Text

Reactor Containment Bldg Integrated Leak Rate Test Summary Technical Rept.
	ML17299A347
Person / Time
Site:	Palo Verde
Issue date:	05/07/1985
From:	Roman W; ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	;
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ML17299A346	List: ML17299A345; ML17299A347;
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	NUDOCS 8506100595
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ARIZONA PUBLIC SERVICE COMPANY PALO VERDE NUCLEAR GENERATING STATION UNIT NO. 2 REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST

SUMMARY

TECHNICAL REPORT PREPARED BY WILLIAM D. ROMAN ARIZONA PUBLIC SERVICE COMPANY OPERATIONS ENGINEERING SECTION MAY 7, 1985 8506100595 850528 PDR ADOCK 0500052~

A PDR

P TABLE OF CONTENTS PAGE INTRODUCTION.................................................... 1

SUMMARY

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TEST DISCUSSION....................................... ~ ~ ~ ~ ~ ~ ~ ~

A. Description of Containment.....................'.:........... 3 B. Description of Instrumentation.............................. 11

1. Temperature Instrumentation.....................,...,... 11

2. Dewpoint Instrumentation................................ 12

3. Pressure Instrumentation................................ 12

4. Flow Instrumentation............................,....... 12

5. Ancillary Instrumentation.....................,...,...,, 12 C. Description of Computer Program.......................,..... 13 r

D Error Analysis................................,,.....,...... 18 E. Description of Tests........................................ 19 IV. RESULTS AND VERIFICATION.'-.;-;.................................... 24 V. C ONCLUSIONS..........................,,....,.................... 25 VI. F IGURES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ i ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 27 VII. "APPENDICES....,................,.................'................ 39 A. Computer Generated Report

1. Stabilization ..............'............................ 41

2. Integrated Leak Rate Test (ILRT)..............,......... 53

3. Controlled Leak Rate Test (CLRT)...,.................... 69 4 General ................................................ 85

I. INTRODUCTION A preoperational Type "A" Integrated Leakage Rate Test (ILRT) was per-formed on the containment structure of the Arizona Public Service Company,

,Palo Verde Nuclear Generating Station (PVNGS) Unit No. 2 pressurized water reactor in February of 1985. The results of this test were analyzed utilizing the "Absolute Method". This test was performed for a period of eight and three quarter (8.75) hours at a pressure equal to or greater than the calculated peak containment internal pressure related to the design bases accident (P ) and specified in the Technical Specifications. This a

report describes and presents the results of this preoperational Type Rate Test including the supplemental test method (Controlled "A"'eakage Leakage Rate Test or CLRT) utilized for verification.

The test results are reported in accordance with the requirements of 10 CFR 50, Appendix J,Section V.B.2., ANSI N45.4 (1972) and ANSI/ANS 56.8 (1981).

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II. SENARY Prior to performance of the ILRT, Local Leakage Rate Tests (LLRTs) were performed to verify containment integrity. These Type B and Type C tests were performed on containment electrical penetrations, mechanical penetrations, containment isolation. valves, fuel transfer tube, equipment hatch and air locks. The acceptance criteria for the LLRT is that the total leakage from these tests does not exceed 0.60 (La ) where La is the maximum allowable leakage rate at pressure P a stated as a percent of containment free volume per day (24. hours).

The total leakage from these tests was well within these limits and the results are presented in the official copy of preoperational test procedure 91PE-2CL01, Local Leak Rate Test, which is on file at PVNGS.

At the start of the Type "A" test, all valves were in their normal position for accident conditions. Exceptions to this valve .lineup were noted and corrected prior to test start and are listed in the official copy of preoperational test procedure 91PE-2CL02, Integrated Leak Rate Test, which is also on file at PVNGS.

The first order, least-squares fit analysis of the data utilizing the

'Mass-Plot method yielded a leak rate of 0.0056X per day with a 95X upper confidence limit of 0.0092X per day. The first order least-squares fit I

analysis of the data utilizing the Total-Time leak rate yielded a leak rate of 0.0063X per day with a 95X upper confidence limit of 0.0292X per day. These values are well within the allowable limit of 0.075X per day.

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III. TEST DISCUSSION A. Descri tion of Containment The containment design basis is to limit release of radioactive materials, subsequent to postulated accidents, such that resulting calculated offsite doses are less than the guideline values of 10CFR100. In order to meet this requirement, a design '(maximum) containment leakage rate has been defined in conjunction with performance requirements placed on the engineered safety features (ESF) systems.

The capability of the containment structure to maintain design leaktight integrity and to provide a predictable environment for operation of ESF systems is ensured by a comprehensive design analysis and testing program that includes consideration of:

'The peak containment pressure and temperature associated r

with the most severe postulated accident coincident with the operating basis earthquake (OBE) or safe shutdown earthquake (SSE).

'Maximum external pressure loading condition to which

. the containment may be subjected as a result of inad-

, vertent containment systems operations that potentially reduce containment internal pressure below outside atmospheric pressure.

The bases in determining design are containment peak pressure (and temperature) and external pressure. For the containment structure peak pressure analysis, it is assumed that each postu-lated accident is concurrent with the most limiting single active failure in systems required t'o mitigate the consequence of the accident or to shutdown the plant. No two accidents are postu-lated to occur simultaneously or consecutively.

A. Descri tion of Containment (Cont'd)

The design basis accident (DBA) for each of the categories of:

containment peak pressure (and temperature) and containment maximum external pressure is defined as the most severe accident expostulated for each case. The difference between the design pressure (60 psig) and the calculated peak pressure of the as-constructed design (49.2 psig) results in a design margin of approximately 20K.

The containment structure is designed to house the reactor cool-ant system (RCS) and is referred to as the containment. The containment is part of the containment system whose functional requirements are summarized by the following criteria:

'The containment must withstand the peak pressure and time-varying thermal gradient resulting from a hypo-thetical failure of the RCS or main steam system.

'The containment must provide biological shielding during normal operation and following a postulated loss-of-coolant accident (LOCA) to minimize radiation exposure.

'The containment must be leaktight in order to minimize leakage of airborne radioactive 'materials.

'The containment must provide approximately 150 pene-trations for piping and electrical cabling, as well as, personnel and equipment access, and provides rigid anchor points for piping entering or leaving.

The containment consists of three basic parts:

'Flat bhse slab with a central cavity and an instru-mentation tunnel.

'Right circular cylinder

'Hemispherical dome

0 A. -Descri tion-of Containment (Cont'd)

Principal nominal dimensions. of the containment are as follows:

'Interior diameter..............146 ft.

'Interior height (above.........206 ft. 6 in.

filler slab)

'Cylindrical wall thickness.....4 ft. 0 in.

'Dome thickness.................3 ft. 6 in. at .dome apex 4 ft. 0 in. at wall springline Base mat thickness.......... ....10 ft. 6 in.

'Liner plate thickness....... ...1/4 in.

Internal free volume........ ...2,600,000 ft3 net The containment is constructed of reinforced concrete prestressed by post-tensioned tendons in the cylinder and the dome. The base mat is designed and constructed of conventionally reinforced con-crete.'pecial reinforcing details are provided at discontinuities and at openings in th'e shell.

A welded steel liner attached to the inside face of the concrete limits the release of radioactivity from the containment. The base liner is installed on the top of the base mat and is covered by a 2 ft. 9 in. thick concrete slab. The containment building provides biological shielding during normal operation and following a LOCA. It also functions as a leaktight barrier following an accident inside the containment.

The post-tensioning or tendon system consists of high strength wires which are used with button-head anchorage techniques. There are 186 one-quarter inch diameter, wires per tendon.

Each tendon assembly consists of wires together with end anchor heads and ring nuts. The tendons transfer load to the structure through shims and a bearing plate.

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Tendons are installed in sheaths that form ducts through the con-crete between anchorage points. Trumpets, which are enlarged ducts attached to the bearing plate, allow the wires to spread out at the anchorage to suit button-head spacing requir'ements. Further, trumpets facilitate field button-heading of wires.

Tendon sheathing provides an enclosed space surrounding each tendon.

A valved vent at the highest points of curvature permits release of entrapped air during greasing operations. Drains are provided at the lowest points of curvature to remove accumulated water prior to insta3.ling tendons. After the greasing operation, the vents and drains are closed and sealed.

The prestressing tendons are protected against atmospheric corrosion during shipment and installation, and during the life of con-tainment. Prior to shipment, the tendons are coated with a thin film of petrolatum containing rust inhibitor's'. The sheathing filler

.material used for permanent corrosion protection is a modified, refined petroleum-base product. The material is pumped into the sheathing after stressing.

Prestressing of the cylindrical wall is achieved by a post-ten-sioning system consisting of both vertical inverted U-shaped and circumferential (hoop) tendons. Vertical tendons are-anchored at the base slab and extended up and over the dome to form an inverted U shape. Three buttresses are equally spaced at 120' around the cylinder and extend over the dome joining together at the crown. The hoop tendons are anchored at buttresses located at 240'part. The successive hoop tendons are anchored. at alter-.

nate buttresses so that two complete horizontal loops are achieved by three consecutive horizontal tendons.

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A. Descri 'tion 'o'f 'Containment (Cont'd)

Prestressing of the hemispheiical dome is achieved by a two-way pattern of tendons, which are an extension of the continuous vertical tendons and are anchored at the base slab. They are arranged to produce two families of tendons 'mutually intersecting each other at 90'n the horizontal projected plane. Hoop tendons extend into the .hemispherical region to provide a two-way pattern up to the 90'olid angle of the dome.

A welded steel liner plate covers the entire inside surface of the containment (excluding penetrations) to satisfy the leaktight criteria. The liner is typically 1/4-inch thick and is thickened locally around penetration sleeves, large brackets, and attach-ments to the basemat and shell wall. The stability of the liner plate, including the thickened plate, is controlled by anchoring it to the concrete structure. The shell wall and dome liner plate 4

system is also used as a form for construction.

A circular equipment hatch and two personnel airlock assemblies (100'nd 140'levations) penetrate the concrete cylinder walls.

Penetration assemblies consist of steel sleeves or nozzles, rein-forcing plates and anchors. They are anchored to the concrete walls and are welded to the steel liner. Hatch and air lock doors are provided with double-gasketed flanges with provisions for leak testing the flange-gasket combinations.

The 100'levation personnel air lock is for emergency access.

Each personnel air lock has a door at each end and is an ASIK Code. stamped pressure vessel. A quick-acting"equalizing valve connects the personnel air lock with the interior or exterior a

of the containment to equalize pressure in the two systems.

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A. Descri tion of Containment (Cont'd')

During plant operation, the two doors of each personnel air lock are interlocked to prevent both being opened simultane-ously. Remote indicating lights and annunciators in the control room indicate the operational status of the doors. Provision is made to bypass the interlock system during plant cold shutdown.

Single barrier piping penetrations are provided for all piping passing, through the containment walls. The closure for process piping to the liner plate is accomplished with a special flued head welded into the piping system and to the penetration sleeve which is, in turn, welded to a reinforced section of the liner plate. 'n the case of piping carrying hot fluid, the pipe is insulated to prevent excessive concrete temperatures and to prevent excessive heat loss from the fluid. Closures to these penetration assemblies are provided by the piping systems that are served by the penetrations.

Electrical penetration assemblies provide means for carrying one or mor'e electric circuits through a single aperture (nozzle) in the containment pressure barrier while maintaining the inte-grity of the pressure barrier.

Medium voltage power penetrations are configured in the. form of tubular canisters slightly shorter than the containment structure nozzle into which it will be installed. The penetration assemblies are installled in 24-inch diameter nozzles. The canister is used as a pressure chamber to monitor penetration leakage rate by pressurizing the interior space with nitrogen and'easuring the leak rate with a pressure gauge. The medium voltage power pene-tration is flange-mounted to the outside containment wall with nuts, bolts, washers, and lock-washers. The aperture seal is formed between the header plate and the flange with two concentric Viton O-rings.

A. Descri tion of Containment (Cont'd)

The low voltage power, control, and instrumentation penetrations are also flange-mounted to the outside containment wall in the manner described for the medium voltage power penetrations. Each penetration in this category has a stainless steel header plate at the outside containment end. Stainless steel feed-through sub-assemblies, containing electrical conductors, pass through the header plate and are secured and sealed with special stainless steel compression fittings. The interstices between the seals and feed-through subassemblies provide a pressure chamber which is used to monitor the leakage rate.

A fuel transfer tube penetration is provided for refueling. An

. inner pipe acts as the refueling tube with an outer pipe as the housing. The tube is fitted with a double-gasketed blind flange in the refueling canal and a standard gate valve in the spent fuel pool. This arrangement prevents leakage through the refueling tube. Outer sleeves permit the transfer tube to penetrate the refueling canal wall, the containment shell, and the exterior wall of the fuel handling building, while maintaining a pressure-tight boundary at each wall. The sleeves are anchored into each wall respectively and welded to each wall's liner plate. The housing is supported by the sleeves in the vertical and hori-zontal directions. Bellows at both the interior and exterior faces of the containment shell and of the fuel handling building permit thermal expansion of the transfer tube and of the housing. The same expansion bellows permit differential move-ment between structures.

The structural acceptance criteria complies with ASME Section III, Division 2, Article CC-3000. The fundamental acceptance criteria for the complete containment is successful. completion of the structural integrity test with measured responses within the limits predicted by analyses.

A. Descri tion of Containment (Cont'd)

Prediction of limits are based on test load combinations and code values for stress, strain, or gross deformation for the range of material properties and construction tolerances specified.

The structural integrity test is planned to yield information on both the overall response of the containment and the response of localized areas, such as major penetrations or buttresses, which are important to its design functions.

The design and analysis methods, as well as the type of con-struction and construction materials, are chosen to allow assess-ment of the structure's capability throughout its service life.

Additionally, surveillance testing provides further assurances

.of the structure's continuing ability to meet its design functions.

The report concerning Structural Acceptance Criteria is submitted r

under separate cover and shall not be addressed for any other purpose other than ILRT interface within this report. The inter-faces shall be noted since both tests were performed concurrently.

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B. Descri tion of Instrumentation A "state-of-the-art" ILRT instrumentation package was utilized to allow leak rate determination by the "Absolute Method".

The primary measurement variables include containment pressure, dewpoint temperature and drybulb temperature as a function of time. Ancillary measurements include outside ambient temperature and barometric pressure. During the supplemental CLRT; contain-ment verification (fixed-orifice) flow is also measured. Instru-ment readings were output at 15 minute intervals via a data acquisition system and line printer. The measurement system is shown in Figure 8.

PV(P-P)V RT RT where: P a

air partial pressure V free volume gas constant temperature pt total pressure, psia p

wv water vapor pressure, psia

1. Tem erature Instrumentation Twenty-four (24) precision platinum Resistance Temperatur'e Detectors (RTD's) were located throughout containment to allow measurement of the volumetrically weighted average dry-bulb temperature. The specified accuracy of the RTD's is

+ O.l'F (40'F to 120'F range). The specified repeatability for each sensor is 0.025K of temperature or 0.05'C, whichever is greater.

B. Descri tion of Instrumentation (Cont'd)

2. Dew oint Instrumentation.

Six (6) chilled-mirror Dewcells were located throughout the containment to allow measurement of the volumetr'ically weighted dewpoint temperature. The specified accuracy of each of the sensors is + 0.3'C (+0.54'F), nominal .over a range of -50'C to +100'C (-58'F to 212'F). The specified repeatability for each sensor is ~ 0.11'F.

3. Pressure Instrumentation Two (2) precision fused quartz bourdon tube pressure indicators (0-100 psia) were provided for the determination of containment absolute pressure. One pressure indicator was utilized as a primary while the second indicator was available as a backup. The specified accuracy of the indicators is

+ 0.010'f reading + 0.002X full scale or + 0.0095 psia.

