4.2.15 Verify leak tightness of all ILRT boundry
~N. (~s valves by the use of ballons on vent or l/
K- \- drain valves, use of ultrasonic leak detector or equivalent, or snoop leak detection solution or equivalent. Record any leakage on General Observations, Attachment XIII, and notify Test Supervisor immediptely. } p f, n iiL;;5{ I
~'
I [6.5 Pressurication from 12 psig to 47 1 pais. NOTE: If ILRT is to immediately follow the S AT (SUM-C-147), pressurization may proceed from 0 psig to 47 1 psig. NOTE: All ILRT Staff Personnel on duty shall be in the Test Control Center except those directed otherwise by the Test Supervisor. All other persons shall be directed to stay out of the exclusion areas. The Safety Inspectors are responsible to enforce safety regulations and keep all unauthorized persons out of the exclusion areas during the pH 6.5 1 test. Start the Air Compressors. k)k 652 Throttle open Leak Rate Test Air Dryer drain valve 911-La to establish a continuous blowdown. j hJ4 L I 653 Open 919A-LR. k} he (^'/T 6.5 4 Throttle open valve 914-LR and let pressure cor. trol valve I?V-7316-LR throttle as necessary to aintain , upstrea: pressure, indicated by ?I-7315, at psig. > 6.5 5 Slowly open valve 914-LR to the full open position. Maintain upstrea: pressure a 30 psig with treasure control valve I?V-7313 as ne c e s's ary . klhr 6.5.6 When valve 9tA-;R is fully open, adjus pressure con:r:11er ?C-7313-LR f:r 30 peig and allow pressure control valve I?7-7313-LR to opera:- , aute=a:10 ally UOTE: 7erify upstrea: pressure is maintained at 30 psis by observing PI-7315-LE. Adjust cc pressor,}Rgad-ing as required. N 6.5 7 During the ILRT Tes: =cnitor the followings at the sa:e \[ frequency: P 6.5 7.1 Ecurly (A :ach:ent 7). A u
- I L
%)
C t7 ",f .
- I, p:-::_ ..
.2..
( INITIAL /DATE At ospheric windspeed and direction (') l,, Relative humidity Baro etric pressure Averace air temperature Control Roo: Log hJ r 6.5 7 2 Quarter Hourly (Attachment II, III, IV). TL J*\ R.B. Air Te:perature R.B. Moisture g R.B. Pressure k)M NOTE: R.B. Data will be provided through the data acquisition system located in the ILRT panel 436' elevation Inter:ediate Building. Atmospheric data will be recorded on Attach ent V. In case of data acquisition syste: failure, data sheetc are provided in Attach =ents II, III, and IV. for ; Reactor Building data. , 6.5 3 Observe pressure indicator ?I-7301 and verif~ that , Reactor Building pressure is increasing. A)k ; 6.5.9 Adjust pressure controller PC-7313 as neces ory to =aintain a steady pressurization rate. 6.510 Increase the Reactor Iuilding pressure until I -s ( (v)
\
PI-7301 -1R indicates 47.1 psig (-10.0,-0.0) and then:// 7t h 6.5 10.1 Close XVT-911-LR TQi\A [M@s 'f"
)t 6 5 10.2 Close XV:-919A-1R T.G( [WA_1' 6.5.11 Upon closing pressurizing syste valves, ven; air inle line. cfx T'Q ,g 1 J 6.6 Ca:a IOllection at 27.1 psig #fnp .-
6.6.' 'ihen pressurization 0 47.1 psig has stopped, all:w i a rir.inun er f:ur (4) hours for 3 abilizaticr -1:e. The R3 is considered stable when the average te:perature d o es r.;; v ary :o r e than 1,0 * ? p e r ho ur f o r -".e las t, tvc kI'
\
hours. EbtA_ \ i r)B ) i 6 . 6 .1.1 St a\ r'Y3 0 4R* stabilization period Srqs( s jg 6.6.1.2 Completed stabilization period 7?a /- /5 e, 03Hs 6.6.2 Record the fcllowing at specified intervals for a rini u of twenty-f:ur (21) h:urs. 7?/4 /-/6 -#/ ' 6.6.2.' "Ourly ' A tach ent VI t AI O'EheriO dindsteed and DireO*.i*n At:: sih e .-i Eelat'i te Eurii;. (} i
.r w . ?. _ . !
I -C=LC ~.L.,. I
INITIAL /DATE 6.6.2.2 Quarter Hourly (Attachment II, III, IV) n t.~ / .
.-s ;
i R.B. Air Temperature ! R.B. Moisture R.B. Fressure 72// /-/f. 9 6.6 3 Upon completion of the 24 hour minimum data accmulation period a determination of the leak rate of the Reactor Building shall be made. -Tr A /-/4-6 / : 6.6.4 The Containment Test Coordinator and the Test ! Supervisor will verify that the ILRT leak rate data evaluation indicates that the leak rate is within allowable limits in accordance with known instrument calibrations. Leakage rate (La c) * ;
, ow % wei6ht/ day.
Containment Test Coordinator \ m. Test Supervisor
. ns.[ -,
/,Mr. le,.~ -dje /-/4 -// -
6.6.5 The final LAM is: 955 UCL + add on 1 75% L. ki 6.7 Leak Rate Data Verification at 47 1 (,10.0,-1.0) psi. ! 6.7.1 Cpen valve 930-LR, Leak Rate Tes Panel Flev ; Indicator Inlet. Tce- /- //. -.o/ ; dp 1 o me r
-72,#-
J 6.7.2 Open FI-7304-LR Inl: Roo Valve. /-/g,-a< TG 52 b ow r-6.~.3 Open FI-7305-LR I-n4+t Roo 7alve. Te'/A / n..pf i 6.7.4 Open Co: mon Isolation 7alve for flev [ indicators in IIRT panel. G /-/c. py j 6.7 5 Slowly open the following valve and establish
/ .,'i g/ a flow ecual to 4+R through one of the fl:V
"# y'
~
indicators: '* 9 '/68 7 l MT 6.7 5 1 FI-7304-LR 9 -l. "T(# /~/4- h i
$l Od(;, wu
{ 6.~.5 2 FI-7305-LR n:r'?- . 6.7.6 Record :"e f:llcwine at indicated intervals for , a minimu: Of fcur (!) hours. 6.7.6.1 bar:er Rourly ( Atta:h:en: II, III, I7 5 7I) . ) E.3. Cem,rerature ef/6fd/ E.3. 2rSSSuT9 C\.M / /ri/A t , R.E. cia Ore
. 5 \i( ./ft/t/ l Su':e ri Oos ei flO'/ fr05 II-730*
an'i FI.I305 c: ILR: panel. 'M dKh'~/ ,-~ O...'.. '
' 4 6 ' ~ I',' . '- i
)
i
INITIAL /DATE rs 6.7.6.2 Rourly (V & X) 1 Atmospheric Avg. Temperature I~lIhh d Gl61
'Atzespheric Baremetric Pressure sAs . lag t Atmospheric Relative Rumidty ' L>s .h s h , t Control Room Log ' s3< . f, ay ,
6.8 Leak Rate Data Evaluation. < 6 . 8 .1' The ILRT Verification Test has demonstrated , that the known superimposed leak rate is within gs. .
+ 25%
Ic + 25%of = that indicated LAM + Lo. by the ('ILRT Data Szgg? ____ d t (- U w a.iqu g/q n 6.S.2 Leak rate calculations indicace that ILRT and 7erifica icn Test are comple*e. gg ktdtf Test Coordinato._\ NOTE: Frier to deprescurization a decision on the satisfaction cf data and leakage rate shculd be made by the Contain=ent Test Coordinator and Test Supervisor. 69 Depressurization fr0: 47.1 (-f0.0,-1.0) to O psig. r~g 691 Slowly open valve 9193-LR and depressuri:p gg3 g{ tf (,/ Reactor Building to C (-0.1, -0.C) psig. ' . NOTI: De not exceed a depressurization ra*e of 5 psig per heur. : NCTI: Open valve 9190-LR if required. '~232 s kft l 692 Cbserve pressure indicator ?!-7501-LR and ve.-ify , that Reacter 3uildin -7
~~
cressure is decreas' b S ql l 692.1 Record the R.3. pressure hourly during the decressurizati:n. : ( n..e_
?
. a v .,. e n. a. ..a,. ~ Q , p, y i ?
6.9 3 'cl hen Reacter 3u11 ding pressure reaches ! l (-C.1, -0.C) usig, leave valve 9193-LR c'rer.. W ( .1hd >
, i NCTI: Leave valve 919C-LR Open if required. i 6.9.a Review all data and resolve any problems. :f all '
is satisfactcry, the ILRT Test is considered't4? c::ple:e. 4 / -/G -l/ l i l ,c r fx ^ Tes: Ocerdina$ C$ _
. sy ' ;
\ 2: , v..... O I p.
- - - ..i.; 1 i
. ~ . - . .-
f -
)
INITIAL /DATE I, e :- f91 6.10 Restoration
%Ja .
l 6.10.1 Install blind flanges at the following locations: j 6.10.1.1 . Pressurization Line inside R3 Cont fr....:.h p Jn
/ / '
6.10.1.2DepressurizationLine3 insider 3C-s.n=ntlK2
/ 23
/ / y
'6.10.1 3 Depressurization Line C inside R3 ir n
/ '!
6.10.1.4.Leck rate test#^01. 2 penetration canel 2 flow detection [#g' -;2./37/f/ }
/ / :
6.10.1.5 Leak rate test ranel- pressure _ detec" an ?
@ penetration #210. 8 2215/f/ / /
i I 6.10.2 Rotate Spectical Flanges at the following l locations so.that-the spectical is visable: i i 5.10.2.1 Pressurization Line by valve 919A. , l
.3YT/ l
/ /
/
6.10.2.2 Depressurization Line b i o 1 7 valve 919"91 m&/ 6.10.2 3 Depressurization Line by valve 919
// -
/ / h 6.10.2.4 Leak Rate Test ?anel Flow Detection -- j i Penetration #201. '
2/2 ' <C7 - !
/ / i 6.10.2.5 Leak Rate Test Panel Pressure Detec*: n at !
Penetration #210. _ z ' jG7 i
// !
6.10 3 C1cse the following valves: i 6.10 3 1 XV9-900-LR 3/fr/r/ 6.10 3 2 XVG-901-LR /IkY / 6.10 3 3 X7G-902-LR 2dhh 6.10 3 4 XVG-903-LR zkkf l t
/
6.10 3 5 I?3-904-LR l 6.10 3 6 XYG-?05-LR /b W l 1 i SUM-: l 145-2? RI7 1 ! e i l l 2
. . ._ - . . - ~. .. . _ _
i INITIAL /DATE ! 6.10 3.'7- XVG-906-LR 2 f/g/f f
- . -.-- z -
q
~
6.10.'3 8 XVG-907-LR
~6'.10 3 9 XVG-908-LR sdhI ;
6'.10 3 10fXVG-909-LR /db7
'6.'10 3 11 XVG-928-LR~
6.10 3 12 XVG-930-LR . ) : 6.10.4. Notify the appropriate system Test Supervisor that the [ ILR0 is complete and that the Actuation of the Ingineered i Safety Features Actuation Systems by Reactor 3uilding i pressure cay be placed back in service. ! l l/$$l l
,/ / i 6.10 5 Recalibrate the instruments listed below: r 6.10 5 1 FI-7304-LR
/ /JEp!g7
/ I
/' l 6.10 5 2 ?I-7313-LR 6.10 5 3 TI-7314-LR _
l 6.10 5 4 FI-7305-IR !
