ML20081C051
| ML20081C051 | |
| Person / Time | |
|---|---|
| Site: | Cook, 05000000 |
| Issue date: | 04/10/1978 |
| From: | AMERICAN ELECTRIC POWER CO., INC., INDIANA MICHIGAN POWER CO. |
| To: | |
| Shared Package | |
| ML20081B916 | List: |
| References | |
| FOIA-83-296 NUDOCS 8310310080 | |
| Download: ML20081C051 (121) | |
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'- d IICHIGAN
' RECORDS FACILITY BR ANCH I.
)MPANY j
; REALTOR CONTAINMENT B~UILDING INTEGRATED LEAK RATE TEST i
(PRE-OPERATIONAL) L. j ptCAN Ettc7 Y c AEP "O WER SYST i 8310310080 830706
" PDR FOIA CONNOR83-296 PDR
b o , D. C. COOK NUCLEAR PLANT - UNIT NO. 2 ' REACTOR CONTAINIO!T BUILDING INTEGRATED LEAK RATE TEST _ (PRE-0PERATIONAL) TABLE OF CONTENTS
,- SECTION EAGE 1.0 Introduction 1 2.0 Integrated Leak Rate (Type 'A') Test Acceptance Criteria 2 30 ILRT (Type 'A') Test Results 31 Leakage Rate Summary 3 32 Discussion of Type A' Results 3 33 Discussion of Type ' C' Leak Rate Penalty 5 4.0 Conduct of Test 4.1 Organization of Test 7 4.2 Log of Time and Events 10 50 Test Instrumentation and Equipment 5.1 Test Instrumentation Specifications ly 52 Sensor Locations 19 I
53 Pressurization Apparatus 23
. 6.0 containment Model and Leak Rate Calculations 6.1 Discussion of Containment Free Volume 26 t
6.2 Containment Volume Weighting Factors 29 63 Temperature Sensor (RTD) Weighting Factors 30 6.4 Containment Leak Rate Equations 32 6.5 Statistical Treatment of Data 35 6.6 Discussion of Computer Program 39
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- o TABLE OF CONTENTS i SECTION EA25 70 Analysis and Interpretation 71 Discussion of Graphical Test Data 5'+
72 Discussion of Parametric Study 63 73 Instrument Error Analysis 66 8.0 ILRT Tabulated Sitmmary gg 90 Local Leak Test Program 106 10.0 References lig
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i I l AEP:NRC:0002C Errata and Additions to the Report on the P.eactor Containment Building Inegrated Leak Rate Test (Pre-Operational) for
. Donald C. Cook Muclear Plant Unit 2 Operated by the Indiana and 1 Michigan Power Company-l Page Comment 1 To be consistent with rest of report, 0.25 in 2nd paragraph should be preceded by minus (-) sign.
2 LAM sh,ould be L am, LA should be La and L'AM should
. . , , be L am' 3 Same comment on subscripts am as above. Item E,
-0.00S1, is Item D-A, not A-D.
4 Subscript am, as per comment above. 5 Subscripts am, as per comment above. 8 Person, not man in 1st line under Containment Inspection Group, i 16 Hygrometer, not Hydrometer. 18 PSIA, not PSIG in Pressure / Accuracy box. 22 On Fig. 5.1, the number "51" appears twice in the section J-9 view. The "51" in the triangle with "53" at K-7 should be "55". 23 Stage, not state in 4th line. 24 Was, not has be, in 6th line. 35 Axes, not axis in 4th line of Section 6.5. I Run-on sentence in 2nd to last line. 37 Additional information: 'the confidence interval i used is two-sided. 57 . Effect,not affect in 7th to last line.
< Periodic, not periodi-c in last line.
63 Effect that, not affect in 4th line. Delete "so" in 2nd line of 3rd paragraph. l
Page Comment 64 Insert "that" before "the" in 4th to last line. Effect, not affect in 4th to last line. 65 To avoid ambiguity, insert .75La'after " allowable leak rate," in 3rd to last line of 2nd paragraph and at end of 3rd paragraph to show what is meant
- by allowable leakage.
66 Insert "that" at end of 2nd to last line. . ~ 105 & 106 Additional information: the acceptance criteria for Type 'B' and 'C' leak rate tests were determined as fcile.s: the acceptance criteria on p. 105 were gi/an in the e:h. Specs. The acceptance criteria on
- p. 106 were determined by the licensee within the constraints of 10 CFR 50, Appendix J.
116 Reference 10.5 naads publisher, city and year
,rublished: International Textbook Company, Scranton, PA,-1968.
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1.0 INTRODUCTION
The Pre-Operational Integrated Leakage Rate Test (ILRT) for the Donald C. Cook Nuclear Plant - Unit 2 Reactor Containment was successfully completed on October 2, 1977 by members of the Indiana and Michigan Power Company ana the American Electric Power Service Corporation. As per FSAR and Technical Specifications the containment allowable leakage rate L, is limited to 0.25 percent by weight of the containment air per twenty-four hours at a pressure P a f 12.0 PSIG. In conformance with the criteria specified in Appendix 'J' of 10CFR 50 this allowable leakage is reduced to 0 75 L a which is equivalent to -0.1875 percent by weight per day. The ILRT was performed as specified in the I&M approved Pre-Operational Test Procedure 2 PO-033-334 written'by AEPSC. The American National Standard - ANSI N45.4-1972-Leakage Rate Testing of Containment Structures for Nuclear Reactors and 10CFR 50; Appendix 'J' were used as guidelines for the procedure as well as
, for the associated leak rate calculations. The absolute test method was used to calculate the leakage rate using data taken e
every thirty minutes for thirty-one and one-half hours. The normalized weight of original air remaining.in the containment determined from these calculations was plotted against time and a statistically averaged leakage rate in per cent by weight per day was obtained by a linear least-squares fit to the resulting graph. ( Following the thirty-one and one-half hour test, a Supplemental Test was performed by imposing a known leak on the containment to verify the validity of the original measurements. O
2.0 INTEGRATED LEAK RATE (TYPE 'A'S TEST ACCEPTANCE CRITERIA . 2.1 as specified in Section 6.0 of D. C. Cook Kuclear Plant Pre-Operational Test Procedure 2 FO-o33-334 and in accordance with 10CFR 50; Appendix 'J' requirements for c-Type 'A' leak tests, the test was considered acceptable when the following had been verified: 2.1.1 The measured leakage rate (LAM), as determined by a linear least-squares fit to a graph of calculated points, proves to be less than 0 75LA as specified in the D. C. Cook Nuclear Flant - Unit No. 2 Technical Specifications. 2.1.2 The accuracy of this test has been verified by performance of the Supplemental Test. The measured leakage rate (LAM) is validated when the difference between the leakage rate L'AM, determined from the Supplemental Test, and the leakage rate LAM, determined from the linear least-
~ squares fit to the graph of calculated points, is within = 0.25 L g.
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30 ILRT (TYPE 'A'T TEST RESULTS ,. 31 Leakage Rate Summary Measured Leakage
- Allowable Leakage
(% wt./24 hrs.) (% wt./24 hrs.) A. ILRT Type 'A' Leak Rate LAM -0.00428 -0.1875 B. Supplemental Test Composite Leak -0.19028 N/A C. Imposed Leak -0.1779 N/A D. Leak Rate L'AM (Item B-C) -0.01238 N/A l E. Supplemental Test Correlation -0.0081 0.0625 (Item A-D)
- Negative sign denotes leakage out of containment.
N/A Not Applicable. 1 32 Discussion of Type 'A' Test Results As indicated in the Leakage Rate Summary above, the ILRT Type 'A' leak rate LAM and the results of the Supple-mental Test are well within the maximum allowable limits for acceptance established in the D..C. Cook Nuclear Plant FSAR and Technical Specifications. The containment integrated leakage rate reported here was determined from data recorded during the September 30
. o ,
, 32 Discussion of Type 'A' Test Results (Cont'd) through October 2, 1977 performance of I&M Pre-Operational Test Procedure 2 PO-033-334. A discussion of the mathematical and statistical treatment of this data to yield the containment leakage rate may be found in ( Section 6.0 of this report. i Item 'A' of the Leakage Rate Summary.is the measured containment leakage determined after thirty-one and one-i half (31 5) hours of data taking, recorded at thirty l 1
~
minute , intervals. The measured containment leakage rate j was calculated using the " Absolute Method" on a " Total [' Time" basis as described in American National Standard 7 N45.4 - 1972. i
,, In accordance with 10CFR 50; Appendix 'J' the accuracy of the Type 'A' leak test was verified by the performance of a Supplemental Test. The Supplemental Test was conducted for eight (8) hours while a metered leakage of f 2 77 SCFM (0.1779 % wt./24 hrs. equivalent) was imposed
, on the containment. Thus, Item 'B' of the Leakage Rate 7 s
Summary represents the composite leakage measured for the
; containment, that is, containment leakage plus the imposed leak.
When the known value of the imposed leak is deducted from the measured composite leak the resultant is the contain-ment leak rate L'AM measured during the Supplemental Test, s _y_ _ _ _ . _ _ _ _ _ _ _ _ _ ____ __________.__J:t_ _ _ _ _ _ _ _ __
32 Discussion of Type 'A' Test Results (Cont'd) This is represented as Item 'D' cn the Leakage Rate Sum =ary. The results of the Supplemental Test, that is, the correlation between ILRT Type 'A' leak rate (LAM) and the resultant containment leak rate (L'AM) is indicated as Item 'E' on the Leakage Rate Summary. Here the difference s between the containment leak rate reasured during the Type 'A' test and during the Supplemental Test is shown to be -0.0081 % wt./24 hrs. As stated in Section 2.0 "IERT Acceptance Criteria", the maximum allowable
- i. difference between these measurements shall be within
- 0.25 L awhich is equivalent to
- O.0625 % wt./24 hrs.
( As can be seen from the Leakage Rate Summary, excellent
, correlation has been achieved.
33 Discussion of Type 'C' Leak Rate Penalty Prior to the performance of the Unit 2 Pre-Operational ILRT, the NRC imposed a prerequisite that required the draining and venting of additional systems or portions f of systems not specified in the test procedure. In the event this could not be implemented, the results of the
; isolation valve local (Type 'C') leak tests for these systems would have to be added to the measured contain-ment (Type 'A') leak rate.
~
A review of the affected services revealed that it was not practical, due to the existing piping configurations, 4 t
33 Discussion of Type 'C' Leak Rate Penalty (Cont'd)
- to comply with this prerequisite for all cases. 'lhere possible, the test procedure was revised to implement the aforementioned prerequisite. For the remaining services, the associated containment isolation valve local leak rate test data was taken from Fre-Operational Test Procedure 2 FO-033-332.
i As a result of the measurements made during the local i valve leak rate tests, the total Type 'C' leak rate penalty was calculated to be -0.0294 % wt./24 hrs. Thus, the total reportable containment leak rate is ' increased to (-0.00428) + (-0.0294) or -0.03368 % wt./ f 24 hrs. (0.14 L,) which is still well below the acceptance criteria of -0.1875 % wt./24 hrs. (0 75 La )* f L s x
l 4.0 C0liDUCT OF TEST
, 4.1 Organization of Test The D. C. Cook Plant Performance Engineering Section was responsible for the Integrated Leak Rate Test. The functions performed by persons involved in the test
[ could be subdivided between pre-test activities and test
- activities. Figures 4.1 and 4.2 illustrate the organiza-6 tion of pre-test and test activities, respectively.
L Pre-Test Restonsibilities
,~ Test Supervisor Organized efforts to ensure the readiness of the Unit 2 f' containment systems and test instrumentation for the conduct of this test. Responsible for the proper t ! documentation of the test, and. instrument calibration.
Operations Interface Arranged for operations manpower to perform containment
~
9 isolation valve line-up and system venting as required by the test procedure. f Startup Interface ( Coordinated construction work required to place the i
, containment in the final state of readiness for the test, and coordinated the test schedule with the construction schedule.
. . Instrumentation Coordination Group Four performance engineers, each responsible for the t
t . ._ .
Pre-Test Rasconsibilities (Cont'd) proper operation and set-up of some portion of the test instrumentation required for this test. I O Technicians Performed work required to place test instrumentation
, in proper operation for the test.
( Containment Inspection Coordinator Coordinated Containment Inspection Group. Responsible for evaluating the containment inspection results and coordinating efforts for resolving any discrepancies in the containment systems that vould jeopardize the p success of the JLRT. f Containment Inspection Group Four two-man teams dispatched to inspect the contain-ment, containment electrical and piping penetrations,
; and containment system piping for any deficiencies.
1 Reported to Inspection Coordinator. f 4.1 Organization of Test
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Test Resnonsibilities Test Supervisor
}
(1 per 12 hour shift) Responsible for maintenance of test documentation, l data inspection, and the general conduct of the test. Computer Operator /AEPSC Cognizant Engineer and Support (1 per 12 hour shift) Responsible for the on-site processing'of raw data and
/
-I
Test Restonsibilities (Cont'd) results analysis. Time Keeper / Data Coordinator (1 per 12 hour shift) Coordinated data collection and transfer of data to the computer input format. Data Takers I (4 per 12 hour shift)
, Responsible for the recording of specific test instrument readings.
Technical Support. Coordinator
, (1 per 12 hour shift) i Responsible for dispatching of manpower for support in
( the area of test instrument maintenance, repair work,
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installation and removal of the pressurization line spool piece and flanges, and the emergency support of the regular test crew. f Technicians (2 per 12 hour shift) Responsible for maintaining all test instrumentation ( in a proper operating condition. 1 Startup and Maintenance (On Call) Responsible to assist and coordinate any repair work that may be required during the test. s Containment Inspection and General Support Group (On Call) Provide manpower from the pre-test Containment ,1 l Test Resnonsibilities (Cont'd) , Inspection Group for troubleshooting containment leakage and support to the regular test crew. 4.2 Log of Times and Events j~ Prior to the commencement of this test, an inspection of all accessible interior and exterior surfaces of the 1 containment structure, containment electrical penetrations, piping penetrations, associated piping, vent valves, and penetration and weld channel pressurization piping was performed. This was a visual inspection intended to uncover any evidence of deterioration or system de-ficiencies that would' violate the integrity of the containment pressure boundary. The inspection did not
\ uncover any adverse conditions. Therefore, after having verified the completion of the valve line-up and all of the other test prerequisites and initial conditions,
{ ( containment pressurization was initiated. f Pressurization of the Unit 2 reactor containment began at 0114 hours on September 30, 1977 Data collection for this period consisted of an hourly log of containment average temperatures, pressures, vapor pressures, and ambient temperature and pre 4sure. At 1200 on September 30, a pressure of 12 5 PSIG was achieved and pressuriza-tion was terminated. This marked the beginning of the stabilization period.
- ~
4.2 Log of Times and Events (Cont'd) All test parameters were recorded in half hour intervals for a preliminary determination of the containment leak rate and the establishment of stability criteria. The stabilization period was terminated at 0600 on October 1, f when stability criteria had been demonstrated. The pressurination spool piece was removed, a blank flange installed and bubble tested for leak tightness. The Integrated Leak Rate Test data collection began at s 0600 on October 1. Data was collected in half hour intervals for 31 5 hours, 7 5 hours in excess of the f 24 hour requirement. At 1330, October 2, the test period was declared over and a leakage of 2 77 scfm was established as the " imposed leakage" for the Supplemental Test period. The " imposed leakage" was allowed to stabilize for a I half hour and data collection for the Supplemental Test
, began at 1400 on October 2. The test data was collected in half hour intervals for 8 hours, 2 hours in excess of the 6 hour requirement. The test was declared complete at 2200 on October 2. The containment was subsequently i
t depressurized and systems were restored to normal as required by plant Operations. During the performance of ILRT, repeated problems with j the on-site method of processing raw data proved tc be 4.2 Log of Times and Events (Cont'd) too overwhelming, due to the large volume of data, to calculate up to the minute leakage rates. Moreover, because of the ever increasing backlog of data, the continued use of the on-site programmable calculators was eventually abandoned. The collection of data continued, however, based upon the trend of leak rate calculations performed early in the test which indicated a leak-tight containment. Thus, the final hours of data collection for the Type 'A' Test and all-eight hours for the Supplemental Test were conducted without the benefit of on-site knowledge of the final measured leakage rate. 1 It was for these reasons that the Type 'A' Test and
,- Supplemental Test were extended beyond the original i \'
twenty-four hour and six hour test periods, respectively, to provide additional data for subsequent analysis. j Upon termination of the Supplemental Test, a second ( attempt was made to present on-site leakage rate calcu-f lations to the NRC inspector for his review. In place
, of the programmable calculators, the original computer l programs used for the Unit 1 Pre-Operational ILRT were i accessed from the American Electric Power Service Corporation's computer disc storage. A computer punch card deck was assembled from the Unit 2 ILRT data and transmitted to the New York computer facility via micro-wave. A complete review of New York computer printout
, t
_ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ ____m______
o 4.2 Log of Times and Events (Cent'd) revealed that the data format and the containment model represented in the existing program would not be accept-able for this test and in effect on-site leak rate calculations were not possible. l' On September 21 and 22, 1977 members of the American Electric Power Service Corporation, Indiana and Michigan { Pouer Company and the Nuclear Regulatory Commission met to discuss all unresolved items concerning the ILRT. A presentation was made to the NRC inspector describing the revisions to the original ILRT computer program and the
). - basis for the revised containment model represented therein. After the presentation was concluded, a thorough i \ review of the data and final leakage calculations was made by the NRC inspector. The results of the NRC inspection were that no items of noncompliance or l,
deviations were identified and that the Unit J2 Fre-Operational Containment Integrated Leak Rate Test was b indeed acceptable. ( l l L - 13-W Eh 4+ &
PRETEST ACTIVITIES Test Supervisor I P Operations Start-up Instrumentation Containment Interface Interface Coordination Inspection Group Coordinator i
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Instrument ! Containment i Technicians Inspection Group i Fig. 4.1 1 ( .. I TEST ACTIVITIES i i l Test Supervisor , l Computer Operator Time Keeper Technical Support AEPSC Cognizant Data Collection Coordinator ( Engineer and Coordinator Support ( ( l Data Takers l j Instrument Startup ' Containment Technicians and Inspection Maintenance and General (On Call) Support Group (On Call)
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Fig. 4.2 L. 14 ,
50 TEST TUSTRUMENTATION AND ECUIPMTI?T 51 Test Instrumentation Specifications The best state of the art pressure, temperature, and vapor pressure instrumentation was employed during the ILRT test. The ice condenser reactor containment is l unique in the fact that containment design pressure is limited to 12 PSIG. This low pressure requires more accurate instrumentation to detect leakage to the same degree as for conventional containments with design i pressures of 30-60 PSIG. Six precision Mensor Quartz Manometers were used to measure containment absolute pressure. Two sensed lower volume pressure, two upper volume, and two ice condenser s pressure. A seventh Manometer measured ambient pressure during the test. Each instrument was supplied with an NBS certified standard calibration correction chart. These instrument corrections were pre-programmed into [ the leak rate computer program to allow direct input of b the manometer readings. When the aforementioned instrument r corrections are applied the manometer accuracy is (' specified as
- 0.01% full scale with manometer resolution specified as 0.0001 PSIA.