The repeatability of the indicator is + 0.0005X full scale.

Flow Instrumentation Two (2) thermal mass flowmeters with a range of 0 to 10scfm were utilized during the supplemental CLRT for verification ,

flow. The specified accuracy of the instrument is + 1.0X full scale. The specified repeatability of the instrument is + 0.2X full scale.

5. Ancillar Instrumentation The outside ambient temperature and barometric pressure as well as wind speed and wind direction were measured utilizing the site meteorological tower.

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C. Descri tion of the Com uter Pro ram The ILRT computer program is an APS-specified vendor-supplied program which performs the leak rate calculation utilizing the Generator Temperature Monitor (GTM) mini-computer (LSI 11/23).

The computer is connected via a data link to the Data Acquisi-tion System (DAS). The drybulb temperature', dewpoint temperature and absolute pressure data that are scanned by the DAS are fed to the computer for storage and printing. The ILRT computer system consists of:

'Volumetrics A-100 DAS

'DEC VT55 FE graphics terminal with hard copy unit

'LSI 11/23 ILRT computer system with dual double-density disk drives.

'Parallel line printer, Data Royal 5000 After every scan by the DAS, the computer wi13; print a "Raw Data Summary Report" (RDSR).'he computer stores the data and, on demand, prints the "ILRT Program Report" (PR). From this report, temperature stabilization can be calculated from average temperature.

The ILRT computer uses the Total-Time or Mass-Plot analysis technique to, calculate the measured leak rate, calculated leak rate, and 95K upper confidence limit leak rate. The 95X upper confidence limit leak rate is used to determine if the test has met the acceptance criteria. During the verification test or CLRT, the computer will calculate the composite leak rate (L ).

c To aid the Test Director in data analysis, plots of the data are made. The RDSR, PR and plots are contained in Appendix A.

The computer contains the following:

'DEC LSI 11/23 processor with KEV ll option

'128K bytes of memory

'two double-density disk drives (RX02 format)

'two serial line interfaces

'one for console device

'one 'for serial link to DAS

e C. Descri tion of the Com uter Pro ram (Cont'd)

'DEC VT55-FE graphics termial with hard copy unit

'TCU-50D timing control unit

'Parallel line printer The system software"consists of an operating system and an applications package. The operating system is supplied by DEC as the RT-11 version 4.0 Foreground/Background monitor with the appropriate RT-ll version 4.0 device handlers.

The applications package consists of the following programs (not including 'special maintenance and editing programs):

'LOOK SCAN

'EXAM

'CONTI

'CALPRE CALC

'RELHUM INERR

'PLOT

'INLEAK Program LOOK will read data from the A-100 DAS. These data are displayed on the console device. The data output from the DAS are in the same form as is output during the ILRT (i.e., 24 RTD temperatures, 6 dewpoint temperatures, 2 pressure readings, time and date). This program is used during the initial phases of the equipment set-up. The program is a never-ending loop and requires operator intervention to exit.

C. Descri 't'ion of the Com uter Pro ram (Cont'd)

Program SCAN is designed to r'ead data from the A-100 DAS and re-format the data into a form more digestable to 'the other programs in the application, package. The program will run con-tinuously until a total of 257 data scans have been received or halted by operator intervention. This program will also run concurrently with the other programs in the application package; it has priority in execution if a conflict arises. The operation of the program is transparent to the user.

Program EXAM is designed to display the contents of the raw data files acquired by the program SCAN. This program will inspect the data files to determine if the raw data file needs editing

'before being utilized in the calculation sequence.

Program CONWEI is used to create or modify the containment weighting factors of the sensors used in the calculation,r program..

The containment is divided into various sub-volumes. The sub-volume is represented by RTD's and Dewcells. Their readings are proportionally applied to the total volume.

Program CALPRE is designed to compute the calibration constants for pressure gauges. The program requests the true pressure

., and gauge readings for both pressure gauges, then derives the multiplication factor- and correction constant for each gauge.

Program CALC is the main application module in the applications package. This program takes the pre-formatted data from the raw data files and performs various calculations with it to produce the .various parameters required in the final report of leak rate. The results of these calculations are stored in two data files for use in the plot routines.

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C. Descri tion of Com uter. Pro ram (Cont'd)

Upon execution, the. program CALC reads the scan data files, containment weighting factors and the pressure gau'ge calibration constants (see Appendix A-General). The RTD and Dewcell temperatures are then multiplied by their corresponding weighting factors and summed. The program checks each sensor reading to insure that it is within the allowable deviation for that set of readings. The elapsed time from "time zero" is calculated and a true pressure is determined from the gauge readings and calibration constants. The pressure is then corrected for the effects of the water vapor pressure. The weighted average containment temperature, average weighted Dewcell temperature and containment pressure are used

'to compute the measured and calculated leak rate for the Point-to-Point, Total-Time and Mass-Plot methods.

From these values, a regression line is calculated by the least-squares fit method to compute a calculated leak rate for each of the methods. The upper confidence limit is calculated with the "Students T" analysis of n-2 degrees of freedom where n is the number of data samples utilized at each time n.

Program RELHUM is designed to read the average containment dry-bulb and dewpoint temperatures and compute a value of the relative I

humidity in the containment. \

Program INERR is designed to compute the instrument error as a function of average containment temperature, number of RTD sensors, average corrected containment pressure, number of Dewcell sensors, elapsed time and the accuracy of the various sensors Usedo Program PLOT is designed to accept computed data from the programs:

CALC, RELHUM, INERR, and display the results on the DEC VT55-FE graphics terminal.

C. Descri tion of the Com uter Pro ram (Cont'd)

Program INLEAK is designed to calculate the value of the installed leak for the CLRT as measured by the ILRT system. The program requires the operator to enter the various leak rate parameters.

This program interacts with the user to convert the leak rates obtained in weight percent per day to standard cubic feet per minute. The conversion is obtained by calculating the initial containment mass and applying the measured leak rate to this mass. The program also calculates the installed leak.

D. Error Anal sis The instrument system error analysis is based on the Instrument .

Selection Guide (ISG) formula ANSI/ANS 56.8-1981 "Containment System Leakage Testing Requirements." The formula is:

ISG =+-t2I400 ~e P

2

+2 P 2

+ 2 'T 2

X/day where,

'p absolute pressure measurement repeatability error divided by the square root of the number of sensors.

(.0005K) (100 psia)/(1)

.0005 psia

--epv,. ~va or pressure measurement accuracy error divided by the square root of the number of sensors.

= (.54'F) (Q.Q124 psia/ F)""/(6)

.00273 psia From steam tables at dewpoint temperature range 69-71'F et drybulb temperature measurement repeatability error divided by the square root of the number of sensors. ~

(0.1'F)/(24)4 = .0204'F

~ P Test pressure 63.9 psia Test temperature (nominal) 540' Test duration in hours

'2 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Therefore, the ISG= 24008 ISG 2 '2 ISG = + 0.0244K per day is:

.0005 63.9 for 8

.00273 63.9 hour1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months ILRT

.0204 540 X/day s

Additional error calculations are discussed in Section III.C.

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E. Descri tion of Tests The containment was made ready for the Integrated Leak Rate Test (ILRT) with final containment inspection, closure and exclusion areas established at 2230 hours0.0258 days 0.619 hours 0.00369 weeks 8.48515e-4 months on 2-03-85. It should be noted that the Structural Integrity Test (SIT) was scheduled and was performed in conjunction with ILRT. The official start of this milestone was 0145 on 2-03-85 which was the first data set for SIT baseline at 0 psi:g taken twenty-four (24) hours prior to commencement...of containment pressurization. The details con-cerning SIT performance such as instrumentation, data collection, acceptance criteria, etc. shall be transmitted by others under seperate cover and shall not be specifically addressed in this report with the exception of interface areas such as pressure

'hold points, outgassing, etc. During the period between 1200 hours0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months on 1-29-85 and 2230 hours0.0258 days 0.619 hours 0.00369 weeks 8.48515e-4 months on 2-03-85, various tasks were completed including ILRT instrument sensor installation, in-situ testing, temperature survey, Type "B" and "C" rtesting, valve .

line-ups, etc. Various problems were encountered and corrected concerning the DAS/Computer system, sensor connectors proper, cabling connections and buttress platform malfunction. Dewcell number 2 exhibited erratic behavior during this period and was to be closely observed for possible future deletion if the condition continued.

Six (6) portable circulating fans were installed to prevent stratification within the containment with two (2) fans located on the 80', 120'nd 170'levations. These fans were positioned 180'part on each elevation but 60'part with respect to each other. The 115 VAC fans were controlled from electrical distribution panels external to the containment and were designed to deliver,.

6200 cfm at nameplate amperage at 51.0 psig utilizing a 1.5 HP 4

motor. Therefore, the heEt input to containment from these units was insignificant. The fans were tested satisfactorily and were left de-energized until containment pressure was scheduled

1 E. Descri tion of Tests (Cont'd) not to exceed 51.0 psig. Fans were energized at 0750 hours0.00868 days 0.208 hours 0.00124 weeks 2.85375e-4 months on 2-06-85 and de-energized at 2100 hours0.0243 days 0.583 hours 0.00347 weeks 7.9905e-4 months due to air impingement on the Dewcells, and the resultant unstable effects on the sensors proper. A pneumatic test (nitrogen) was satisfactorily performed, prior to ILRT start, on the steam generators (secondary side) up to the MSIVs at approximately 70 psig to identify'nd correct any leaks detected. This pressure was reduced to less than 10 psig to satisfy Chemistry Department's requirements for a nitrogen blanket on this "dry" system and to assure no potential adverse effects on the ILRT test results. The RCS was dry and vented to containment. Just prior.to containment pressurization an additional test was done on the containment personnel lock

'(140'levation) and the emergency lock (100'levation) to re-verify their integrity. Both locks were tested satisfactorily 8

with zero measured leakage.

At 0145 hours0.00168 days 0.0403 hours 2.397487e-4 weeks 5.51725e-5 months on 2-04-85, pressurization of the containment commenced with all eleven (ll) mobile compressors in service having a total capacity of approximately 10,000 cfm. The compressors were oil-free, diesel-driven, rotary screw-type units. These units were connected to the'containment as shown in Figures 9, ll.

'0 and A rate of approximately 3.4 psi/hr was obtained and a'n air inlet temperature to containment of approximately 70'F to 80'F was maintained by adjusting cooling water flow to the aftercoolers and chiller-dryers. With an ambient temperature in containment of approximately 70'F prior to pressurization, this inlet temperature reduced the stabilization time by limiting the temperature gradient. During initial pressurization, a problem with the 140'irlock inner door was experienced. Airlock pressure followed containment pressure with no leakage detectable at the outar door. As a result, the outer door was opened to evaluate the actual point of leakage. When the outer door was opened,

E. Descri tion of Tests (Cont'd) inner door leakage ceased, probably as a result of additional differential pressure across this door. The inner door handwheel was found not to be completely closed. The problem was corrected with no additional leakage or increase in airlock pressure observed.

Pressurization continued with SIT holdpoints satisfied at 10, 25, 40, 55 and 69 psig (the latter being the overpressure test condition). The leak survey team was deployed at approximately 0445 hours0.00515 days 0.124 hours 7.357804e-4 weeks 1.693225e-4 months on 2-04-85 at a pressure of approximately 10 psig.

Numerous minor leaks were detected and corrected during this period but none were of any consequence and resolution was obtained by installation of missing pipe caps on vent/drain valves.

At 0345 on 2-05-85 the overpressure test plateau of 69.0 psig (115K of containmgnt design pressure of 60 psig) was achieved.

At 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months depressurization to the outgassing plateau of 41.8 psig (85K of P ) commenced with one (1) SIT a

holdpoint satisfied at 55 psig. Depressurization was maintained a't a maximum rate of 10 psi/hr. Depressurization was secured at 1320 hours0.0153 days 0.367 hours 0.00218 weeks 5.0226e-4 months at

'approximately 41 psig. This started the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months stabilization period at 85X P . During this period, no additional leaks were and airlock pressures remained at 0 psig.

a.'bserved An unofficial "ILRT" was also performed during this period with excellent results. Consequently, the'leak survey team was secured until further notice.

Pressurizationto peak accident pressure (P a ) commenced at 1330 hours0.0154 days 0.369 hours 0.0022 weeks 5.06065e-4 months on 2-06-85 with the leak survey team again deployed.

Pressurization was secured at'1630 hours0.0189 days 0.453 hours 0.0027 weeks 6.20215e-4 months at a pressure of approximately 50.0 psig. A 0.8 psig "buffer" was intentionally installed to assure pressure did not fall,,below P due to temperature stabilization.and/or potential leakage. The

E. Descri tion'of Tests (Cont'd) pressurization line to containment was vented to atmosphere and the stabilization period commenced at 1630 hours with stabilization achieved and all criteria satisfied at 2045 hours0.0237 days 0.568 hours 0.00338 weeks 7.781225e-4 months .

The ILRT was officially started at this po3.nt (time zero) and a meeting was later held with NRC representatives for concurrence on a reduced duration test of eight (8) hours, minimum. At 2340 hours0.0271 days 0.65 hours 0.00387 weeks 8.9037e-4 months number 2 Dewcell was deleted from the test data due to erratic behavior. With on-site NRC agreement subsequent to a review of, all data and all requirements for both ANSI/ANS-56.8 (1981) and BN-TOP-1, (Revision 1-1972) satisfied, the ILRT was successfully completed at 0530 hours0.00613 days 0.147 hours 8.763227e-4 weeks 2.01665e-4 months on 2-07-85 for a total duration of 8.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months . 'he results yielded a calculated Total-Time leak rate of 0.0063K per day and 0.0292X per day

'at the 95K upper confidence limit. The calculated Mass-Plot leak rate was 0.0056X per day and 0.0092K per day at the .

95K upper confidence limit. It should be noted that during this period there were no significant diurnal effects due to overcast sky, minimal sunshine or light rain. Test results being satisfactory, the leak survey team was terminated.

The CLRT commenced at 0545 hours0.00631 days 0.151 hours 9.011243e-4 weeks 2.073725e-4 months following the successful completion of the ILRT by installing a fixed-orifice "leak" for verification of the ILRT data of 7.83'cfm which is approximately equivalent to'.1X per day (La ). The CLRT successfully completed at 1115 hours0.0129 days 0.31 hours 0.00184 weeks 4.242575e-4 months on 2-07-85 for

'as a total CLRT duration of 5.50 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months (including one hour for stabilization). The results yielded a calculated Total-Time leak rate of 0.109K per day and a calculated Mass-Plot leak rate of 0.095X per day. It should be noted that no data sets or individual data points were rejected for either the ILRT or CLRT.

E. Descri tion of Tests (Cont'd)

Depressurization to atmosphere commenced at 1125 hours0.013 days 0.313 hours 0.00186 weeks 4.280625e-4 months with SIT holdpoints satisfied at 40, 25 and 10 psig. Depressurization was again maintained at a maximum rate of 10 psi/hr. At 0745 hours0.00862 days 0.207 hours 0.00123 weeks 2.834725e-4 months on 2-08-85, 0 psig containment pressure was achieved followed by containment air sampling and personnel entry at 0850 hours0.00984 days 0.236 hours 0.00141 weeks 3.23425e-4 months on 2-08-85. All sumps were verified to be dry as they were prior to pressurization. The exclusion areas were removed and no abnormalities were noted. The nitrogen blanket on the secondary side (less than 10 psig) was confirmed to have no indicated pressure decrease or increase and the ILRT test log was closed at 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on 2-21-85 following restoration.