) 6.10 5 5 PI-7301-LR ,
6.10 5 6 PI-7302-LR i 6.10 5 7 ?I-7303-LR [; 6.10 5 8 TI-7317-LR ! t 6.10.5 9 ?0-7308-LR l i 6.10 5 10 Data Acquisition Syste: ; 6.10.5 11 RCD's (x 24) ! 6.10 5 12 TI's (x 15) , l 6.10 5 13 RED's (x 5) v 1 I I t k f( ). SU::-C l 146-30 EI7 1 ; 8
p (g' I.O DATA REQUIREMENTS %) .' 71 Data is to be collected on the following data sheets: 7 1.1 Attachment II - Reactor Euilding Pressurization / Depressurization 7 1.2 Attachme nt III - Tarpr-ature Data 7.1.3 Attachment IV - Moisture Data 7 1.4 Attachment V - Atmospheric Data 7.1.5 Attachment XIII - General Observation s F 7 1.6 Attach =ent II - Data Acquisition Systec ; 7.1 7 Attach =ent VI - Flow Data i 7 1.8 A :achment Z - Control Roo: Icg 3.0 ACCEPTANCE CRITERIA
**e aasured leakage ra e (La=) at pressure ?a (27.1 psig) sr.al(be less Akan 0.75 La and not areater than Idj penetrations that are .n \
use ("ie.LR) or not lined up in accordance with this procedure rust l be type 3 or C tested and their results add to the r,,4t uppe. ,_s confidence level. - Refer to A::achmen XVII of this procedure for the calcula; ion of the axima: allowable leakage, la, at Pressure Pa. [ F f i t s e t >D' 4 E s_/ i b 4 6'. " 4
; ; t.e .
i* *j4.T4
I' ATTACEMENT I
- 1. Valves with an asterisk. (*) are Containment Isolation Valves 1 r'3 ( ' (CIV) and shall be operated as below.
Q ). ; A. If the CIV is initially closed: open the CIV and then reclose the CIV via its normal =eans of operation.
~
B. If the CIV is open: close the CIV via its normal means of operation. NOTE: .The use of " cheaters" or any assistance in closing a CIV is strictly prohibited. Caution: Insure penetration volume is j drained of all water or fluid. If dead les or loop seals are feand, use air if necesse?y, to drain all liquids. Remove TC caps as indicated on valoa tags. .
- 2. To properly. drain the penetration:
A. Close the penetration boundry valves.
- 3. Open the indicated Test Connections (TC's) and allow all fluid to be vented or drained.
C. Upon ccepletion of step B close the CIV. lete closure of power opere.ted valves (i.e. MCV's, 3 Toinsurecoc"Iholdthecontrolswitchinthe" air diaphrag closed" position for'a few extra seconds after the closed indicator light indicates the valve is closed. e f 9 f I
?
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; w. .,
- 25-:2 s:T.1 ;
e 4
I
- - ~ ~ ~ ~
l 2M r. 2- t;- 63 .; , Ph ./.A=CN 1 3 01 O' = =c4 n-en-un ! 1 Y e f I r s O .I I si 1 m-n-a l\e e L g N m-22-a f 6 t I m;,. l res==s l ==ni= 7.p.T;,-. l 2c ==s lrr=n2= l !
- l U3-23-AH l CdSD yf l l
. .m-21-u l Ccsa .I ., o l l ;
I I I I i i I l I I I I l l 1 I l l l I I f I l I
, I I l- l l l j i i i i i .
l l i l l t ! I O I I St 4_,c I I I l l
.36-;3 1
- 33. , ,
l l 1
.. _ _ . . _ . _ . - _ _ . _ ~.. . _
P.\GF. J.,,( 8F p, *
?"fE 3AT*0N 1 102 [ ' G .- -
d,, DRA;.EtG d 0-302-222 B r" : yng 31113-52 O o xe b x 31CSC-N 31.53E-SW G N
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/
31033-5 M.: 3~** b ' 31 SW 153D-5W d.! l G-U-
- 0TE: This system is water filled and operating during an ac:1 dent.
I" 7AL74 7AL l mp, l703*--~3 l UU/M Mh, l?CC"ZH l *3C/ ~ A3
- u m -su l cose l ggg l l n m -su j cosa l U l l 3u30-su I c=so l l l nus-s I casa l l l non-su nesa l l l
,u n-se l ora l l l
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nny-se I nnso l l l l ! vr e I n ,s n I r I ! ; ! I t l t l I i i i l l d > I Sta t-C I I ! l 146-34 hi',V. l ! 5
.,,-,,w,- ,,,4 ,.-.,.p -
-.rr,er,-e eve,,---'
- . ~ . . .. .
* ' ACTACIC:C;T 1 .
-l PAGC i O L* 6%i :
pct../.AT*cti 1 101 O',, DFA'cIG J 0-302-861 l t f I l n - l t iC-l~-E ; A A > f \0 D o 0 5 7-E., Y 6062-E l 6056-E . ; ,
* .j C E 6063-E i l i I
p h , 20= - ===.I -16 /:1 7-
- 6oS6-a coSo l l I 96r d4h l l
. 6037-a I ccsa I
'l l l l 6063-E?. l cCSD l l l l f
- c -<. -a i c?ct l l l .
l I ? I I ~~ l e-3-a I orci i y l l I I I I l O I I l i 1 l j sim-c 1!.6-25 ? U' -.l . I
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- - .. .. = '
ATTACI':llIT C PACF, 5 W 63_ ; PETE 2ACCN 4 105
DFX,.CIG 1 E-M2-86 L ;
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@60513-E @60533-a 6058B-E X' -
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505C3-E 60523- a
' $"d "50593 x -2 Z )
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l I C<:,Z Z-X- l 60613- E 6060E-3 I Ih(QD) I (v"'} QITIC- -) DI5CO.niIC j
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7 ALT-
$tteb. 20
- a-T Z/M l -h l 7CSCS N* /M l 4 605u-n I coso I (8f MJ l l l l
. 605n-a i cCso I p/ l l l 60su-a l Ora l l l l em.-use I cra l l l l l i
l l I 4 sc,50s-a c:.cs a l l } l ;
- 6052?,-RC f CLOSD l l l l M5F-C CICSD I -v = \ cr= \ t !
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l ons-xs- i or= l ) l l l O I i ! l l StT.4-C 146-35 RI/.3.,
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-PLr.a.AIION 1 201 .-
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O !!OTI: This penetracion in-service during SAT /ILRT. l l t l 1 g~ 7nn i l PCS!""""3 ' l u. /*.Z'"! g" l?Ca.."3 T/TA-*! l ; La i l l l l i l l l : l l I I I l ! i l l I ., l l , I l I I l l I I ! ! ! l : 1 l ! l l l l l l l I I I O 5;"'t - " i t. 6-37 g f, 1 l 1 I I
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P/4 F. OF Jg, P aI 2A;" N 1 204 _j OR/SDC 1 0-102-612 9590A-C0 t $33-C" 95905-C 9602-C0 , Q l i i l$ 9601-C: l seco-C gggg cc l ll 7 i l 7 9603-C: 597A-C0 9 i aa 939 7C. 93972-C: ml ul "c>0C <:
.- c:
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- 96m-ce I caso l# %II l l l
[959eA-ce i cesa l ll l l l 95903-r: l CLOSC l l l l l 9590c-c- I caso l J l l l l 9 m -C- I cra l l l
,se2-ec j sei l l m _. c l nem l l ; j e x-e- ! .- , e i ! l l l j m ..cc . I ct, , l l i ; i i u ns-ce I cteso i l l j j n
v 939:c-ce l a:sa I , i l j l CT* f.t* T46-38 R:~/ ,1
ATTACit?!F.NT I P,' C r i r?" 6 3. . .
?Dc,..:.ACC'.I I 210
'- CRA;CIC 1 D-102-8ll
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- C I: This pane::a:1:n in-se: rice during SA*/I'R"'.
f , l ?CS!"'~;N l~7I"!OA~I l , l703;"*H l 4. /?.AC UA 1 I l l l l l l 1 I I I ; I I I I I 1 l ! I I _.! I I I I I l ! l l l l i t .
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ATTAR.htic:7 t-P.'.C g .9 r r 63 J. PDTdT3A;;CN f 211 ; CPAT.IG !) 0-102-811 . I r i
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4\\ I X : 9193-G 9203- u dl I i i 4 O :1CTI: This pene::a:icn in-se:tice during SAT /UJ.T. I f
, l 705-- 03 l IT/:A:2 l [ , l?1-_03 l -r- /: c l l MA I I I I I :
I I I I I ! l l l I I ! I I i .. .' l i I I ~ I I I I l I 1
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l ! ! l I i I i i !
.:0 l l I I I l StH-C 146-40 r,rft . 1-( j i
NET.\ Cit C::T I P'4E IQ, DI 531
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) ?CTI""JX"'C!T 1 2 ! 2 DPE.* dig J D-102-811 l1) '
919C-71 2CC-T1 4 i ,r> 1 j
- 0TE: This penet:s:i:n in-serit:e during SAT /CJ.T.
. ~, l ?CS~-- J l w*-'!O.L~2 l ,
l705~~~-7, ~ l r /O A. 2 l l MA I I I I I l l l l l l l l l l l l l l l l l l l l l l l l l l I I I I ! I I i i i I I i i I ,m, l ! I i l l ! l l l l l Ff *:! /*
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I ATT.\riNC;T T , PACE 11f5 ~ OF 662 !
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' l PDTETRAT:CN f 216 .. ,
O DFJSETC # D-302-811 !#A./ , l i i b
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'I O i NOTE: *his pene::stice in-service during SAT /C.R*. ;
l l U O MA I I I l l I I I I ! i l l I I l l l l l i i l I i ! i
! l I I i I I I ! !
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j O I l l l stS!-C E ' 146-4' e --mr .. - - <--a ,- e- - , - .- - y -w w.e.w,. , , - . , - . ,e e
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.%TT.tcliilr:!T I-PACE' Q, nF g PETCLCCN . J 221 V W '
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8382A-CS [ 8350C
/ l 3 -CS 3386C-CS 3102C-CS 3369C-CS g
g e
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TC7-CS TCS-CS ! l F J l l l PCS!""3 l"TC/LC2 , l TCSC3 l ..-/LC" l
- 3102c-CS l CLOSD l [fh/ l l l l 3386C-CS - l N/A ! f I l l l 3350C-CS l CLCSD l T* -7'-C S CPU ,.
l l f TC 2-CS PLOSO , 8369c-CS 0?D f l l _, 21.a,2.1-r5 l eLOSD l l l l a 100 ",-75 ' FLCSD l r.$ l O?Of
.t182u, Sl CLOSD l l / 3330.\.,5 CLCSC l S t t-C 116-43 '?:7. _1 1
,m . . _ . . - . _ . . _ . _ . . _ . . . _ _ . _ . _
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l I ATTA'ft:r*:T I-
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P.aC E D or 63
! Ph. JL :CN ') 415 i 722 fm' -.
U- ' 3991A i ,
DPJGUG # DIS-12-002-1 .
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l y? 'd"X , , b<U j g - 8884-SI TC-34-5 g /jn-co7
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TC7-122-5; fp , 3998A 5994A-5! p U383-5 0 33 ~*'
'C' 9953
'A-{/l i9983 X
39945-5~ p f.T -:.7-SI
/(~C13-5.