The three containment compartments were instrumented with a total of forty-six (46) precision RTD sensors. The number of sensors for the Upper, Lower and Ice Condenser compartments was sixteen (16), twenty-three (23) and t - - - - -._ _
5.1 Test Instrumentation Specifications (Cont'd) seven (7) respectively. Unlike the Unit 1 Pre-Operational ILRT, platinum RTD's with stainless steel probe bodies were selected. The sensors temperature coefficient was specified as 0.00385 ohms / ohm /oC with a resistance of 100 St = 0.2% at 0*C. The 100.fL platinum RTD's were found to be much more durable and as accurate as the 2330,J2. copper sensors used during the Unit 1 ILRT. Each platinum sensor was calibrated with a linearized bridge amplifier as a matched set. Both the sensor and its associated bridge amplifier carried the same serial number so that matched calibration would be maintained. All RTD sensor / bridge calibrations are certified traceable to NBS. The 0-50 mV bridge output was connected to a digital printout device programmed to accept a linear 0-50 mV output for l: an output of 0-100aF. Overall temperature monitoring
\
system accuracy is
- 0.078*F.
i' Four Cambridge Dev Point Hydrometers were used to sense
! containment humidity during the test. Two units sensed L i lower volume dew point, one Ice Condenser and one in the upper volume. Each unit is complete with its own sample pump which draws the sample through the mirror surface sensor. The sensor is cooled until' vapor is formed on the mirror surface and electronic circuitry is used to maintain an equilibrium condition on the sensor. The L _-
51 Test Instrumentation Specifications (Cont'd) sensor temperature is measured by the use of a platinum RTD. Each RTD had certification to UES. The overall dew point temperature sensing accuracy is = .5 F. A rotameter was used during the Supplemental Test to measure and maintain a constant flow rate for the imposed leak. The rotameter has a calibrated range of 0 58 to 5.86 SCFM air at one atmosphere and 70 F and an accuracy , ; of = 1.0% of full scale. As all test instrumentation associated with the leak rate test, the rotameter has its calibration traceable to U.B.S. The chart shown in Table 5 1.1 lists the specifications of test instrumentation used during the test in tabular form. ( f L. t e
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t e m u c - u o a - n e d f id a r b e r te e u r u p y e as R S e T t li r t T ze Preag re - r e n o _ t m at o m _ ro ed en r o d an ua 0ni 0ir ni ir i r t o r o QM 1LB LP M H B g
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m e e g t e d s l g ei e ey e a a m rr r rS r t G e uB u u tu n t e t/ t tl nt e e I r as at al ia m r u rr ru ra or e u s s eo ps eo pd er pe Pe p l pk s s e r mn ee ma ee mv e wm ee pa ue e r P TS TR T (O DT SL P s
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5.2 sensor Locations - The Test Instrumentation, which included forty-six RTD's, six absolute pressure reading quartz Manometers, and six vapor pressure sensing points, was located throughout the containment to give an accurate accounting of the con-i~
, tainment environmental conditions during the test. The r- actual location of each sensor can be seen on the i
elevation and plan views of the containment found on Figure 5 1 of this report.
~
The breakdown of sensor locations as per containment volume are as follows: 5 2.1 UPPER VOLUME a) Sixteen Resistance Temperature detectors [
- 1. ETR-101 9 ETR-109
- 2. ETR-102 10. ETR-110 3 ETR-103 11. ETR-lll l
4. ETR-104 12. ETR-112 I 5 ETR-105 13 ETR-114
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- 6. ETR-106 14. ETR-128 i
15 L 7 ETR-107 ETR-133
- 8. ETR-108 16. ETR-113*
b) Two absolute pressure reading Quartz t Manometers. c) One vapor pressure sensing point (one t
- Hygrometer). l
- With the reactor missile shield removed, this RTD is considered to be in the Upper Volume, t - -
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v 52 Sensor Locations (Cont'd) 1 5 2.2 LOWER VOLUME I
, a) Twenty-three resistance temperature detectors
, 1. ETR-122 12. ETR-135 -
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- 2. ETR-123 13 ETR-136 3 ETR-124 14. ETR-137
- 4. ETR-125 15 ETR-138 F
! 3 ETR-126 x 16. ETR-139 r 6. ETR-127 17 ETR-140 l ,
18. 7 ETR-129 ,- ETR-141
- 8. ETR-120 --
19 ETR-142 > 20.
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9 ETR-131 ETR-143 s i
- 10. ETR-132 21. ETR-144 3
- 11. ETR-134 22. ETR-145 g, L -\
23 ETR-146 6 i_ A b) Two absolute pressure reading Quart'z ( .,
.4 .g f
3 Manometers. f
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c) Four vapor pressure sensing points'(two.' Hygrometers). _
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[ 523 ICE CONDENSER VOLUME a) Seven resistance temperature detecEors n l t
- 1. ETR-ll5 5 ETR-119 -
i 2. ETR-116 6. ETR-SJO 3 ETR-117 7 ETR-121 1
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- 4. ETR-118 h '
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523 ICE CCI DE::SER VOLUIE (Cont'd) b) -Two absolute pressure reading Quart:: Manometers. c) One vapor pressure sensing point (one Hygrometer). 4 9 g I 6 a 4 i
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,. 53 Pressurization Apparatus The Plant air system was used to pressurice the contain-ment for the Integrated Leakage Rate Test. A three
{ state centrifugal air compressor located in the turbine room supplies compressed air to the plant air system.
- The compressor is designed to provide 1500 cfm of oil free compressed air at a discharge pressure of 100 PSIG
[~ continuously. Air discharged from the plant air compressor i t. retains the third stage heat of compression. An after-cooler installed in the discharge line, is designed to cool the air to within 10 F of its inlet cooling water 7 temperature. The condensed moisture resulting from the
- 3. , cooling is removed by a cyclone-type separator installed ,
i immediately downstream of the aftercooler. The air
, discharged from the moisture separator is fed through the plant air system to the containment test pressurization filters and dryers. In order to avoid condensing water vapor during the test the plant air supplied is dried 1 ,
to a dew point that is below the coldest temperature anticipated in the ice condenser. Two parallel, 100 t r percent capacity strings of prefilters prevent contam-ination of the drying dessicants from mositure carryover 4 (' or scale. Two afterfilters in parallel' protect the , l. containment from dessicant dusting. I b The dried and filtered air is fed through a three inch'
-f test line, spool piece, and valve to penetration #CPN-57 L
This valve was used to throttle the' air flow during - r
,. pressurization and depressurization.
~ e + m .e e % + + + - ..+.-e .p..., += . * - - * . . < - - = . < * - . . -e
53 Pressurization Apparatus (Cent 'd) The valve uas used to isolate the containment e volume from the pressurication system after pressurisation to the test pressure was complete. The spool piece was removed after stabilization ( of the containment had be achieved. A blank I. flange was installed and leak tested to prevent out leakage from the pene ' tion. See , Figure 5 2 for sketch of pressurizatir apparatus. 8 9 t f ( I L i t I u .. 4 l
~ >,..p= = , _
l ' a C u T %
.1 ' WE M ME QI- y ZO FF092 TV db '
g 50 ' 5 I l- M O Id M
-SC a
c4 /N al'u s . 2 -
. m Y. E
-,cl.
i
$" a.4 i -
~
a Mv Cd. { b m m I CV
- i. Y
{] e cv. Ut 1 w - i C. . LN a ipe.3
- t--
J La l TO - 3 - l Cf CD C G ' { CL O > .
- C 4 c
- C w M i l
w P i
~
g__, - g L... m x a s . 10 f ' -+^ - ? t~ I N I g et s c2 m, {,g i s Y \ 5 6 I I < 6
=
x
.Z [5a Si i :: o i\ w t i e e s E<
u l-E rm N EE t c z ' is an O I
, MU \\
\
m s . - e. .. , ..,4 . -i%, . . . . _ . . ..
r-6.0 CotiTATI!?E?!? MODEL AtiD LEAK R;TE CALCULATIOt S h 6.1 Discussion of Containment Free Volume The reactor containment is designed to insure that I acceptable limits for leakage to the environment of [~- radioactive materials are not exceeded under conditions t resulting frcm the Design Basis Accident for doses dictated by the 10CFR 100 criteria. The steel-lined, reinforced concrete containment structure, including i I foundations, access hatches, and penetrations is designed and constructed to maintain full containment integrity p-when subjected to accident forces. The containment
- j. design pressure is twelve (12) PSIG.
The reactor containment is divided into three co'mpart-ments; a lower compartment which houses the reactor and Reactor Coolant System, an intermediate compartment housing the energy absorbing ice bed and an upper compartment which accommodates the air displaced from the other two volumes during the unlikely event of a loss-of-coolant accident. A detailed tabularization of the individual free volumes which comprise the three containment compartments is i listed on Table Q.P.1-1 of the D. C. Cook Euclear Plant ( FSAR. The free volume study was originally compiled in t. response to Question Q.P.-l concerning the input para-I meters used in the ECCS evaluation model and may be
, found in FSAR Appendix 'P' (Amendment 60).
1 i L 1
; m. 1
)
j
- 1 6.1 Discussion of Containment Free Volume (Cont'd) f i
The following is a summary of FSAR Table Q.F.1-1 on a compartmental basis: TABLE 6.1.1 COMPKRTMENT FREE VOLUME (FT.3) Upper Volume 734,829 Lower Volume 365,614 Ice Condenser 163,713 I Total Free Volume 1,264,156 l [~ as was previously mentioned, the free volume study was L originated for ECCS model evaluation and therefore, while the total free volume figure is correct, the compartment breakdown does not reflect the true contain-ment configuration during the Integrated Leak Rate Test. Structural barriers within the containment result in a t normal operating containment configuration with the l 1 following free volume distribution: l l
" l TABLE 6.1.2 l
[ COMPARTMENT FREE VOLUME (FT.3) L. Upper Volume 687,819 r Lower Volume 365,614 Ice Condenser 210,723 Total Free Volume 1,264,156 i m. The differences between Table 6.1.1 and Table 6.1.2 lie
-27 t
,m. em . ..r*4e, e m m* %y+.=.. ='+=v e + =
= ;
- f 6.1 Discussion of Containment Free Volume
[' in the fact that in Table 6.1.1 the upper volume includes the free volume (47,010 Ft.3) of the ice condenser upper [ plenum which, under normal circumstances, is physically
.. separated from the upper volume. It is also important i
L to note at this time that the ice condenser free volume { in both Table 6.1.1 and Table 6.1.2 include the free volume that would normally be displaced after ice basket i loading. Thus, to obtain the actual free volume for this compartment the volume of ice resident in the ice baskets r~ must be deducted. l: Prior to the performance of the Unit 2 Pre-Operational ILRT, ice basket weighing data was collected from which the average weight per basket and the total volume of ice was calculated. These values were found to be 1481 lbs./ basket and 53,412 Ft.3 total ice volume based upon an
' ice density of 56 lbs./Ft.3, During the performance of the Unit 2 Pre-Operational ILRT, L
the missile shield normally located directly above the reactor cavity was removed. The reactor cavity, which is identified as Volume XIV in FSAR Table Q.P.1-1, has a free m. volume of 16,147 Ft.3 and is normally associated as part
'of the lower volume.- With the missile shield removed, however, direct ccmmunication with the upper volume is established.
. l ._ ___... _ __ m
, When Table 6.1.2 is adjusted to reflect the reduction in L ; L.
_ _ . _ . - ~. ._ -
6.1 Discussion of Containment Free Volume (Cont'd) ice condenser free volume due to the displacement of ice t and the re-distribution of Volume No. XIV, the following I
! free volume distribution thus represents the actual ILRT values:
TABLE 6.1.1 r-
! COMP.ARTME!!T FREE VOLUME (FT.3)
Upper Volume 703,966 [ . Lower Volume 3'9,467 I~ Ice Condenser 159,311 Total Free Volume 1,212,744 6.2 Volume Weighting Factors Volume weighting factors (VWF) are used in the compart-f mental calculation of the containment air fraction. The definition of a volume weighting factor is the ratio of the free volume for a given containment compartment, te, L Upper Volume, Lower Volume or Ice Condenser, with respect to a " Base Volume". r For purposes of the Unit' 2 Fre-Operational ILRT the L Lower Volume was selected as the " base volume". Thus, for the containme.tt free volume distribution of Table 6.1 3 the free volume ratio for each containment compart-ment using the Lower Volume as a " base volume" results
, in the following volume weighting factors:
6 L e i s-
+
L l . - . . . - . _ . . _ - . - _ _ _ _ _ _ _ _ __ _
t 6.2 Volume Weighting Factors (Cont'd) 1aBLE 6.2.1 i Coi TAIN G'T CO?G A?TME?!? V'c F Upper Volume 2.0144 Lower Volume 1.0C00 Ice Condenser O.4559 A discussion of how the volume weighting factors (VWF) { are applied in the leak rate calculations is presented { s in Section 6.4 of this report. F 63 Temperature Sensor (RTD) Weighting Factors A parameter of importance concerning the determinatien of containment leak rate is the containment air tempera-ture. Assuming an isovolumic relation exists within the l containment pressure boundary, by definition of the f perfect gas law the pressure of a gas varies directly L with temperature. Therefore, it is necessary to L temperature ccmpensate the pressure measurement (s) made for each compartment with its associated average air temperature. P Due to large free volumes of air under consideration, it r- would require an infinite number of sensors per compart-L ment to determine the average air temperature by the simple arithmetic average of all associated measurements.
. u.
Being a finita number of sensors must be used, a
" weighted average" is computed for each of the three t
-30' -
'.L
6.3 Temperature sensor (RTD) 'deighting Factors (Cent'd) containment ec=partments. The weighted average temperature for each compartment is computed by summing the products of sensor reading and t
', its associated temperature sensor (RTD) weighting factor for all sensors located in that particular containment $ compartment. This =ay be expressed mathematically by:
1 i=n Tavg. = 35) K 1 T 1 i=1 I Where: T 4 = the measured te=perature
^
for sensor 1. K the associated sensor 1 = weighting factor. The temperature sensor (RTD) weighting factors are 5 derived by a volumetric analysis of each compartment to l determine each sensor's " representative volume" t Representative volumes are constructed by imaginary and/or physical boundaries separating the various
- temperature sensors within a particular containment
[ compartment. The volume contained within these boundaries L is calculated using approved scale drawings for the D. C. Cook Nuclear Plant. Once all the representative L volumes have been determined, the individual temperature L sensor (RTD) weighting factors are computed on a compartmental basis using the formula: e i
- o :
63 Temperature sensor (RTD) Weighting Factors (cont'd)
=
Representative Volume (Ft.3) Weighting Factor
$[3 Representative Volumes (Ft.3) r' The total of all temperature sensor (RTD) weighting factors for each containment compartment is equal to one.
?' 6.4 Containment Leak Rate Equations i As indicated earlier in this report, the American National Standard - ANSI N45 4 - 1972; Leakage Rate Testing of Containment Structures for Nuclear Reactors was used as a guideline for leak rate calculations. I' i The following is the deriviation of the equations used in the calculation of containment leak rate. { From the ideal gas law: PVo
= W oRT o and PV1
= W 1RT 1 Where: Pg = total absolute pressure in containment at the first test interval.
r P i
= total absolute pressure in containment at the end of test interval 1.
{ T U
= weighted average absolute temperature
( at start of test (*F + 459 7). L T u weighted average absolute temperature 1 t at the end of the test interval 1.
! l V = internal volume of containment assumed to remain constant.