~~

/

IV. RESULT AND VERIFICATION The Type A Integrated Leak Rate Test was conducted for a period of eight and three quarter (8.75) hours starting at 63.971 psia (49.729 psig) with a total of thirty-six (36) samples or data sets taken and ending at 63.889 psia (49.647 psig). The results of a computed least-squares statistical fit of all data revealed a fitted Total-Time Leak Rate of 0.0063X per day with a 95X upper confidence limit of 0.0292X per day and a fitted Mass-Plot Leak Rate of 0.0056X per day with a 95X upper confidence limit of 0.0092X per day.

Following satisfactory completion of the ILRT at P , a five and half (5.50) hour verification flow or CLRT was performed a'ne with' total of twenty three (23) samples or data sets taken.

This test was conducted by superimposing a known fixed-orifice leak approximately equivalent to La (0.1X per day) of 7.83 scfm.

The calculated Total-Time Leak Rate for the CLRT was 0.109X per day and the calculated Mass-Plot Leak Rate 'was 0.095X per day.

,r

-No 'data samples were rejected in computing the results for either the ILRT or, the CLRT and all data were recorded at equal fifteen (15) minute intervals.

V. CONCLUSIONS The Integrated Leak Rate Test at P a

(49.2 psig) provided acceptable results as evidenced by the computer printouts in Appendix A of this report. The computed leak rate is well within the specified limit.

The acceptance criteria for the ILRT is as follows:

1 The maximum allowable operational leak'ate shall not exceed 75K of L (0.1X per day) at a pressure of not less than a

P (49.2 psig):

0.075X per day 2 The accuracy of the ILRT is verified by a supplemental test (CLRT) where the difference between the containment leakage rate measured during the CLRT and the ILRT must be within 0.25 (L ):

L = L + L + 0.25 (L )

Leak Rate (L )

~Xer 24 hre h wei ht ILRT Fitted 95K UCL

'Total-Time Analysis 0.0063 0.0292 .

'Mass-Plot Analysis 0.0056 0.0092 CLRT

'induced flow 7e83 scfm (L or 0.1X)

Leak Rate CLRT er 24 hrs b wei ht

'Total-Time Analysis 0.109

'Mass-Plot Analysis 0.095

V. CONCLUSIONS Cont'd CLRT Limits CLRT Limits X er 24 hrs b wei ht Total-Time Anal sis

'Upper Limit 0.1313

'Lower Limit 0.0813 Mass-Plot Anal sis

'Upper Limit 0.1306

'Lower Limit 0.0806 The computer generated reports based upon verified data substantiate for both the ILRT and CLRT that an acceptable test- has been performed in accordance with 10 CFR 50, Appendix J, -ANSI-.N45.4 (1972) and ANSI/

ANS 56.8 (1981).

VI. FIGURES

t 1

-2U-Figure 1, RTD & ME LOCATION

~ r >r/ >IO4' cV O O O O Oi O O O I e N O.

e O

~

O . 8 EL.245" Top oF r~ c Rpe 6 Fop oI'poLLET'AILcc RIe 6 I 6 M II/.~

NlAR CPA IIX' Srr/ud vud MAtu HOOK PALM 6 ~ M.ZOIPse(OIK) Cl R/f /r

~~

eorrou.oF oAe a Iee'-6' 011 CF CIROCR CI. ROT <ilk ELRO6 e 0 0 EL. 1 ceo// vor/>/fc fcc4 91,'16 Ch r/VO rfu CO O ~

O rrrr crc cd/

O O O f/Vj/' A/ EL 003 rp Rrccc/

015 004 178'c/v/p uw rcA/

014 r.. ~n. 5 iC /S/> dr n'/Seto't Srrr 013 VO/

EL'-153 019 ~~

~~

~ I

~II>t>AI

.018 ~ I>>>> ~ >I >d >

)

) f/ A. /44 'ftt'A>

017 VOPA/fC fr.u 006 EL-130 ',

~ r-

>. Tj

~ r 005 ~~ ~

~

r ~ >r'o

'> ~

020 EL-.11Q'L-107 oza SC. / dfoduo f/ fl. /4 t'C

~ ~ ~ ~~

~

022 I

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~

I P.

~ ~

I I I~

023 glq/ ~

~ I ~

~ ~ '

J t CC.II I

024 I t

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, 'I ~

., AP. C A'P/P r

, pi rr frIcSJ

~

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sfu./rrr 6 rfcA/ zcrccro//erne S/Oe/ ~ \

~ ' C/VA'AI/IrC / t ~, S:O-/A cc ee:o fi) 4 ~ r " /A/COPC

~

~ ~ ~' ~ ~

, /vsr//vpfcvflr/o NOTE:

RTD's 1-6 are elevated above the polar crane at approximately elevation TEMPERATURE .ELEMENT (RTD) from containment spray headers) 245'suspended DEWCELL ELEMENT (ME)

t h,+

II Kg

RTD & ME LOCATION CavfAICIPIC'ill i/Coo TE-024 VDRP/AC ACCI/II/Cthef//'

ef ccf PI>>VCV CO/e/ (RSPCP vooppf c Acl/'eII/cr/IefreR p/vcv eo/f IRCRJ (frp f pccci CONIOC NOOCICC SIC COOLWf

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sip

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~:

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~

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~ I

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Ib P~OP ac Cl I!7 IOOI'hr I>>~ ~'I>>~ i IIC PINIP 5(l Of 5 fcirfAIIIIC

~ >>

0 IIID I OPCNNIS tMCACCNCr Ni ICN

~

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r

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//.VCV O'OI fRS/fl pf/O A'M ACIIDCICt/IAArAR vACeel/D(Ra/f5 TE22 Alps'lls AN c /rs>> ME-005 TE- 023 ME-006 ~ >>

PLAN AT EL 100'-0" TE(a 020 through 024 are located at EL.107'E 005 and 006 are located at EL. 110'

I RTD 6 ME LOCATXON CallrA4lrICAIT AI{dd A/IS SISTFIV lode/A{ ice/ )AAK//Aocd(A2A/)

if nA/POWSP/. ~ TE=019 Ceo'erkVCTIdcr dreAIIAI4 1

AC/I AANCI/ AOIO (ttdr) ~

COIIIP. illtell AL',c<<c f<< ~ ~

naa POCC IIAs/t ~ ~

tAIIIT IN/ICIIOW llIVK Ib P$

rAOJ /IRt Ndtl CTJI P NOVABCC )Ct

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' ~ ,~ OVPPORT FRANC

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IAact i J 511141

~

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)

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tiff'N/CCIIONIANK dl EE-017

~ .~c ~

c A/>>I patcclc Aw IICN lait(ttd{ NORAAAC ACI/ AI IICKMOIO(gtdc)

TE-018

/%0 Ilcl'

{TIP.IIC wry. e/cc4 PLAN AT F CA ~ ~ c I ~

/6'E's;817 I 0'-0 are located at EL.130'

'-thorough 019

r Figure 4 RTD 6 ME LOCATION rttfwcEf$$ NGRNAI. 'cdurl/u//cur scoo AIU

&NENIGIAITZIG I AISS J TJ Tr~ - TE-!008 Sdd/8 //Sfd// IITC/.I 54IZIY IICIICrror/ TAICC'4 sk as TE-007 SJ4 scrc//R //Arc/v Ia Ad CRANE MAS'I SVrlsORT Is/ M CCN Sa&$ C RSCsatd/ j'O/sS/ CNI CRA/IE M ZCN GOC Aa/'d

'I SS CrOS /VS/CO uTCSSRf/

IIW/4.AC/Cs'a S/VS STOSrroS 4'CSC JCIO Crr Crs AIRZRNYS CION.CIZBII ACTA ICCTSCZI/vol

'II NAX. / AAIc/I Aul/AJCG Srdd sCSV T.CZ&.QJCR ld AOI IRR/CL l I K NOON

~o/J/

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r//Z///C

//ASP.'

VCV r/PARI f OCal SAAsAO/CT C/AC Cl NC'l(HC II/IIr C /u/

o/u Ir/IACCI)

/ASS/ CO/ ~5ffNftf fCC CIRNu~WAVI A& CRA S/EA// d Vs d 8& CRANE M ZCN GOSO MAST ~RT

~ I Ic MASt SaI B CRANE M'EN OO1Ao/B XCZO. CLIA&IIrr M4CN GO E I&CRANE CCN ~A II ZC44, CZ. Jct I 0

\ CA/54 W-/ j a

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CO/6 IC) saTO/l

' J v/

r ZCZRNNNT IASOORN RAZWORQ A&IRK At CLIS&C'

~ a%r J Q ~ Ia

~~

TE-009 rZCI CSIITI///klf/IT AY ///A//dR, C~) IICIKffr NAIICI'a a Slff III/fCflGIIfAICIC fA CAfflY IACAstfrOW fAHA'54 TRZsICEZS HORNJ4.'f scccss AAC/IICR f/rdu N.IOIfOld E- 010

/IAT/'GRu cc./cdII/ To rCSr/"OR/f CC.IS+ Cs POLAR C IIAN8 cdd Accc55 n.lrrasAA Cl IPtIC TE-Ol1 PLAN AT EL 140'-0" SEAS 41 I'sORO TE- 012 NOTE:

RTD's 7-12 are lowered from the crane to an elevation approximately below the top of rail.

30'he crane TE's 007 through 012 are located at EL.191'

~ ~,

~~

i II f

Figure 5 RTD & HE LOCATION fRC<CC ISS HOISCAL C Jl/fJ/All//f/r /IcoO Alv IpHCIpIGIAIYCIO

)

ups'ar/r TE- 016

~ k COP/P //JfCV 1RI/O

$ 4flIY IH/ICIIOH l

~

TE- 013 fJ4 cof//p /lAro//

C JS CRAHC MAST SUPPORT ~

M CCH HOS C AL XO/ COrm JO CAAHC M CCN ~ OO4 Act'8 BJCrOr VCJO ueo/NP'

~ k4/J Sf/Ci J/

SCARC 4/VS JfO/frfBC

~ I I '

ICIO Cfl SC ALSQASU' ClDICJKRW J/fJ IIIII/CC/I/41

' '/C AAJC/I kfflCJJAI

'I"-/ CSIN'AX, J/f'CA/

AOI mfCH/

m o/f/

ALA.NXX

'I RA/0 ILIIHHOCH '>O/P Ti>VCL r-.

I Pnrbmf'tOL rAHa Ca'ac I Ct I A/ .f/AO it ..

I VCTJAWIO NS-'JO/J ~

IIMYS I g/JI/CC QVCV./IO h'J CA/ IRC/U

.HC (CHAL SSAMOIB (lJC u I 8//II//f/f I'f /IJCCII CICCISICui~JVS

/APCC.CO/8 rfW r I SCS JS CIIAHC MIST L'APORT HCTf'/CJ/f JS CHARS Sl/HOISrl M 1CH ~ OOS 0 ~ I ~

MASI Sf JS CIIAHC I+tCN~AAe/8 MRS.11 118'IO M4CH GOSSIP

'IO C AAHC M ZCN C/Of* ZRRCL If OCR'l A/JIH SICIJC fffl/I I

re/A lb)

SHIIT P lw

'pr '\

L:0 /

~

~ ~I d

I

. 1.,

'L C ASO/C AT SL INC LADOeN ILJOTORU

, ~ 1/p

~ ~ D. r~ ~~

l. Lrl4 M ~ P f".gg'rL 8 CJIffJ///If/If/

J I'/QO/B nLr'fC/I SANDY IH III'JHJOCf IOH f1 AM( SC

'I 11111Y IAU$1ÃW fJHH Sb fRS~SS RCC/SS C JPOE/T P/Ioff a.ICNIaa NOANAL'IU TE-014 pc/rro/Irf fc./s JII/ ro tCJ P'O/Ilrf /C. IPf'r Ibb PDCR/I CRRIIB CJB JCCCSS rLJffORIC TE-015 FC IP/LCr PLAN AT EL I40'-0 SCAL CI I ~ <0~ 0 TE's 013, 014, 015 and 018 are located at EL.153"

4 t

zigure o RTD 6 ME LOCATION FRC<CCTSS NOFWIL Co/ITJIv/FAIT Jttoo ~

AFU ISHCIFFGtA OOAO I A//z Crore oou/r vJfcv (Rt/.)

~ 4 ME~1 FJOF-C'IFV/r /u re JS C:llAHC MASt 5VPPCKf M ]CD io05 C o/ YoARI Jtt CRAKC M.CCN GOA AcrO p),

cxcror wtf u Tcxuew g

/'k/SJ

~

5/'4/R cut O CCRC C/VO CfafJOO NAX C~l Icto trf cc sttcwstT o AITAItfft/TSIACI AAIF/JSA1 Cfog CCV A feCK XIALCVAA I AtfI T RA%1.

I &/at/

wOl/I HIIKKOCN ~ tale 5

'tSAVS L co'ce 'enoir I POCK. SM R'AC Vma. rA/Ia V&o C'ArtO SCA JGIA p

Cl VCV JO FO

/IACp.' IRARF Sdl JO/8 KrAC a Ndl/&

IfIt/

CII //V a/Jt /tJtc/I ~ Ul

/AOC/./OIO /,SFCIIFTC Ctftffltm~~Jrr C'/CAI/ dCAI JS CAAKC MASt LP%OWf JS CIIAK~C SCWrfa M ZCN GOSO ~ I ~

MASf Sl JO CRAKC M~K GOAAa/5 aa.CC TASSE M<OK GOSC/l ZCK ~A CRAKC 5 MG,CLIFF 0 AIWFF cff/J/ (nA ecoIA ICO

'COFSCKT LAOOWN RATF OR@

AWtC AT CL IQf%

IIMCC 5I/f/S V CFKrk'AQIF ~

OP/I J V lll'J Fifo/r) CINAIIS cA/clY IAIRCTION FA/ef 54 RCCCSS t Ace/If IIIIIW IOO'CUCC Sl/CTY I/IJICTIOII T FRCMCCSS N.TCN<aS NORUAL'FU Qg Zl

/

I'E-rt Jrfo/ll/ rL/Aollfro 002 rc JT/'o/IAF CC./&'P POCPrf Accc$ 5 TLAffoo/o Clf/IIIC'od cl /PPS4" PLAN AT EL l40'-0 SCAS Ct I MO'0 NOTE:

ME's 1 and 3 are elevated above the polar ME's 001 and 002 crane at approximately elevation 245'suspended are located at EL.245f from containment spray headers)

P t'

II

'N

RTD & ME LOCATION FTTC~CCCSS HORHAL COAlfJIVHCVP PCDCf AFU Q fglfKrN(P2JO VJ'4'YJTf~

/CO

~ 4 ceu/r NJfcv (RLf.) ~AC/C/)'ICI(Cr/Tu TAFCC'AT Pj ME-003

~ "CA

\

ran COulr I/RE JS CRAHC MAST SVfPCHf M.CCH iaOSC

~

~An (o/cv J8 OIAIIC M XCH GO4AcrS AIMIR4NC,2I

~

'hic soc ouAJJP AIYcsMv c/ve Jfef)oc ACCI CRT'BCMCFR clat.~ Jill/cRcxl~

lb~ NJlAkV

'~ / I i Cfog 6CAt

~( A~ TR~ INC ILLSV~LN 4 I M~ICLCI OIII .COle I

I'

r Ca' I I / p P'I FLIC,SM R'Ale cymar rwa I

-v vAotA u SW0 iIL.

ICAL I AT SQ 1CVl I

~ IJ guucc VCV fere

/IACh.'iduHI N~ Sea.Jo/e CIACu CWITJ/AN OIII QJCQ) NI PAucY relent ccrc( Hu~~av urJI

~5rrulflf'RAW JS CRAHC IKE\T LIHART AS CRAHC M ZCH GOSO ~ T ~

MAST SJ JO CRAHC MWH OOAAcrO ICS SLdCSSIO MQCH GOSC

%8CRAHC 7ACi.rr-)4950' M CCH40SA 4 '

~

HAW Attar (F(A r

HT Pil<

~ '~i.