= ,
i
-.}svrco Q - 1 8995C b l
/HZ X 5994C ;- a 3998C
- !CTI: This system is water filled and oper ting during an a :1 dent. ,
l ?CC3 l ../'x :
~
s_- l ?C3- 3 lUI~/01 2 , l 8834-5I l CLCSD l hfh l l3485-5I l CLCSD l[jh l ; 9885-5! l CLCSD l lIf TC-17-SI CLOSD
/ f
- l l l i 5991A-5: lL0u.w CPE! l TC-13-S! l CPEI l 39913-5 LCcIDCPE!l 3108-5I l CLOSD l f f l 1
'991r-51 LOCKD CPU l l f 399aA-SI lLCCKD CPC: l l l 099L5-51 lLCCKDCPC:l l l l 1 I
O C N. r-S I !D.Y':-) T "' l
- l l I
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l su ,-si I c.Csa l l l l i i ) 5130A-31 PLC50 l l l f l 5:*t r 146-44 ?.; / . ,1
1 ATToc!ltiE::TI Peu _a. ,
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PErC2A;::0N 4 221 b y 32 W CIG # D-102-771 l lv 9363C-SS l X X 9364C-SS
# X 9365C-SS X
936dC-S3
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Q9307C-SS W !
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A 39308C-S3 b
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- 9364c-53 -l CLOSC lfhl Qf l l J
- 9365C-55 l CLCSD- l Il l l 9363C-SS- l CLOSE l l l l
9366C-55 CLOSD l l l 9307c-SS l OPE: l l l 9308r-55 l CPri l j l I I I l : i I l I i ! t l I I I O . nc 146-45 n- j , , , y rn+, n- ..m. -
P.A.CE ,,1 0 F 3 y,_ Pnc ..<.AT CN $ 226 Dwz;c 4 .1';5-L'-nn2 I. , 4 1 U.TC7-4023-?5 I 37083-73 \*d W~ ^ Du - s m.? J1 N,C IN I 40 se il vv B 7003-PR -
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' ' TC69
" I 57 -
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.(3354Ef LK.m ce*B) ,[
38093-?2 - jd I ; l : I e i i O ;iCTE: *'t.is system in-se: rice during SAT /!*.2T (? sc-Op), F
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!'203~~---a -l T ! A~2 l ,
, l ?cs!"" 03 l :r /m l .}.[ Q %f
- 37013-RE l C'CS D l l S7023-RH l COSD l l l l TC-19-RE l CLCSD l { l ,
TC7-402R22l CCSD l l l S S 12 3 -?.F. ' l CI.CSD l l l = 37293-RH C~OSED l l l 1 won rit f c!.c.5 n l l l, I c 7 :". n-P.R l Cr'sen l l l l
. :. 3 l '"r .~ "< -n l l l wwe v l l I
- 1. ...., . . . . .
l e.. . g- i, ". i i ; i i l I O StM-c 1 14 .'. 6 U 1_ i i I
- - 4-~ . , , _ , - - , . - , . -w._ ,, .me__,____,, v.-.,-r,, .v..,e ,,_..-,,-,.I
_ _ _ . __ __ . . _ _ _ _ _ _ _ . . _ _ . _ . . . . . . _ ._ m es,.c.t e r FACE 16.OF 6 d PDs .tA- .CN 4 2 0 7 y L?E -'*C 1 L:!S-12-M2-1 I
'7 % A 88873-5I EIC2-5I i rl, I 397 3-5I b y t.=-
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l l M, 3973C-5 -~ 397aa-52 l# i [ 38883-5I
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021-52 g' b
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d i l IC7-60 3-51
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/ X- 3385-52 T 3801.1-5!
38013-SI . / I i .._/ M0'"7. . ~his pene :ation is water filled and operating during art accide.n:.
~
- c. ?CCI E /21~2 , l 705%"~_0'.I l a. /kCI l
- 38833-5: l CL'CSD lNf jfd} N f IC-21-SI l CLOSC l djh f39743-SI l N/A l lI f l l TC-23-5I f CPCf f f' l 33013-5! l CLCSD l f l 3801A-5I l CLOSD f l l l l
3335-5: l CLO5D l l l 89 22-51 l C'.,CS D l l TC-22-5! CLOSTD l f f RC**E-Fi P'.05 n f l FC'lAn5P.-5!l . .CSD l l l ! ! ! jiirt-0;u-3: i C'.;;: ' i l l l
.--'/-6 c : 7. -:: l -'05:3 l l l l (v
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,._._.....w:.
P '.0 " 17 - i' 662 PCTC7.AT*CN 4 II9 . O~ .
. _ , , u s c. -c = t I
w - {3102C-C3 I 810 3-C3 O c-0. x _. 835C3-C3 5 83 43
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l 33633-C3 ! 310:3-C5 33693-C3 338:3-C3 X I 1 T0-68-CS 7
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- 31023-Cs l C;.OsD l jfj l l p'
336a8-0s l x/4 l I l l 2330s-es I cosa i f l l ;
- C-n -03 l e.:sc l l l l !
non-es I ctesa l l l ! 6:c-Cs I tosa I I I ! w:. es Ict0m i l l l l m.,s L,. e i ! i i ! ! i
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l I 1 1
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,\ T,' c ha '- - t F.iC C18,* th' 63 PEir"?x"*0N 3 2'I \/
cysctc a D-302-7L3 I W W W X ' l lnf Ud,' 375a-on area-cN a767-c:r 877 f 3766-cN 3764-CN b l 'd b i
!O*E: 'Jacer supply 4111 need :o be isolated (via 3761) . *his a111 s op all de=in satar nuclear se:tices.
l ? h - 03 l I/".Z"I l l h, l705-~".*.*3 l r "/"ATI l e76a-o:: I case Rfi q d l l 37 67-w j j- ; j l cose , l l 3753-w l cosa l l l l 3771-ON l Ct.Os0 ! l l l l h l I l 376c -a I cra l I I I l I I I I I I i I I I i, i o v l l ! j S:(-C 1!.6-a 9 '"* ..'.
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STTAC10!f". :T I l
- ' i
' P.'.C E *fo yL l PI:fE"2ADCN :) 101 g/ ;
( ;RAWCIG ,) D-102-86L' l l [ 6053A-E .! G E /\fT X . D.E Z 60 ! l 60511-E -
. f b
; s. .<! -
- [ 6052.L-E 605:A-ER
^
7J Xl X X-Z' 605 9A-c~.'4. i
~ ~ E 6050A-3 -
6061A-EF. 6060A-E l O . -o?=-6 = 4 l 6054 -3 1 301A 3013 ! t f , l ?CSI~~3 l w..! AU l , l ?C3~.'"_"03 l a /CCi' l {
- 050A M
- 6051A-ER l C' 0SD l[lh
- l CLCSD l gih l .
- 6051C-E jII 6052A-ER j. CLOSD j l CLCSD l l l& 6
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.REACTORLEUILDING'. PRESSURIZATION /DEPRESSURIZATION DATA I . h.
Date ! . TIME PRECISION HEISE AVERAGE I TIME ' PRECISION HEISE AVERAGE I- ! GAGE GAGE PRESSURE N GAGE GAGE PRESSURE N 1 -2 T 1 2 T N 0600- ; 0015 0615 .i 0030 0630 j 0045 0645 O100 0700 l 0115- 0715 : 0130 , 0730 -l 0145 0745 ~t
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-1315 1915 :
1330 1930 1345 1945 i 11400 2000 ! 1415 2015 f 1430 2030 e 1445 l 2045 1500 I. 2l00
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i nell FR3C1510N E315E A V 5ftAG3 I IIME FRECISION d31S3. AVERAGE i } GA.GE GAGE PRESSURE N GAGE GAGE PRESSURE N i 1 l 2 . T 1 2 7' M g.r::x % A W J2 s ., /' ~ l600 N. N
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t' Date /-/9-8f TIM 3 in3GI51GN E315I AVERAGE i TiMZ PR3GI510N HEI53 AVEAAGt i GAGE GAGE PRESSURE N GAGE GAGE PRESSURE N , 1 l 2 T 1 l 2 T M v i.cni3c.7 2 /,c z o fra 0 BOO cx.2 2 f + rp 4 0.o r {} c; 0015 t h :. w irl.r 9 t /7 0rf f f.->i0615 S7. 32. M 7S 9 t. / o fred 00 30 I? > 23 t i;'. 94 i sy, Af i e.- c 0030 iSA.p?irt 7i i 42 . i o I (f fc::: i G0 4o i'? 4./e t? / 70 it s 7 n i #9 c.:' Go45 i t'v9 '/ i cvA+ 14 2, l'.o i rvrp G1GG Fy r /3 I? G r i/ '. G to l *t?ral0700_ fo C/ fin 9/ l9 4. 2.9_ti &%./ .: , 0115 isr_.,r isc;ii,n.c.cr i 'iWr10715 tr r,9;CW r7(i pg , -s ,/P K~;f: G 1 $G iy 7 /0 i .: s ./ y iii.iO i lorsiG130 16L9tX l /:./gf . th. J l l m?
- O \ 45 i?N O t57 /1 l2 ?. ro i /Oc2l07L5 it 1 m i. ,e .04s'1 h~r.1I . r5Gr.- i 0 200 i .! <r. 09 n A e,4 113, to i POepi0600 h,w w r_, i u ,g, p i ag-g- 1-; g ;
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(_/ REACTOR BUILDING PRESSURIZATION /DEPRESSURIZATION DATA Date f- t o. 81 TiMt FREGISION HEISE AVERAGE I TIME FRECISION SEISE AVERAGE L GAGE GAGE PRESSURE N GAGE GAGE PRESSURE N 1 2 T 1' 2 T-TM u,ses o w n. 49 sw vs 1c00 M /FF 4A024 2 R 6 .T ~ emd ' 1215 /,t.. A7o 144,457 I 44*% I i"Q-C- 'Idi5 42 M 4(.9 22 l '27, B C -60*4 - 1230 fas 53 !aaa n i enA l ' ses:._ ie30 14( S3o ido.4W3 26. to FM ' 1249 I/ a , m v lt,4.n w i aa. ,8 I se i I d45 640.2451M2M i 24.95' i ,We4 13U0 leg m u4t oi u_rr c i is,=r l 1900 136.'N ol30.olo t 23.60 I WF '
- s 1317 l u, m (A % f i 4 7.:r i I w l1915 I ? 7.7 col u.WCt1 42.40 t /ep i Yb0 l G.C. *Lv.l(A- >Bi l 49.95 \ &GI 1930 2 4 r /al t e. 4cl Z /. ] S' i tf c")
1345 M 4451(,3f.,20i 48.V i IWm961945 3 S.Ifd V4 9/31 ? A o r l </#eg , 1400 l(.+,724 !(f Z M&i 4 7.75 i Ir'nPI 2000 i 7 4.C4of J ?. IoTl /A #0 i - [cg , T413 1/J.3.0%i (+/. :;e/ I 44.60 t he,'W'I2015 131. /wi e /.</g;1 / 7. go l Opp 1430 I r /.Myy.o. Icel 4555i I W M 2030 13/ 52 $14o.7 9 1' /e.g o 6 ' rep. 1445 I g o f/M 4% FA.Sl .24.12 I l'r#**'- 20 4 5 17 n,2 542 9,J/2J rc. /S I (PWo 1 wo 150.2 o 715'7 /X91 4 2.,9 o 6 (o79 2100 #7 9,c4 2 M ,J7c i/4.c c i fjf fj. I 515 WP.o19WC, .m at .'70 t tvrP*2115 127 92262 7. i41 I / :, a o I mprp , 15 50 >% 792 f 55 2?oe 4c. 50 I v=M 2150 lL6, Un i2 A.c ce I/t, A 7 s v$9 c p IbaD t Ec Sa llf-h 025; 39. SS I iX+r':A i 14 5 87s,908 IT_ t i27 l p t . 90 l / pci 1600 \ 54. ? 5,l 52.T'11I ?6. (6 l 17trH4 2200 ILS a w 6d g.L y \/, a o l vncy 1615 152 029 I f/. 6441 3 7. Of i tWP'*4 2215 I t( a v in .*. 3 4 i e ao I ./#c .;;:.