1 L W = original weight of air in containment ) at first test interval. ; 1 l
6.4 Containment Leak Rate Equations (Cont'd) I W1 = weight of air in containment at the end of test interval 1. 4 ; R = gas constant for a perfect gas; applicable s to air for ILRT test conditions. ('t Therefore,
/~ Wo = PV g and W4 : P,V
_,m L RT o RT 1 1 If Wn is the normalized weight of air remaining in the I containment at the end of test interval 1, Then: Wn =W
', J Wo k Substituting, i Wn = PV x RT
_4 _.,,g. RT 1 PVc f" Since V and R are constants, Wn
- b PT
{ o1 L. f Compensating for condensation or evaporation of moisture i" within the air, r a w = (P 1 - VP1 ) T g ri (p _ ypg ) 7 i i Eauntion 6.4.1 i. k. L
6.4 Containment Leak Rate Equations (Cont'd)
. 'iner e ,
VP = <'ater
- vapor pressure at Cne 0
start of the test. t-c i VPy = vater vapor pressure at the end of test interval i. ! , \
. Thus, equation 6.L.1 =ay be used to cetpute the normalized l l
weight of air within a contaipment, of total volume V, I at the end of any time interval (1) during the test. J g Due to the physical separations between containment 4 - compartments and the distinct differences in their associated environmental conditions, inherent in an ice i condenser containment, the calculation for the normalized
\
veight of air is best determined on a compartmental P h t. basis. Thus it is assumed the total mass of air in the
, entire containment is equal to the sum of the individual f air masses for the three containment compartments.-
On this basis equation 6.4.1 is revised as, (- VWF (P-VP)
, + VWF (P-VP) * ^
(VwF (D-VP) m
' T -
U1 Li Ii
- y . . - - -
{ n . . . . . . VUF (P-VP)
+ VWF (P-VP.)
, + VWF (g-]Q)
* ^ T Uo Lo Io e
Ecuation 6.4.2
\
t-
's s
6.4 Containment Leak Rate Equations (Cont'd) Uhere: VWF = Volume Weighting Factor U = In subscript indicates Upper Volume
<' parameters.
L = In subscript indicates Lower Volume
,. parameters.
' I = In subscript indicates Ice Condenser parameters.
- ! 0 = In subscript indicates parameters at start of test. i= Ir. subscript indicates parameters at end of test interval 1. 1 As can be seen above, equation 6.4.2 is actually the
,- normalized weight equation 6.4.1 calculated three times,
[ once for each containment compartment. The fractional
, amount of air for the three compartments are proportion-i ately combined by the volume weighting factors (VUF; which are computed as described in Section 6.2 of this
, report.
( 6.5 Statistical Treatment of Data l L The resulting values of the normalized weight of air Wn , calculated as described in Section 6.4 of this report,
!- are plotted on a graph whose axis are W versus time. A n
- least-squares analysis of the resulting graph yields a
(. straight line. The slope of the regression line represents the' change in the normalized weight of air per unit of time, thus it t is the fractional leakage per hour. This is converted to t. 1 i
, - 3 5-
- .-. . . _ . - . , . _ _ _ . _ - - . . _ _ _ - ._ _ _ _ . . . . _ ~
._____m._._,,.,..._;
65 Statistical Treat =ent of Data (Cont'd) leakage rate expressed in per cent per day by multiplying by 2LCC. The slope (b) of the regression.line is computed by, e-t b - (2t
- 1) Z nw t - ZN n 2t k
(2t + 1) IC 2 _ ( gg t)2 Where t is the time in hours. r In order to determine the confidence limits on the leak rate analysis, the following calculations are performed: [ The vertical intercept (a) of the regression line is given by,
=
Bt2 ggy, _ gg 7g;g^ ,
^^
t a (2t + 1) E t2 _ ( g g)2 i ( The mean square deviation or variance of Wn is given by, 2 _ l8 (Wn - a - bt)2
/
n (2t - 1) The variance of the slope (b) is given by,
\
S 3 2 = Sfg 3$(t-E)2 Uhere I is the average value of time t. 4 =* *= -* ,v .--==..e.,., , , , g , , , ,
+
65 Statistical Treatment of Data (Cont'd) From the above prerequisite calculations, the confidence limits on leakage rate (slope b) are, expressed as [ B = KSb , where the value of 'K' is dependent upon the desired level of significance and the appropriate number f~ ( of degrees of freedom. The value of 'K' is taken from f- Table 6.5.1 of this report showing the distribution of
'K' with respect to the level of significance and the l number of degrees of freedom.
p The level of significance (et.) is the term used to describe degree of possible error associated with all
, points on the regression line. For a ninety-five (95) per cent confidence level the level of significance is i ; five (5) per cent. Thus, those values of 'K' listed under a le ml of significance (M ) of 0.05 are applicable, depending upon the existing degree of freedom.
Two constraints determine the regression line; the centroidal point (t, E n) and either the slepe (b) or
\ intercept (a). Therefore, if n is the number of readings / for W.,
the number of degrees of freedom (4 ) is given by, L. h=n-2 i During the ILRT, readings are takuc at time intervals of or.e half hour with time t equal to zero for the first reading. -Thus,thenumberofdegreesoffreedom())is ( also given by, i L. I ( ,
1 e Tables 309 T1BLE 6.j.1 Dis 7aisution or 2. o K
-K grus d Probabihty e freedorn , e 0 10 ( 0 u5 l 0 01 1 0 001 i ! 6.314 12.706 63.657 636.619 2 2.920 4.303 9 925 31.598 3 2.353 3.182 5.841 12.941 , 4 2.132 2.776 4.604 8.610 5 2.015 2.571 4.032 6.859 6 1.943 2.447 3.707 5 959 7 1.S95 2.365 3 499 5.405 , 8 1.860 2.306 3.355 5.041 9 1.833 2.262 3.250 4 781 10 1.812 2.228 3.169 4.587 11 1.796 2.201 3.106 4.437 12 t.782 2.179 3.055 4.318 ' 13 1.771 2.160 3.012 4.221 14 1.761 2.145 2.977 4.140 15 1.753 2.131 2.447 4.073 16 1.746 2.120 2.921 4.015 17 1.740 2.110 2.898 3.965 18 1.734 2.101 2.878 3.922 19 1.729 2.093 2.861 3.883 20 1.725 2.086 2.845 3.850 21 1.721 2.080 2.831 3.819 ; 22 1.717 2.074 2.819 3.792 ' 23 1.714 2.069 2.807 3.767 24 1.711 2.064 2.797 3.745 25 1.708 2.060 2.787 3.725 26 1.706 2.056 2.779 3.707 ! 27 1.703 2.052 2.771 3.690 28 1.701 2.048 2.763 3.674 29 1.699 2.045 2.756 3.659 30 1.697 2.042 2.750 3.646 40 1.684 2.021 2.704 3.551
% , 60 1.671 2.000 2.660 3.460 120 1.658 1.980 2.617 3.373 ' ' = 1.645 1.960 2.576 3.291 ( This tab 4e gives the values of a corresponding to war.ous values of the probaoihry e (lesel of signi6cance) of a randorn variab4e tallmq msaae the shaded areas en the Eeure. for a enven number of irgrees of free. enm e avadat er for the estimauon of error. For a one-saced tes. the enniidence hmits are obtamed for e/2
, Tks sab.e is taaea troom Tab 6e ill of Fisher L Yanes. .% usual Tobin for Baeterwat. Agnalse*et. and
.tfedwet /trwewe oubhshed by Ohsee & Bosd L :L. Ecanburgn, by permassion ei the authors and pubbsbers.
t. The above table is used to determine the appropriate j value of 'K' based on prevailing degrees of freedom. 1 This table has been extracted from Basic Statistical Methods For Engineers and Scientists. t I l f ;l i
. - .~ - .
..-~.._m-~ . ~ . _ , _ . _ _ . . . , . . . - _ . . , . _ _
6.5 Statistical Treatment of Data (Cont'd)
) = (2t - 1)
The text " Basic Statistical Methods for Engineers and 7 Scientists" by A. M. Neville and J. 3. Kennedy was used
)
i as a reference for the statistical analysis.
/
6, 6.6 Discussion of Computer Program The computer calculations performed for the containment leak rate analysis is implemented by two separate
/ programs.
The first program creates a data file from which the
~
second program for linear regression and confidence limits draws its information. The data file is established by first constructing a deck of computer 4 i punch cards containing the run number, elapsed time, 4
, and the corresponding temperatures, pressures and dew points as recorded at the end of each time interval
{ during the test. All calculations and printout formats L for each of the measured parameters are executed on a compartmental basis. ( The data file program takes the millivolt values i representing air temperature and, from the instrument calibration data, converts them to the corresponding F temperature. Each *F air temperature is then multiplied t ( by its corresponding RTD weighting factor and summed to 9 i_ e f l 7- ....
._._..,;_........,.__.._ . . . . . _ . . ... I
- t 6.6 Discussion cf Computer Program (Cont'd) i provide the weighted average temperature in *F. To express the weighted average temperature in absolute e
units, 459 7 is added. Finally the data file program , prints out the individual millivolt input values, the I ' corresponding unweighted temperatures and a "Su= mary of / Weighted Average Temperatures" expressed in both *F and *R. i , The data file program determines the dew point, and hence vapor pressure, by taking the hygremeter millivolt output and, from the instrument calibration data, converts , this initially to dew point expressed in *F. The re-
- f. sulting dew point is then converted to vapor pressure ,
(FSIA) based on the Goff-Gratch formulas for saturation ( vapor pressure over water or over ice. The data file program prints out the individual millivolt input values, the corresponding dew point, resultant vapor pressure and su=marizes these parameters for each compartment. f 5 The portion of the-data file program dedicated to con-I tainment pressure reads a total of seven input values of I uncorrected absolute pressure, two per containment
\;
compartment and one for the prevailing ambient condition. i i The program corrects the input values-from instrument calibration data and averages the two associated pressures for each compartment. An average of all three containment compartments is taken thus representing the mean contain-i ment absolute pressure. The ambient reading is subtracted i L e I k_
....y.,--u .~ , - . - - - - ~ . - - . .
s 6.6 Discussion of Cc=puter Frogram (Cont'd) from the cean containment absolute pressure to yield the mean contain=ent gage pressure. The program then prints each uncorrected and corrected pressure as well as a "Su==ary of Corrected Average Pressures". The establishment of a data file serves several useful functions. As mentioned before, its primary function is to provide weighted and/or corrected information to the linear regression and confidence limits program for ultimate leak race computations. As can be seen in the accc=panying Table 6.6.1 it also provides a ec=prehensive and highly organized hard copy of measured parameters for documentation purposes, from which test personnel may easily perform aninput error check of the data. Moreover, through the convenience of the parameter su== aries, on the spot confirmatory calculations may be easily per-formed by the site NRC Inspector as well as the test supervisor. ( Once the data file is complete and verified to be free
/ of input error, the second program for linear regression
( and confidence limits is executed. The program calculates the amount of air in each compartment, using the equations presented in Section 6.4 of this report, as based on the original amount of air in each compartment at the start of the test 41_
i 6.6 Discussion of Computer Program (Cont'd) r (Computer Run #1). The fractional amounts of air in - each compartment are then combined to yield the fractional amount of air for the entire reactor contain-ment. The program computes the leak rate at a given time i r-i from input values of pressure, temperature and vapor . pressure stored in the data file. The leak rate, on a per cent per 24 hour basis, is determined by the least-squares method as dese;ibed in Section 6 5 of this report. The program is designed to allou evaluation of test results every half hour after the first 3. sets of data. A print out for all sets of data up to and including the ( data just submitted'is provided in the form of a tabulated su= mary. Included are fractional air reports for each
- compartment, for the containment as a whole, as well as
.; the 24 hour leak rate at the time the last set of data
( was taken. In addition, the upper and louer leakage bounds associated with the 95%' confidence limits are [ printed out. t ( Reproductions of the aforementioned tabulated summary for the Integrated Leak Rate Test and Supplemental Test may f be found in Section 8.0 of this report.
?
)
\
.- .. -~ a..~. ~ n... - , ~ ,, .- -r e.q . , .
O n m Rt#4 lA313ER 64 . ELAPSED Tit 1E 31.50 TAlliM 6.6.1 C0llTA1101Elli TEttPERATURES DATA CHECK UPPER VOLUt1E LOL!ER VOLUME ICE C0tOEilSER RfD HILL 1-VOLTS DEG. F. RfD NILLI-VOLTS DEG. F. RfD HILLI-VOLTS DEG. F. ETR-101 37.19 74.38 ETR-122 45.96 91.92 ETR-115 11.28 22.56 ETR-102 37.14 74.28 ETR-123 45.35 90.70 ETR-116 10.48 20.S6 ETR-103 37.14 74.28 ETR-124 45.56 91.12 E Til-117 13.74 27.48 ETR-104 37.45 74.90 EIR-125 45.59 91.18 ETR-118 12.67 25.34 ETR-105 36.68 73.36 ETR-126 39.67 79.74 EIR-119 10.24 20.52 ETR-106 37.09 74.18 ETR-127 38.60 77.20 ETR-120 10.47 20.94 ETR-107 36.95 73.90 ETR-129 37.63 75.06 ETR-121 11.44 22.88 [TR-108 37.10 74.20 ETR-130 39.97 79.94 ETR-109 37.41 74.82 ETR-131 33.67 77.34 ETR-110 37.43 74.86 ETR-132 37.20 74.40 ETR-111 37.32 74.64 ETR-134 38.76 77.52 ETR-112 37.78 75.56 ETR-135 39.00 78.00 ETR-114 37.20 74.40 ETR-136 37.65 75.30 ETR-128 35.72 71.44 ETR-137 39.26 78.52 ETR-133 36.70 73.40 ElR-138 38.24 76.48 ETR-113 38.48 76.% ETR-139 37.32 74.64 ETR-140 33.77 67.54 ETR-141 36.79 73.58 ETR-142 36.45 72.90 4 a EIR-143 34.69 69.38 ,j .p- ETR-144 37.19 74.38 p ETR-145 38.26 76.52 j 8 ETR-146 36.44 72.88 -I 5t091ARY OF 54EIGHTED AVERAGE TEtsPERATURES UPPER Volut1E (DEG. F.) 74.33 LolER VOLtNIE IDEG. F.I 78.48 ICE ColotplSER (DEG. F.) 22.16 UPPER VOLT #1E (DEG. R. I 534.08 LOWER VOLtN1C IDEG. R.) 534.18 1CE Cor1DLt!GER (DEG. P.) 42.1.86 CONTAINHENT VAPOR PRESSURE DATA CHECK C0tlTAllRIENT PRESSURES DATA CitECK ti!LLI- . DEW POINT VAPOR PRES $URE UrtCORI:ECl[0 COP.7ECTED HYERot1ETER VOLT 5 (DEG. F.I (PSIAI flAH0tt[TER READII:G (FSIA S RE AD!!T, I PSI &l l , VPU-1 33.00 30.91 0.0848 00-1 26.6110 2E .6 32 7
; VPL-1 36.00 43.09 0.1371 PU-2 26.0910 26.6047 VPL-2 39.55 57.33 0.2328 PL-1 26.4604 20.6273 VPI-1 29.13 15.38 0.0403 PL-2 26.7292 26.8498 i FI-1 26.6323 26.6294 ?
PI-2 25.9353 26.6366 SuttlARY OF VAPOR PRESSURES AtIDIENT 14.1760 14.4353 i ,i UPPER CONTAIt#1ENT IPSIAI 0.0848 L AVERAGE LOCIER CONTAll# TENT (PSIAI 0.1849 SuttfARY Of CORRECTED AVEPt.GE PRESSU2[S il V ICE C0teENSER IPSIAI 0.0403 V l} AVERAGE UPFER IRESSURE EPSIA) 26.6287 i AVERAGE LatiER 812ES3URE IPSI A) 26.6305 AVLRAGE ICE CCt0E6SER P2 ESSURE (PSIAI 26.6330 AVERAGE C0tliAINT.EMT PRESSUPE (PSIAI 26.63 % 'l. a AVERAGE Col 3TAlt&1LHT FRESSURE (PSIS) 12.1471 1
- t D. C. CC0K NUCLEAR PLANT - UNIT NO. 2 CO:!TAIUMENT INTEGRATED LEAK RATE TEST (PRE-OPERATIONAL) i.
COMPUTER PROGRAM "CCVDREP" l I k
-w-l
14ER3CAN ELIGIRIL MU' SU:VICE LM' M AllD'8 (, CDt Q Af ATIC IVIS 'l NBRzCCVDREP 01/14/75 L1;2:ncou rca SDURCE LIDRA4Y OUTPUT 11/04/77 05.53.32 PACE 0102 000100 aC **===**eessema.eme eameemasses ... massummones e *
==
g -- 000200 *C *e 000300 *C = COOK CONTAII;MLIIT VESSEL DATA PRDGRAM # 000400 *C e " 000S00 *C
- Tit 1S PRDGRAM ENTITLED CCVDREP
- as a W
a es 000600 uC e se
= e ' 0007G0 *C 1. READS RAW IttFUT D ATA FDR THE LINE AR
- u 00C600 aC REGRESSICH AllALYSIS PROGRAft:CCVREPT 000900 *C a 2.l:PITES THIS DATA AS A NEA!IS OF m
*e
*a g.
001000 *C
- ERROR CHECK!HG a * **
001100 *C 3. CALCULATES THE AVERAGE TEttPERATURE 4. 001200 *C a PEESSLVE t.tB VAPCR PRESSURE FDR EACH e 001300 *C a CllANSER AND OUTPUTS THESE RESULTS a **
** 10/1S/77 g
001403 *C # AS A Cl#7)LATIVE SUMt1ARY. a * ** 001500 *C 4. CALCULATES A W FOR EACH CHAMBER AS 001600 *C e L ELL AS A TOTAL W.THESE CALCULATIutts
- 001700 eC
- ARE SAVED C:4 A DISK DAT A CET TO DE * .=
*=
g* ' 001800 *C
- USED AS Tite DATA FOR THE REGRESSIDtf
- a *.