COIO l4)

I' o Al ae/A lb)'< AS'TSL E

KOJDlCÃf tAOONM RJCTOPg IQf4 O'5 I I 'I IIII)TS~C g~I ~

AIP I/5

'Sf I)

( 1 T CIHFAWIIr 4fWA'NC1%

('TCR) aver rruuar

,. ~ r

<<Cr'A/ZIY SA((TY IIV(C(lou (A hCCCTRW MVfSS tRt4CCXSS HORME,'FO RCCYSS CA7ere fedW Vm)Twas Q<

pzrrpoRN rc,/4 JI4'o ME-004 tz Jo'ouphe rc.l&'

POLAR CRANE Cfe ACCCSS I'LA(fetor A.I~IC PLAN AT EL 140-0 SCARC I I'HOIO NOTE:

HE's 2 and 4 are lowered from the crane ME's 002 and 004 are to an

', ll elevation approximately 30'elow located at EL.178' the top of th'e crane rail.

f

Figure 8 ILRT MEASUREMENT SYSTEM SCHEMATIC PEN ETRATION NUMBER RTD'S DR~~ T~ERATU~

DEN 6

DEWPOINT TEMPERATURE

. ILRTMS 9]

(DAS /COMPUTER PRESSURE 62B FLOW 62C

Figure 9 PRESSURIZATION SYSTEM Rented V007 V019 Conptessot (Typ. of 12) V008 V020i V009 V021 V010 V022 PI TT 5

Rented Steel Braided Flex Hose vith VOI1 V023 Can-Lok Fittings V03L (Typ. of 12) V024 V012

. V013 V025 Cont. or V014 V026 Page 2 Male Can-Lok Fittings vith V015 V027 Dost cap of chain (Typ. of 12)

V016 V028 V017 V029 VOLS V030

TI 8

Cooling water to drain or" Connect to flushing bypass V040 V041 around oil-hfter-cooler Uater moisture separator Beps'xatol'rain Refrigerant hir Dryer PI Tl 29 26 C den at Drain To Q Drain O 0 V032 V045 V031 V044 Cont. froca Page I .

Cont. on J4 Drain Page 3 V033 V035 V046 V041 V043 Drain Refrigerant hir Dryer hfter-cooler moistu're separation V038, V039 Female fire hose fitting Cooling uater supply (yard fire mal

II t

1 h

II i,

htwosphcre BloudoMn Silencer V049 PSV-1 V052 V056 VQ52 After Filter Cone. frow V048 V050 V053 pg. 2 of pi 2

V051,

l. Valves that are blacked shall be closed.

2. Valves that are noe blacked in shall bc Orain open ~

-39.

VII. APPENDICES

I APPENDIX A COMPUTER GENERATED REPORT

1.

STABILIZATION

I.

ARIZONA PUBLIC SERVICE COMPANY PALO VERDE NUCLEAR GENERAT ING, STAT ION RAW DATA SUNMARY REPORT I

SCAN NO. DATE TINE PRESS 1 PRESS 2 RTD ¹1 RTD ¹2 RTD ¹3 RTD ¹4 RTD ¹5 RTD ¹6 RTD ¹7 RTD ¹8 RTD ¹9 sn.io4 37 142 30 58.022 58.098 73.271 73.196 73.054 73. 1 ji5 !73. 175 72.995 72. 981 72. 995 7? <24 SD. 105 37 14 45 S8.828 58. 898 73.613 73.526 73.417 73. Q9 l73. 593 73.'336 73. 324 73. 358 73 2 sn.io6 37 152 0 59.628 59. 696 73.904 73.855 73.677 73. 817 73.872 73.617 73.593 73. 681 73. Sm>

sn.io7 37 152 15 60.418 60.485 74.095 74.086 73.941 74. Oi54 74.079 73.764 .73.796 74.018 73 829 sn.ioa 37 15230 61.211 61.270 74.317 74 '84 74.102 74.261 74.276 74.072 74.009 74.089 74.O44 SD. iv9 37 152 45 61 '97 62. 052 74.464 74.433 74. 258 74.4i15 74.443 74.220 74.1r25 74. 284 74. 214 SD.110 37 162 0 62.783 62.834 74.678 74.580 74.401 74 '69 74.630 74.322 74.319 74.411 74.371 SD.111 37 162 15 63.247 63.301 74.279 74.189 74.035 74.220 74. 240 73.970 74.066 74.134 74.009 Sn.112 37 162 30 63.473

'78 63.527 73.471 73.425 73.226 73.472 73. 445 73.194 73 '13 73.391 73 '33 SD. 113 Sn.114 37 162 45 63 63.432 63.376

72. 326 72. 311 72.016 7?. 213 7? ?5~ 72 '64 72. r210"; 7r2. 334 7?.175 37 172 0 63.323 71.510 71. 513 71.3vl 71.461 71.505 71.295 71.S92 71. 723 71.632 SD.115 sn.116 37 17215 63. 288 63.342 71 '55 71.093 70.907 71 008 F 71. 026 70.915 71.191 71. 3r24 71.?.37 37 17230 63.264 63.318 70.774 70.793 70.631 70.741 70.733 70.613 70.933 71.053 71.033 SD. 117 37 63. 247 63.300 70 '52 70. 594 70.375 70 '62 70.552 70.431 70.7?7 70. 881 70. 872 Sn. 118 37 18 0 63.233 63.287 70.423 70.331 70.352 70.457 70.465 70.329 70.594 70.768 70. 6ai SD.119 37 18 15 63.222 63. 275 70.323 70.326 70.295 70 '69 70 '75 70. 239 70.510 70.652 70. 541 Sn.120 SD.lr21 37 37 18230 18245 63.213 63.204

63. 265 70.259

63. 257 70.198 70.216 70.108 70.224 70.259 70.329 70.217 70 '65 70.555 7O.463

70. 121 70.202 70.246 70.079 70.320 70.498 70.407 SD.122 SD.123 37 19 0 63.196 63. 249 70.111 70.076 70. 057 70 '35 70.199 70.063 70.266 70 414 F 70.326 37 192 15 63.190 63. 243 70.027 69.990 70.018 70.051 70.095 69.998 70.167 70.385 70.260 SD.124 37 192 30 63. 134 63. 236 69.975 . 69.391 69.986 70.021 70.100 69.931 70.150 70.313 70. 217 SD. 125

'7 37 192 45 63.179 63. 231 69.966 69 '05 69.886 69.960 70.008 69.879 70.141 70.256 70. 169 Sn. 126 202 0 63.173 63.226 69.892 69 '33 69.871 69 '28 . 69.975 69.838 7O.04O 70.190 70. 12 SD. 127 37 202 15 63.168 63.221 69.870 69.807 69.8S7 69 '03 69.941 69 '19 69 '93 70.182 70;086 Sn. 128 37 20230 63.164 63. 216 69.348 69.792 69 '93 69.853 69.394 69.775 69.963 70. 124 70.045 SD. 129 &7 202 45 63.159 63.212 69-795 69 '63 69 '43 69.815 69.885 69.761 69.921 70. 114 69.99O

li tr

I I

ARIZONA PUBLIC: SERVICE COMPANY VERDE NUCLEAR GENERATING STATION'ALO RAW DATA SUNt1ARY REPORT' SCAN NO. RTD ¹10 RTD ¹11 RTD ¹12 RTD ¹13 RTD .¹14 RTD ¹15 RTD ¹16 RTD ¹17 RTD ¹18 RTD ¹19 RTD ¹20 SD. 104 72. 906 72. 906 72.950 72.181 72 '90 72. 493 72.003 71 ~ 21 7 71.821 71 ..490 71.374 SD. 105 73. 303 73.283 73. 388 72. 398 72.740 72.813 72.221 71.374 72.0 9 71.701 71.550 SD.106 73. 567 73.582 73.591 72.576 72 '82 73.043 72.4'57 71. 484 72. 212 71.849 71.694 SD.107 . 73.848 73. 829 73. 817 72. 789 73.129 73. 21'9 72.653 71 '89 72. 370 71 '81 71.781 SD.108 73.962 74.037 i4. 223 72.956 73.321 73.384 72.796 71 '01 72. S34 72.111 71.905 SD. 109 74.203 74. 186 74.426 73.'106 73. 460 73e 553 72.964 71 7<9 72 670

~ 72. 227 71.963 SD. 110 74.362 74.433 74 '64 73. 259 7 3 63'5

~ 73.645 73.109 7 1 ~ 865 72 792

~ 72.338 72.070 SD.lii 74.145 73.939 74.266 73.020 73.419 73.420 72. 959 71. 6'56 72. 721 72.355 71.765 SD.112 73.300 73.165 73 '39 72.685 73.022 73.063 72. 572 71. 336 ~ 72. 503 72.209 71.588 SD.113 72.222 72.029 72.326 72. 126 72 '16 -

72.348 7 1 ~ 807 70.95O 72.113 71.913 71.420 SD.114 71.664 71.528 71.638 71. 615 71.913 71.765 71. 476 70.771 71.820 71.655 71.246 SD.115 71. 327 71 '75 71 ~ 269 71. 231 71.562 71. 441 71. 052 70.692 71 '71 71.472 71.O49 SD.116 71.113 70.855 70.990 71 ~ 015 71.339 71 '99 70 '34 70 '03 71.382 71. 237 70 '86 SD.117 70.965 70.716 70. 803 70. 852 71.188 71.025 70. 617 70.536 71 255 71. 095 70.785 SD. 118 70.730 70 '08 70. 698 70 '15 70.866 71.003 70 '59 70.474 71. 106 70.956 70.713 SD.119 70.613 70.'538 70.565 70.599 70.776 70 '24 70.407 70.422 71.029 70.866 70.634 SD.120 70.558 7O.49S 70.512 70.465 70'.681 70.867 70.294 70.361 70 '44 70.761 70.544 SD.121 70.440 70.417 70.405 70.431 7O.64O 70.776 70. 246 70.298 70.903 70. 649 70.510 SD.122 70.382 70.326 70.381 70.362 70.546 70.719 70. 147 70.256 70.863 70.578 70 '11 SD.I23 70 '26 70.248 70.280 70. 288 70.515 70.640 70.103 70. 225 70.805

'52 70.533 70.365 SD.124 70 '78 70 '93 70.277 70. 254 70.503 70.362 70.561

70. 513

- 70.083

'90

70. 185 70.135 70 70.727 70.449 70 417 70.318 70.228 SD.125 70.253 70.230 70. 202 70. 172 ~ 69 F SD.126 70.187 70.204 70.159 70. 163 70.350 70. 472 69.987 70. 103 70.678 70.382 70.248 SD. 127 70.167 70.196 70 '23 70. 114 70.352 70.440 69.912

'97

70. 074 /0.637 70.358 70.149 SD ~ 128 70.108 70.011 70 '56 70.088 70.283 70.361 69 .70. 018 70.616 70.340 70. 153

.,SD. 129 70.066 70.054 70.051 70.062 70.338 70 '32 69.894 70.025 70.613 70. 271 70.114 ARIZONA PUBLIC SERVICF. CONPANY PALO VFRD'E NUCLFAR GFNERATING STATION RAW DATA SUGARY REPORT

C I

e ~

8 I ZOhtA PUBl. IC SERVICE CONPAWY PALO VERDE NUCLEAR GENERATING STAT IOhl RAW DATA SUNNARY REP ORT t

I SCAN hlO. RTD ¹21 RTD ¹22 RTD ¹23 RTD ¹24 DEW CELL ¹1 DFW CEI 1.. ¹2 DEW CELI tt3 DFW CFLL ¹4 DEll CELL ¹5 DEll CELL ¹6 SD. 104 71. 517 71.592 71.307 70.643 64.360 63.398 64. 482 65. 325 63.133 63.777 SD. 10.> 71.615 71.759 71.489 70.863 64.657 63.655 64.630 65. 628 63. 145 63.783 SD. 106 71.788 71.881 71 '52 71.038 64.932 63.960 64.817 65.928 63.409 63. 601 SD. 107 71.900 71.991 71 '74 71.159 6 ~ 1 O 64 '24 65. 016 66.146 63.261 63.972 sn. 108 72.001 72.102 71.910 71 '01 65.377 64.386 65.179 66.351 .

63. 19$ 64.358 SD. 109 72. 064 72. 197 71.994 71. 427 a5. 614 (4.585 65.350 66. '561 63.604 64.189 sn. 110 72. 119 72. 271 72 '38 71 '31 65.812 64.869 65. 515 66. 729 63.786 64. 104 SD. 111 71. 841 72. 190 71 '51 71.716

71. 39.> 65.850 64 '92 65.635 66. 757 63.472 64.469 SD. 112 71. 594 72.018 71.221 65.826 64;8$ 0 65.480 $ 7.019 63.629 $ 4.569 SD. 113 71. 272 71 '01 71. 342 71.002 65.435 64.602 65.730 66. 639 64.296 65.373

~

sn. 114 71.104 71.443 71. 191 70.813 65.101 64.384 65.78+ 66.,734 64.498 SD. 115 . 70.982 71 ~ 316 71 ~ 128 7O.7O9 64.958 64.184 65.547 66. 55f 64.561 65.354 SD. 116 70.864 7 1 ~ 189 , 71.078 70.607 64 '81 64. 190 $ 5.460 66.543 64 339

~ 65.484 SD. 117 70.774 71. 057 71.005 70.515 65.029 63.978 65.4f6 66.381 64-439 65. 202 sn. 118 70.715 70 '91 70.938 70.442 64.898 63.931 65.370 66.210 64. 231 6.>. 235 SD. 119 70.713 70.970 70.852 70.320 65 '83 63.783 65.356 66. 247 64 ~ 292 65. 417 SD. 120 70.626 70.872 70.759 70 '56 64.854 63.726 65.362 66. 290 64. 129 65.426 SD. 121 70.585 70. 808 70.700 70.169 64.918 63.739 65.379 66. 168 64.204 *65. l 27 sn. 122 70.536 70.779 70.$ 49 70.097 64 '71 '63.595 65.132 6$ .24$ 63.957 65. 196 SD. 123 70 '81 70.698 70.599 70.025 64.849 63.705 65. 264 66.230 63. 874 65. 110 sn. 124 sn. 125 70.426 70.394 70.655 70.599 70.571 70.507 69.992 69.944

$ 4.906 64.941 63:616 63.768

65. 237 6'60 64.096 65. 171 65.025 66. 186 63.954 65.

Sn. 126 70.361 70.573 70.430 69.891 64.804 63.586 65. 129 66.122 64.033 068'5.196 SD 127 70.315 70.561 70.451 69 '19 64.820 63.790 65.'14 1 66.049 64.149 65.034 sn. 128 70.265 70.529 70 '04 69.802 64 671 63.621 65.039 66. 050 63.836 65.208 6'09

~

SD. 129 70. 260 70. 510 70.381 64.712 63.555 65.206 65. 972 63.864 65.000

J,

~ ~

ARIZONA PUBLIC SERVICE COMPANY.