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' GAGE . GAGE PRESSURE N ' GAGE GAGE- . PRESSURE N.
t '. 2 T l' 2 T' T2DG~ ij;.y# v1.4a Me e'L LX 1doo (4 .228 &4.319 .' 49 9 y h % /1 . 1215 r. r., 2 71 6//. a6 so, s ( 4/t 1815 fog. 7,2.+ 64.3/s' 49.77- 214/7 t ' 12$0 : ! t, u) er 'avu 'ae,ec \ kW 16$0 &&.270 64'3 // M9.10 tb5/ 1245 c . i(4 e.r/. s# 49.9 1 iDR I6Ao c r. 2 ir 69.cov 9 9. ro ./M/> t 1puu r.G sA i a ,in f .:sc s s (M.1 61900 c6.'bl2% 430+ M.W !
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..v) REACTOR SUILDING PRESSURIZAT!0N/DEPEESSURIZATION DATA . Dai:e / 2[6"/ - , T itlE PREGISI0ti HEISE AVERAGE I TIME PRECISION HEISE AVERAGE I. GAGE GAGE PRESSURE N GAGE GAGE PRESSURI N. ' 1 2 T 1 2 T'
\200 ft,o n 14.is7 try'. 47 'M I500 K6. 0!W t% //t U't'. s n r s id--
1215 ;%.es'6 tsf./W 4 Y. y7 % Wyn 1815 6/> 0!'S' 6% M 49. 70 _ My l e:0 i+4.ory WF irt us. q1 rJh IC30 (6.0/T b'tu/ 2-~ YY. VO *:.sff' 1243 l(t.s> V+. ira 4 9. + 7 wb. Icab 66.ca 6 'i. it u 9. To -t er tL : 1 )UU (46.09/ ibe./st-f 4'X v. 7 24.w I900 G6. c// 6-E /v/ .: # 3D A f' 131*) v.x,. coon ist are o cu,9 7 i/1411s 1915 t, s . oc~l n., n m ~rt u .co (W l$$U % oa7R w in s i a e. 4 n l%)]I1930 .r _ec 9 m. I6? <19 m g i 345 lu,.Mo w e42! 40. 4-7 Id>hti945 r. r, 0061 u /s a ct . <ro e ri 1400 92.. c.m>lut. /</19 I 44.#7 l / Tat / I 2000 1/.6 cm- le . . in-=. .m.co tab I 415 16 6.4 a Tr.</. [] pri c/.9. fa l ILW 2015 li. r, . oc 4-l e. r . I o t- t9.ro (d<4r 1430 (4.ce, 7 l64./Js2 i /.W. r0 i kz9t'1 20 30 1,. 6. . 1 1 w ,,o ,
. 99 4 A%,0 1445 f6.0 fiI6V /J6 i W ( 0 i !91h*, 2045 l( 6. o a a !(A e 99 49 + 4 t't' E 0 0 t/4.0 7 yl W /f f"l V 9. S o i IZpm 2I00 IGr. ter r i G4.c '7 6 40 , do W 1515 s is.ow f64.i 31 I:n co I i wsm 2115 I:, r.a m ic+.e e rl e +s i Vt w I 5 30 i es. c >+.lg p,/ pr-iv f. .ro I tur-+ 2130 16_S. o n rito + cui o w 4 e T 19,. .9 15 4 5 16 e .0/ 2 M u. /e; e v/. r o i t-W W l45 j u .. sis.. n e t l e y . f S I 4p v 1600 16 e. cr3t r l b *. /2i 1 4 9. 5 0 > tt w 2200 Is c. eat le s y / I s o ,4 2 l 19cas 1615 lbb. 0 2 7 lp+./2 7 t v* f f/ i c'fMt 22 l 5 l 'i r, W / 1/ C _ 0'?o i e 9 3 */ 7 l "l / r/
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T utt FREGISION HII5E AV5 RAGE I IIME FRIGISION E315E AVERAGE I. ; GAGE GAGE. PRESSURE N GAGE GAGE PRESSURE N ; 1 2' T 1- l 2 T T2UU~ l600 1215 i I 1815 l 1230 I t i !1d30 l l l l 1247 i i e i i154?. 1 I I l ! I;v0 i i i { l1900 l t l ; I31> 1 l- 6- .i i1915 1 I l i l G0 l 1 1 I i1930 I i i
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ATTACEMENT II PAGE 1 of 3 !,,) v REACTOR BUILDING PRESSURIZATION /DEPRESSURIZATION DATA Date /-/4 - A/ IiMZ FRECi5LON HEISE AVERAGE 1. IiMZ FR1GibiON d5155 AVERAGri I GAGE GAGE PRESSURE N GAGE GAGE PRESSURE N 1 l 2 T 1 2 T W f G000 /R.I.W /1. H7c 36's 9 CA GD15 0015 /<7. 3/A I/R.<%Q 9 . R r- l 6f(/c~ ~) 0030 i 0030 ?6 4 c/l19 9tHI S. 3 7 l **Tf'r2 0047 i 0o45 17. /.n el2 /, o / ol <; . 4. R I Mfry , O t 00 I i 1 0700 122.r77 la 4.ovo ! 7. 3 f- I 'rW9A 0115i i l l t0715 1214 9 o P Z < * ( l M .s 'o I i e.74 J UI j0 t I i l l0/j0 i M 75 ')I > .t. / 4 / l 4. (., f I 4/JA.E ai47 i i t i i0745 12r 4 sf 1.tr.L3 71 / o. o 7 t flyJ 0200 l l \ l l i0600 U? <o. 911I 2.6. 2 n l ll. '70 i Jm/J ; 0217 i i i i i i0615 ire errin sre i <1.so I if(4 0250 i l i i l 10630 12 6070 IItWer I/7 9 o i 1%72n 0247 s s I t t lOca5 l3a.ir e12 7.v4 y t/ 4.9 u l t i.riq>,, 0 j(.O e t i i i 609GO 17/. A F7 17A $W v3 ; + o i L f% 05i5 i i i i i i0915 32; 317 i 3 .s r/ I/r.:7 / I ium 0550 l ; I i i t0950 l 73.uo ru'2. cau s t r.a u t trmw 0;4-) I i i l i I0945 17p Wa'if). 6 J/ l / / s (l'- 1 IT/W 0400 i i i i i i 10C0 i3.r. 3r313e+991 /9. 9 p i i jg),d 0415 i
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PAGE 2 'of 3 : ,; i
, REACTOR L BUILDING PRESSURIZATION /DEPRESSURIZATION DATA Date l~~ S W . -,
h J s I Tih FR5G iS LON H3ISE AVERAGE I' TIME FR5CIS10ii HEISE. AVERAGE I.. GAGE" PRESSURE N GAGE PRESSURE N f 1 GAlGE 2 T 1 GAlGE 2 T- : T2UU~# 2,W7i4% 7/O 27.20 7p*'1600 eu,3s h W l 1215 yy.9Jr 92,6/r 2 f. 2 0 W -r1815 6s co7 63 7/N 41, z,r"' -{ 1230 y % 5&P y7. 7ao M7. l u '44%i 1630 65.5% 3 63.o/8 4 '/, 2 6 ;; 1247 %. o/9 44 g,,5130 3 0 #1// 1645 & v er t r. a c+1 #1,1o I i i
' I jVO l 47. /0 4 14 , RG#l gr.Sf- I l g]6 1900 cf. set ira.c.2/ l Sf /e i l h.r ,
1315 14f/R7 i m 9/7 I c .40 i f4h+"I1915 t.,q- to.d &, 3 cci 4-e r, i
- I kp I))O 149.1-F% 47960s 13 4.f'I l #fhl 1930 J cse,el 6 3,5:=> s-9 . o 7 l - 'W '
1345 iso.'M.L wLer 91 37- So i ipo/a 1945 cr.44/t63.rsi 4e.o A i fj<url = ! l 400 'St. s+3 I So o Gol 3r. Go I th6kH 2000 GSA 2 7163. C491 49.07i 'M 1415 D.rxof r/. /offI %. 6, $r i 6W 44.2015 t, r, e s t.] G g pil 4-9 . O o i N,p i 1430 153, we I 52./56 M/Jo i I N I2030 #A S, eevia a i w .co ! e + 1445 15443163 17.01 36.h5 Ibyi2045 16s o:rvs wr i u.e e 4 i Hs l I 500 ist, W8i eg. is,i 39,10 IhwI2100 E rme tau % i ao . o n, t- 5-fune !* 1515 IG.9041 ff. sci 40,0'1 Lhut 2115 tc.r.w.ici r 3.uce t as us e i rc-e_. ' 15 30 trr717)I G,/551 u/, /oD I lhGv!2130 Ir c r.se; louro i 4 oo l I :;; p:. ; I 5 4 3 i'rf.930 5 ?, /w v2.. ?u 1
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PAGE 1 of 3 l ,\ - / REACTOR' BUILDING PRESSURIZATION /DEPRESSURIZATION DATA Date / S~ J.?/
// i TIME .FREGISION HEISE AVERAGE i. TIME FREGIS10N HELSE A il,nAGE i GAGE. GAGE PRESSURE N GAGE GAGE PRESSURE N !
I '2 T 1 2 ' T' I Af 977 6 5 4se<r ag,94 :gr 0600 (,S. p9 e- r.1,3:3 4 e 92 y~ i
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.0115 vr.24 L % 9. n 8 46 FA 'I ITm=i07\5 I W 'lL t d ;'. 3'" 4 Y. 8D i 1&l/X.--- }
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'ATTACEMENT II PAGE 2 of 3
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REACTOR SUILDING PRESSURIZATION /DEPRESSURIZATION DATA , 8'/ ' ' Date df' /' b T iH:. FREGISION dEISE AVERAGE i TIME FRECISION dEISE AVERAGE L GAGE GAGE PRESSURE N GAGE PRESSURE N' 1 2 T 1 GAlGE 2 T TM (a.m <t /,3.1y0 4 5. 76 fPrh 1600 cc. ires 63. 2 si rl + e.s v Ani ?