001900 aC
- Af1ALYSIS FPOCRAM
- 5.THE DUTPUT OF THIS PRD; PAN SERVES * **
0020C0 *C 002100 *C a AS THE FIllAL FOfit1AT FOR FRESENT AT10tl TO THE II.R.C. a
==
** 10/18/77 g
00:220 *C ** 002303 *C
- o.
002400 *C **m***********ve4=..namesumunm***.suses...unes 002500 a RE AL*8 T EMPUCt 16 ) .TEMPLCi t'e l ** 10/27/77
** 10/27/77 g
002500
- REAL*8 TEMPICt7) VFPEt4) 002700
- RE AL*8 TEt1PUt 16 ),1f ttPLt 24 ),TENPIt 7) ** 10/27/77 002300
- INTEGERm2 HR.HRReidR 002900
- IliTECER*4 RTDLl( 321.RTDL2(43).RTDL3(14 3 ** 10/20/77 {gg I , , **
003000 m RE AL*8 WUCDEM,WLCDCit.WICDEff,WDEM.WUCt 99 ),WLC( 99) .WICt 99) .Wt 9 9) 4r RE Al*8 TINEt 93),rRESt 7 8,FPESCt 7 3 ** 10/25/77
\Jt 003100 m 8 003200 m RE Alas V'g rt 3 ).Ct 6 ).Kt 121.SRt 70 3 ** 10/20/77 003300
- RE AL*G W1.'CtrJM.WLCliUtt WICtfU't.WHUt1,WTUPt 16 ).WTLOWt 24 ) .WTICEt 7 3 R E A Lu 8 TI .SituC .T t::: TLC ,1 ttSMIC . VPL AVG 10/24/77 10/05/77 g
003400 m 003500 m RE AL* S D Pt 4 ) .TitSitua.Vra t 4 ) .TitsitLR ,THSNIR . LVPt 4 ),PRESCU.PRESCL. am 10/20/77 003600 m a PRESCI.ACPA.AEPG me 10/20/77 a* 10/20/77 j 003700 m DATA RTD L1( 1 ) .R TDL1( 21.R T 0 Lit 3 ) .R fDL18 4 ) ,RTD L115 ) .R TDLi t 6 ) , g* 003800 a
- RlDL18 7),RTDLit C).RTDL18 91,RTDL1810) RTDL1811). ** 10'20/77 I 003900 m
- RsDLl(12),RTLLill33,RTOLl(14),RTUL1(15) RTOL1(16), ad 10/20/77 00'e000 m a RTDLl( 17 ) .RTULit 13 ) .RTDLl(191.RTDL18 20 ) .RTOL18 21 ), ** 10/?0/77 004100 m
- RT DL18 221.RT DLit : 3 8,R TD Lit 24 8.R T 0 Lit 25 ) .5:TDLit 26 ),
RTDL18 27 9.R1DLit 28).RTDLl(24),RTDL1t 30 ),RTDLit 31). a4 10/20/77 um 10/20/77 g I 004200 *
- 004300 m
- RTUL1(32)/*ETC *,'101 *,'ETR *,*102 ','Elp *.'103 *.*ETR '. en 10/20/77
. ** 10/20/77 004400 * * '104 *,*ETR '.'105 *,*ETR ' '106 '.*ETR ' '107 ','CTR ' *103 *.
i 004500 e * 'ETR '.'109 *,*ETR '.'llo *,'ETR *.*111 '.*ETR *,'112 *.*ETR ', ** 10/20/77 10/23/77 g-I 004600 m a '114 ' , ' E TR * ,
- 123 * .
- E TR ' ,
- 13 3 ' ,
- E TR ' , ' 113 '/
DATA RTDL3f i l .RT DL3( 21.R TDL3( 3 ),RTD L3(4 ) .RTD L3t S ),RTO L316 ), #= 10/20/77 004700 m 004800 m
- R TD L3t 7 3.RTDL3t o ) .RTD L3t 9 ),RTDL3( 10 ),RTDL3( 118, == 10/20/77 l
- RTDL3(12 ) .RTDL3( 13) .R TD L3( 14 3/'ETR * , *115 ' ,'ETR * . '116 ', me 10/20/77 ggg 004900 *
} * 'ETR ',*117 '.'ETU ','118 '.'ETR '.'119 '.'ETR *,'120 '. ** 10/20/77 005000 m
- l. 005100 m * *ETR ',*121 '/ am 10/20/77
. ** 10/20/77 = 005200 m DATA RTDL2t i l,RTDL2( 2 ),HTDL2( 3 ),RTULO( 4 ),RTDL28 5 ),RTDL2t 6 ) .
l* 005300 m
- a RTU L2 t 7 ) .R TO L2 t S ) ,R TU L2 t 9 ) .R TD L 2 ( 101.91D L2 ( 11 ) . RT O L2( 12 ) ,
RTUL2(13 3,R TDL2(141 RTDL2(15 ),RTDL2t 16 ).RTDLZ117), au 10/20/77 am 10/20/77 g 005400 m 6 00L500 *
- RT UL2413 3.CTDI 2( 19 ),R TOL2( 20 ) .R ID L2 t 211,RTD12 t 22 ), me 10/2P/77 1 O O O ,
t.
_ . . h L .. 2VDR.. J1/la. LIE
.*see 500...
LICR,.. JUTPL / i -..*4/71
.J. 5 3. . .
mY J ' PA.. . 03 005600 # # RTOL21231.RTDL2( 241.DTDL2f 25).RTDL2f 26 ).RTDL2t 27), en 10/20/77 db 005700 e
- RTU L2 t 28 3.RTDL2 8 29 ) .R TO L2( 301.RTDt2( 31 ),RTDL2( 32 ) . ** 10/20/77 **
005800 *
- R TO L2( 33 ) .R TD L2( 34 3.R TD L2( 35 ) .R TD L2136 ) .R TD L2( 37 ) . == 10/20/77 .
005900 w
- RTDL2t 35 ) .R TDL2( 39 ).R TDL2( 401.R TDL2 E 41).R TDL2 8 421 ** 10/20/77 006000 *
- RTDL2t43),RTOL2(441.RTDL2845).RTOL2(46),RTDL2(47). . 10/:0/77 4*
* ~~
006100
- RTDL24431/'ETR *,'122 *.'FTR *.*123 ' 'ElR *.'124 ',*ETR '. ** 10/20/77 006200 m * '125 *.*ETR ','126 '.*ETR ' '127 '.'ETR ','129 * ,' ETR *.*130 *. ** 10/20/77 036300 * * *ETR ','131 * . ' ET R ' , ' 132 * .
- E TR * . ' 134 * . ' E T R * .
- 135 ' .
- ETR * . == 10/20/77 006400 * * *136 '.'ETR '.*137 *,'ETR ',*138 *.'ETR *.*139 '.'ETR ',*140 ', ** 10/20/77 **
006500 * * *ETR '.'141 ' ,' ETR *.*142 '.'ETR *.*143 ',*ETR * *1*4 *e*ETR ', ** 10/20/77 006600 * * *145 '.'CTR *.*146 * ,'ETR '.*113 */ ** 10/20/77 006700
- DEFINE FILE 4( 99.146. L. ID ) **
006800
- READi5,300.END=121C ** 1C/10/77 **
006900 #300 FORMATt6F6.31 am 10/10/77 007000
- READ (5.301.END=121K ** 10/18/77 C07100 #301 FORMATt6F11.6/6F11.61 ** 10/10/77 007200
- RE AD( 5,302 E UD=12 )SR ** 10/10/77 **
007300 m302 F02 MAT (10F8.5/10FS.5/10F8.5/10F8.5/10F8.5/10F8.5/10F8.51 ** 10/24/77 007400 m READt5,303.EHD=121HTUP,HTLOH.HTICE ** 10/18/77 007500 m303 FORM 4T t 10F 6. 5/6F6.5/11F6.5/13F6.5/7F 6. 5 3 == 10/13/77 007600
- REAG(5,304.END=123VWF em 10/13/77 **
C07?00 *304 FCRHATf 31'7.51 ** 10/18/77 007600
- ERITEt6.305)C.K.SR ** 10/13/77 007900 *IOS FCRMATE1H1.44X.**** THIS IS A CHECK OF THE INPUT DATA man'////1H . ** 10/IP/77 000000 e * 'RTD MILLI-VOLT TO FAHREN'tEIT CONVERSICH COEFFICIENTS'/1H .6X, ** 10/18/77 **
008100 * *
- UPPER * .12X. ' LOWER * ,13X ' ICE */1H ,F 5.2,3X.F 5.2.4X,F 5.2.3X. ** 10/13/77 000200 *
- F 5. 2.4X . F S . 2,3X , F S . 2////1tl .'HYGRCMETER HILL 1-\CLT TO ', ** 10/IS/77 00S300 * * 'FAHEEMHEIT CCHVERSICH COEFFICIEHIS*/1H .14X,'U?PLR*.27X, ** 10/18/77
'. e 003400 * * *LDWER-1*/1H .5tF10.5.1X).F10,5//)H .13X,'LcWER-2*.23X.' ICE * ** 10/10/77 **
JP C00500 * * /1H ,$t F 10.5.1X ),F 10.5////1H e 'HANOMETER PRES 3U;E CCPRECTION * , ** 10/le/77
- CN 003600 * *
- COEFFICIENTS'/1H .304.'PU-1*/1H ,9t F 7.4.1X ) .F7.4//1H .30X. ** 10/24/77
' 8 000700 * * ' PU-2 */1H ,9( F7.4.1X I F7.4//1H .3 3X 'PL-l'/1H . 9 t F 7.4.1X ) . ** 10/24/77 003300 m F7.4//1H .33X.'rL-2'/1H 9(F7.4.1XI.F7.4//1H ,LSX,*PI-1*/ ** 10/24/77
, 0C8900 e # 1H .9t F 7.4.1X ),F 7.9//1H .38X,'PI-2*/1H .9tF7.4.1/.l.F7.4// ** 10/24/77 009000 *
- IH . 33X,'P-ATH'/1H .9t F 7.4.1X I .F7.4 8 ** 10/24/77 009100
- WRITE 16.3061HTUP.Hitcu,HTICE.\KF *a 10/10/77
' I 009200 #306 FORMAT (1H1,'RTD WEIC1tT1HG FACTORS'/1H .27X.'UPFER*/1H 9(F5.4.1XI. ** 10/18.*77 ** 009300 *
- F5.4/1H .5(F5.4.1XI.FS.4//11t 27X.' LOWER'/1tl .10fF5.4.1X), ** 10/1?/77 009400 m
- F5.4/Ill el2( F 5.4,1X),F5.4//1H .28X ' ICE */1H .6( F5.4.1XI .FS.4// ** 10/18/77 009500 * * //1H . ' VOLUME HEIGHT 1HG F ACTORS'/1H .1X,'UPFER'.2X,' LOWER
- 3X. ** 10'1L/77 009600 * * ' ICE'/111 .2(F6.4.1XI.F6.4) *a 10/10/77 *D 009700
- 13 READt5.100.END=123t'R.TII;EllR) as 009800
- 100 FORilAT(12.1X.F5.2) **
009900 m SRITE(6.200)HR,TIMEIHR) == 010000
- 200 FOR1ATt 1H1 *Ruti IR40Ut' .4X.I2/111,* ELAPSED Tit 1E' .2X FS.2///1H , em 10/24/77 4*
fi 010100 * * 'C0flT 41ttNIllT TEttPERATURES DATA CHECK'//1H .7X. 'U.'PER VOLUPE', ** 10/18/77 CIC200 *
- 21X
- LCHER VOLUME * ,1%X.
- ICE cot l DENSER */1H .3X.*PTD' 2X. ** 10/24/77 t 010300 * * 'NI LL1-VOLTS * ,2X,
- DEG. F. ',7X, *RTD
- 2X. 'NILLI-VOLTS * .2X. == 10/18/77 010400 * * 'O EG. F . ' .7X,
- RTU ' .2X 'nILLI-VDLT S
- 2X. 'D EG. F . ' l ** 10/18/77 *b f; 010500 4 READ (5.1011(TErfPUCIII.1 1.16) ** 10/18/77 i 010000
- 101 F09ttAT(10tFS.2.1X3/6tF5.2.1Xil au 10/IS/77 f 010700
- READ (5,102t(TEMPLCIII.I:1.24) ** 10/24/77
- 8' 1
, 010300
- 102 FDPNAT(11tF5.2.1X)/13tF5.2.1XII ** 10/24/77
. ;, 010900
- READIS,1031tTEttPIC(II.I:1.7) ** 10/18/77 r
=
011000
- 103 FCRMAT( 7t F5.2.1Xi' ** 10/16/77 011100
- DO 400 JAH1:1.16 ** 10/23/77 011200 m IF( TEltPUC t J Atil l .EQ.0. lTE MPU( J AWi l:0. == 10/24/77 4D
,j 011300
- IF(TEMPU2(JAH15.E4.n.lEOTO 400 em 10/29/77 J
.r
@ O O s
- ~_ - m s _g. _
%w# *.se .-
'g5R=r-* ~ EP * * ** 4/75 **'l:ca ~ -*o -
" AC E " " 't2 Y ""**VT m -
11/** ~7 0 * ;52 "GE r* " 011400 m TEMPUtJAW11:lC(11sTEMPOC(JAW 1))*C(2) es 10/24/77 011500 E400 Cot 4TINUE me 10/24/77 011600
- DO 401 JAW 2:1.2% == 10'24/77 **
011700 m IF( TEMPLCt JAW 2 ) .EQ.0. )TEttPLI JAW 2 ):0. ** 10< 4/77 g]g . 011200 m IF(TEMPLC(JAW 2).EQ.0.)GOTO 401 ** 10/24/77 011900
- TEMPLtJAN2)=tCt39*1EMPLC(JAW 2))*C(4) 64 10/04/77
~
012000 m_401 CONTINUE ** 10/04/77 012100 e 00 402 JAW 3:1.7 ** 10/20/77 {}g 012200 e4C2 TEMPItJAW31=ttt5leTEMPICtJAW3))*C(6) == 10/20/77 012300
- TMStfUC:0. ** 10/20/77 012400
- D0 1 J:1.16 ** 10/20/77 01:500 *1 TMCh0C THS:1UCe t TEMPUt J ).WTUP( J ) ) ** 10/ 0/77 gag 012600 m TMSt:L'R = TM;ttVC + 4 59.7 **
10/s0/77 - 012700
- THEMLC:0. == 10/00/77 012600 m DO 3 L=1.24 em 10/04/77 012900 m3 f t:SitLC= TM3t1LC + ( TEMPLt L i sWTLOWI L I ) ** 10/20/77 g-013000
- 1 N 3t1LP = TitSMLC + 459. 7 ** 10/20/77 013100
- TMSMIC 0. == 10/00/77 013:00 m CO 6 IT=1.7 ** 10/;0/77 013300 a6 Tristt1C 1MS!1IC*t TLHPI(IT)*WIICE(IT)) ** 10/20/77 g*
013400
- Tt1SitIR:Tf10MIC +459. 7 ** 10/20/77 013500 m READ (5.5093VPRE. PRES ** 10/1/77 013600 a509 F0PMATt4F6.3/7FS.5) ** 10/21/77 013703
- DP(11:(K(1)*VfRE(1)mVPRE(1))+tK(2)*VFREll))*Kt3) ** 10/00/77 {}g 013000
- DPt 2 ):(l:( 41*VF9E t 2 )"VPP[t 2 ) l+ t K t 5 )*VFRE( 21 )*K( 6 ) ** 30/20/77 013900
- DPt 3 3 E Kt 7)*VFREt 3 38VPPEt 31)e t Kt 8)*VPREt 31)+Kt 9) ** 10/20'77 014000
- DP( 4 ):t K( 10 3 mVPRE( 4 3 *VPG E t 4 ) )+ t K t 11 )*VPP E t 41 ) *K! 12 ) ** 10/*4/77 014100 m DO 403 J:1.3 ** 10r:0/77 (g 014:C0 m LVPt J ):(-7.90290* t t 373.16/( t ( 5.* t DP( J i-32.11/9. )* 273.1613-1 ) ) + ** 10/20/77 +
e 014300 m * ( 5.02803*DLO3108 373.16/t (( 5.u t 0Pt J )-32.11/9.1 +2 73.16 ) ) )+ ** 10/20/77 4P 014400 *
- l-1.3816*(10.**t-7.llat10.**(11.344*tl-(((15.atDP(J)-32.31/9.)+ ** 10/04/77 SJ 8
014500 e 014600 m
- 273.16)/373.16)))-1)l+(8.1328at10.**(-3.1)htt10.**t-3.49149a a f ( 373.16/t t t 5.* t CP( J )-32. l l/9. I +273.16 ) )-1) ) )-11 ) +
10/24/77 10/20/77 g 014700 *
- DLOC1011013.246DO ) ** 10/24/7/
014800 403 C0tlTINUE ** 10/20/77 014900 m LVPI 4 ):( -9. 09 710 4 ( t 2 73.16/( i l 5. p t DP t 4 )-32.11/9. ) + 2 73.161 )-11 )+ ** 10/20/77 peg 015000 m * (-3.56654*DLLC108273.16/t(45.*(DPt43-32.11/9.)*273.161))+ ** 10/20/77 015100 m
- 10.876793* ( 1-t i t t 5.e t DP( 4 3-32. ) )/9. )* 2 73.16 )/273.16 3 3 3 + ** 10/e4/77 015:00 *
- DLCG10(6.107100 9 ** 10/24/77 015300 m 015400 #404 DO 404 FAY:1,4 VFR(YAf)=(10.**LVPtKAY))*.0145338
*=
10/24/77 10/?5/77 g r 015500 # VPLAVG:EVPRt2)*VPR(3))/2 ** 10/ 0/77 l 015600
- D3 405 N:1,70.10 ** 10/20/77 015700
- H1:Nel me 10/20/77 gg 015800
- N*:H+9 ** 10/20/77 015900
- NY:ttM-11/10)+1 ** 10/ C/77 016000 # 00 406 Hall 1.H2.2 ** 10/20/77 016100
- 016:00
- IFt rRES(NY ).LT.SR(H))GOTO 406 IFI N.EQ.fil. AP:D. PRES (NY ).GT.SR(H1)GOTO 444
** 10/20/77
** 10/;*/77 g
016200 m PRE SCillf ):( ( PR E St Mf )-SR( H 3 ) e( ( SR( H-3 ).SR( tg 1 ) )/( SR (b-2 )-SR( H ) ) ) ) ** 10/ 8/77 016400 * **SRtH-1) ** 10/;2/77 016500
- 016609 #406 GOTO 405 C0t4TINUE .