PALO VERDE NUCLEAR GENERATING STATION ILRT PROGRAM REPORT STARTING DAY 37 STARTING TIME 14:30: 0 STARTING SCAN SD. 104 ENDING SCAN SD. 129 POINT TO POINT TOTAL TIME MASS PLOT SCAN ELAPSED AVERAGE AVERAGE MEASURED CALCULATED MEASURED CALClJLATED UPPER MEASURED CALCULATED UPPER NO. TIME TEMP. PRESSUR E LEA)( RATE . LEAK RATE LEA'K RATE LEAK RATE CONFIDENCE LEAK RATE LEAK RATE CONFIDENCE (HR) (F) (PSIA) (WEIGHT PERCENT PER DAY)

SD.104 0.00 72.43 58. 787 SD.105 0.25 72. 72 59.601 -0. 128E+03 -0. 128E+03 -0. 128E+03 -0. 128E+03 0.000E+00 -0. 128E+03 -0. 128E+03 0.000E+00 SD. 106 0.50 72. 96 60.408 -0. 126E+03 -0. 1 26E+03 -0. 128E+03 -0. 128E+03 0.000E+00 -0. 128E+03 -0. 128E+03 0.000E+00 SD.107 0.75 73. 15 61.205 -0.124E+03 -0. 124E+03 -0. 327E+03 -0. 127E+03 -0. 127E+03 -0. 127E+03 -0. 127E+03 -0. 125F+03 SD.108 1.00 73. 33 62.005 -0. 122E+03 -0. 122E+03 -0. 127E+03 -0. 127E+03 -0. 127E+03 -0. 127E+03 -0. 127E+03 -0.127E+03 SD.109 1.25 73. 47 62.798 -0. 1 21E+03 -0. 121E+03 -0. 127E+03 -0. 127E+03 -0. 127E+03 -0. 127E+03 -0. 127E+03 -0. 127E+03 SD.110 1.50 73. 60 63.591 -0 119E+03 -0. 119E+03 -0. 127E+03 -0. 127E+03 -0. 127E+03 "0. 127E+03 -0.127E+03 -0. 127E+03 SD. 111 1 75

~ 73.34 64.060 -0.758E+02 -0.980E+02 -0.121E+03 -0. 124E+03 -0. 119E+03 -0. 121E+03 -0. 122E+03 -0. 116E+03 SD.112 2. 00 72. 80 64 '88 -0. 441E+02 -0. 719E+02 -0. 112E+03 -0. 1 19E+03 -0. 109E+03 -0. 112E+03 -0. 114E+03 -0. 104E+03 SD.113 2. 25 71. 97 64.192 -0.285E+00 -0.386E+02 -0.993E+02 -0.110E+03 -0.963E+02 -0.993E+02 -0. 102E+03 -0.873E+02 SD.114 2. 50 71. 47 6'4 ~ 136 -0.832E+00 -0. 162E+02 -0.89SE+02 -0. 101E+03 -0 '44E+02 "0.895E+02 -0.902E+02 -0.736E>02 SD ~ 115 2. 75 71. 14 64.101 -0.793E+00 -0.720E+00 -0. 814E+02 -0.922E+02 -0.743E+02 -0. 814E+02 -0.796E+02 -0.626E+02 SD. 116 3. 00 70.92 64.077 -0.336E+00 0.103E+02 -0.747E+02 -0.838E+02 -0.657E+02 -0.747E+02 -0.705E+02 -0.537E~02 SD. 117- 3. 25 70. 76 64.060 -0.427E+00 0. 182E+02 -0.690E+02 -0.760E+02 -0.583E+02 -'0.690E+02 -0 '26f+02 -0.465E+02 SD.118 3.50 70.64 64.046 -0.209E+00 0.239E+02 -0.640E+02 -0.689E+02 -0. 519E+02 -0.640E+02 -0.558E+02 -0.406'El02 SD.119 3. 75 70.56 64.034 0.302E+00 0.282E+02 -0.598E+02 -0.624E+02 -0.462E+02 -0.598E+02 -0.500E+02 -0.357E+02 SD.120 F 00 70.48 64.025 -0.232E+00 0. 312E+02 -0.560E+02 -0.566E+02 -0. 41 1E+02 -0.560E+02 -0.450E+02 -0.31/E+02 SD.121 4. 25 70. 41 64.016 -0.195E-01. 0. 333E+02 -0.527E+02 -0. 513E+02 0.365E+02 -0.527E+02 -0.406E+02 -0.282E402 SD.122 4. 50 70. 34 64.008 0.343E-01 0.349E+02 -0.498E+02 -0.464E+02 -0. 321E+02 -0.498E+02 -0.369E+02 -0. 253Et02 SD.123 4.75 70.28 64.002 -0.344E+00 0.359E+02 -0.472E+02 -0421E+02 -0.280E+02 -0.472E+02 -0.336E+02 -0.229F+02 SD.124 5.00 70.23 63.996 0. 215E+00 0.366E+02 , -0.448E+02 -0. 381E+02 -0. 241E+02 -0.448E+02 -0.307E+02 -0.207E+02 SD.125 5.25 70.18 63.991 -0. 287E+00 0.369E+02 "0.427E+02 -0.345E+02 -0.203E+02 -0 '27E+02 -0. 282E< 02 -0. 189E<02 SD.126 5.50 70.15 63.985 0. 213Et00 0.372E+02 -0.408E+02 -0. 312E+02 -0. 166E+02 -0.408E+02 -5. 260E F02 -0. 172E E.02 SD.127 5. 75 70.11 63.980 0. 137E+00 0.372E+02 -0.390E+02 -0.282E+02 -0.131E+02 -0.390E402 -0.240E+02 -0. 158E< 02 SD.128 6. 00 70.07 63.976 -0.356E+00 0. 371E+02 "0.374E+02 -0.254E+02 -0.969E+Ol -0.374E+02 -0. 222E F02 -0. 146E t.02 SD.129 6. 25 70. 05 63.971 0.391E+00 0.369E+02 -0.359E+02 -0.229E+02 -0.645E+01 -0.359E+02 -0. 207'2 -0. 135E+02

I~

ARIZONA PUBLIC SERVICE COMPANY PALO VERDE NUCLEAR GENERATING STATION ILRT PROGRAM REPORT STARTING DAY 37 STARTING T IME 14: 30: 0 STARTING SCAN SD. 104 ENDING SCAN SD. 129 ILRT RESULTS AFTER 6.25 HRS.

POINT TO POINT TOTAL TIME MASS PLOT AVERAGE MEASURED LEAK RATES (WEIGHT PERCENT PER DAY)

LEAK RATE LEAK RATE STD.DEV. LEAK RATE STD.DEV.

-0.34SE+02 -0.792E+02 0.383E+02 -0.792E+02 0.383E+02 CALCULATED LEAK RATES (WEIGHT PERCENT PER DAY)

LEAK RATE LEAK RATE STD.DEV. UPPER CON. LIMIT LEAK RATE STD.DEV. UPPER CON.LIMIT 0.369E+02 -0.229E+02 0.794E+01 -0.646E+01 -'0. 207E+02 0. 420E+01 -0. 135E+02

ARIZONA . PUBLIC SERVICE COMPANY PALO VERDE NUCLEAR GENERATING STATION RELATIVE HUMIDITY PROGRAM SCAN NO. AVERAGE DEW POINT AVERAGE CONTAINMENT AVERAGE VAPOR AVERAGE RE(.ATIVE TEMPFRATURE TEMPERATURE PRESSURE HUMIDITY (F) (F) (PSIA) (%)

SD.104 64.312 72.425 0. 297 75.662 SD.105 64;493 72.724 0. 299 75.380 SD.106 64 '35 72.957 0.301 75. 293 SD. 107 64 '67 73. 148 0. 303 75.286 SD.103 65. 101 73. 327 0. 306 75.449 SD. 109 65. 239 73. 470 0. 307 75.448 SD.110 65. 424 73.604 0.309 75.594 SD. 111 65. 428 73.341 0.309 76.278 SD. 112 65.432 72.795 0 '10 77.837 SD. 113 65.563 71.974 0.311 80.251 SD. 114 65.559 71.467 0 311

~ 81 ~ 633 SD. 1 15 65.406 71.143 0. 309 82.097 SD.116 65.386 70.924 0. 309 82.653 SD. 117 65.323 70.764 0. 308 82. 923 SD.118 65.215 70.644 0. 307 82.947 SD. 1.19 65.309 70.560 0.308 83.460 SD ~ 120 65.230 70.479 0.307 83.460 SD. 121 65.193 70.405 0.307 83.562 SD.122 65.147 70.344 O.306 83 '03 SD. 123. 65.111 70. 278 0. 306 83.683 SD. 124 65.160 70.235 0.306 83 '50 SD. 125 65.085 70.184 0.305 83'77 SD. 126 65.084 70.145 0.305 83.'986 SD. 127 65.070 70 '12 0.305 84.038 SD.123 64.985 70.066 0.304 83.921 SD. 129 64.988 70.046 0.304 83.989

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I I AR I ZOtlA PUBL I C SERV I CE .Cot tPANY PALO VERDE NUCLEAR GFNERAT INO STATION RAW DATA

SUMMARY

RFPOPT SCAN NO. DATE TINE PRESS 1 PRESS 2 RTD ¹1 RTD ¹2 RTD ¹3 RTD ¹4 RTD ¹5 RTD RTD ¹7 RTD ¹8 RTD ¹9 SD. 129 37 20: 45 63.1 9 63.212 69.795, 69.763 69.743 69.815 :69. 885 6?. >61 69.921 70. 114 69.990 SD. 130 37 21: 0 63.155 63. 208 69 '43 69.722 69.734 69.755 69.853 69.'51 69.894 70.086 69.990 SD. 131 37 21: 15 63.154 63. 207 69.793 69.764 69 737 69.776 69.809 69.798 69 '53 70.079 69.989, SD. 132 37 21: 30 63.152 63. 204 69.810 69.760 69.751 69.776 69.798 69.772 69.955 70.057 69. 94'l SD. 133 37 21: 45 63.149 63.201 69.796 69.761 69.722 6'?. 758 69.805 69.780 69.964 70.059 69.964 SD. 134 37 2~ 0 63.146 63. 198 69.757 69.734 69.714 69.735 69.741 69.735 69. 926 70.048 69.940 SD. 135 37 22: 15 63.142 63:1'95 69.761 69.677 6'9. 682 69.715 69.751 69.728 69.903 70.030 69.944 SD.136 37 22: 30 63.139 63.192 69.712 69. 697 69.656 69.693 69. 714 69.688 69. 862 69.967 69.882 SD.137 37 22: 45 63.136 63.188 69.682 69.651 69.638 69.662 69 '82 69.697 6'9. 825 69.996 69.897 SD. 138 37 23: 0 63.134 63.185 69.668 69.650 69.598 69.642 69.650 69.647 69.824 69.949 69.845 SD. 139 37 23: 15 63.131 63.183 69.657 69.584 69.577 69.633 69.619 69. 627 69 '95 69.908 69.833 SD.140 37 23: 30 63.128 63.180 69.604 69.592 69. 575 c9.586 69.627 69.599 69. 773 69.891 69.802 SD.141 37 23: 45 63.126 63.177 69.589 69.572 69.546 69.551 69.567 69.567 69.764 69 '86 69 772

~

SD.142 38 0: 0 63.123 63.175 69 '03 69.528 69.541 69.56l 69.554 69.570 69 '25 69.883 69.770 SD.143 38 0:15 63.121 63.172 69.572 69.531 69.499 69.522 69.519 69 '41 69.708 69.834 69.722 Sn.144 38 Qt 30 63.118 63. 169 69. 572 69.505 69.496 69 '16 69.531 69.534 69.703 69.838 69.744 SD. 145 38 0:45 63.115 63. 167 69 '22 69.496 69.45Q 69.505 69."38 69.523 69 705i 69.804 69; 691 SD.146 38 1s 0 63.113 63.164 69.512 69.471 69 455 69 '64 69.459 69.511 69.647 69 '10 69.700 SD.147 38 1s 15 63.111 63.162 69.435 69.456 69.438 69.459 69.505 69 it 56 69.641 69.781 69.689-SD.148 38 1:30 63 '09 63. 160 69*496 69.422 69.418 69.459 69.473 69. 470 69 '35 69 '67 69.662 SD.149 38 1 45 63.107 63. 157 69 '64 69.432 69.412 69.459 69.422 69. 426 69.596 69.729 69.616 SD.150 38 2: 0 63.106 63. 15'5 69.441 69.407 69.384 69 '12 69.450 69.45Q 69.603 69 '15 69.621 SD.151 38 2:15 63.103 63.153 69.426 69.390 69.374 6'9. 409 69.397 69.397 69.574 69.676 69.607 Sn.152 38 2:30 63.101 63. 151 69.401 69.351 69 '57 69.383 69.415 6'9 393 69.563 69.668 69.584 SD. 153 38 2:45 63.098 63.148 '9.392 69.345 69.331 69.368 69.384 69.371 69 '45 69.673 69. 55il SD. 154 '38 3: 0 63.096 63.147 69.397 69 '31 69.323 69.343 69.381 69.368 69.522 69.682 69.566 SD.155 38 3:15 63.094 63.144 69.343 69.332 69 '10 69.342 69.335 69.339 69.508 69.638 69.520 SD. 156 38 3:30 . 63.092 63.142 69.360 69 '79 69. 294 69.303 69 '58 69. 337 69.500 69.625 69.519 SD. 157 SD.158 38 3:45 4: 0 63.089

63. 088 63.140 63.139 69.306 69.305 69.308

69. 288 69.276

69. 265

69. 296 69.305 69.328

69. 285 69.329 69.306 69.476 69.473 69.621 69 '85 38 69. 613 69.503 SD.159 38 4:15 63.087 63.137 69.310 69. 268 69 '44 69.276 69.302 69 '88 69.462 69.589 69.494 SD.160 38 4:30 63.084 63.135 69.293 69. 274 69. 220 69 273 69. 273 69.274 69.432 69 '57 69.456 SD.161 38 4:45 63.082 63.133 69. 279 69. 236 69. 235 69. 265 69.285 6'9. 268 69.419 69.558 69.439 SD.162 38 5: 0 63.081 63.131 69.264 69.223 69.189 69.22c 69. 273 69 '38 69.422 69. 52'5 69.424 SD ~ 163 38 5:15 63.079 63.129 6'9. 256 69.201 69.195 69. 203 69 '26 69. 249 69.398 69.528 69 '50 SD.164 38 5:30 63.078 63.127 69. 247 69. 215 69. 177 69. 229 69. 220 69.236 69 '77 69.516 69 '35

AR I ZONA PVBL IC SERVIL.. Cot1PAtPY PALO VERDE NUCLEAR GENERATING STATION RAW DATA SVNNARY REPORT SCAN NO RTD ¹10 RTD ¹11 RTD ¹12 RTD ¹13 RTD ¹14 RTD ¹15 RTD ¹16 RTD ¹17 RTD ¹18 RTD ¹19 RTD ¹20 SD.129 70-066 70.054 70 '51 70.062 70.333 70.332 69.894 70.O25 70 613 70,271 70.114 SD. 130 10 ~ 063 70.050 70.030 69.976 70 '66 70 '40 69 '39 69.999 70.622 70.309 70.018 70.115 SD. 131 70.024 70.082 70.047 70.018 70.365 70.188 69.730- 70.388 70.512 70.175 SD.132 70.033 70.077 70.063 70 '39 70.362 70.198 69. 764 ~ 70.413 70.405 70.146 70.098 SD. 133 69.996 70.056 70 '92 70.011 70.260 7O.19O 69.766 7o.n23 70.391 70.138

'30 70.097 SD. 134 69 '73 70.047 70.007 69.989 70.222 70.262 70.188 70.132 69,763

'05 70.410 70.353 70.364 70.344 70 70.089 70.077 70.063 SD.135 69.973 70.015 70.027 69.972 69 SD.136 69-906 69.979 69.995 69.932 70.147 70.126 69.741 70.358 70.323 70.083 70.031 SD.137 69.924 69.955 69.966 69.885 70.199 70.072 69.651 70.304 70.265 70 '23 69.999 SD. 138 69.894 69.952 69.938 69.'373 70 '14 70.063 69.624 70. 298 70. 274 70.004 69.969 SD. 139 69.873 69 '06 69.928 69.360 70.190'0.016 70.054 69.6'33 70. 272 70. 228 69.990 69.970 SD.140 69.821 69.899 69.903 69.851 69.978 69.596 70. 262 70. 211 69 e 935 69.928 SD.141 69 79r 69.879 69.863 69.813 7o.onn 69.950 69.598 70.257 70.204 69.940 69.931 SD.142 69. 810 69.847 69.880 69.812 70.089 69.966 69 '54 70. 213 70.156 70.175 69.921 69.333 69.931 69.885 SOD 143 69.767 69.850 . 69.S48 69.772 70.042 69.952 69.540 70.213 SD.144 69.761 69.819 69.825 69. 743 70.011 69.911 69.529 70.185 70.126 69.880 69.S57 SD.145 69.731 69.802 69.798 69.737 70.066 69.385 69.535 70.175 70.126 69 '80 69.S56 SD.146 69.717 69.776 69.776 69. 696 69.976 69.S82 69 448 70.163 70.092 J69. 831 69.323

'21.