\213 _ /,it'f 7 14 3. 2 7 9 ! 4 W. 7g W7/-T 1615 6C //9 63.2r/ \ 48 74 7dM)t/
1 i $G ti 5.196 !4 3.2 7 7 l uV. 7? l 1Jb-I1d$0 65. !!9 63.Lso I 'K2 7 A! ! A6 AP 1247 14's./9 r 14 J 2 7/, i Y r. 7r I W--i 1047 (f' // 7 16 7.2uf I 4W W l 2JW*r 1 )UV I/eSa sW ird.175l <M.7<;' pf4ni1900 lc, r ,,6r k,= w3 I ap ,74 ! W-1512 l&S.tw;1e3 31M~ UR.75 t/hK 1915 la Gudisa wfl a v 4- 1 2b=7= - 1 j jU IGr./ei 43 27 rst 1 R 7 r i l M/v i930 f. c' ,, a < L 2. mye aA 14 I w l ie s l/.,r. <3erl <,3. 2.7er l 4ta. > r i l#;// 1945 6.criv in w A asn a, 1 Je=g , 1400 t,r.otr !cs. 2uri m vr i l#/Mt 2000 Ig.5 un,. lam i ugno. I Qgen 141o (4 /3fz l4,5 ael 48.15- I W44 2015 1,, ,,1., I r,t a r i a R 72, I 3 g_ 14 30 16r /sgr1ra.,ar 71 4 f. 7 T I It&9BI 2030 r.,s. n t. I am I a ga a, I egg 1 4 45 I( M ./3 9 % 3.OGl.t J46 75~ l I/NMJ 2045 u ff, I ra . >.a l umI igpm. 1 D Gu I ta..r 151.h t.,3 2:, 51 e g . 9 .C l l .8% Jf l 2100 /,S ji/ l U. 2a:41 Dt.1% ! l}fsy) 1515 l <.,r. / 3 / is f. 2.4 31 4877 I IAffhl2115 v.f M W u,_l au q3 1 1- m~ I530 1 6f.f30 141.24rff 4 5'. 7 f' l I Ath12130 Irg, y,c r- : s .p <- I apy 2, I l p-g 154J 165. / L.91c3. 2Wfi 4.R 7f I I#AMi21d5 II ,S, /g 751 6 7. a n.io I u p, y i i Ig/m I c00 !G S./J6 '63.X>C I 48.7'5'I i//4dci 2200 izf. f o v 14 3.;t vi e. 7 , I lt//rs 1 c 15 tr. <,/J716 Sa5yT u W . 7<' ~ l i //'wd 2215 '4g /eu f u,23xl ,j,7;2 I i /r%t? D I6.s;/2 4' ! C 3.w7 6 4 <<. -r a i If./>-- 22$0 'Ar, /ny %.1. nt a 1 t/r. 90 e s t/trt ["\ J49 t, f /2 &< ' 6 3 2451 4-9. 7 0- 1 I /".JB t 2 2 4 5 145, ,mge,avoi ut,no I gpv/t L' 1 7 00 f f. T.12.4 t 6 s. s :7,. t + 8. 7 a f f J:36 2 500 / 6, rp,?9 ft.2, Sql y V, 20 t gryt i < I o i r#.n. 5 4 c. 3. 2 str i n ? < i th il_2317 k.rm z q,2 wei a a 3._. i h 17 30 Igr./ t/ t4 J.25'YI th 74 I IC7& 2330 egg, is pS l u, wg l yy, ot> ! pm 1743 It.,,r l10 lGJ.LS%) 66?. *? u i If.0/11 2 345 'gg. pc ip 't,3,,a33 r l ,r t. ga cy l l gym 1, RIMARKS: o O - OUM-v, i / 1d6-96 RZ7, 1
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., ..f ATTACEMENT IT PAGE I 0F 3- 1 a
?( - , ,- . PRESSURIZATION /DEPRESSURIZATION DATA ,
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> i DATE: 1 15' Bi __ I ,
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( J: C1?TACEMENT II i oPAGE 1 of I . O' aziotoa auttorno earssaatzieron/orrarssuarzieron citi Date L /c, /g 1
-l / ,
TIME .FREGISiON HE LS E . AVERAGE i TIME PREGISION E3153 AVERAGE I GAGE _ GAGE PRESSURE N GAGE GAGE PRESSURE F 1 2 T 1 2* :T' W ,KJm ! C ' M. L 5 2.9 W8.tA ~T;De 0000 /Sr0?!S (341t & 4 t. b f" [n~ g 00\5 kr.ino 6 5. n ts I no. td TEFl0015 \Mr WO M Q100 M Y,4 5 m
- 0030 kr. oggoks. t.u q I aug i m I0030 t/5.075 143. xy +6 b! //gt fe ~
00A? I6s. em fa..n r<< l a k'. scs l th t0o45 M 0710 n.'wi 4V.GS & , 0100 heets2.ls m i u.9 , tA i w>l0700 c.r. o pu c 3. us,3 4.g c,3 _ _ L444 0115 QS,d9y tanon l ur.ta l lprm-l0715 (Co74163.2ef/1 yr 6/ kr.W G \ $0 ks.nCr?ni/3. *L%< I A./ V, I, Q \ lWm O'l $0 45.o70 lit 12o~fG' 9 % 4 / l ws. . O \ 45 65.c%/ Vr.12t? 41 1, n i I//m 07A5 c.r c.u r c3.2 o a 4.y. u ftq q . 0200 gg,og a ! a , n.r)q w/, si) \ I.gs7 0800 I gsocn is,, c o ag. y My/J 021) 45.p949 tA3 2m a f/. /,6 I irM i0615 ( r. 44 tr. :r ea l v v e; / -/A' 0 2.30 thS ofa5 M3.n7/ I AV.bt. I t/RA I0830 frop.d . 4 7./99 i ter!4/ r 247 0242 14S.0939 06!. n t.rl a r, b /, l Fffin I 0645 65.062 is 3. i94 I ue u l l 7j~ 0$00 b6.0W7 M,Mu9i W Job W P'~#:C. I U100 /'f'N/ i63. /fJ' I #- 8'.6 / l l #4).orr 0 3 I 5f' r09:7 63.2% i ##w i W C:5"F l 0915 I/ f OSV 16I /W I47, 6 / I l LIE O330 f65.o'j/Sf43 M ani 44 & S I I 7+s l0930 6 dCo5'YIf 3.lTd. t4 f *. K f 40 l l .gyW i 03L7 bc Mr4 W uni % t- I rgr-. 0945 i4 C ordit 3,/9 o le,e.V. ( o I i ur/< J 0 ACO gr.eqa, L:t . m I 4 At I rJ t:.61 COO !4 5 os r 16 7./rerI g y g o t igg l 0415 les m rL,n uuine w I lgpl1015 1/r:or416 3. / rt1 </ y. 6 o l l;es e ,
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m3 7,.. . ATTACEMENT II
> PAGE 1 of J h REACTOR SUILDING PRESSURIZATION /DEPRESSURIIATION DATA Date N TIM 3 fliEG i310N ELI5E AVERAGE i TIME PRisGI510N 53153 A(ERAGE L
. GAGE- GAGE PRESSURE- N GAGE GAGE' PRESSURE K.
1- 2 T 1 2 T' UUU6" 0000 0019 0e15 i 0030 i i Co30 i i i i 0047 l l 1 60045 I i i 1 % 0100i ! I i !O700 6 i 0115I i l i 10715 I i i 0120 t l I i 607j0 i i !
.0145 6 I I l0745 I i I l
'0200 I i i IG500 I i i i I U215 i i I i0415 I i i i !
0230 i i i i i 10830 t l l t 1 0245 i t i i i 10645 I i i i 6 5jGu i I- i i i i0900 t I i i i 0315 i i i i i 10915 l l t i i 0330 I i i l 10930 i i i i 1 0j47 i I i i 10945 i i l i : 0400 i i i 1 -t i1000 i l i i 4 0415I
~
i i i i i1015 i i _i i , I 0i I i i I i1030 d X/i,4, # A z Z 47~/o p-Q .45 I I I i i f1045 c)4%<t* 'v~Y M A.<, a r.fso pis b/ 0500 l I i i 1 I i100 16Y.3ir2142.5nt e 7, 9 i iq m 051o 1 I I I I l 1115 4.i. / /d l6 /. 779 l ue,7 i i %g 0530 i e i i i tt30 6(.'i rl l u. 13 e t + S; 6 i m 0545 i i t i i i 1145 i M,/ro lft.w 2. j e % -J i 3% REMARKS: . t Q SUM-c 146-9 RE7 1
.1 ATT'ACEMENT II l
PAGE 2 of 3 .: REACTOR 3UIEDING PRESSURIZATION /DEPRESSURIZATION DATA Date N- - f T ih .? REC IS ION E3153 AVEftA03 i TIME FR3 CISION, d31S3 AVERAGE I. j
. GAGE PRESSURE N GAGE PRESSURE N .
. GAlGE 1= 2 ' T 1 GAlGE -2 . r i M (V. Si>i Lf7. Wra 93.2. Y%'l-t1BGO EOMr~l~)- Ys 6 20 /C O ~2er#77,l
'1215 5T. 2 57 1566J2 92.o l Fl.S% 1 1 e15 l29. o7112 fr//>ol / 7. 7 l'///r>7 :
1230 5 7. cra y t f r;ve .y q. O. g- l Mahl idj0 p.e6 7 6 2'7.7071 / ? r., I l 1;'yJwt ii 12 45 Lf6 02 r $v. 23/ I J'/. 9 I Ip7hli645 :f. . Ji ih W2,1 1#. 4 I IW A- . ! I jGG iSs. sro f*L // r (*3 Y. 4 1 I W"/tH \900 :CVo% mu4FhI le .4 I lW? ' i U I 5 15'J. s'// 1r2. # 73 17 7. J ~ l iof#hl 1915- 20G9L74 M I 9,+ 1 r$s9 l
~
13 3V 15 J. 2 74 p o /4r 74. v. I t=2 ar>rt 1930 8 18-o f 23.6 M 'A n i IM:T'~ - l 1345 S'/. 0 % 4 IW4/o63C/ I P7//rr 1945 ri en IJl.u r e G.M i K 7z. i lAGO #'I.r7tlef 5)"Al3 J.9 i t-M M 2000 19 yir1segaA f. t L., I ; rgir l 1 L 15 lu y.4 5'3 l4 7.13 2l 12. 7 l \"h%--4 2015 l ro , c- lo es (7 a l 4.u 7 l q -P. l
.14 30 iYZ N > l/f t. /'i' rt f/. I l- IL7 I 2030 1/6. 21 1, r 4 I 3.1C I RET'- i I 445 14(. 2/ t la u.95 y I .7o.4 i pt t2045 If 4.es I s SR i / . # 2. I h e r- '{
1 n.,v 144 ceart </ 3 ra ri / 9. 2 l i':E .t 2iQO t U_,..o 17. I c u fl i i .I t i FA 'A 1515 N 7. 72 / lY2.rf Jl 17. V l I7t///-t 2 1 1 5 Ii r. A lis ep l p . st l f l ~5 y;.-
.i 15 30 t a2.Y(.ri 4! it'1i 14 r- t t '2.I]"2130 i eh s c trz=A5 L. /. 2 o s-l uo./ w t 17. ? i iza% 21a5 s t I q fo e./ct s I e00 t 75. tf A 177.92 9 i 2 v. 7 I i u24= 2200 l I i 'I l !
. l e l 5 6 7a, w o #7/. v1* i 2 7. 2 I (St-I2215 i i i i i i
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I REMARKS: I i t t r f 1 f i O sa-c 116-96 RI7. t- ! f I
. - , . ~ . . . ... . . . . - .- - - . , . -
ATTACHMENT II .. j PAGE J OF 3 -{ PRESSURIZATION /DEPRESSURIZATION DATA l
.] c 1
DAT3' i 16 Al ;
- .o . ;t i 2. - iw i.
l SC4-0 1t6-97 ?.I7 . 1 i j 1
- l l'
ATTACHMENT III PAGE 1 of 1 ('; TEMPERATURE DATA ' v DATE
</ evi
-lO be., LA SM -(o/ Cow.&/ eTitE[EMP~h1 {r 1M -
itT D No . 8 l- INT.