10/20/77 10/20/77 rg 016700 e444 WWITEl6.4079 ** 10/24'77 016000 e407 FORtlAT(1H '**n NAt10 HETER READING OFF SCALE ===*) ** 10/20/77 016900 e405 C0;4TINUE *a 10/;0/77 pqg 017000 d PRESCUr( PR ESC ( 1 )* PH ES-( 2 ) )/2 ** 10/23/77 - 017100 m PRESCL:8 PRESCt 3 )* F Ct431/2 ** 10/20 I 4
~
M -- _- - . - _ _ . . ___- ._h_ SOUR.. .! BRA.,
./77 _53.5 PAG
_ Gbf 5
.i MLn-L6 VOTER wa/14sem LI3a==--s*** .J T PU'. .
** 10/20/77 8P 017200 # PRESCIst PRESCt 5)+PRESCf 613/2 0173C0 # ACPA= t PR ES CU. PR EEC L* PRESCI I/3 ** 10/20/77 ..
017400
- ACPGrACFA-PRESCt78 ** 10/20/77
- 017500 m DO 500 IW1T=1.7 ** 10/20/77
== Ic/:c/77 E>
017600 m ME:(2eggRyl-1 017700
- HO:ME*1 ** 10/03/77 .-
017800
- WRITE 16.501)RTDLitME).RTOLitNOS.TEMPUCtIWRTI.TEMPUEIW7T). ** 10/03/77 017900 m o p TD L0 t ME l .RT D L2 t H0 3,TEMPLCI IWR T I .TEMPLi lkR T I . ** 10/00/77
. ** 10/10/77 **
01C000 m RTDL3t ME l RTDL3t Mol. TEMP 1Ct IWRTI.TEMFit IWUT) 018100 501 FORMAT 11H .2A4,2X.F6.2,5X,F6.2,5X.2A4.2X,F6.2,5X.f6.2.5X.2A4 ** 10/06/77 010200 *
- 2X.F6.2.5X.F6.21 ** 10/2o/77 018300 *S00 C0f1TIHUE ** 10/20/77
** 10/2J/77 8>
018400 m 00 E02 IWRT2=S.16 010500
- ME2*ttalWRT1-1 ** 10/ 0/77 016600
- tt02:ME 2 1 ** 10/20/77 018700
- IF E IWRT2.EQ.16. A NO.TEMPUCt IWRT2 3.EQ.0. lWRITEt 6.5C4) ** Ic/04/77
** 10/2*/77 8>
013800 *
- RTP'2tME2).RTOL2fM02).TEMPLCIIWRT21 TEMPLtIWRT2) 018900
- WRITE 4 6.50 3 )R TOLi t t1E2 3.RinL1 t NO ).1EMPUCt IWRT 21.TEMPUE IWRT2 ). ** 10/04/77 019000 *
- RTC L2 t NE O ) , RID L2 t HO2 ) .TENPLC t IWRT 21.T EMPL8 IW9 T 2 ) ** 10/20/77 019101 *S03 F ORMATE 1H .2A4.2X.F6.2.5X.F6.2.5X.:A4.2X,F6.2.5X.f 6.2 5 ** 10/27/77 FOPMAft1H .32X.2A4.2X,F6.2.5X F6.28 ** 10/27/77 8>
. 019:00 *504 019100 *LO2 CONTINUE - ** 10/20/77 f/ ** 10/20/77 019400
- DO 505 IWRT3:17,04 0195C0
- HE3:42*!HRT39-1 ** 10/20/77
/ ** 10/00/77 8>
019600
- M03:NE3*1 019730
- IFE IU3T3.EQ.24. A'10.TEMPLCt IWQT31.EQ.D lGOTO 505 f *
- 10/2%/77 019S00
- WRITEt 6.506 tRIDL2t ME3 3.0TDL2t NO3 ).TEMPLCIIWRT3 3.TEMPLf 1W7T3 3 ** 10/20i77 019900 *S06 FURHAft1H .32X.2A4,2X.F6.2.5X.F6.25 ** 10/27/77 em 10/20/77 8b 020000 *505 CONTINUC 000108 # WRITEt 6,507 )TMSMUC THSNLC.THSi1IC,TnSrf 9.TMSMLR.TMSHIR ** 10/20/77 4P 0 02C0 *507 FDPNAT(1H .17X,'SUt31ARY OF MEIGitTED AVERAGE TEMPERATURES'//1H . ** 10/27/77
. CD C20300 * ** UPPER VOLUHC (CEG. F.I ', F5.2.4X,'LCW;R VotUME (DEG. F.) '. ** IC/27/77 ED 023400 e
- F6.2.4X.
- ICE CONDEllSER (DEG. F. I ' F5.2/1H , em 10/:7/77
* .F6.2.4X,
- LOWER VCLUME (CEG. R. ) '. ** 10/24/77 020500 m * 'UFPER VOL'JME IDIG. R. )
* ,F7.2 ) ** 10/2,/77 0206CO a e F7.2.44
- ICE CONDENSER (DEG. R. )
020700 m WRITEt6.50SI ** 10/21/77 a VFRE l l t ,0Pi l l .VPn t i l . PRE St i l . PRE sci l l ,VFRE t : 1.CPt 2 8.VPR i t t , ** 10/01/77 8" 020600
- 020900 *
- PRESit t.FRESCl2 3.VFPEt 3).0Pt 3 3.\ Tot 3 9 PRE 98 31.T RESCl 3 9.VPGEt4). ** 10/*1/77 021000 m
- DPt4).VPRt41.FRESt41.PRESCl4). PREST 5),PRi.0459.P7Est63.PRESCt61 ** 10/21/77 021100 e * .FR ESt 7 ) .PRESCt 7 3.VPR t i l .VPLAVG.VPR t 41.PR E 3CU. PRE SC L.PRESCI . ** 10/21/77
* *. 10/;g/77 db 0 1200
- ACPA.ACFG 001306 *508 F09 MAT E 11tl.11X.*CCHTA1HMEtIT VAPOR PRESSURE DATA CHEC'C',L5X. ** 10/21/77 I
021400 * * 'COHTAINNENT PRESSURES C ATA CHECK'//1H .19X,'NILLI * .6X. ** 10/01/77 021500 * * ' Deli POINT
- 4X. 'VAF CR FRES5URE ' ,2 0X,'UtaCCRRECTED * ,7X. ** 10/21/77 e ' CORRECTED'/1H .2X.'HTCPOMETER*,0X.' VOLTS',8X,*fDEG. F.l'.7X. ** 10/21/77 8" 021600 m 021700 * * 'fPSIAl',23X.' MANOMETER'.0X,'READIl8G IFSIAl',2X.'READIt#G *, ** 10/21/77 021000 * * ' t PSIA l */1H .5X 'VPU-1
- 10X.F 5.2.10X.FL 2,9X.F7.4.25X ' PU-1* . ** 10/24/77 021900
- a 10X . F 7.4. 8X, F 7.4/11t 5X . 'VPL-l' .10X.F 5. 2.10 X. T S. 2 ,9X .F 7.4 ** 10/24/77 2 5X. ' PU-2 ' ,10X . F 7.4. 8X.F 7.4/1H .5X , ' VP L-2 ' ,10X .F 5. 2.10 X. F 5. 2. ' ** 10/21/77 db 022000 m
- 022100 m
- 9X.F7.4.25X. ' PL-l' .10X.F 7.4.0X ,F 7.4/1H .5X. 'VP1-1 * .10X.F5.2. ** 10/24/77 022:00 m a 10X.F S. 2.9X,F 7.4.25X. ' PL-2 * .10X.F 7.4.8X.F7.4 /1H .01X,' PI-1 * , se 10/06/77 022300 m
- 10X.F7.4.eX.F 7.4/1H .81X .
- PI-2 * .10X,F 7.4.8X.F 7.4/1H .17X. ** 10/06/77
' SUM;1ARY OF VAPOR T RESSURES',38X. ' AMSIENT ',7X.F 7.4,8X.F 7.4// em 10/26/77 8b 022400 a m 022500 m
- 1H .154. 'UF PER CONT AINMLHT ( PSI A l' .6X F7.4/1H .15X. *t% ER tGE * , a* 10/a4/77
= 022600 m a ' LOWER CotiTAIHMENT (P3tAl'.5X.F7.4.08X.'
SUMMARY
OF CORaECTED *. ** 10/04/77 0 2700 * * ' AVER AGE PJE SSU"ES*/1H .1SX,
- ICE CCHDEHCER ( FOI A l' .5X.F 7.4/1H e ** 10/24/77 8b a 80X. ' AVER AGE LTPER PRESSU ?E ( PSI A l' 10X.F 7.4/1H . ** 10/01/77
'j' 022200 *
** 10/21/77 80X
- AVER AGE LC11*P PREE0UPE ( PSI A l' .10X.F7.4/1H .
022900 *
- n @ O O th
- i t < ,
f
,_Y GCce -
s
~ '~
~ 'C E t - " t v c' -~ *T - - 11/0^ m . 05 tLE2 . mf 0 0 %_ , F c Cf P O __ '75 "I 7-ca 10/24/77 023000 # C/' 80X.* AVEIAGE ICE CCf1DEt45E3 PRESSCE (PSI Al' .2X.F7.4/1H , F 80X.
- AVER ACC CCt4 T AIP: met!T PRESSL'RE ( P31 A l' ,4X,F7.4/1H me 10/26/77 023100 # 0 .
** 10/26/77
. 023:00 m e 80X.' AVERAGE Cot 4 Tait:MEtaf PRE 55L'RE ( PSIG)' .CX.F7.4 9 , ,,
am 023300
- IFtHR-118.S.9 ** 10/25/77 023400
- 8 WUCDE'1:t PRESCU-VPRilll/TmtSt WLCC D1:l PRE!C L-VF LAVG I/ Tit;s1LR ** 10/25/77 023500 *
** 13/25/77 023o03
- WICDEM=tFRESCI-VFRt411/TM0MIR
** 10/29/77 023700
- WDEti:V!4Fil )*PJCDEHeVWF t 2 )*WLCDFt16VWF t 3 8 *WICDEN se * ,
023500
- NOR*NR -
023900
- WRITEt4'13t422.T1HElit RI.WUCDEN.WLCDEN.WICDEM.WDEN ==
024000
- I4RR:14R se
{ 024100
- WRITE t 4' 99)ttPR
- m. #
024200
- 9 RE ADt 4'11H2R. tit 1E t H2R ).WUCCEH.WLCDEM,NICDEN.WDEM
,, ** 10/25/77 024303
- WOCHUM:t PRE SCU-VPP t 191/Tr'S?fJR 024400
- WUCt ItR ):UUC11Utt/WUCCE N
** 1J/25/77 024500
- WLCt&is t FRESC L-VPL AVG B/IN0MLR 024600
- WLCittil:WLCl4UN/WLCDE!1
** 10/25/77 0247CO u WICtantis t PRESCI-VPRt 411/THSHIR ** ,
024000
- WIC!!N ):WICt4Utt/tsICD EM L H yt:VWF t ll*VOCtTJit*VWF t 2 kWLCtAR1*VMF g 3)uulttapyt se 10/29/77 024900 m == *
/ 025000
- Wi tzR ):Put/WDEtt **
025100
- Is t ria.1110.10.11 =*
025200
- 10 tJ2R:tt? ** 10/25/77 L 025300
- WRITE t 4 'l ltCR .T IME t tI2R ) .WL'CDEN.WLCDEN.WICDE N.WDEtt.TMSMUR PR ESCU.
** 10/05/77 *
'. 025400 m
- VPR i l l .T tt0t1LP .PR ESC L.VPL AVG .T M0tfIR . PR E SCI .VPR t 4 ) .
*a 10/21/77 02SE00 m mVUCI tCR 3.54 LClll2R I .WICI t42R ) .WI fl2R 3
== <
025600 m GD 70 13 025700
- 11 Wt21T Et 4
- ttR ltG . TINE t tN ) .Tritt1UR .PRESCU.VP 4 t ! ) .ittSt'LR .F 3ESCL .VPL AVG.
== 10/25/77 g
^ me 10/05/77 #
025800 *
- TitSHIR.PRESCI.VPRt4),
** 10/21/77 ,
025900 * *WUCi t R ) .54LCi t1R I .WICi til l .ll( NR I
*=
s 026000
- R E AD t 4
- 99 8 t'RR he -
026100
- IFillR-tRR)13.13,14 *
-F am
/026200 a 14 117R:ta T O26300
- WRITEt 4
- 99)t RP 0264E0
- GO TO 13 me 026500
- 12 STOP se #
026600
- Ef40 e
. g i
O i I O l g '
~
4 O O O , i
;* t r
I D. C. COOK NUCLEAR PLANT - UNIT NO. 2 - i CONTAINMENT INTEGRATED LEAK RATE TEST j" (PRE-OPERATIONAL) COMPUTER PROGRAM CCVREPT" i l I F i 1 l i I. 1 L , i I l 4 l~
-- - -- - ---- - .- - :- L
(,. - .- - - n- - , - - -- _~ ~ ., , , e $ ,-
- AMERICAtt ELECTRIC PDHER SERVfCE CorPORQTI0tl COttPUTER APPLICATI0 tis DIVISI0ll **
NBRzCCVREPT 01/22/75 LID:amew**** SOURCE LIPPARY OUTPUT 10/31/77 15.59.11 PAGE 0002 0C0100 #C wommammassena musemessen**meamwaveemana.emem4 maw ** 000200 *C * * ** 000300 *C
- COOK C0t4TAlt t1EttT VESSEL REG?[SSI0tt P90 GRAM * **
000'.03 *C * * ** 000500 *C
- THIS FR03PAtt ENTITLED CCVREPT: * **
00C600 *C * * ** 030700 *C
- 1. READS THE DISK DATA SET THAT * **
030C00 *C
- WAS CRE ATED C( 1HE CC\DREP P.70SRAN
- 68 000900 *C
- 2.FERFORt;S A lit 7AR REGRESSIC4 * **
001000 *C
- Al'ALYSIS TEST O!1 1HESE DATA POIllTS * **
001100 *C
- 3.THE AtML) SIS IS PEPFORitED 078 THE * **
001200 *C
- CUnRENT iMXIltUd IR4L'ER OF D AT A POIllTS.