F 4D. 147 69.715 69.767 69.746 69.702 70 69 '56 69.459 70.130 70.082 69 83 I

~ 69.821 SD. 148 69 '89 69.755 69.751 69-685 70.022 69.822 69.435 70. 123 70.019 69. 821 69.825 SD. 149 69.691 69 '02 69.722 69.651 69.931 69.801

'90 69.418

-69.438 70.120 70.105 70.010 70.024 69.793

'64 69.764 69.783 SD.150 69.653 69.715 69.732 69 645 69.799 69 69 SD.151 69.651 69.708 69.708 69.648 69 '94 69.786 69.470 70.0S8 69.999 69.773 69 '57 SD.152 69.654 69.680 69.677 69.622 69.871 69 '37 69.389 70.059 69.979 69.749 69.758 SD.153 69.609 69.656 69 '71 6'9. 586 69 850 69.775 69.386 70 '53 69 '60 69.725 69.713

.SD.154 69.624 69.653 69.644 69. 598 69.784 69.744. 69.348 =70.028 69.947 69.715 69. 715 SD. 155 69.566 69.632 69.613 69.566 69 '99 69.7?0 69.368 70.030 &69.915

'00 69.694 69.635 SD 156 69. '570 69.624 69 '38 69.551 69.780 69.706 69.380 70.008 69 69.688 69.685 SD.157 69.546 69.619 69.599 69-532 69.761 69.693 69 '31 70.007 69.929 69.664 69.663 SD.158 69 '34 69.593 69.601 69.506 69.836 69.664 69.337.'9. 69.993 69.918 69.641 69 '51 SD.159 69.538 69.566 69.530 69-503 69.830 69.653 291 69.966 69.883 69.606 69.656 SD.160 69.548 69.580 69.557 69.494 69.738 69. 618 69 '05 69.964 69.908 69.642 69.613 SD.161 69.522 69.545 69.552 69.463 69.749 69.606 69. 273 69.947 69.856 69.619 69.63S SD.162 69.491 69.549 ~ 69. 528 69.455 69.661 69. 607 69. 259 69.940 69.848 69.596 69.616 SD.163 69.474 69.541 69.519 69.441 69 '22 69.596 69.233 69.929 69.859 69.581 69.601 SD.164 69 '74 69.503 69.505 69.441 69.665 69. 575 69. 274 69.909 69.816 69 '64 69.580

C ARIZONA Pt tBL IC r CONPANY SERVI CFr.

PALO.'ERDE, NUCLEAR GFNER*T ING STATION RAW DATA SUNNARY REPORT SCAN l'lO. RTD ¹21 RTD ¹22 RTD ¹23 RTD ¹24 D'EW CEl.l ¹1 DEW Ccu. ¹2 DEW CFl.L>>3 DEW CELL ¹4 DEW CELL ¹5 DEW CFLL ¹6 SD. 129 70. 260 70.510 70.381 69.809 64.712 63. 555 65. 206 65. 9,72 63.864 65.000 SD. ian 70.239 70.489 70.358 69.735 64 '24 63.732 65. 228 66. 030 63.890 64.979 SD. 131 70.141 70.227 70. 221 69.531 64 '24 63. 668 65.148 65.921 63.938 64.962

.SD ~ 132 70.091 70.121 70.184 69.484 64 '663 63.565 64 '97 65.890 63.958 6'5 '28 SD. 133 70.079 70.095 70 '43 69.479 64 '45 63.586 64 '47 66 004 63.781 64 '75 SD. 134 70.036 70.076 70 '92 69 470 F 64.642 63.609 64. 901 65.802 63.670 64 '32 SD. 135 70.039

'90 70.048 70.076 69.415 64.582 63.436 64.985 65.898 63 780 65 '66 SD.136 69 70.016 70.044 69.426 64.590 63.476 65. 078 65.853 63.761 64.886 SD.137 69.961 69.999 70.001 69.363 64.578 63.401 65.051 65.786 63.684 64 '74 SD.i38 SD. 139 69.949 69.937 69.981 69.964 69.987 69.975 69.361 69.334 64.556 64.585 63.507 65.017 65.875 63 '39 64.8 i6 63.319 64.941 65. 792 63.638 64.860 SD. 140 69.921 69.934 69.932 69.279 64 '58 63.559 64.942 65. 815 63.722 64.917 SD ~ 141 69.892 69.918 69.914 69.299 64.588 63.496 64.976 65.780 63.635 64.819 SD.142 69.894 69. 900 69.908 69. 235 64.498 63.481 64 '99 65.794 63.745 64.796 SD. 143 69.870 69.882 69.873 69.236 64 '68 63.447 64 '56 65.782 63.627 64.782 SD.144 69.866 69.865 69.868 69.198 64 405 F 63.421 64.791 65.820 63.684 64.755 SD.145 69.834 69.839 69.841 69.206 '23 63.317 64.881 '21 SD. 146 SD.147 69 'i5 69.821 69.833 69 '18 69.819 69 '01 69.183 69.128 64 64.453 64 '88 63.362 63.363 64.910 64.851

,65.734

~

65 '15 6 r. 708 6'3 os 736 63.572 64.744 64.738 64.736 SD. 148 69.812 69.807 69.776 69.136 64.471 63.313 64.859 65. 716 63.514 64.700 SOD 149 69 '61 69.775 69.760 69.102 64 '85 63.092 64.848 65.734 63.568 64 '82 SD.150 69.780 69.764 69. 751 69.093 64.381 63.172 64.865 65.705 63.494 64 '57 SD.151 69.749 69.749 69.734 69.104 64.843 63.209 64.778 65.715 63.516 64.639 SD.152 69.780 69 '41 69.717 69.061 64.326 63. 267 64.875 65.539 63.578 64.636 SD.153 69.718 69.729 69.725 69.064 64.212 63.130 64 '69 65.599 63.604 64 '25 SD.154 69.738 69.711 69 'n3 69.039 64.238 63. 259 64.842 65.565 63.415 64.613 nD.155 69.6'94 69 '93 69.674 69.017 64.263 63.102 64 '92 65.554 63.438 64 '98 SD.156 69.718 69.694 69.653 68.959 64.186 63.125 64.773 65.606 63.543 64 '75 SD. 157 69.663 69 '76 69.651 68.978 64.157 63. 043 64.645 65.594 63.398 64 '53 SD.158 69 '59 69.662 69. 638 68.963 64.120 63.189 64.602 65. 56'5 63.281 64.538 SD ~ 159 69.711 69.636 69.612 68.,930 64.105 63.102 64.749 65. 576 63.502 64 '30 SD.160 69. 645 69.624 69.615 68.956 64. 180 62.976 64.530 65.579 63.378 64.526 SD. 161 69. 662 69.6i5 69.589 68.930 64.122 62 '71 64. 608 65 '70 63.444 >4.505 SD ~ 162 69 619 69.606 69.567 68.937 64. 128 62.956 64.569 65.495 63.360 64.485 SD; 163 69.651 69.583 69.564 68.911 64.108 63.'067 64.657 65.539 63.305 64.476 SD.164 69.639 69.581 69.545 68.881 64.169 62.930 64.532 65.550 63. 238 64.477

~ ~

ARI ZONA PUB(.IC ERVICF. CONPANY PALO VERDE NUCLEAR GEtlFRAT ING STAT ION ILRT PRGGRAYi REPORT STARTIIIG DAY 37 STARTING TINE - 20:IIS: 0 STAR'I ING SCAN SD 129 ENDING SCAN SD.164 POINT TG POINT TO I Al. T It1F. NiASS PLOT SCAN F I.APSF D AVFRAGE AVERAGE I'IFASVRED Chl.CULATED NEASURED CALCULATED VPPFR NEASVRED CALCULATED UPPER NO. TINE TENP. PRESSURE I.EAK RATE LEAK RhlE LEAK RATE 1.EAK RATF. CONFIDENCE I.FAK RA1E LFAK RATF. CONFIDENCE (F) (PSIA) (NEIGIIT P(-:RCEI'IT PER DAY)

( IIR )

rrrrrirrm:rrrrrrrrrrrrrrrrri.rrrrrrrrazr rrrrrrr ariirrr--- --- ----r-----"--.--===

z x SD.129 0. 00 70.05 63.971 SD.130 0. 2'5 70. 01 63. 967 -0.114E-ol -0.114E-01 -0.114E-01 "0.114E-01 O.OOOE+00 -0. 107E-01 -0.107F-OI 0.000F+00 SD.131 e. so 7O.OO 63.966 -0.252E-01 -0.2SRF-O) -0.189E-01 -0.189E-01 O.OOOE+OO -0. 192E-01 -0. 192E-01 0.000FsOO SD.132 0. 75 69.99 63.964 -0.526E-01 -O.SO4iE-OI -0. 301E-01 -0.29SE-01 -0.?33E-01 -0. 299F.-O I -0.398F.-01 0- I 82E.-O 1 SD.133 1.00 69.93 63.961 0.211E+00 0. 127E+00 0. 306E-0 I 0.978E-OR 0.838E-OI 0.306E-01 0. 341E-01 0.161F+00 SD. 134 1 ~ 25 69.95 63.,958 -0.165F+00 -0.227E-ol -0.870E-02 0.329E-02 0. 571E-01 -0.839E-02 0. 100E-01 0-776F.-01 SD. 135 1.50 69.93 63.9S4 0.360E>00 0. 17SE+00 0.530F.-01 0.320F.-01 0. 858F.-01 0.530F-01 0.529E-01 0.119E+00 SD. 136 1.75 69.90 63.951 -0.141Eioo 0.543E-01 0. 251F.-01 0.351F.-01 0. 813E-01 0.?52F.-01 0.474E-01 0.921E-01 SD. 137 SD. 138 2.00

2. 25 69 '7 69.85 63.948 63.946

-0. 813E-01

-0. 101E+00 0.348E-OR 0.118E-Ol

-0.763F.-03 0.311E-01 0 769E-01

~

0.235E-01 0. 712E-01

0. 1 19F.-01

-0. 63iRE-03 0.341E-01

0. 189E-01

0. 695E-0 l

0. 503F.-01 "0.374E-01'0.559E-02 SD. 139 2. 50 69. 83 63.943 0. 721E-01 0 669E-02

~ 0.206E-01 0.656F.-ol 0.669E-02 0.146E-01 0.396E-01 SD. 140 2. 75 69. 80 63.940 -0 121E+00

~ -0.443E-01 -0.499E-02 0.147E-01 0. 593F.-01 -0.498F.-02 0.502E-O?. 0.282E-01 SD.141 3. 00 69.73 64.933 -0.515E-01 -0.519E-OI -0.368E-02 0.921E-02 O.S30E-01 -0.871E-02 -0 127F.-02

~ 0,185F-01 Sn. 142 3 25 69. 77 63.935 0.260E+00 0.282E-ol 0. 12OE-OI 0. 10/F.-o 1 0.516F.-01 0.119F.-01 0 ~ 277E-02 0. 199E-01 SD. 143 3. 50 69. 74 63.933 -0.299E+00 -0.539E-01 -0.102E"01 0. 612E-02 0.463F.-01 -0. 102E-01 -0.320E-02 0. 1?6F-01 SD. 144 3. 7S 69. 73 63. 930 0. 209E+00 0.468F.-02 0.439E-02 0.604E-OR 0.441E-01 O. 441E-02 -0. 208E-02 0. 116f-,ol SD. 145 4. 00 69.71 63.927 0.223E+00 0.544E-01 0. 180E-01 0 907E-02 0. 'I57E-01

~ 0.181E-01 0.429E-OR 0. 176E-01 SD. 146 4. 25 69.69 63.924 -0. 201E+00 0.30iRF.-OR. 0. 512F."Oc2 0 '72E-02 0.438E-OI 0. 515E-02 0.373E-02 0.155F.-01 SD. 147 4 50

~ 69.68 63 '22 0 '24E-01 0.150E-01 0. 830F.-02 0 908E-OR 0. )2/E-01

~ 0.826F.-OR 0. 501F.-OR 0. 1S4F-01 SD. 148 4. 75 69. 66 63.920 0.378E-01 0 200E-01

~ 0.985E-OR 0 966E 0? 0.420E-01 0.98SE-02 0.646E-02 0. 158F.-oi SD.149 5.00 69.63 63.918 -0.312F+00 -0.408E-01 -0.629E-OR 0. 714F.-02 0 39rRE 0 1 -0.622E-OR O.r263E-02 0. 1 18F-01 SD.150 i C'.

69.62 63.917 -0.572E-OR .-0.375E-01 -0.63RE-02 0.500E-02 0.365E-01 -0.630E-02 O.OOOF+00 0. 871E-02 SD.151 50 69.61 63- 914 0.203E+00 0.667E-03 0.320E-02 0.480F.-OR 0.353F.-ol 0.320E-02 0. 299E-03 0.820E-02 SD. 152 5. 75 69.59 63.912 -0.664F.-01 -0.105F.-01 0, 149F-03 0. 413E-07. 0.338E-01 0.155E-03 -0. RSOF.-03 0 '9/E-02 SD.153 6. 00 69.57 63.909 0 '53E-01 0.330E-02 0.372F-OR 0. 411E-02 0.329E-01 0.373E-02 0. 21 1F-03 0.683E-02 SD.154 6. 25 69.56 63.907 0.635F.-01 0. 128E-01 0. 609E-0 '. 0.445E-02 0.3?SE-01 , 0..612E-02 0. 143F.-02 0.758F.-02 SD.155 6. 50 69.54 63.905 -0. 192E+00 -0. 165'E-01 -0. 158E 0.362E-02 0. 311E-01 -0.156F-02 0.307E-03 0.604E-02 SD ~ 156 6. 75 69.53 63. 903 0. 213E+00 0. 146E-01 0. 6'38E-02 0.402E"02 0.308E-01 0 643E"02

~ 0. 132E-02 0.671F.-O?