/ 'F / "F / 'l /'F ,
7307A / / / / 7307B / / / / 7307C / / / / 7307D / / / / 7307E / / / / 7307F / / / / r 73070 / / / / r 7307? / / / / 7307I / / / / l l 7'07J 1 / l / / / Il v ~7 307K l I / / / / 7307L / / l / / l 7307M / / / /
'?O~U / / / /
~3070 / / / /
~307? / / / / j
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j ;
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~307U l / / l / / .
t 7?C"7 / / / /
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l __ = 1 ~ *d I e r=- : 126-93 EI7. _1
I l l ATTACHMENT IV Page 1 of 1 i ts/ i MOISTURE DATA DATE cY O L LA st' Q M tOLrk b1 A ne- 0% u ' TIME /% HELA 2IVE HUMIDITY \ INT. ME. NO. / / / / i 7306A / / / / - 73063 / / / / > 7306c / / /- / - 7306D / / / / 7306E / / / / e N p i /m , t") 5 '."-I-C 146-99 ?.I'l . I
.i ATTACHMENT V l PAGE 1'0F 1 l ATMOSPHERIC CONDITIONS g~s,
\-) pgyg T1014 WINDdFEED AVG RELATIVE BAROMEIRIC INITIAL DIRECTION ~~ AIR TEMP "F HUMIDITY PRESSURE 0000
/
0100
/
0200
/
0300
/
0400
/
0500
/
Vo00
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07G0 ,
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0900
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1000
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1500
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1500 ' i 1 l / l t900
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)
3 i
.. . . . . . . .. .... .___. . . a
.i
. l ATTACHMENT V PAGE 1 0F 1 I
' ATMOSPEERIC CONDITIONS
.s I
DATE \N J:ih sifwdtstu A 'iG nr tan y t 5AdOM41AiG illil'i Ah DIRECTION AIR TEMP *? HUMIDITY PRESSURE , 0000 0100 0200-0300 3 , 0400 .
/ \ / :
0700.
-/ \ / ;
Oc00 N / i '
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l ae , 't i l' j f., / #-f k l l 4 ') 91 XIS sa_c /-f 7/ 9'/fMM CM i, 11.6-100 EI7. 1 r
ATTACHMENT V PAGE 1 0F 1 ATMOSPEERIC CONDITIONS i c)' r. DATE'JAN 10 font E Rit diNU6rstD A 'iG RELAfivs dAROMalh1G IN I T I Ai, DIRECTION AIR TEMP *F HUMIDITY PRESSURE 0000 iy$ v 'f g es, / , I t %% J+rA 0100 ggr vn / } % 9. 9 T hk U200 ;o e
,n / < 2.9.71 M.m.
0300 20 tL
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.n ATTACEMINT 7 PAGE 1 0F 1 f, ATMOSPEERIC CONDITIONS q") .t s.
i DATE JAN 1 1 1981 - g ;,% n13p 4seu AVG rimi,AT L E b An0ML fItiG INifiAL DIRECTMN AIR TEMP *? HUMIDITE PRESSURE OCCO 5 o '* \t y997 p, $in 0100 2*
, al $, M.9 7 lMn 0300 R*q*o j 2o V
) '
> 1 91 h/M 3a l C 29.9% Ab 0400 0
;&Og j k 2191 /YYA U?* TO 4 '
- 2. 3 o / 4 29.93 7'/8/r t UD 9# 4 1?o l U 27.9i r7?IM i l A9 9Y ??$4 I i;;, i l l r .cm /o CSOO /#
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' ATT ACEMENT 7 ")
. PAGER 1 0F '1 i ATMOSPEERIC CONDITIONS j DATE JAN 121981 ;
RALAT1VL INITIAL ) 1AML- .rsiduettnD. A V tr - HUMIDITY- _BARUMsTR1C
) DIRECTI0tP) AIR TEMP *? PRESSURE - zi
*f, P /$ 29.96 Jew 0100 cP A w'
l a/s /pdco AS. 55 ! o'/Yf $1f 8(u i% v . xn w- .
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ATTACHMENT 7 ! PAGE 1 OP 1
'ATMOSPEERIC CONDITION 3
- DATI JAN 1 3 1981:
X1M w UiDeif t 6D AVG R6LATiV6 3AnVMIniG INITIAL ' DIRECTION AIR TEMP.*? . EUMIDITT PRESSURE ~ -
"UU
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ATTACHMENT-7 ..e
. '. PAGE' 1 0F 1
. ATMOSPHERIC' CONDITIONS
- (' -
.DATE JJAN 14:1981 ,
Erlas nuuMnD . A 'i G RtLATiV5- 3 ARUMSIRJ.G J Hi AL ' S'
- D,IRECTION ~ AIR TEMP 'F HUMIDITY PRESSURE
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146-1CC RE7. ), s,-.u -
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, ' ATTACHMENT-V PAGE 1 OP .1 ,
ATMOSPEERIC CONDITIONS-3315 M 9ggg , I1M4 #1NVdf$sD AVG- RELAliV4 3 AdV MmT hic. iR1TIAL J, DIRECTION = AIR TEMP'*? ' HUMIDITY PRESSURE < -- T 0000. 2) ,2o 2'/',3 J 2'f g- .
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ATTACEMENT V [ . PAGE 1 0F 1 F. . U ATMOSPHERIC C03DITIONS
' ['I DATE
,4 A s /e t n .44 witivs yn D M0 R21,An VI DARGriE; hic INITIAL .
DIRECTION AIR TEMP 'F HUMIDITY PREESURE coco -
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ATTACEMENT 7 'q
? AGE 1 0F 1 l q., ATMOSPHERIC CONDITIONS l
a- DATE ' JAN 16 1981 / fids - mif(Udf 5LD . Ayg nhATiid . ii AdUti4T hic illiTIAh DIRECTION AIR TEMP'*? ' HUMIDITY PRESSURE -
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ATTACEMENT 7 PAGE 1 0F 1 ATMOSPHERIC CONDITIONS (^') G' do~ w t Qe n DATI Id /Al J ., 43 i i n .4 :. Wiiip s. inD A 'i G A .LAll'il 3 ARL eil:RIC 1H121^L DIRECTION AIR TEMP 'F EUMIDITY PRESSUR.E c000
/ ? A 'Is o - o '?. u, T 0100
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ATTACHMENT VI ' FAGE 1 of 2
/~ FLOW DATA DATE TIME l FI-7304-LR FI-7305-LR INT. TIME FI-7304-LR FI-7305-LR IN1.
t t 0000 0600 ; 0015 0615 0030 0630 e 0045 0645 ' 0100 0700 i 0115 0715 0130 0730 0145l 0745 , 0200 0800 005 0815 g) N 02:0 0830 0245 1 0845 ] 0300 0900 ! 0315 091: 0330 0930 l l 03:5 0945 l O AC.0 1000 f Odi: 1015 ! oc01 1030 l l
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d FLOW DATA DATE INT. TIME FI-7304-LR FI-7305-LR INT. TIME I FI-7304-LH FI-7305-LR i 1800 1200 1815 1215 1830 , 1230 1845 1245 1300 1900 . 1315 1915 , 1330 1930 , 1 1545 1945 2000 l l 1400 2015 23 1A30 2030 _ 2045 l 1:45 i 1500 l 2100 1515 l2115 2130l l 15?O
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% tu m i u. /t s. Ann u no_ u/t 0000 \ 0600 9 tA Tgfc 0015 \ 0615 Q ,g a. W 0030 \ ! 0630 R.14 h 0045 \ 0645 ~~
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. . . . . . . . . --- . - = _ - . - ..... - .
ATTACHMENT VI - PAGE 2 of 2. O '- etou oiTi DATE FI-7305-LR Ili T . TIME FI-7304-LR FI-7305-LR INT. IIMEl FI-7304-LR / 2 2x \ / iew \ /~ i2is \ / ieis \ / i230 \ / isso \ /' - i24s \ / iets \ / 2 3x \ / iew \ / i3,s \ / isis \ / ' me \ / mo \ / n4s \ / ien I \l / : uwI \ / I 20x I \1 / I is I \ / I 20is I \ / I O m30 I I\ / I 2030 I l\ / I mas i V I I 204s i IV I sco i /\ l i 2ix i i /\ i.
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'ATTACRMENT VII Page 1 of 4 REQUIREMENTS FOR PERSONNEL' ENTRY OF
(} 'w- REACTOR BUILDING,AT 12 PSIG
' Personnel who are designated to enter the Reactor Buildin6 while it is pressurized to 12 psig shall be familiar with the following precautions:
- 1. Assure that the following pressurization schedule is used: (posted inside and outside of the personnel airlock).
0-3 psig in not less than one minute Hold-check for discomfort 3-7 psig in not less than one minute Hold-check for discomfort , 7-12 psig in not less than one minute
- 2. Assure that the following depressurization schedule is used:
12-0 psig is not less than.3 minutes (rate not to exceed t psig every 15 seconds) i 3 Personnel with head colds, sinus trouble or trouble equalizing pressure across the ear should disqualify themselves from entry. s A. The atmosphere in the Personnel Access Airlock and the R3 shall be tested prior to the internal inspection to verify the following con-ditions: Oxygen concentration greater than 19 5% {} a.
- b. Carbon Monoxide concentration less than 100 pps.
- c. Pla==able gases less than 1 5%
5 All personnel entering the R3 at 12 psig shall have had a =edical checkup within 1 month prior to entry certifying that said personnel ; are in suitable health for entering a co= pressed air atmosphere. >
- 6. In the event an employee is absent from work for 10 days or is absen due to sickness or injury between his physical and the ,
Reactor Building entry, he shall not enter the ccepressed air atscaphere until he is re-examined by the physician and his condition reported as satisfactory. i f'N d SUM-C 145-103 RIV. ;
I ATTACHMENT VII i Page 2 of 4 IT PERSONNEL ACCESS AUTHORIZATION J u) , NAME I do not have any of the followins conditions: . Initial /Date Head Cold Sinus Trouble Equalizing pressure across the Eardrum . I have had a sedical check-up allowing =e to enter a compressed air atmosphe re of 12 PSIG. PERSolifiEL DATE Examined: f( ) DA22 f MEDICAL EXAMISER DATE Approved: Zes dupervisor vate i I^) %) \ SUM-0 126-104 R E*l . i
l ATTACHMENT VII PAGE 3 of 4 C
/ REACTOR BUILDING AIR QUAILTY
(]') HEALTH PHYSICS AND ! 1.. INSPECTION ENTRY-@ 12 PSIG. CHEMISTRY LOCATION OXYGEN CARBON MONOXIDE FLAM. GAS INITIAL /DATE
>19 5% <100 PPM <1.5%
AIR LOCK n.E. LOWER LEVEL R.E. UPPER LEVEL TESI buf6RVISOR HEALTH PHYSICS AND
- 2. INSPECTION ENTRY AT TEST COMPLETION. CHEMISTRY !
LOCATION OXYGEN CARBON MONOXIDE PLAM. GAS INITIAL /DATE !