- ud 001300 *C
- 4.THE W EXPERINEllTAL.1HE W PEGRESSICil. * **
0014C0 *C
- Tile LEAEACE RATE.CottFIDEtJCE LItt11S * **
001500 *C
- FOR THE RATE. AS WELL AS THE ItliERCEPT * **
001600 *C
- APE ALL DUTPUTED. * **
001700 *C
- 5.THE Lt:1PUT OF TilIS PROCRAt1 SERVES AS * **
001000 *C
- THE FIllAL FORitAT 10 DE FRESEllTED TO * **
001900 *C
- THE ti.R.C. * ** 10/17/77 000000 #C * * **
002100 *C ****************uaus.** ..wamuseauvv ..m======== == 002200
- RE AL*8 ATl>C. APUC. A*.rUC./ TLC. APLC. AVPLC, ATIC. APIC. AVPIC **
8
- 00 3C0 m RE AL* 3 UCC( 99 ) .l!LC( 99 ) .WAC( 99 ) .Wi 99 ) . tit 1E( 98 ) **
)[} 002400
- RE A L*C WR( 99 ) .NLR( 99 ) .WUR( 99 ) . AT A8( 99 ) *w i 00:500
- It4TEGER* 2 ilR.!:RR.t:2R *a 002600
- DIttEll3I0ll TAELE( 96) e6 002700 m PEAL *S A.B 0L.CH **
002000 m REAL*8 WUCDEN.WLCOEN.WICDEN.WOEM *w 002900
- DEF1t4C FILE 4( 99.146.L.1D ) **
003000 m RE A L*C TSS.TS.WS.TS2W. AtrJM. ADEN.E.i1UH.EK.WSUH.SIGMAB.KNRR . SIGMA am 003100
- REAL*8 AT.AiTil.Et:K. TOT.F2.F1.F.FF ar 003:00
- READ (4'99)N1R **
003300
- IF(flRR-331.2.2 **
003400
- 1 WRITE (6.200) **
003500
- 200 F0EllAT(1Hl.10X.'It4 SUFFICIENT ffUt1CER OF DATA P01tlTS FOR A HEANIt1GFU **
00Io00 * *L AffAL1 SIS TO DE PUti. It0KE DATA Poll 4TS ARE NEEDED.') ** 10/17/77 0037C3
- GO TO 3 **
003000
- 2 183R1 =2 **
003900
- 847 IERI:l!GR1+1 em OC4000 m TSS:0,0 **
i 004100
- TS:0.0 *m 004200 m CO 4 I:2.NRR1 mm
"" 004300
- READ ( 4 'I lta. tit 1E(I ) . ATUC. APUC. AVPUC. ATLC. APLC. AVPLC. ATIC.APIC. AVPI **
004400 * *C.WUC(I).WLC(I).WIC(I).W(I) *w 004500
- TSS=TSSeTIt1E(I)wm2 em 004600
- 4 TS=TS+ TIME (I) **
004700
- RE AD(4'l lN2R. TIME (H2R) .WUCDEH.WLCDEN.WICDEN.WDEH. ATUC. APUC. AVPUC. A **
004800 m
- T LC. APLC. AVPLC. ATIC. APIC . AVPIC.WDC( H2R ) .WLC( H2R ) .WIC( t42R ) .Wt HOR ) We 004T00
- WS: WIN 2R) em 005000
- 00 5 Ja2.f4Rn1 au
"" 005100
- RE A0( 4
- J )NR . TIME ( J ) . ATUC. APUC . AVPUC. ATLC. APLC. AVPLC. ATIC. APIC. AVPI me 005200 * #C.WUC( J ) .WLC( J ) .WIC( J ) .W( J ) ==
005300
- 5 WSrWS+W(J) **
905400
- TS2W20.0 **
905500
- DO 6 K=2.HRR1 mm
(
(3
#L- g -- -, . - - ~ _
, _.y y ~- - - - - . - ~ , -
NBR=CCVREPT 01/22/75 LI!=sessassa COURCE LIES ARY OUTPUT 10/31/77 15.59.11 -* 005600 * ' 005700
- PEADt 4'K )tlR.TIttE(K ). ATUC. APUC. AVPUC. ATLC. APLC. AVPLC. ATIC. APIC'. **AVPI
*C.WUCt K ) WLC( K ) .llIC( K ) .W( K I **
005000
- 6 TS2M:1S2W+TIMEIK)*WIKI 005900 m ** ~
ANUM:TOS*WS-TS*TS2W ** 006000 m XNpR:tt;pt
, 006100
- ADtit:XilRR*TSS-TSma 006:00 * **
A: Ariutt/ ADEN 006300
- BNUit:XtTR*TS2W-TS*WS 006400 m **
B;Cl#Utt/ADEtt 006500
- 006600
- O AT A TABL E/12. 706.4. 30 3. 3.102. 2. 776. 2.5 71. 2. 44 7. 2. 36 5. 2. 306. 2. 262. **
006700 * *2.228.2.201.2.179.2.160.2.145.2.131.2.120.2.110.2.101.2.093.2.0e6, == OC6800 m m 2. 0 8 0. 2. 0 74. 2. 069. 2. 0 64. 2. 0 6 0. 2. 0 56. 2. 0 5 2. 2. 04 8. 2. 045. 2. 04 2. 2. 04 0. ** 006S00 * *2.033.2.036.2.034 2.032.2.030.2.027.2.025.2.023.2.C21.2.020.2.019 == C07000 * *;.013.2.017.2.016 2.015.2.014.2.013.2.012.2.011.2.009.2.000.2.007. ** 007100 m #2.006.2.005.2.004 2.003.2.002.2.001.2s2.000.3ml.999.3 1.993.3 1.99 == 007200 m *7.3*1.976.3*1.995.3*1.994.3*1.993.3*1.992.3*1.991.3ml.990.3*1.989 e2*1.989/ == 007300
- WR t i l: A 0C7400
- me CC7500
- PC AD( 4' 2 ))la. TIME t 2 ). ATUC. APUC. AVPUC. A TLC. APLC. AVPLC. ATIC. APIC.** AVPI
*C.WUO t : 1.WLCl 2 ) .WIC( 2 ) .W( 2 ) **
007600
- WR12) t*D*TIttE(2) 007700 * **
DO 7 IIs3.!JP1 , 007J00
- RE ADf 4'II )HR. TIME (II ). ATUC. APUC. AVPUC. ATLC, APLC. AVPLC. ATIC. APIC. AV **
007900 *
- PIC . WUC ( II I .H LC ( Il l e l11C I II I .WI II I 008000 * **
e STIIII A*D*TIllE(II) ==
\J1 008100
- EK:TADLCIII-2 5 000200 m ==
h)
' 000300
- RE AD( 4 '1 )!a2R. TIfiE t t12R ) .WUCOEM.WLCDEll.WICOEN.WDEN. ATUC. A PUC**. AVFUC. A
- TLC. APLC . AVPLC. ATIC. APIC, AVPIC.WUC(1).WLC(1 ) .WICll ).W11) 000400
- IFIDAEstW(11-A).LT.1.D-39)W(1):A
*e C05500
- ou WSuttu t tl( 13-A lu w2 ,,
008600
- 00 0 L:2,t: ppt 900700
- 000000
- READ f 4 ' L itlR. TIME ( L ). A TUC. APUC. AVPUC. ATLC. APLC. AVPLC. ATIC. APIC. == AVPI
*C.WUC(LI WLCILI.WIC(L).WIL) ==
a 008900
- 8 H50;t WSUN* ( W( L )- A-C
- TIME ( L ) )u u 2 0090C0 m m.
SIGMA D37RTi(1./Xt3RR )'WSUtil **
; 009100 m AT=TS/Xf E R ' ' 009200 * *e 009300
- REAL( 4 'IIlllR.TItf2(III . ATUC. APUC. AVPUC. ATLC. APLC. AVPLC. ATIC. APIC. AV ma 009400 m
*PIC.WUC(II) FLCfII).WIC(II).W(II) ==
ATTH:ITit1E(II)-AT)**2 == 009500
- TOT =ATum2 009600
- 00 9 tt:2.t:RR1 ,,
009700
- l 009800
- READ ( 4 't1 H A . tit 1E( H l . ATUC. APUC. AVPUC. ATLC. APLC. AVPLC. ATIC . APIC. **AVPI
; #C.WUCi til.WLCitt).WICf M).WIM) ** ?
C09900
- 9 10T = T OT * ( TIl1E ( H )- A T )m e 2 010000 m mm
- F2=ATTil/ TOT
"" 010100 m **
F1:( Xi1RR +1.1/XHRR 010200
- en F:FleF2 010300 m em 3 FF:Fe(XtlRR/( XHRR-2.15 ==
010400
- ATAC(III DSQRTIFF)mSIGNA i; 010500 * **
; WLRtII):WREIII-EKuATAD(II) un I
010600
- WUR( II I:l;R( II)+ EKW A T AB(II) 010700 * **
7 COilTIlrut { 010C00
- me B Cu240J.
010900 * ==
"." SIGttAD=DSORit WSUM/( t XtlRR-2. 4* TOT ) ) ==
{ 011000
- EKK: TABLE (itRR1-2) j 011100
- au BL:B-tEKKmSIGNADin2400. en
}
011200 m BH D+EEKKaSIGNAB)=2400. 011300
- mm
'l( REA0(4*HRR1)NR. TIME (HR).ATUC.APUC.AVPUC.ATLC.APLC.AVPLC.ATIC.APIC. #m i
m_ .. . ~ . . . . ~ . _ NOR CCVREPT 01/22/75 LI3=es****** COUDCE Libp. SPY CUTruT 10/31/77 15.59.11 .. 011400 * *AVPIC,liUC(l'R ),HlCt t:R ),WIC( H1),W( Hl) **
- 0115C0
- WRIT E t 4't!7 411tQ .TIttE( HR ) . ATUC. AP'JC. AVPUC. ATLC. APLC. AVPLC. ATIC. APIC **
011600 * *,1\ FIC.WUC(HR ) .WLC(f.R i e(JIC(ItR ) .Wil:R I BL B.DH. A ** . n117c0
- H71TE(6.201) **
011000
- 201 FCPM A T( IH1,4CX. '
SUMMARY
OF AVEPAGES'///1H .2X,'RUN s',2X.' ELAPSED ** 011900 * * * .0X,3t 34H AVG TEttP AVG PRESS AVG V PRESS 1/1H .10X,' tit!!'.6X.'O au 01:000
- aFPER',5X,'UFFER' 7X.' UPPER',7X,' LOWER'.5X.' LOWER',6X,'LDHER*,8X,'I **
C12100 m *CE',7X.' ICE *,9X,' ICE */3 .
==
012:00 m PE A D( 4 '1 )H2R TI!1E(142R ) .WUCDEM.WLCDEN.WICDEH.WDEf t, ATUC. APUC, AVPUC. A ** 012300 *
- TLC.APLC.AVPLC.ATIC.APIC,AVPIC **
01:400
- ATDC:ATUC-459.7 **
012500
- ATLC:ATLC-459.7 **
010600
- ATIC:ATIC-459.7 **
012700
- W91TE f 6.202 )fl2P. TIME ( H2R ) . ATUC, APUC. AVPUC. ATLC. APLC. AVPLC. ATIC. API **
012000 * *C.AVPIC ** 012900
- 202 FORMAT 11H .2X,I3.4X,F6.2.2X,3( F9.4.2X,F9.4.3X,F 9.4.2X)) **
013000
- DO C46 JG:2.tf2R1 **
013100
- RE AD( 4
- JG illR.TIf1E ( HR ), ATUC, APUC. AVPUC. ATLC. APLC. AVPLC,dTIC. APIC. AV **
013000 * *PIC ** 013300
- ATUC ATUC-459.7 **
01?400
- ATLCsATLC-459.7 **
01I500
- ATIC=ATIC-459.7 au 013500
- 846 WPIT E( 6.IO2 HfR .TIf1E( HR ) . ATUC. APUC. AVPUC. ATLC. APLC. AVPLC. ATIC. A PIC. **
013700 * *AVPIC m* i 013800
- WPITE(6,205) **
syg , 013900
- 205 F07ttLT(1H1.34X,'PESULTS OF Tile LIllEAR REGRESSIDtl At1ALYSIS TEST'/// **
LA3 014000 * *1H .2X,'PL43 c' ,0X 'W' .11X,' LE AKAGC R ATE ' 9X,' LE Af'. AGE * ,9X.
- LE AKAGE **
s 014100 #
- RATE *,8X,'W UPPEP',7X,'W LO.1ER',9X,'W ICE */1H .10X,*EXFERItlENTAL*, **
. 014200
- e6X. ' LOl!!R lit 1IT ' ,11X , 'R AT E ' ,11X. ' UPPER LIMIT ' ,5X.
- CON TAINMEt4T' . 3X. **
014300 * *
- Cot 4T A ltit tDIT ' . 5X, ' CONDEi!SER '/ ) **
014400
- DO CAS JG2:3.tMR1 **
014500
- REA0(4*JG2)HR. tit 1E(JG2) ATUC.APUC.AVFUC.ATLC.APLC,AVPLC ATIC.APIC, **
014600 m
- AVPIC .WUC( JG2 ),WLC( JCO ) .WIC( JG2 3.Wl JG2 ) .CL .D.BH , A **
014700
- 845 6 2ITC( 6,206 )t1R .W( JG2 ),DL.D.BH.WUC( JG2 ),WLC( JG2 ),WIC( JG2 ) **
014000
- 206 FCRdAT( 1H .3X,I 3.4X,F 9.5.9X.F 9.5.9X,F9.5.10X.7 9.5,8X,F 9.5.5X.F 9.5, **
014900 * *6X F9.51 ** 015000 m REA0(4'99)HRR ** 015100
- IF(ISR1-flPR )J47,044.E 44 **
015200
- 844 REAU(4'NRR1)HR. TIME (NR).ATUC.APUC,AVPUC.ATLC APLC.AVPLC.ATIC,APIC, se 015300 m *AVPIC.WUC( HR I .WLC(IG ) .WICf HR ),Wt HR ),BL.B.BH A **
015400
- W2ITE(6,203)D.A **
015500
- 203 F09 MAT (1H0,21X,' fit 4AL LEAKAGE RATC (X PER DAY) ='.F9.5.5X,'IliTERCE **
015600 * *PT=' F9.5) ** 015700
- WRITE (6,204)BL.BH **
015J00
- 204 FORMAT (IHO.21X.' FINAL COHFIDENCE LINITS FOR THE RATE ARE ',F9.5,' **
"" 015900 * *TO ',F9.5) **
016000
- 3 STOP **
016100
- END **
i i me I W e 5
- t I
1 70 ANALYSIS UTD INTERPRETA'" ION The previous sections of this report described the method of measuring and computing the containment leakage rate. This section will be dedicated to a discussion of the observations and conclu-sions drawn from the performance and subsequent analysis of this r containment ILRT. Also included in this section is a presentation ,. on the error analysis related to the test instrumentation. I 71 Discussion of Graphical Test Data i Figures 7 1.1 and 7 1.2 are the graphical representations of the Integrated Leak Rate Test and Supplemental Test data respectively. The axis cf these graphs are the i normalized weight of original air versus time. The slope of the regression line is the leakage rate. f Examination of Figure 7 1.1 reveals the dispersion of data points, representing the normalized weight (W ) ' n containment air, results in exceptionally horizontal regression line. A regression line of this nature over the indicated 31.5 hour test period is indicative of an extremely leak-tight containment which is confirmed in the fact that the average change in W
, n Per unit time, hence leak rate, is -0.00428 %/24 hrs. when expressed on a daily basis. The dispersion of data points yields a variance (mean square deviation) in the leak rate of
= 0.00422 % wt./24 hrs. The variance is computed on a 95% confidence level which results in a lower leakage limit of -0.00850 % wt./24 hrs. The 95% confidence level
. -S-(
s f 71 Discussion of Graphical Test Data (Cont'd)
~
lower limit is still well within the specified allowable leak rate of -0.1875 % wt./24 hrs. i ( The graphical representation of the Supplemental Test may be found on Figure 7 1.2 of this report. As illustrated, { with the supplemental leak rate imposed on the contain-ment, the change in the normalized weight (Wn ) of y containment air per unit time is much more pronounced I ohan in Figure 7 1.1 as would be expected. It is interesting to note, however, that because the measured containment leak rate was extremely low, the change in ( Wn per unit time as shown for the Supplemental Test is y only 1.5 per cent greater than the Technical Specification t l limit for containment leak rate and, thus, may be viewed as a dramatic comparison with the measured containment l leak rate shown in Figure 7 1.1 For ease of comparison ( the portion of the regression line from run 1 to 17 of ( Figure 7 1.1 has been superimposed on Figure 7 1.2. Figure 7 1 3 is a plot of the average absolute pressure f (PSIA) for each containment compartment. As indicated, L each containment compartment generally exhibits the same steady decay in pressure during the 31 5 hours of the ILRT. A calculation on the measured change in the average absolute pressure over runs,1 to 64 for the f Upper, Lower and Ice Condenser Compartments results in
& P of 0.0868, 0.0887 and 0.0870 PSI respectively
~
a Y ~55~
.a. . _ m _
1
- o i i
l i 71 Discussion of Graphical Test Data (Cont'd) : I with an overall average change in absolute pressure of 0.0875 PSI. When the standard deviation is computed for the average absolute pressure measurements the standard error is found to be = 0.00085 PSI. As can be seen in Section 7 3, the ILRT instrument error analysis uses [ the very conservative value for standard error of I
= 0.003 PSI.
Figure 7 1.4 is the graphical representation of the i average vapor pressure (PSIA) for each containment com-partment as measured during the ILRT. This graph clearly f demonstrates the contrasting environmental conditions experienced in the three containment compartments. As shown on Figure 71.4 the Upper and Ice Condenser com-partments demonstrate relatively stable moisture content throughout the test while the Lower compartment experiences i an appreciable " drying out". The steady decrease in the t partial pressure of the water vapor present in the Lower [ compartment air is probably brought on by a migration of relatively colder drier air from the Ice Condenser com-L partment which, in turn,' promotes condensation therein. The weighted average temperatures for the three contain-ment compartments have been plotted on the graph of Figure 715 The Lower and Upper containment volumes exhibit
' about the same steady decreasing trend in temperature.
Both compartments experienced an approximate 1.5 'F drop { c i
,~. _ . . - . _ . _ . . _ . . . . _ _ ,
l i
)
i l I 71 Discussion of Graphical Test Data (Cont'd) ,'~ in temperature over the 31 5 hours or 0.05 *F/hr. Thus, it may be concluded from this observation that the Upper I and Lower containment compartments will stabilize in temperature and tend to maintain their stability through- [ out the course of the leak rate test. f l The plot of Ice Condenser compartment average temperature, however, illustrates that stabilization here is quite another matter. While the overall change in temperature p from Run 1 to Run 64 is an increase of only 0.68 *F for the 315 hours, much larger *F/hr. changes are experienced
- f. because, unlike the Upper and Lower compartments, the trend is not constant but rather tends to cycle. The f
i cyclical variations in Ice Condenser average temperature,
, whose magnitude is typically 0.06 *F/hr. and as much as l 0.23 *F/hr. are caused by the periodic defrosting of the Ice Condenser air handler cooling coils. This was also a problem on the Unit 1 Pre-Operational ILRT and steps were taken during this test to minimize this affect by s-manually actuating defrost on selected air' handlers.
- While the defrost affect on average temperature was
{ somewhat reduced by this effort, compared to the Unit 1 1~ test, its affect on temperature stability makes compliance with the 0.1 *F/hr. stabilization criteria impracticable. I 1 1 A revised stabilization criteria for the Ice Condenser-i- compartment is under consideration for use in future containment perodic re-tests. l i 57-
. 7% , wes=-.,+ -gow-.m-,~e-+~. -*-~-*--w*~- - * - -
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t-- -=..+m ic+i.i :i=.1 =:1 =!=n.