SD.157 7. 00 69.51 63.900 0.647E-01 0. 219E-01 0.846E-02 0.465E-02 0.309E-01 0.849E-02 0. 251E-02 0.76SE-02 SD. 158 7. 25 69.51 63. 899 -0.858E-01 0. 867E-02 0.525E-02 0.479E-OR 0.304E-01 0.525E-02 0 '97E-02 0.776E-02 SD. 1S9 7'. 50 69.49 63.398 -0.114E"02 0. 76 )E-02 0.502E-02 0.488F-oiR 0.300F-01 0.503F.-02 0.311E-02 0.759E-02 SD.160 7.75 69.48 63.895 0. 129E< 00 0 ~ 228F.-01 0.904F.-O?. 0.546E-02 0.301E-01 0.909E-OR 0.424E-02 o.854E-o2 SD.161 8.00 6'9. 46 63.893 0.916F.*01 0.318E-01 0.116E-01

O.628E-O2 0. 305E-01 0.116F-01 0.547E-02 0. 970E -02 SD.162 8. 25 69. 44 63.892 -0.283E+00 -n. 3S IF-OR 0.270E-02 0.598F.-02 0 ~ 298F-01 0. 27i".E-02 0.508E-02 0 907 E-0i2

~

SD. 163 8. 50 69. 44 63.890 0.204E+00 0. 195E-01 0.862E-02 0.637F.-oi2 0 ~ 297E-01 0 '64E-02 0.565F-02 0.'945E-02 SD.164 8. 75 69. 42 63.889 -0. 129F+00 0.376E-02 0.468E-OR 0.630F.-02 0. 293E-01 0.467E-O? 0.560E-OR 0. 9 18E-02

l CO I

0 AR I ZONA PUPl, IC ERV ICE COt)PAtlY PALO VERDF. NUCLEAR GiEtlERATING STATION Il.RT PRQGRA)1 RFPORT STARTING DAY 37 STARTING TItlF. - 20:45: 0 Sl'ARTIt'lG SCAN - SD. ) 29 FNDING SCAN SD. ) 64 ILRT RFSULTS AFTER 8.75 llRS.

~ ~ ~ ~

'H I T4P M T4 ~ ~

POINT TO POINT .TOTAL TINE HASS PLOT AVERAGE NEASURED LEAK RATES (WEIGHT PERCENT PER DAY)

LEAK RATF STD.DEV. 'EAK RATE STD.DEV.

~,

LEAK RATE

0. 471E" 02 0.434F-02 0 ~ 140E-01 0.438E-02 0. 140E-01 C

- a aa - '

~ = '- = 0 ~ l.

CALCULATED (.EAK RATES (WEIGil)T PERCENT PER DAY)

LEA'K RATE LEAK RATE STD DEV. UPPER CON. Llt')IT (.LAK RATE STD. DFV. UPPER CON. LINIT 0 376E 02 0. 630E-02 0. 113E-01 0. 292E-01 0. 560E-02 0. 212E" 02 0. 918F.-02

~~

AR I ZONA PUBLIC SERV~COMPANY PALO .VERDE NUCLEAR GENERATING STATION RELATIVE HUMIDITY PRCIGRAI1'VERAGE SCAN NO. DEW POINT AVERAGE CONTAINMENT AVERAGE VAPOR AVERAGE REl.AT IVE TEt1PERATURE TEMPERATVRF. PRESSVRE HUMIDITY i (F) (F) (PSIA) (%)

SD ~ 129 64.983 70.046 0. 304 83. 939 SD. 130 64.9SO 70.012 O. 304 84.061 SD. 131 64.974 70.003 0. 304 84.072-SD. 132 64.932 69.987 0. 304 83.995 SD. 133 64.906 69.976 O. 304 83.949 SD.134 64".831 69.948 P. <03 83.809 SD.135 64 '87 69.929 0.303 84.027 SD. 136 64.869 69 '98 0 '03 34 066 SD. 1'37 64.833 69.871 0.303 84.036 SD. 138 64.844 69.848 0.303 84.133 SD. 139 64.805 69.830 0. 302 84.071 SD.140 64.823 69 '97 0.303 84 '20 SD. 141 64.804 69.779 0.302 84. 215 SD. 142 64. 799 69.769 0.302 84 '29 SD. 143 64.718 69.743 0.302 34.067 SD. 144 64.719 69 '29 O. 302 84.llo SD.145 64.743 69.714 0.302, 84 '23 SD.146 64.741 69.686 0.302 84. 298 SD. 147 64.713 69.675 OS 3O2 84. 2)6 SD. 148 64.697 69.662 0.301 S4 ~ 238 SD.149 64.650 69.632 0 '01 34.185 Sn.15O 64. 660 69.622 0.301 84.244 SD.151 64. 634 69.611 0 301 F 84.201 SD. 152 64. 622 69.591 0 301 84.220 SD.153 64.582 69.574 0.300 84. 151 SD. 154 64.567 69.562 0.300 84 143

'39 F

SD. 155 64.522 69 0.300, 84.07=:

SD. 156 64.560 69.530 0.300 84.213 SD. 157 64 '93 69.514 0. 299 84 077 SD. 158 64 '52 69.505 0. 299

~

83.970 SD. 159 64.512 69.491 0. 299 84.186 SD. 160 64.471 69.477 0. 299 84.104 SOD 161 64.475 69 '65 0 ~ 299 84.151 SD.162 64.437 69.444 0. 299 84 101 F

SD. 163 64.449 69. 437 0. 299 84 155

~

SD.164 64.433 69.423 0. 299 84.149

~ r ILRT

63. 988:. GNTADRENT PRESSt]RE (PSIA)

SCANS SD;X29-f84 ==

63.&88 =:

63. 840:-

63.928--

63.888 := 2. e:- 8.8::

J i

I I

l

ILRT

~

AVHkAM RTD TEHPHQTLM (1KB.F'):.

BCAHB SH

?

2. 8=- 6. 8:-

(83URS)

P i

ILRT 3B4 CBJ gEHP ERATURi (Dig.

BCA6 SD =i29- 164

64. 768

64. 648-:

TIJOU

64. 528 6'..488 =: 4. 8:- 6.8:- 8.8 ELAPSE) =. (HOURS) hh

ILRT WASURiZI HA5S PLO) LBC RATE (~GHT 2/DAi) r 1 C

4.¹ 6.8 =: 8.8 =

ELAPSED: TILE (HOURS)

I t

'J

XLRT 8.M8 = TOTAL TIP'GC RATE (+IGHT /~Y)

BCANe Sa. ~~1M

8. 848:-

Cp

-8.828

-8. 848 2.8=: 4.8:- 6.8 = 8.8 --.

ELAPSED::TIP~ (83LIRB)

ILRT

8. 288:-

~ I~

? ?

8.888 -:

?

8.828 --.

-8 848--

2.¹ 8.8 =

i ILRT TOT~t fg~ =:<bKIGHT /~Y)--:

SCA% B3. f29.-i64

2. 8:- 4.8::

ELAPHED =:TINE (~>8.8 8. 8:-

Wh '"I ~ h ~ hW lh 'p J ~,

ILRT

&8.888 =. A~AGE RELATIVE g&~IBITY 72.888 =:

54.888 =-

36. 888::

i8.888 ':

8.888 .-

2.¹ 4.8:: 6.8 TIfK (HOURS)

8.8:

ELAPSE) =

ILRT 8.9

30 CONTROLLED LEAK RATE TEST (CLRT)

li ARIZONA PUBLIC SERVICE COMPANY PALO VERDE NUCLEAR GENERATING STATION RAW DATA

SUMMARY

REPORT SCAN NO- DATE TINE PRESS 1 PRESS 2 RTD ¹1 RTD ¹2 RTD ¹3 'RTD ¹4 RTD ¹5 RTD ¹6 RTD ¹7 RTD ¹8 RTD ¹9 SD.165 38 5:45 63.075 63.125 69.210 69.189 69. 174 69 207 69.210 69. 232 6'9. 368 69.499 69.419 SD.166 38 6: 0 63.073 63.123 69.210 69.197 69.169 69.181 69.233 69.206 69.360 69.502 69.358 SD. 167 38 6:15 63.071 63.120 69.189 69.165 69.143 69.194 69.183 69.189 69.346 69.500 69.380 SD.168 38 6:30 63.068 63.118 69.180 69.142 69.140 69.148 69.192 69 '83 69.332 69 470 69.384 SD.169 38 6:45 63.066 63.116 69.160 69. 133 69. 108 69. 142 69.172 69.146 69.320 69.422 69.358 SD.170 38 7: 0 63.064 63.114 69.177 69. 114 69.097 69.146 69. 146 69.142 69.291 69.462 69.325 SD.171 38 7s15 63.061 63.111 69.148 69.099 ~ 69.094 69.122 69.178 69.151 69.300 69.429 69.334 SD.172 38 7:30 63.059 63.109 69. 162 69.108 69.091 69. 114 69.110 69.123 69.293 69.416 69.314 SD.173 38 7:45 63.057 63.107 69.111 69.078 69,079 69.096 69. 117 69.119 69.270 69.406 69.314 SD.174 38 8: 0 63.055 63.104 69.119 69.079 69.050 69.079 69.117 69.119 69.262 69.413 69.316 SD.175 38 8:15 63.053 63.103 69.084 69.076 69.044 69.082 69.108 69.082 69.255 69.383 69. 299 SD.176 38 8:30 63.051 63.100 69.119 69.055 69.047 69.081 69.085 69.094 69.262 69.410 )( 69. 288 SD.177 38 8445 63.049 63.098 69.085 69.041 69.023 69.038 69.096 69.065 69.227 69.358 69.261 SD.178 38 9: 0 63.047 63.096 69.056 '9.029 69.015 69.041 69.073 69.076 69.238 69.348 69. 239 SD.179 38 9:15 63.043 63.094 69.065 69.032 68.997 69.026 69.058 69.044 69.215 69.313 69. 247 SD. 180 38 9:30 63.043 63.092 69.052 68.998 68.988 69.018 69.070 69.035 69.186 69.326 69. 233 SD.181 38 9:45 63.040 63.090 69.049 68.981 68.985 68.997 69.003 69.001 69.171 69.310 69. 189 SD.182 38 10: 0 63.039 63.088 69.046 68.977 68.969 68.986 69.035 69.024 69 177 69.261 69.189 SD. 183 38 10: 15 63.037 63.086 69.039 68.956 68.962 69. 004 69.017 69.009 69.166 69. 281 69. 183 SD.184 38 10: 30 63.035 63.084 69.018 68.945 68.956 68. 981 69.003 68.981 69. 133 69. 268 69.194 SD.185 38 10: 45 63.033 63.082 68.994'8.985 68.'956 68.934 68.978 69.004 68.988 69.143 69.238 69.154 SD.186 38 11: 0 65.030 63.080 68.940 68.946 68.963 68.960 68.957 69.139 69.245 69.152 SD. 187 38 11:15 63.028 63.078 68.960 68.917 68.940 68.946 68.980 68.978 69.117 69.229 69 '57

I ARIZONA PUBLIC SERVICE COMPANY PALO VERDE NUCLEAR GENER AT ING STATION RAM DATA SUNNARY REPORT.

SCAN NO. RTD ¹10 RTD ¹11 RTD ¹12 RTD ¹13 RTD ¹14 RTD ¹15 RTDi¹16 RTD ¹17 RTD ¹18 RTD ¹19 RTD ¹20 SD ~ 165 69.470 69.496 69.494 69.432 69. 682 69.599 69. 184 69.902 69.822 69. 551 69.563 SD.166 69.444 69.413 69.487 69.487 69.477 69.479 69.429 69.395 69.624

'36 69.563 69.290 69.880 69.780 69. 531 69 '51 SD. 167 69 69.529 ': 69. 207 69.879 69.766 69. 522 69.525 SD. 168 69.403 69.456 '9.462 69.361 69.674 69.516 69.137 69.868 69.810 69. 511 69.535 SD. 169 69.389 69.427 69.471 69.438

. 69.435 69.389 69.639 69 '12 69.212 69.856 69.751 69.490 69.520 SD.170 69.438 69.360 69.590 69.493 69.122 69.836 69.743 69.490 69.502 SD. 171 69.377 69.430 69.426 69.358 69.586 69.484 69.146 69.825 69.747 69.490 69.491 SD. 172 69.374 69.416 69.406 69.323 69.587 69.462 69.131 69.799 69.711 69.429 69.476 SD. 173 69.326 69.395 69.421 69.313 69.584 69.464 69.175 69.801 69.694 69.448 69.451 SD. 174 69.381 69.380 69.393 69.313 69.584 69.462 69.087 69.793 69.741 69.426 69.491 SD.175 SD.176 69.343 69.358 69.404 69.383 69.375 69.284 69.645 69 '55 69.101 69.783 69.715 69.427 69.442 69.361 69.290 69.563 69.421 69.079 69.778 69.679 69.430 69.467 SD. 177 69.329 69.343 69.355 69.281 69.503 69.415 69.090 69.767 69.670 69.412 69.433 SD. 178 69.331 69.366 69.329 69.281 69.589 69.403 69.075 69. 761 69.682 69.403 69.422 SD. 179 69.311 69.348 69.335 69.261 69.563 69.403 69.064 69.743 69.667 69.377 ,69.426 SD. 180 69.313 69.313 69.343 69.245 69.537 69.375 69.090 69.738 69.625 69.401 SD.181 69 '74 69.323 69.306 69.238 69.535 69.355 69.062 69.725 69.619 69. 381 69.409'9.382 SD.182 69. 271 69.328 69.320 69.233 69.444 69.343 69.024 69.718 69.638 69. 369 69.371 SD.183 69.244 69 '00 69.302 69.233 69.453 69.384 69.015 69.694 69.595 69. 351 69.363 SD. 184 69.210 69.267 69.282 69.195 69.581 69.335 68.981 69.686 69.574 69.349 69.352 SD.185 69.233 69.287 69. 284 69.203 69.424 69.328 69.043 69.680 69.635 69.329 69.334 SD. 186 69 '55 69.270 69.261 69.183 69.439 69.310 68.988 69.673 69.574 69.331 69.326 SD. 187 69.207 69. 247 69. 253 69.157 69.525 69.313 68.974 69.668 69.555 69.314 69.339

i ARIZONA PUDLIC SERVICE CONPANY PALO VERDE NUCLEAR GFNFRATING STATION RAW DATA SUNNARY REPORT SCAN NO. RTD ¹21 RTD ¹22 RTD ¹23 RTD ¹24 DEW CELL ¹1 DEW CELL ¹2 DEW CELL ¹3 DEW CELL ¹4 DEW CELL ¹S DEW CELL ¹6 SD.16S 69.609 69 578

~ 69.S4S 68.899 64. 230 62. 869 64.621 6S.548 63.301 64.430 SD.166 69.596 69.578

69. 548 69.545 69.523 68.829 64.170 62.995 64 '72 65.521 63.195 64.486 SD. 167 69.514 68.827 64.080 62.927 64.588 65.S28 63. 182 64.422 SD.168 69 '89 69.532 69.496 68.803 63.969 62.867 64.648 65.493 63.188 64.440 SD. 169 SD. 170 69.575 69.569 69.S19 69.502 69.490 69.473 68.815

68. 812 64.0SO 64.061 62.881

62. 890 64.624

'53 65.480 63.096 64 '28 64 65.388 63.209 64.381 SD.171 69.574 69.496 69.461 68.772 63.987 62.858 64.593 6S.440 63.092 64 '%6 SD. 172 69.531 69.491 69.453 68.760 63. 867 62.843 64.S26 65.454 63.220 64.343 SD. 173 69.523 69.491 69.430 68.737 64.021 62.936 64.468 65.437 63.082 64 '17 SD ~ 174 SD. 175 69.557 69.523 69.465 69.464 69.430 69.429 68.759 68.721 64.093 62.908 64 '95 65.409 63.154 64. 299 63.946 62. 760 64.442 65.339 63. 110 64. 292 SD.176 69.528 69.456 69.403 68.736 63.798 62.689 64 F 402 65.365 63.046 64. 277 SD.177 69.528 69.436 69.401 68.708 63.841 62.872 64.460 6S.419 62.995 64 '71 SD.178 69.509 69.427 69.386 68.716 63.894 62.785 64.427 65.330 63.049 64.248 SD.179 69.477 69.413 69.378 68.669 63.818 62.678 64.411 65.263 63.009 64 )~234 SD.180 69.482 69.416 69.366 68.658 63.859 62.854 64.462 65.339 62.965 64. 256 SD.181 SD.182.