>19 5% <100 PPM <1.54 AIR LOCK :
R.3. LO'4ER. ! LEVEL R .. ; . UPPER f (} LEVIL zs: suisavIs0R j REMARKS: , f i i S L*M- 0 126-105 RT.~ . 1 ! j l
ATTACHMENT VII , PAGE 4 0F 4 .n ' (,_)
SUMMARY
OF REACTOR BUILDING INSPECTION AT 12 PSIG ELEV 388 ELEV 412 ELEV 43o ELEV 463 ELEV 515 ELEV 552 BUILDING- r _ INTERFERENCES EQUIPMENT VENTED
~ETRUCTURAL
__ MEMBERS WATER ACCUMULATION BOUNDARY VALVE LEAKS If condition observed is satisfactory,. write "OK" in appropriate blank and attach to General Observation, Attachment XIII. If condition observed is unsatisfactory, write "XIII".in appropriate blank and attach to General Observation, Attachment XIII. l 3 () , i b i i l
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ATTACHMENT ~VIII i , PAGE 1 0F 5 i i (- ILRT STAFP RESPONSIBILITIES:
-1.0' The following are the personnel that constitute-the ILRT Staff.per j shift and their responsibilities:
NOTE: Some of these personnel may'be required to make , the 12 psig entry) to Attachment III f the Reactor Building (refer
-DOTE: Those personnel who may be. required to make the 12 peig entry are identified by an asterick (*). >
2 '. 0 Test ' Supervisor ( *) ; 2 .1. Responsible for overall coordinating'and conducting the ILP.T Test ' and ILRT Staff. 2.2 The following are considered Test Supervisors: - PRINT NAME INITIALS INITIAL /DA*? 2.2.1 f,h WM' _ //9 M 2.2.2 AfP itA' /) $f /d 2.2 3 Dl0bM H # ' l 2.2.4 d, b/rA/ 2 3~bV h-(/ & No I
,0
- s. Nuclear :.,nSine f1( &> & ;
31 Responsible for reviewing data collected during the ILRT Test ! with the Test Supervisor and assisting the Test Supervisor in i resolving proble=s. 32 The following are considered Nuclear Engineers: bb 3 2.1 Ch b 3 d C\ O '
)
3 2.2 ; 323 i 3 2.4 ; 2.0 Plant Operators (*) l 4.1 Responsible for operating per:anent plant equip =ent and assuring ! that plant equipment is not endangered during test. l 4.2 Tr.e following are considered ?lant Operators: f O SW-: 1 126-1C7 REY. 1 i i
ATTACHMENT VIII PAGE 2 0F 5 O (~ INITIALS INITIAL /DATE V PRINT NAME
~
4.2.1 OO \ 4 2.2 D02[h5 4.2 3 4.2.4 4.2.5 , 4 2.6 50 General Observation and Safety
- 51 Responsible for assuring that no personnel are within the Exclusion Areas as defined on Attachment XII during portions of the ILRT Test or as directed by the Test Supervisor.
52 Responsible for recording observations on the outside of the outside of Reactor Building durins the conduct of the ILRT Test and the reporting any abnormalities to the test coordinator immediately.
#~
5.3 The following are considered Safety Personnel: O) c 531 M6 A%l 6 YV - 532 533 534 535 _, 536 537 , 536 539 5310 _ 6.0 Data Reduction Responsible for taking data collected during the conduct of the 5.1 ILRI Test and p;otting results to assure that test is ac c ep' cble . t / a V S2-0 116-105 RI7. _1 l b
ATTACHMENT VIII PAGE 3 0F 5 ; (. ' PRINT NAME INITIALS INITIAL /DATE 6.2 Responsible for taking temperature and pressure readings at
'15 min. intervals and recording results on Attachment 'II,
.III, and'IV. .
63 The-following are considered Data Reduction Personnel: ; 631 dhM h Mh / f f/ - 632 O lAhYA. SCP 633 Gn Grud N ' 5' M 634 q ;># , 635 . 7 '. 0 Co= pressor Operator and Maintenance , 71 Responsible for starting, stopping, oiling and fueling air compressors during the conduct of the ILRT Test. 72 The following are considered Cocpressor Operators: , 7 2.1 S $ c1%l d 7.2.2 723 7 2.4 i 3.0 Data Acquisition System ; 3.1 Responsible for operating the Data Acquisition System and support " equipment and recording results en Attach =ents II, III, and IV.
- S.2 The following are considered operators of the Data Acquisition Syste :
S.2.1 % 4tg ch. 5 b i b 6.2.2 ,, 8.2 3 j 8.2.4 , l 9.C I 4: C Technician
]
i
?.i Responsible for assiting in the reslution cf any prob'.e:s which may arise with any instru:entaticn during the condue Of the
=^ " ' '
'O SIDI-0 146 *C9 RE'T . 1
-, ,. . - . . ~ . . - -.- - .-. _ .
i
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e ATTACHMENT VIII l PAGE 4 0F 5 . O .V
/
PRINT NAME INITIALS INITIAL /DATE
, l 9 1- The following are considered I &-C Technicians:
9 1.1 bifoM5 BY- //9/A1
'9 1.2 & $A<//# . l 9.13 5 Ny-MN ,
4 9 1.4 6,l/JMal SL- ;
/ '
9 1 5- l 9 1.6 'j 10.0 Electician
.10.1 Responsible for assisting in the resolution of any proble=s which '
may arise with electrical equipment during the conduct of the i ILRT Test. f 10.2 The following are considered Electricians: 10.2.1 d6 M$r'3 /88 .
/ !
I
-, 10.2.2 O. 10.2.3 i i
' ~ ~ ;
- 10. 2. .t 10.2 5 10.2.6 :
11.0 Pipefitters j 11.1 Responsible for assisting in the resolution of any proble=s i which may a:'ise with pipes, valves o." any other echanical i equipment during the conduct of the I'.RT Test, j i 11.2 The following are considered ?ipefitters: ; 11.2.1 A6 dM/ //d?c 11.2.2 11.2 3 > l 11.2.4 l 11.2 5 j i O SUM-C I 146-110 RE7. -1 i i
N l ATTACHMENT VIII PAGE 5 0F 5 PRINT NAME INITIALS INITIAL /DATE I o] L (~ j l 11.2.6 l 12.0 Welders 12.1 Responsible for uaking repairs as required to equipment during the conduct of the ILRT Test. 12.2 The followin6 are considered welders: 12.2.1 k6 ch 63 / 4/M 12.2.2 12.2 3 12.2.4 13 0 Laborers 13 1 Responsible for cleaning the Reactor Building interior if required. 13 2 The following are considered laborers: 13 2.1 b $ h S O / /$ n U 13 2.2 _ 1323 13 2.4 13 2.5 13 2.6 13 2.7 13 2.8
>O SE-C 126-111 RE7. 1
i ATTACHMENT IX ; Page 1 of 1 C DATA ACQUISITION SYSTEM OUTPUT ! RAW DATA i A l l l- i
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ILRT RAW DATA 'v t i n n - START--0345 on 1/15/81 4 V 'I i COMPLETED--0345 on 1/16/81 i i ENGINEERING UNITS ,
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** / / uoI .b 3 U f us? c:64;ogo r v;t aut J4c ( Ull 062,380 f Jil G u d . ;* u U E uti us;,940 ( ,
v;g a s s ,a l ', g F U/J u to y .J o d ( ' U2U 0 0 7 ,s 9 t> f - . - . U 6 2 . '3 0 0 a ;u o r, , . a J n, ( a/U 0i9 us2 ,330 f muse ulu 0 6 2 ,U J u E Jly vo y *3 3 u ( l s~ o - ks ale :sur sju 5 a dio U 6 2 ,4 5 0 ( wowH US3 UdE.4db I. al3 u ta ,460 r n en ts - al3 U s i ,4 S u Y , ( Ji1 0(,2 ,930 (
? UI/ 30/ .S S U US7 Uc) ,02nx2 F o - >le-ali v6: 346 f O t to Ot;7 ,75y y p d u s ,l n t, V Ulb U 6 Z .l 40 I. Uld DJ2 s _/ t;~Jf
;Is V dlb U o d , y t, 0 ( UIb U t> 3 ,3 *o a f r Ulb UOE e$ / U al> vh1 6 t,3 i dl4 Uo?,fl0 F Ul4 U o f ,1 ] Q f V
USN UOE el3U J1S UL6 ,l i d ~ 01J O G 7 ,6 2 u g: JIJ 062.14U I UIJ 062,aIU ( ei i s a t, ;, 13& & Ull OG;,3bC f U l ** U
- E .4 I U I 082 U d 2 ,4 0 c r J6i 45U ( O lo ? j ] d uJe ,
UII Ubl.blU I Uli L) to 2 ,'s % ;) ( Uli ( (
.e l i U :o ; ,:, 5 3 ( ' ud3 0 5 s ,1 g y l' d 1 0 ;* J . 'l b U l vuJ oy4 ,; 5 u f
.aJ v 3 s ,9 4 0 r 00] Utg $)$ g, y UJE O2:0.504 kV 3O] O g y ,$ g; y ,.
sb J s u a' ) ,5 3 5 :-e y U it g -100 ,yug g,., y UJI ~ l 'i d ,U U U t5% 0 :l g -gau ,0co :4y a11 -IJJ ,uda g:V a ni n y y y ,y q 4 ,y J .e u ., i .s ,a ( ; t . ', U i st UJa.3U0 h4 uu3 a 3 u :, y g g,, a l 's g ;, : 4 ;, : a a bl3 3a;l4;uG asy g y : ,4 ::,
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1 ILRT DATA 1/15/81 1600 to 1645 n _ V . M - JZ% 4C'3 QN es
=
o r4 QoooaO .:: Q Qc3 cs n as ce N 3 -. J 3 a3 c 4 0 o c o o e3 rw oo 13 N 3 aw w N .a w3 c3 'M 83 == Q Q Q 7 % .c ** w '3 % N *3 3 =, "') "Ji 20 J3 y "l* N 34 .c N ** *e *p W 7 k"3 e* ,
.1 e e e e e e e e e e e e e e,3 e e e e e o e e e e e e o e ,
*N *1 N N NN M si t C3 *e I": *) 'S *? N /*) 69 FS t% *P *P 7 3 N N f% N 4w
** ** 4 D so .a y Q to *4 a3 o %3 *4 SC 'O '1 4 4 Q 'O 'O O *1 W4 Pe '*3 J **
C @ C QQQ C Q C O O == *) J "J 3 2Q O CC QCCCCOO **1 G *. t r 61
*e f*) N % M fe == e4 ==
*n % v *5 N =. O Os % ati * S N e, C') C4 33 A .3 W) I
*e 8% N NN == == mi. a. *. == % * == Q 7 s4 7 ,0 7 *i *S f*3 **) 8* *3 N NN
~J QQ Q *3 O ~3 C DCCQC QC 'a Q O C QO 7C CQQ Q C
?