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-- r - r 1~.=..E.(Y. '** " ** ~ ' 7*. r=-.=- 1
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- -h ~"fis.i.id' -hf
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d = j - t'L,.G, Q , y ----4=k . .; ;q.-a 3 , . ...i , ..Nj h.4;g;;. _ Q ;__ _. __.. . - .. sy i.:N. ., .$h_ .. ..Q
.U..
_ gu :=
.j u -m"y -: - .d
,: = t = 7 ;._. . g - p
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+ r =p g=Qrr_af
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- 4. p.- ;gvi-4 ;, . it . gp ;
p=z 1. . O, n. . .= m i .ni.r M- t-i-cf r Q-*wrw=;
- 7. -- r .m a
- g. . l +:-.j . =p: =-. l.:3 L a.4M4 wq: .r_. c-i
_y h M.+-
;.. p q= l==.p _
..w.=
7_g m y.u.&=i- p3 4 .::ey g ;== u.=a p.mw; w p. g= %g -
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E-fs L t"^.:i-E +iir-
~ ::j~T=^- & T'Y .. -p';-Q 'l :p:_ 5..;_ ~
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=v ._ h
} 7; _
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. .. .... m..u v. m.o.c o m .
. . . . .- .- .- - . ~ _ - . . . . .
- t 7.2 Discussion of Parametric Study A parametric study was performed using the test data f collected during the Unit 2 Pre-Operational ILRT to determine the affect varying the volume of ice resident in the Ice Condenser ccmpartment would have on the leak ate calculations.
I L , The parametric study was comprised of three conditions of ice basket loading, i.e., Case I maximum ice load, Case II minimum ice load allowed by current Technical Specification and Case III actual ice load. In the case of maximum ice load, the entire internal volume of each ice basket was assumed to be occupied by ice. The ice volumes for the actual and Technical Specification lower limit were calculated based on 1481 and 1220 lbs. per I basket respectively. l By varying the volume of ice in the Ice Condenser the associated net free volume is so affected. The resultant i' Ice Condenser free volume for the three cases is reflected I accordingly in the Volume Weighting Factors (VWF) used in the calculation of normalized weight of containment air. t A detailed discussion on VWF is presented in Section 6.2
; of this report.
The results of the parametric study has been tabularized
%4 4
. +, T-,w-- - -
. ,a ..- ..
- i 72 Discussion of Parametric study (Cont'd) in Table 7 2.1 below:
TABLE 7.2.1 Ice Containment ILRT Supplemental Basket Measured 95% Lower Test i Loading Leak Rate = Confidence Limit
- Leak Rate =
Maximum +0.00270 -0.00166 -0.18199 Actual -0.00428 -0.00850 -0.19028 Minimum -0.00708 -0.01126 -0.1936L '
= Leak Rate expressed in % wt./24 hrs.; - denotes out leakage.
j Using the actual weight of ice as a basis for comparison Table 7 2.2 illustrates the change in the calculated leak f l rate: l l - l l TABLE 7.2.2 _ l Comnarison Containment ILRT Supplemental Test Aethnl With: 4 vt./2k hrs.= 4 $k 4 vt./2k hrs.* 4 $k Maximum Ice +0.00698 163 1 +0.00829 4.36 Minimum Ice -0.00280 65.4 -0.00336 1,77 i L.
* - Denotes increase in out leakage.
t^ A review of the above Table 7 2.2 indicates the affect of
!' varying the ice volume between the extreme conditions of maximum and minimum ice load conditions is not as significant, in terms of per cent difference in the overall leak rate, f .
----m-4 1m.w w 3 - -ps ~ -
os -w q , e . ,w ,. .
;* i 7.2 Discussion of Farametric Study (Cont'd) r when the magnitude of leakage closely brackets the ILRT allowable limit of -0.1875 % wt./24 hrs. as it is for relatively smaller leak rates.
l { In the Supplemental Test, where the magnitude of leakage t is approximately equal to the ILRT allowable limit, the difference in the leak rate between the actual leakage
, and the maximum and minimum ice load leak rates is 4 36 and 1.77 per cent respectively. The overall change in the leak rate for the two extreme ice load conditions is equal to 0.01165 % wt./24 hrs. or 6.2 per cent of the allowable leak rate. Leakage of this magnitude.would be _,
r significant in the event the acceptance of an ILRT was a i borderline case. When the leak rate is small, as shown in Table 7.2.2 for the ILRT results, the affect on the magnitude of the I measured leak rate is dramatic. There is, however, F little significance at these levels of leakage, in that, even with a 65 per cent increase over the actual leak
. ate the resultant leaPage (-0.00708 % wt./24 hrs.) is still only 3.8 per cent of the ILRT allowable.
L_ It is interesting to note at this time that the difference between the maximum and min' i mum ice load conditions represents an ice volume of 30,936 cubic feet or 1 73 x 10 6 pounds of ice. To incur the 6.2 per cent
- L:
- i 72 Discussion of Parametric Study (Cont'd) 1
- r. error in the measured leak rate, as discussed above, due i
\ l to inaccuracies in the ice basket weighing would require
- an error in measurement of approximately o90 pounds of i
ice per basket. The present method of veighing a representative sample of ice baskets and computing the statistical average weight per basket produced a standard t deviation of only 35.45 pounds for the measurements j taken prior to this ILRT. ,~ Thus it may be concluded from the above results, that the variation in the calculated leak rate, as affected by the extreme conditions of maximum or minimum ice volume is small but would be significant in the acceptance of e i borderline ILRT's. It may also be concluded that the i uncertainties involved in determining the quantity of ice within the ice baskets, and hence the net free volume of
, the Ice Condenser compartment, are well within the limits
[ of required accuracy. 73 Instrument Error Analysis The following calculation represents the instrument error analysis performed to substantiate the selection of the test instrumentation utilized to provide inp'?c to the computation of the containment leakage rate. In summary, the instrument error analysis demonstrates the inaccuracies associated with the test instrumentation
, L
73 Instru=ent Error ;.nalysis (cont'd)
,-, may contribute an error of = 0.076 L a t the calculated containment leakage rate. This level of inaccuracy is more than tolerable in as much as the containment allow-able leakage rate La is reduced for purposes of contain-ment integrated leakage rate testing to a value of
- r. 0 75 La . Moreover, the required correlation between the l
ILRT and Supplemental Leak Test is established at
= 0.23.La* .
q-.
\
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- g. -- _ - . .. _ , 4_ ..
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APPEND 1X 'A' UPPER voz.ume - 'D E W Po m'T TEMPER ATvR iss D e w P r. VAPOR press oR E N A
- bog Pacuunes oF "HG PS2.A p s.I A w "H g. f,.m 3r o.Zo342 c.0999i Ses u..w
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f a "r c E cor40s8sER - bEM Pornr 7enpenames
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ENGINEERING DEPT.
- gggg7 [h CF DATE BY N cy C. O .h
* ' Antal:Am Etterar: P:vEn SEnvict Camp.
COMPANY I M M '.8v f d G.O 2 BROADWAY PLANT
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- i ENGINEERING CEPT. SHEET or
*** AMERicAh ELECTate Pcuta Stavict Corp. DATE /
BY NO5 CK C O 8_ . 2 BROADWAY COMPANY Y N [Md a,o NEW YORK PL. ANT . C* M // M M SUBJECT N "8"I A#T MS '#
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APMNDix 'A ' d~d. W. L oId E R l/OLUME - DEu Po,xr 72npe.nnwees No. 2
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UPPER voc.vmE .. S3 4. o S l LowSR VOLUME S 3 8.18 1ce canoens19 4 8 I. 8 (a l Co u re,u m na r V m Ss:s. PS2.A UPPE.R volume C.C848 . towcR votomE C.1849
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C0tli Alt 31Elli TEtIPER ATURES DATA CHECK N N - O 7 UPPER V0tt#tE LOWER VoluttE ICE CCilDEllSER *-j RTD ttIL L I-VO LT S OfG. F. RID HILLI-VOLTS DEG. F. RID #1ILLI-VOLTS DEG. F. 7 i ETR-101 ETR-102 37.19 37.14 74.38 74.28 ETR-122 EIR-123 45.96 45.35 91.92 90.70 ETR-Il5 EIR-Il6 11.28 10.40 22.56 20.96 gMs p 7 a pg 2 ETR-103 37.14 74.23 E1R-124 91.12 ETR-IIT 13.74 27.48 0 'O ETR-104 37.45 74.90 ETR-125 45.56 45.59 91.18 Elit-118 12.67 25.34 E N 1 [- 2"EE
= 0 EIR-105 36.68 73.36 [1R-126 39.e7 79.74 ETR-106 74.10 EIR-119 10.26 20.52 y$,N ETR-107 37.09 36.95 73.90 E1R-127 EIR-129 30.60 37.63 77.20 75.26 ETR-120 EIR-121 10.47 11.44 20.94 22.88 9
g 3 d y$ ou m l*, E ETR-108 ETR-109 37.10 37.41 74.20 74.82 EIR-130 E lit- 131 39.97 33.67 79.94 77.34 O 0 x m* = 0 ETR-110 74.06 37.20 XQ y, tJ ETR-132 74.40 ETR-111 37.43 37.32 74.64 EIR-134 30.76 77.52 }g g p m it
." 4 ETR-112 37.78 75.56 ETR-135 39.00 78.00 - ,
ETR-Il4 37.20 74.40 ETR-136 37.65 '75.30 g g 4 "
,g 33 E1R-128 35.72 71.44 ETR-137 39.26 78.52 g ETR-133 36.70 73.40 LIR-133 38.24 76.48 g
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.' EIR-141 EIR-142 36.79 35.45 71.58 72.90
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SutittARY OF WEIGillED AVERAGE 1EttPERATURES T ou i > f UPPER V0ttAtt (DEG. F.I 74.33 tol;[R VOLUr1E (DEG. F.) 78.48
- ICE Cot 10Et45ER (DEO. F.) 22.16 UPPER VOLUtlE IDEG. R.) 534.08 LO:4ER VOLutIE 80EG. R.I 538.18 ICE Coli0EllSER (DEG. R. I 431.86 G (G Np 2
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~ ~Cd5TAltir1ENT VAPOR PliESSURE DATA CHEis(~ C0tiTAItitlEHT PRESSURES DAT A CHECir, t1ILLI- DEH POINT VAPOR PRESSURE Utic0RRICIED COPaECTED b },
. HYCRot1ETER VOLTS (DEG. F.) (PSIA) itAliCt1E TER READING (FSI A) READII;G (PSIA) .
g 4 Yru-1 h y 1$
; 33.00 30.91 0.0048 PU-1 26.6110 26.6327 VPL-1 36.00 43.09 0.1371 PU-2 26.0910 26.62e7 g pg Jm VPL-2 39.55 57.33 0.2328 PL-1 26.4804 26.6273 L- VPI-1 29.13 15.38 0.0403
- PL-2 26.7292 26.6498 K CQ g 01-1 26.6323 26.6294
- 2. --
I, i ( g PI-2 25.9!53 26.6366 0 y Suttr1ARY OF VAPOR PRESSURES AIPIEllT 14.1760 14.4353 hO X n UPPER CollTAlt31EleT 4 PSIAI 0.0848 I AVER AGE LoutR Cot 4TAlt31ENT (PSTA) 0.1849 SUtir1ARY Or CORRECTED AVERf GE PRESSU1ES Mo ' )'lo ICE Cot 10EllSER (PSIA) 8.0403 . -
# N AVER XE UPrER ERESSURE (PSIA) 26.6207 AVIR AGE LOLLER s'ltESJtsRE I PSI A)
AVERAGE 3CE COtIDE6SER P2ESSurtE IPSIAl 26.6330 26.6305 h \I AVERAGE C0 tat 41H.*.Eter PRL55t;RE (PSI AI 26.6334 l .. AVER AGE ColliA1H;l244f PRE 55HI1E (PSIG) 12.1471 l . . . . .
* ;
- e 8.0 IIRT T.45UtaTED
SUMMARY
The following pages are tables listing the =easured parameters and calculated values for the data taken during the Unit No. 2 Pre-Operational Contain=ent ILRT. 8.1 Cc-ta4-rm-t TLRT and Surriamental Tast Table S.1.1 ILRT - Results of Linear Regression Analysis 4 - _ Table c.1.2 ILRT - Su==ary of Averages Table 5.1 3 Supplemental Test - Results of Linear Regreseion Analysis Table 5.1.4 Supplemental Test - Su==ary of Averages r Table 5.1 5 Cc=puter Progra= Fixed Input Data 6.2 Pararetric Case I Table 5.2.1 Parametric Case I - Results of Linear Regression Analysis (ILRT) Table 5.2.2 Parametric Case I - Su==ary of Averages (ILRT) l Table 8.2 3 Para =etric Case I - Results of Linear Regression Analysis (Supplemental Test) Table 6.2.4 Para =etric Case I - Su= mary of Averages
; (Supple = ental Test)
[ Table 8.2.5 Parametric Case I - Cc=puter Program Fixed Input Data i 83 pararetric case II Table 8.3 1 Parametric Case II - Results of Linear Regression Analysis (ILRT) Table 6.3 2 Parametric Case II - Summary of Averages (ILRT) t Table 8 3 3 Parametric Case II - Results of Linear Regression Analysis (Supplemental Test) Table 6 3.4 Parametric Case II - Summary of Averages (Supplemental Test) Table 8.3 5 Parametric Case II - Computer Program Fixed Input Data
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0 0 9 O StRO14RY OF AVENAGES O a O . TADIR 8.1.2 O" RUH 0 ELAP5fD AVG 1EMP A%G 8'R[55 AVG V ITL53 AVG 1EMP AVG FRESS AVG V PliE55 AVG lillP AVG PRESS AVG V P.1[5S TlHE UPPER UPI'L R UPPEH l(ERR LOWLR LOWER ICE ICE ICE [) 1 0.0 75.7610 26.7155 80.1140 Q 0.0979 26.7272 0.2491 21.4759 26.7200 0.0408 2 0.50 75.7181 26.7134 0.1011 6C.0734 26.7255 0.2510 21.5342 26.7502 0.0369 3 1.00 75.7048 26.7127 0.0973 80.0400 26.7247 0.2502 21.6289 26.7175 0.0411
] 4 5
1.50 2.00 75.6961 75.6691 26.7108 26.7088 0.0976 0.0970 80.0108 79.973% 26.7227 26.7207 0.2495 0 . 28.8 S 21.6616 21.6013 26.7154 26.7134 0.0369 0.0606 6 2.50 75.6531 26.7063 0.0995 79.9292 26.7385 0.2400 21.5171 26.7113 0.09.*4 7 3.00 75.6328 26.7059 0.1009 79.9063 26.7174 0.2466 21.5540 26.7104 0.0417 8 3.50 75.6234 26.7045 0.0985 79.6699 26.7860 21.6081 26.7090
' 9 4.00 75.5933 26.7031 0.0959 79.6470 26.7148 0.2652 0.2434 21.5707 26.7078 0.0423 0.0458 g