69.465 69.473 69.390 69.380 69.357 69.342 68.679 63.816 62.782 64 '05 65.339 63.029 64.224 68.655 63.795 62.820 64.216 65.289 62.989 64.205 SD. 183 SD.184 69.427 69.436 69.378 69.372 69.332 69.331 68.646 68.629 63.745 63.749 62.693 62.654 64.277 64.372 65.266 62 '36 64. 184 65.220 63.064 64. 144 SD.185 69 '27 69.352 69.314 68.624 63.768 62.617 64.241 65.176 62.905 64. 151 SD.186 69.418 69.339 69.308 68.637 63.745 62.727 64.390 65.234 62.918 64.122 SD. 187 69 '01 69.334 69.293 68.614 63.757 62.689 64.167 65.184 62. 822 64. 112

'(

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ARIZONA PUBLIC SERVICE COMPANY

.PALO VERDE NUCLEAR GENERATING STATION ILRT PROGRAM REPORT STARTING DAY 38 STARTING TIME - 5:45: 0 STARTING SCAN - SD. 165 ENDING SCAN - SD 187 POINT TO POINT TOTAL TIME MASS PLOT SCAN ELAPSED AVERAGE AVERAGE MEASURED CALCULATED MEASURED CALCULATED UPPER MEASURED CALCULATED UPPFR NO. T IME TEMP. PRESSURE LEAK RATE LEAK RATE LEAK RATE LEAK RATE CONFIDFNCE LEAK RATE LEAK RATE CONFIDENCE (HR) (F) (PSIA) (WEIGHT PERCENT PER DAY)

SD.165 0.00 69.41 63.886 SD.166 0. 25 69.40 63.884 -0.252E-oi -0.252E-01 -0.252E-01 -0.252E-oi 0.000E+00 -0.263E-01 -0.263E-01 0. OOOEt 00 SD.167 0. 50 69.38 63.882 -0.320E-01 -0.320E-01 -0,298E-01 -0.298E-01 0.000E+00 -0. 292F-01 -0.292E-01 0.000Etoo SD ~ 168 0. 75 . 69.37 63. 879 '.209E+00

0. 168E+00 0.505E-01 0.364E-oi 0. 173E+00 0. 503E-01 0.892E-01 0.688Etoo SD ~ 169 1 ~ 00 69. 36 63.877 0.692E-01 0. 134E+00 0.552E-01 0.609E-oi 0.115E+00 0. 553E-01 0.956E-01 0. 183E >00 SD. 170 1. 25 69. 35 63.875 0.801E-02 0.794E-oi 0.454E-01 0.645E-01 0. 119E+00 0. 455E-01 0.783E-01 0. 126Et 00 SD. 171 '.50 69. 34 63.872 O. 312E+00

-0. 561E-01

.0. 209E+00 0.899E-01 0.886E-ol 0. 130E+00 0.899E-ol 0. 108E+00 0 153E+00

~

SD. 172 1. 75 69. 32 63.870 0. 112E+00 0.692E-01 0. 919E-01 0. 138E+00 0. 690E-01 0.994E-01 0. 131Etoo SD. 173 2. 00 69. 31 63.868 0. 118E+00 0. 123E+00 0.751E-01 0.957E-01 0. 1 42E+00 0. 751E-01 0 986E-01

~ 0. 121E t 00 SD. 174. 2. 25 69. 31 63.866 0. 327E+00 0. 208E+00 0.103E+00 0. 108 E+00 0. 149E+00 0. 103Et 00 0. 113E+00 0. 137E+00 SD. 175 2. 50 69. 30 63.864 -0. 401E-01 0. 140E+00 0.886E 0. 1 11E+00 0. 154E+00 0. 886F-01 0. 1 1 lEioo 0.130Etoo SD. 176 2. 75 69. 29 63.862 0. 115E+00 0. 139E+00 0.911E-01 0. 114E+00 ,0. 158E+00 0. 91 1E-01 0.111E+00 0. 126Etoo SD. 177 3. 00 69. 27 63.860 -0.458E-01 0. '916E-01 0.797E-01 0.112E+00 0.160E+00 0 '96E-01 0 ~ IO~E+00 0. 119Etoo SD. 178 3.25 69. 27 63.858 0.235E+00 0. 133E+00 0>>916E-01 0.113E+00 0.161E+00 0.916E-01 0. 106E+00 0. 118Etoo SD. 179 3.50 69. 25 63.854 0.267E+00 0. 172E+00 0. 104E+00 0. 118E+00 0. 164E+00 0. 104E+00 0. 1 1 1'E >00 0. 122E ~00 Sn.ieO 3.75 69. 24 63.854 -0. 110E+00 0. 112E+00 0.898E-01 0 117E+00

~ 0. 165E+00 0. 899E-01 0 '09E+00 0. 1 18E+00 SD.181 4. 00 69. 22 63.851 0.526E-ol 0.101E+00 0.875E-01 0. 116E+00 0.165E+00 0.875E-01 0. 106E+00 0. 115C+00 SD.182 4 ~ 25 69. 22 63.850. -0.572E-01 O.68OE-OI 0.790E-oi 0. 113E+00 0. 164E+00 0. 791E"01 0. 101E+00 0. 111Etoo SD.183 4. 50 69 ~ 21 63.848 0.996E-01 0.733E-ol 0.802E-ol 0.111E+00 0.163E+00 0.802E-01 0.972E-01 0.106E+00 SD. 184 4 75

~ 69. 19 63.846 0. 1?SE+00 0.827E-01 0.826E-01 0. 110E+00 0. 162E+00 0.825E-01 0.950E-01 O.IO.E+OO SD. 185 5. 00 69. 19 63.844 0.904E-01 0.841E-01 0.829E-01 0. 108E+00 0. 161E+00 0.829E-01 0.933E-01 0. 101E t 00 SD. 186 5. 25 69. 17 63.841 0.297E+00 0. 122E+00 0. 931E-01 0.109E+00 0. 160E+00 0.932E-ol 0.948F-01 0. 102Et 00 SD. 187 5. 50 69. 17 63.839 0.566E-01 0. 113E+00 0. 9 1'4E" 01 0. 109E+00 b.i60E+00 0.915E-01 0.954F.-01 0.102Etoo

A P

ARIZONA PUBLIC SERVICE COMPANY PALO VERDE NUCLEAR GENERATING STATION ILRT PROGRAM REPORT START I NG DAY 38 STARTING TIME 5: 05) 0 STARTING SCAN SD ~ 165 ENDING SCAN - SD. 187 ILRT RESULTS AFTER 5. 50 HRS.

POINT TO POINT TOTAL TIME MASS PLOT AVERAGE MEASURED LEAK RATES (WEIGHT PERCENT PER DAY)

LEAK RATE LEAK RATE STD. DEV LEA)( RATE STD ~ DEV.

0. 916E-0 1 0.716E-01 0.378E-01 0. 716E-01 0. 379E-01 aaar a -aar raa aa a rara aaraaaaa ar--r-a-- --------------a--------a CALCULATED LEA'K RATES (WEIGHT PERCENT PER DAY), (I LEAK RATE LEAK RATE STD.DEV. UPPER CON. LIMIT LEAK RATE STD.DEV. UPPER CON.LIMI

0. 109E+00 0.201E-01 0. 159E+00 0. 954E-01 0. 374E-'02 0. 102E+00 I'.113E+00

ARIZONA PUBLIC SERVICE COHPANY PALO VERDE NUCLEAR GENERATING STATION RELATIVE. HUMIDITY PROGRAN SCAN NO. AVERAGE DEW POINT AVERAGE CONTAINHENT AVERAGE VAPOR AVERAGE RELATIVE ]

TEI1PERATURE TEHPERATURE PRESSURE HUNIDITY (F) (F) . (PSIA) (X) a r a -a- ra ar-aaa-.aarrrarar aaaaraarraaaraaararrrr SD. 165 64 471 69.414 0.299 . 84.289 SD.166 64.431 69.399 0. 299 84 '12 SD.167 64.398 69.383 0. 298 84.161 SD.168 64 ~ 375 69.372 0. 298 84.125 SD.169 64.375 69.359 0. 298 84.164 SD.170 64.334 69.346 0. 298 84.080 SD.171 64.329 69.338 0. 298 84 '88 SD. 172 64 '02 69.321 0. 297 =84.059 SD. 173 64.307 69.310 0. 297 84.104 SD. 174 ,64.336 69.309 0. 298 84.192 SD. 175 64.260 69.296 0. 297 84.006 SD. 176 64.203 69.291 0.296 83.853 SD. 177 64.229 69.269 0.296 83.994 SD. 178 64.224 69.266 0.296 83.989 SD.179 64.177 69.251 0.296 83.893 SD.180 64.212 69.242 0. 296 84.021 SD.181 64.172 69.223 0. 296 83.958 SD.182 64.129 69.215 0. 295 83.852 SD.183 64.111 69.205 0. 295 83.828 SD. 184 64.135 69.193 0. 295 83. 934 SD.185 64.082 69.186 0. 295 83. 799 SD.186 64 115 69 '74 0. 295 83.931 SD.187 64.047 69.167 0.295 83.752

CLRT

63. 689,- GMfAIHNEHT PRESBgRE (PBIA)

SeQe SD. Xm-<87::

63. 878:-

63.866 =.

63.em::

63.842 ::

63.839 = 3. e:- 4.5:- 6.8 =

ELAPBQ):-TItK (HQLRS)

CLRT AVERAGE RTG TEHPERATURE (HEG.F)::

SCA1% SD. i'-f87

? ~ r i.5= 3.¹ 4.5 =-

6.8 .=

ELAPKi=-TXK (HOURS)

CLRT

? ?

64.588 ==

AVERAGE IKM CELL fEHPERATURE (D. F)

SCANS SB =165-f87

'+

64.488 .-:

?

64.388 =

64. 288' 64.188 =

?

64. 888:: 4.5 .= 6. 8:-

HQURB)

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CLRT

8. 288:: RSS PLQe LEAK RATE (MREBHT X/DAY)

SCAMS 93. i65-187 C

8. i48 '--

8.888 =-

8.828 ="

?

-8.848 .=

?

i. 5-- Z. 8 .--

4.5 = 8.8 .=

ELAPBEB TEnr <HOURS)

=-

l' t

CLRT 8.288 =

(LIIGHT SHAY)

C

8. 888::

8.828 '=.

l i.5= 3.8= 6.8::

ELAPSED =.TGK (HO(KB)

CLRT 8.788 -'.

HASS Pl;.DT LEAK RATE 5KXBHT X/HAY) -:

SCABS BD. f65-187 8.648 =-

8. 388::

8.228 -:

8.868 -:.

-8. 188:- -.-3. 8:- - 4. 5:- 8.8 =.

ELAP~ TIfK (HGURS)

=-

i CLRT

,~

?

8. 288 CALCULATE9 TOTAL JIHAD LEAK RATE.:-<LEXMi //DAY):.

SCAgS BB. 165-f87

? ?

8. 828 3.8 =: 4. 5:-

ELAPSED =. Tits (~B)

CLRT 843489. --.

COÃf'AINNENT MASS BULBS) 84AHB BD. 165-f82 843368.:=

843329. -:

?

843286.=.

843246.--

7 843288.=: 3. 9:-

ELAPSE:- TDK

CLRT 84.389 =.

~ '

2

'84. 18(mj:-

84.868 =.

C r

83. 848:-

83. 828:-"

83.788 = i.5= 3.8= 4.5:-

ELAPSE) =-

TItK (HOURS)

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GENERAL

I CO ARIZONA PUBLIC SERVICE ANY I

PALO VERDE NUCLEAR GFtlFRATING STATION PRESSURE GAVGF. CAL I BRAT JOt4 PROGRAM PRESSURE GAUG'E 1 PRESSURE GAUGE 2 CALIBRATION TRUF. GAUGE htULTIPL ICATION CORRECTION GAUGE t1ULT IPL I CAT ION CORRECTION POINT PRESSURE READING FACTOR CONSTANT READING FACTOR CONSTAhlT 0.000 a 0.000 0. 000 1.01607 0. 000 1 00706 0.000

4. 994 4.915 4. 959 1.01939 -0.016 1. 01052 -0.017

9. 989 9.815 9. 902 1.01628 0.014 1.01134 -0.025 14 '83 14. 729 14.840

- 1.01421 0.045 1.01113 -0.022 19.978 19.654 19.780 1.01442 0.041 1.01?37 -0.047 a 24.577 '4.972

24. 713 1 ~ 01380 0.056 1.01113 -0.016

29. 967 29.504 29.653 1 ~ 01236 0.098 1.01277 -0.065

34. 962 a 34.438 34.585 1.01196 0.112 1.01196 -0.036 39.956 a 39.373 39.520 1.01102 0.149 1.01305 -0.080 10 45.001 44.363 44.500

-( 1.01032 0.180 1.01442 -0.141 49.995 49.306 49.423 1.00868 0.261 1.01360 -0.100 12 54.990 a 5$ '.258 54.351

-( 1.00889 0.250 ( 1 '13'59 -0.100 13 59.986 a 59.210 59.280 1.00909 0.238 1.01421 137 14 64.981 a 64.160 64 '05 1.00584 0.446 1 '0828 0.245 15 69.975 a 69.125 69.158 1.00422 0.558 1.00868 0.216 16 74 '70 74.099 74 '10 1.00970 ~

0.152 .1.00442 0.532

'17 79.964 79.045 79.082 1 '0624 .0.425 1.00060 0.834 18 84.959 84.009 84 '74 0.98970 1 '16 1 F 00000 0.~885 19 89.953 89.055 89.068 a 0.99194 1 ~ 616 0.99842 1 026 94.998 a 94.141 94 ~ 121 1.00726 0. 174 0:99820 1.046 21 99. 993 a 99. 100 99. 125

t~

J

0 PALO ARIZONA VERDE PUBLIC NUC(.EAR SERVIC ANY GENERATING STATION II.RT SUB-VOLUI1E WEIGHTING PROGRAht DATEs 4-30-85 TII1Es 12s02s 17 DAS TYPE OF CONTA I NI1EI4T DAS TYPE OF CONTAINhIENT CHANNEL NO. SENSOR WEIGHTING FACTOR(%) . CHANNEL NO. SEhlSOR WEIGHTING FACTOR(%)

1 RTD¹ 1 4. 83 2 RTD¹ 2 4. 83 3 RTD¹ 3 4. 83 4 RTD¹ 4 4. 83 5 RTD¹ 5 4. 83 6 RTD¹ 6 4. 83 7 RTD¹ 7 4.33 8 RTD¹ 8 4.33 9 RTD¹ 9 4.33 10 RTD¹10 ll 13 RTD¹11 4 '3 12 ~

RTD¹12

4. 33 4.33'.

RTD¹13 3.77 14 RTD¹14 77 15 RTD¹15 3. ~ 77 16'8 RTD¹16 3.77 17 RTD¹17 3. 41 RTD¹18 3. 41 19 RTD¹19 3. 41 20 RTD¹20 3. 95 21 R'I D¹21 3. 95 22 RTD¹22 3. 95 23 RTD¹23 3. 95 24 RTD¹24 3 95 25 DEW CELL¹ 1 28. 97 26 DEW CELL¹ 2 00. 00 27 DEW CELL¹ 3 20. 52 28 DEW CELL¹ 4 20. 52 29 DEW CFLL¹ 5 14.99 30 DEW CELLO 6 14. 99 FAULTY PRESSURE GUAGE 2.

THE CONTAINt1ENT VOLUHE IS 0.2600E+07 CUBIC FEET THE NUI1BER OF RTDS IN USE ARE 24.

THE TOTAL PERCENT FOR RTDS IS 100.000 %

THE NUI1BER OF DEW CELLS IN USE IS 6.

THE TOTAL PERCENT FOR DEW CEI.LS IS 100.000 %

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ML17299A347

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