. wL wwL'LLL LLLL LLLLLLLLL33/ s s
*3 *3 3 O O 2 "O 'O 3 O Q D CCC QCC D OQ QQQ DW fte Q N % c a *F A 4 J% 80 .F) '*) f4 =. Q Q *3
#*)
- a. S
- a e, ws 7 N N Q 'S 'M J N "5 9 % .1 #3 C **
C *n *C evS N ,
.4 1% % *;ll *, y h '* % eC Ce *w e o e e e o e e e e e o e e e o e e e e e o e e o e p * =, N N N .N N N *1 *% NNew m .m c Q +3 *
,J J $ .w N 9
- 9 N ar '"3 **
'O O .3 J D D D 4 'O C 'O O ' 3 'O 'O li NQ v ** .3 J J J J J 4 i O O 2 3 *3 3 3 D C QQ Q Q 3 3 O QC D7C O Q Q Q O == D 4 8 j
#1 ,
S NN h *W D M .4 M b k I j 3 N Y
-*
- 9 9 b
*)
G. 9 ** N N *e N *N N *e *e == =.e m ====% +===="O Q *) O 3
'3 "3 CC 3 >
*: 3 1 0 C Q "l", *3 C C D Q 3 3 Q C O Q 'O CC 3 ""1 N r e -n-. ,
2 r 6 L L6 LL LwL i.- L w L L L 3* .* > L. 6 LL6 6 .a. [ 8 Z .a* .~. t
' .) hQ MD 44 *W )
") ) ) ) . 4 '
-3 N ti Js 'M =. Q Q J
? 'e 4) .9 3 .S "% .) w % $ 4 "4 * .3 9 7 N at n
- 1
.c 93 4 h % C%a ,3e P=,e rug 4 C4 .ti 3 *3 a*
% % $ .3 *t Ja J1 % O 3 9 M i e e e e e e e e e e e e e ' )e e e e o e e e e e e e g "9 N 7 3 7 N ** *e '1 1 N N N N NN 7 *e N N r, a5
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* * 'O .1 4 .3 'S '3 .1 0 4 4 4 3 #3 3 'a '3 4 '.3 '1 '.3 s2 4 w9 es "*3 3 +e i "3 4 0 *: 3 O O O 3 QQ O 70 QQQ "3 == *2 3 a J QC Q 3 '. "". l I %
P i
.i q J 9 % ** *i 5o 3 .* % S so *1 *. , = = :) .3 3 % 4 .) *, 3 N e3 ev I
-a a . *e e. ae % e NN == *, *3 ;) 3 J
** ** 7 ** 5
": "'J 7 'J 3 '"., O "3 Q *2 J *3 "3 *3 O Q 3 0 3 1 "3 7 O e T) "'3 ~3 *3 t
w m w 6 ww wL L wL LLLL >> > e5 N aI. t
') $
3 0 9 0 a *: O O -7, 'O O *s J 3 C O 4 Q C C c Q "J J %==to e c* t* r3 j 4 9 9 '= % 9 P, == 4 4 3 += v ws - == c e3 C m 7 - 9 N N e, h* O .", S % % . ,9 e 4 * ' e e M N ': C. 4 0. ,*h. 23e *1. *t. 3. %. *%e e e e e e .e e . O. "3. ,e., a ,
..e e e e
- , , co 3 3 3 . , 3 ., w .% r% ,s N c. m N , ce .s ., , e ea "
3 $ $ ., * " 3 **, J " '3 'O 'O +5 . ** c 'o a ;,3 4 .i ^e r* **. *e
**
- J * ; 'S ' i
"* 0 #3 7 3 "3 3 .** "1 "J O ": 3 Q % '.: o 4 , *) O .3 "'3 3 *:; ': 1 2 I [
d'
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[ .- . a w . -= 5 * *, , , N y
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ILRT DATA 1/15/81 1700 to em 1745 f t
% f %/
6 LLLLLLLL6 LLLLLLw LLLLLLL > > # 22C a a o d c :. a :3 o t a o a c3 sQo3 4oa:3 '5 s.) 3 o r3 63 = 3
.*4 oy a == al f.a 4 *e ow% C 4 N v3 9 C == % es N e1 q a c3 7
** M *
.n 3l3 N *t 4 N :*n =3 P% **) w 33 $ e1 73 e*
9% % 4 4 9 t 43 % '3 .h e e e o e e a e e e e e e e e e e e e e o e e o e e o ,3 d'"! 3 as r3 4 N 9 M M *) %N N *N N N9 NN N ?v *=. .4 9 ~3 't
'3 l
=e = 3 to <.3 to <,3 .3 o J .3 'C a4 c3 'a 'a *O 'O -3 61 'c 'O tai % '3 73 *
- s ') "'3 ?) *3 3C 4*, C *3 O ~3 O 'l3 D *J C D D Q C 7 D <3 0 ** 'O N i =,
o eh % 4 => M 8N == 3 c'l 9 Pt. @ h*h 4 9 N *
- m. 9N 71 -.
99 s -m M/9r e> IDSS,m ,m@ mN% % c, N N% % - - - - - * = . . - .3 :3 ,, ,. 3
'3 C 3 '3 O '3 ~3 ll', t *lll "3 47 9C a 3 "J *3 "3 -7 *J
- 3 O 3O Q ~3 43 6 LL6 66 L e. L6 6LLLLLA 6 =6LLLL # # **
- f I
*) *) C 34 "3 1 0 4 "*. 3 OtO
- 3 Q "3 4UO "3 C ~1 3 9 63 7 J !
% 3 9 s1 % == N == 9 % ** 85 N *P N r") ul Q *) o *r 4 o *) .* Q 4 3 am aS J => 4 *i 7 Ne "3 ,? => M 3 +3 %
- S N M J % av M 'a Q *)e **
e e e e e e e e e e e e e e e e e e e e e 'Me e e e e
)
7 ) *) *) N J1 "4 *4 N 4 9 7 7*e os N ($ N (* 9 N N N N N 7 *3 *3 4
== w .3 o o .3 '.3 J O 'd 4 4 *c 4 .3 'O 'O 'o 1 0 3 4 O 4 1 N *7 *) **
*3 "3 3 ~3 *3 '3 ~3
- *3 3 '3 0 34"3 *J *'* O OC '3 C "3 Q '.3 Q "4 C3 % a%
l =
-1 f3
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\ 9 9 9 ai M a 9 N N NN N N 'N N % == % == = = = = = = % aC r3 3 3
( V 3 '3 0 7 *37 "3 Q "3 0
- O ~3 O O 7 '3 J y3 "3 ** 3C "3 ~3 O * )
s r
. % 6 .-.6 Lw 6 L6 L L == L L l L L L le. .i3*&. .>
* "3 JC Q a3 3 43 0 *) 3 -3 "3 O O O J ~3 Q 33 C 3 r3 == == = 0 3 4 ev N "% 3 .3 4 m *'t sN N .7 a ** S r, p3 o o r3 f3 o .=3 3 a o% 3 ap
- h M % 3 'h 4 M ?) 23 N 4 (*t N 3 3 % 9 ',e N o.i e *3 *} *e o e e e e e e e e e e e e e e o e e e e o e o e e J 7 mm *e 3 7 9 tw w **1 3
- N N N *w N .N c'9 N N .N 6 <w *3 a 3
= ao 1 t J 7 3 3 'O 3 4 a .3 oW .3 'O 'O ,D .c 3 '@ '3 3 han N
- 7
- 3 7 *J "3 *J O "3 3 ~3 *5 D
- 3 C Q O "3 3 D *J DQ *1 *3 C 3 == 3%
1 =. i 1
. ,, , , ., ,: -. % 3 -. .w - - m es P% .3 .3 e , S. m .- - -
ag av 9 gg g. g. 9mb ".g *q P*g % g % *, 6g 86 em em M h. 84 88.B 84 == ) ") )
- 3 3 3 ; ; 3 3 3 0 '3 '3 "3 % "*, O O O *3 "3 3 0 103 5 3 ~1 i
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I
. . L .. b L -% L 6 LLL L LLLLLL w 6L L 7e 3*
- Ca4
. . *3 'a '3 *3
. 3 '3 ') J O 3 '. 3 .3 43 ') O '3 O O **
"3 3 - *. O 9 '*J *3 .1 3 1 M % 7 61 1 *9 % *e 3 *t O J =, * .n %
- N 4 **> c% %N Q c) a 1
, .: % a *r 4 ** := rr; 3 %e % N 3 3 % 3 ** a. n O aj e l
e e o e e e a. . N Oe **e e e e e
=t e o e e e e o e e e e e m .
+ 3 9 5 , a ? 1 r, *, 3 '9 , N n, = .N iw % 9 (w .i. g N 3 *'
,s ;;' <, ;, 3
** * 'J '* * * .3 1 .) 4 3 'J 3 0 'O 4 .i J 3 '4 4 'S 3 4 % Pe *3 *1 e t 7 '3 4 3
- J3 * "* "3 2 7 ** *) "*) 3 0 ** "J ~3 '3 Q '*3 Q .3 % 7N e ~.
d t G - s e , s .. 3 s . .3 .. ,.. , 2 v - - , - , - - ,
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ILRT DATA 1/15/81 ' 1800 to 1845 (m) (, . v L LLLLLLL L LLLuuuu6LLL LLuuL :. .* 3 .: : : 3 ~3 'J c .3 .3 oooooa3 3 o 7 .1 o a.3 0 m o rg ou, 3 r3 .3 a a a
'A *e v *, t.1 % .1 N N O %; g % *N +g aNas Q "J M O tn O N 'a o s n c.3 3
*, .i % 3 *, e9
* *
- e o e e
'% .r3 e
.3 e
*3 % 9 49 3 e 4e %
e e o e o
*t e Ve % e 43 e 'JNe e '9e *r o ce 4 ** 3 e e e ,.e, 3 1 9 =3 .v 9 7 mrw wm as a e. N N N e e 9 N N N N o a c3 -5 ,
** *, J 3 3 'o o e1 'O s = 3 .3 4 *3 .3 's a 's a t3 's 4 'o .3 .) N.3 7 ..
3 3 33O QQ QO 3 '3 3 3 3 3 **3 7 Q '3 ~J JO 'J '3 *3 0 == 1 3 1 a u3 1 ** , 7 ev a. s3 mN 'i ., r3 N
. a. o3 oN w3 W w c1 N =. m " w a me 1 '1 9 +3 9 9 == w N NNN -, N *e =. == = == == . - . = '1 *1 q *3 3
'3 3 3Q '3 0 4 3 'J 7 3 3 2 #1 **3 O 7 3 '3 ) ~3 '"3 J "J 3 O '*J 3 k
T-6 LLLL LLLW Lw6 LLLLw wLL L L L,6 L 's .*
- .* To .:
.J 9 "3 O O 4 '3 37 "1 C1 O Q "3 a "3 u O s*, 'J '.J Q "3 O 63 r1 1 -3 ~3
* .g N .J Q c1 o 'J <> '3 63 3
% % o .=7 w *% % 3 % at eN N v3 *p N J J
.) % % .1 * .*i 3 o .a .% .a w m as e, N = >> N. 3 o N #9 'a '7 **
*
- e e . e e o e e e o e e o e e o e w.t.1 cJe e 3 71 7 e7 M ?. M M sq ce m rig % mN,e N N N N N ie N te N 3 as '3 3 s
* =e o 'a '4 J .3 's %3 'a o 4 .1 .3 'o o a oQ 'o ' to .3
- 3 oN 1 7
t 1 '3 C *4 C O '"3 Q '3 '3 Q c3 ac3 7 C C CC O '". 4 '7 == '3 '1 4 == 1 e 9 % *, 9 r, , c .3 N u3 9 e5 N g m o a. O o =. m N 7 as ;3 == O ' M 3 n ., ' 3S 9 as e. 3 7 N N NN N N NN *.-a. .= =9QO O '3 v 3 , mo,2, , , a3 , anon,o3, 3,= 3 w
~
L6 LL L6 Lw 6 L 6 L L 6 L. w ,8 * >
. www w -
c.. . 3 a2 3 '3 *) 3 "3 3 '3 C0 3 7 3 4 3 "3 C 3 J O 3Q 'a N w w 3 N 7 = n9 'n N 3 .3 % a ws o 9 o *3 7
-. -e c .3 o M N P M N J 3, 3 9 35 9 *a a% <9 -p a n 1 e
.s %
e e %.}}