10 4.50 75.5946 26.7014 0.0931 79.6059 26.7132 0.2427 21.6642 26.7046 0.0 l?0 11 5.00 75.5595 26.7007 0.0950 79.7439 26.7122 0.2410 23.6936 26.7052 0.0395 12 5.50 75.5405 26.6983 0.0968 79.7364 26.7029 O- 13 6.00 75.5247 26.6976 0.0945 79.7304 26.7099 26.7092 0.2399 0.2333 21.7748 21.7477 26.7024 0.0391 0.0408 g 14 6.50 75.5117 26.6967 0.0971 79.6899 26.7031 0.2366 21.0176 26.7016 0.0426 15 7.00 75.4997 26.6954 0.0953 79.6592 26.7074 0.2352 21.0250 26.7004 0.0450 f 16 7.50 75.4811 26.6945 0.0545 79.6390 26.7054 21.8504 A 17 8.00 75.4577 26.6932 0.0954 79.6056 26.7044 0.2334 0.2320 21.23C4 26.6992 26.65!1 0.04t1 0.0430 g 18 8.50 75.4392 26.6917 0.0947 79.5395 26.7026 0.2303 21.9043 26.6944 0.0338 19 9.00 75.4148 24.6925 0.0921 79.5628 26.7034 0.2292 21.9037 26.6972 0.0437 20 9.50 75.4250 26.6922 0.0953 79.5294 26.7030 0.2268 O 21 10.00 75.3423 26.6914 0.0874 79.5315 26.7022 0.2251 21.9795 22.0417 26.6967 26.6968 0.0405 0.0443 g 22 10.50 75.3457 26.60!8 0.0870 79.4914 26.6996 0.2241 22.0115 26.6935 0.0460 23 11.00 75.3337 26.6664 0.0396 79.4705 26.6972 0.2216 21.99C2 26.6911 0.0468 24 11.50 75.3260 26.6840 0.0924 79.4450 26.6947 0.22C4 22.0814 f} s00
' 25 12.00 75.3012 26.6829 0.0921 79.3855 26.6936 0.2183 21.*/e2 26.6057 26.6675 0.0446 0.0426 0 26 12.50 75.3115 26.6807 0.0876 79.3979 26.6915 0.2180 21.9937
.! 00 27 13.00 75.2391 26.6794 0.0921 79.3620 26.6901 0.2168 P2.on98 26.te55 26.6841 0.0416 0.0458 (~T 13.50 75.2362 26.6767 0.0919
'/ '
4 to 79.3200 26.t875 0.2147 22.0592 26.6el5 0.04 o i 29 14.00 75.2257 26.6751 0.0913 79.3011 26.4076 0.2131 22.0037 26.6817 0.0408 O 30 14.50 75.1803 26.6749 0.0903 79.2093 26.(358 0.2117 22.1443 26.67a3 0.0463 31 15.00 75.1792 26.6725 0.0903 79.2785 26.6639 0.2104 22.0824 26.6773 0.04c0 a 32 15.50 75.1333 26.6719 0.0905 79.2488 26.(327 0.2088 22.0026 26.6767 0.0417 ()N 33 16.00 75.1273 26.6697 0.0887 O 79.2190 26.4813 0.2074 22.0909 26.6737 0.0419
.. 34 16.50 75.1233 26,6696 0.0910 79.1434 26.6811 0.2066 22.15(2 26.6724 0.0398 l'
35 17.00 75.0912 26.6698 0.0905 79.1968 26.6611 0.2054 22.1463 26.6728 0.0395 36 17.50 75.0807 26.6679 0.0912 79.1611 26.6794 0.2036 22.0964 26.6710
}
' } 37 18.00 75.0622 26.6660 0.0906 79.1325 26.f 771 0.2027 22.1236 26.6666 0.0414 c . 0'e 2 5 ggg 1 38 18.50 75.0134 26.6641 0.0921 79.1167 26.6756 0.2012 22.0375 26.6672 0.c435
. 39 19.00 74.9931 26.6606 0.0953 79.1032 26.6737 0.2600 21.9937 26.6654 0.G423
'! 40 19.50 74.9570 26.6614 0.0894 79.0640 26.t727 0.1935 22.0034 26.6647 0.0402
(]' 41 20.00 74.9467 26.6601 0.0033 26.6712 O 79.0367 0.1973 22.04SS 26,6632 0.0390 42 20.50 74.9282 26.6594 0.0873 77.0239 26.6703 0.1957 22.0347 26.6618 0 . 0 'e 0 9 43 21.00 74.9261 26.6565 0.0806 73.9790 26.6673 0.1950 22.1255 26.6596 0.0 20 (T 44 21.50 74.6857 26.6563 0.0826 78.96S1 26.6620 0.1937
'/ 45 22.00 74.8479 26.6553 0.0373 74.9336 26.4658 0.1927 22.1303 12.2404 26.6596 26.65:3 0.0497 0.03s4 g
46 22.50 74.8304 26.6534 0.0879 78.9245 26.6639 0.1921 22.1732 26.6550 0.0416 47 23.00 74.7978 26.6518 0.0876 78.8999 26.6626 0.1910 22.1524 26.6543 0.0414 48 23.50 74.7882 26.6510 0.0J94 78.8722 26.6612 ("} 49 24.00 74.7344 26.4491 0.0353 78.3419 26.(593 0.1905 0.1093 22.1123 22.2005 26.6536 26.6520 0.0412 0.0400 0 50 24.50 74.7116 26.6498 0.0859 78.8307 26.6602 0.1891 22.2053 26.6519 0.0923
=
i 51 25.00 74.6970 26.6487 0.0966 78.7990 26.6508 0.1087 22.2204 26.6532 0.0403 52 25.50 74.7079 26.6461 0.0849 78.7984 26.6563 0.1881 26.6485
;l
(']" 53 26.00 74.6547 26.e437 0.0883 78.7660 26.6541 0.1873 22.1036 22.1807 26.6412 0.0400 0.0419 g 26.50 74.6769 26.6:*31 0.0884 78.7394 2 530 0.1874 22.1143 26.6475 0.0432 r% : (FM) e. 9
-1 i o j
TABLR 8.1.2
- Sut01ARY OF AVERAliES
. RUN 5 ELAPSED AVG TEt1P AVG PRESS AVG V PRESS AVG 1EllP AVG PRESS AVG V PRESS AVG T E tIP AVG PRESS AVG V PAESS litlE UPPER tFPLR t)PPER 10LICR L O'AE R LOWLR 3CE ICE 3CE . 55 27 to 74.6119 26.6419 0.0876 78.7088 26.6520 0.1871 22.1000 26.6464 0.0470 74.6039 26.6414 73.6923 26.6515 22.0341 56 27.52 0.0350 0.3670 26.6460 0. 0 'e 37 57 28.00 74.5858 26.6399 0.0363 78.6604 26.6503 0.1e63 22.1403 26.t445 0.0197 58 28.50 74.5466 26.6330 0.0848 78.6501 26.64C4 0.1858 22.2620 26.6426 0.0*07 59 29.00 74.5221 26.6360 0.0393 78.6117 26.6463 0.1061 22.2139 26.6406 0.0402 60 29.50 74.4770 26.6346 0.0843 78.5037 26.6449 0.1854 22.2056 26.6393 0.0418 61 30.00 74.4834 26.6333 0.0866 78.b577 26.6436 0.1052 22.2600 26.6380 0.0441 62 30.50 74.4345 26.6309 0.0855 78.5369 26.6413 0.1850 22.1477 26.6357 0.0423 i
63 31.00 74.4229 26.6297 0.0049 78.5235 26.6402 0.1849 22.1189 26.6337 0. 0 39'e 64 31.50 74.3793 26.6287 0.0848 78.4840 26.6385 0.1849 22.1650 26.6330 0.0403 1 I ' (D s h I, O
O O O RESULT 5 OF THE L1 HEAR REGRESS 10tl AtlALYSIS IEST
.I O tam.e a.i.3 LEAKAGE RAIE W UPPER H tou!R H ACE RUtt 3 W LEAKAGE RATE lDif AGE LOWiel L1titi liAlt UPPER 11 tift C0tH A1H;1t HT Colli AltCElli CCt. )D.St e EXPERIrlEHT AL 0.81690 1.C00ll 0. 99 9t '. 1. 0t tas 3 1.00006 -0.54203 0.33844 3.95 U 4 0.99992 -0.76060 -0.11720 0.52620 0.99794 0.9'8'39 0 .99 pe 0.5 7? t5 0. 59 7T S 5 0.99990 -0.44098 -0.15681 0.12736 0.99994 0.98?S2 0.99375 ,
6 0.99988 -0.32775 -0.16493 -0.00212 0.97#55 pd -0.37743 -0.06920 0.999s9 0.999E0 7 0.99902 -0.28566 0.99997 0.93950 0.9%)e3 8 0.99984 -0.24081 -0.16031 -0.07'331
-0.08l34 0.999% 0.99976 0.9+948 9 0.99983 -0.20S64 -0.14649 0.99972 0.9 097 10 0.99971 -e.21543 -0.16210 -0 lori 77 0.99va9
-0.12925 0.99952 0.97970 0 . 9'tt 8 O- 11 0.99965 -0.22139 -0.17532
-0.13069 0.99997 0.9a9o9 0.99t%8 12 0.99969 -0.20781 -0.16925 0.993-6
-0.14304 0.9??71 0.99964 13 0.99951 -0.22068 -0.18836 0.99956 0.998'9
-0.00341 -0.16433 0.99964 14 0.99945 -0.24249 0.99975 0.99951 0.99342 O- 15 0.99949 -e.23682 -0.20327 -0.36913
-0.19293 -0.16110 0.99981 0.99950 0.995S9 16 0.99955 -0.22475 0.99968 0.99953 0.99045 17 0.99946 -0.21837 -0.19029 -0.16222 FINAL LEAKAGE RATE IX PER DAYD = -0.19029 IHifRCEPTs 3.00007 FIH61. CONFIDEHCE LINITS FOR 1HE RATE ARE -0.21837 10 -0.16222 6
I O'i' St491ARY OF AVERA(.E5 g TAHLR 8.1.4 RUH 8 ELAPSED AVG TENP AVG PRESS UPPER AVGLOLLER V PHE55LOWLR AVG TEMP AVG PRESS LONER JCE AVG 1CE V PRESS AVG ICE 1Eth8 AVG PNESS AVG V P TINE IJPPER UPPER 26.6352 0.1843 22.2100 26.6298 0.040S 74.3581 26.6254 0.0856 78.4707 3 0.0 26.6341 0.1838 22.1365 26.6288 0.0394 0.50 74.3350 26.6246 0.0e52 78.4432 0.0373 2 0.0031 78.4376 26.6322 0.3844 22.1 E 80 26.6258 3 1.00 74.2957 26.6228 22.1995 26.6236 0.0391 74.2916 26.6196 0.0346 78.4133 26.6290 0. l E.38 4 1.58 0.0353 g 5 2.08 74.2781 26.6171 0.0828 70.38?5 26.6266 0. Its 37 0.1835 22.1671 22.0934 ' 26.6211 26.6197 0.0444 74.2324 26.6156 0.0837 78.3780 26.6252 6 2.50 26.6237 0.3856 22.1467 26.6165 0.0453 3.00 74.1826 26.4140 0.0857 78.3563 7 26.6230 0.1632 22.1902 26.6173 0.04e6 8 3.50 74.1790 26.6131 0.0811 78.3526 0.0395 . g 0.0827 78.3162 26.6207 0.1837 22.2186 26.6150 9 4.00 74.1498 26.6107 26.6130 0.0413 i 74.1513 26.6089 0.0323 78.3167 26.6189 0.1829 22.3961' 10 4.50 26.6172 0.1831 22.4337 26.6114 0.0398 11 5.00 74.1333 26.6072 0.0832 78.2894 0.0433 78.2669 26.6162 0.183's 22.4628 26.6033 12 5.50 74.0741 26.6068 0.0831 26.6076 0.0400 78.2557 26.6137 0.1828 22.5664
@ 13 6.00 74.1038 26.6035 0.0839 26.6105 0.1828 22.4832 26.6046 0.0408 14 6.50 74.0515 26.6003 0.08S3 78.2331 0.0432 78.1996 26.6072 0.1826 22.4475 26.6012 15 7.90 74.0333 26.5970 0.0799 22.3761 26.6006 0.0402 7.50 74.0031 26.5967 0.9796 78.1890 26.6067 8.1828 16 0.1826 22.4391 26.5997 0.0395 0 17 8.00 74.0003 26.5955 0.0820 78.1547 26.6054 O
. _ . . _ _ _ . . . _ _ _ . __ __ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . . - _ _ . _ _ _...__mm _ . . _ _ . . _
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sum THI5 IS A CHECK Of IttE 3HPUT DATA use O . O m w a.1.5 O' AfD ttittl-v0LT 10 F AHREtaltti CotN(4510H C0f f FICitH15 UPPIR 2.00 0.0 2.09 LOWER 0.0 2.00 ICE 0.9 g HVGR0r1ETER ttILLI-VOLT TO 6 AHREl#*EIT C0tWER5IDH COEFFICIEHis UPPER LDHtR-1 0.00227 3.87667 -99.49399 0.00234 3. f 66 72 -99.14546 LCWER-2 IC2 0.00277 3.83471 -98.67056 0.00192 3.90355 -99.95726 O O ttatetCTER PRES 5URE CORRECTIDH CoffrICItHIS PU-1 O 5'"*5***'5**'''''''''*'55' O PU-t 27.9573 27.4035 27.4544 26.9099 26.9561 26.4204 26.4596 25.9277 25.7603 25.4322 PL-1 l 27.9f.73 27.8136 27.4564 27.3102 26.9581 26.8118 26.4596 26.3128 25.*40 3 25.8090 0@' F8 27.9573 28.0286 27.4588 27.5317 26.9501 27.0359 26.4596 26.5400 25.1603 26.0427 PI-1 g 27.9573 27.9575 27.4549 27.4606 26.9581 26.9639 26.4596 26.4614 25.9603 25.9613 g PI-2 27.9573 27.2318 27.4560 26.7394 26.95812E.2529 26.4596 25.7604 25.9603 25.2719 P-ATH 16.4746 16.1106 14.9769 14.6549 13.4792 13.1928 11.9815 11.7310 10.4630 10.2681 G O RID WEIGHTING FACTORS O """'"
.0628 .1161.0831.0831.8960 .09t 0 .0960 .0960 .9296 .0296 e
.0296 .0296 .0740 .C105 .0167 .0513 LfMER O .0415 .0415 .0415 .8415 .9102 .0284 .0546 .0066 .9266 .9566 .3037 g
.1937 .1037 .3037 .0500 .0092 .9244 .0145 .9178 .9249 .9219 .9243 .9423 .0 g' .3750 .0758 .0725 .5725 .2213 .2766 .2071 ICE g
VOLUttC WEIGHT!tIG FACTORS UPPER LOWER ICE 2.9144 1.0000 0.4559 h b
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L t - k a TAlllE 8.2.2 Stac1ARY OF AVERALES RUN O ELAP5ED AVG 1EMP AVG PRESS AVG V PRESS AVG ItnP AVG PRESS AVG V PNESS AVG IEllP AVG PRESS AVG V PRESS TIME UPPER UPPEA UPP(R LDufR LOHLR LOHER ICE ICL 3CC 26.6419 0.0876 78.7068 26.6520 0.3871 22.1000 26.6464 0.0470
! 55 27.00 74.6119 56 27.50 74.6089 26.6414 0.0350 78.6923 26.6515 0.1670 22.0341 26.6460 0.0431 26.6399 0.0063 74.6604 26.6503 0.1063 22.1403 26.6445 0.0397 57 28.00 74.5655 0.0407 58 28.50 74.5466 26.6360 0.0348 78.6501 26.6404 0.1858 22.2620 26.6426 f 26.6360 0.0643 78.6117 26.6463 0.1661 22.2139 26.6406 0.0402 59 29.00 74.5221 0.0418 40 29.50 74.4790 26.6346 0.0843 76.5837 26.6449 0.1854 22.2056 26.6393
.', 41 30.00 74.4034 26.6333 0.0866 76.5577 26.6436 0.1052 0.1850 22.2600 22.1477 26.6320 26.6337 0.0441 0.0423 62 30.50 74.4345 26.6309 0.0655 78.5369 26.6413 ,
43 31.00 74.4229 26.6297 0.0649 76.5235 26.6402 0.1849 22.3189 26.6337 0.0394 26.6267 0.0344 70.4640 26.6365 0.1049 22.3650 26.6330 0.0403
' 44 31.50 74.3793 I
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i l RESULTS OF THE LIleEAR REGRESSICfl AllALYSIS 3EST TABLM 8.2.3 s RUll 0 W , LEAKAGE RATE 5EtKNE LEAKAGE RAit H Ul l'I R W 105:ER H ICE EXPERillit4TAL 10b*tR LillIT RATE UPPLR Lillli COHI Altititl4I COrsi/ It31E HT CONDEllSER 3 1.0000$ -0.45871 0.13018 0.73507 1.00011 0.99994 1.00006 4 0.99992 -0.74312 -0.11433 0. 519'e 6 0.97994 0.99939 0.99965
. 5 0.99990 -0.4 3 e53 -0.15420 0.10613 0.99994 0.99935 0.99986 6 0.99983 -0.32182 -0.16131 -0.00080 0.9999'e 0.99932 0.99973 7 0.99933 -C.01945 -0.37093 -0.0(641 0.99909 0.99130 0.9995S 8 0.99955 -0. 2 3'e 19 -0.15441 -0.07446 0.99997 0.99930 0.99943 9 0.99933 -0.20346 -0.14076 -0.07805 0.99994 0.99976 0.59948 10 0.99972 -0.20633 -0.15466 -0.10249 0.99939 0.99772 0.97S97 11 0.99967 -0.21201 -0.16715 -0.12250 0.99932 0.99970 0.99383
~
12 0.99971 -0.19770 -0.15971 -0.12172 0.97997 0.99569 0.99358 13 0.99953 -0.21318 -0.178*e9 -0.13n19 0.99971 0.59964 0.95J46 14 0.99947 -0.23268 -0.19306 -0.15505 0.99964 0.99956 0.99849 ' 15 0.99951 -0.20724 -0.19391 -0.16059 0.99973 0.97551 0.99042 16 0.99956 -0.21551 -0.18416 -0.15:eo 0.99981 0.99950 0.99359 17 0.99948 -0.20959 -0.18199 -0.15439 0.99963 0.99953 0.99045
, FINAL LEAKAGE RATE IX PER OAYI = -0.18199 INTERCEPT
- 1.00007
, F1HAL CUHFIDEHCE LIMITS FOR THE RATE ARE -0.20959 TO -0.15439 e
i@ Sur1 MARY OF AVERAGES Os
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TABLM 8.2.4 RUN 0 ELAPSED AVG TitlP AVG PRESS AVG V PRESS AVG itNP AVG PRES 5 AVG,V PRESS AVG iTMP AVG PRESS AVG V F RESS TINE UPPER UPP:R UPPER LONER LOWER LOWER ICE ICE ICE 1 0.0 74.3581 26.6054 0.0856 78.4707 26.6352 0.1043 22.2100 26.6293 0.0408 2 0.50 74.3350 26.6246 0.0852 78.4432 26.6341 0.le3. 22.i365 26.6:33 0.0394 3 1.00 74.2957 26.6028 0.0331 78.4376 26.6302 0.1844 22.1800 26.6068 0.0373 4 1.50 74.2916 26.6196 0.0846 78.4133 26.6290 0.1830 22.1995 06.6036 0.0391 5 2.00 74.2781 26.6171 0.08 3 73.339f 26.6066 0.1837 22.1671 26.6211 0.0383 6 2.50 74.2324 26.6156 0.0337 78.3760 26.6252 0.1035 22.0954 26.6197 0.Ce 44 7 3.00 74.1806 26.6140 0.0357 75.3563 26.6237 0.1836 22.1167 26.6181 0.0453 8 3.50 74.1790 26.6131 0.0831 78.3526 26.6230 0.1830 22.1902 26.6373 0.0446 9 4.00 74.1493 26.6107 0.0827 78.3162 26.6207 0.1837 C2.2166 26.6150 0.0395 10 4.50 74.1513 26.6039 0.0823 78.3167 26.6169 0.1809 22.3961 24.6130 0. 0'e 13 11 5.00 74.1333 26.6972 0.0032 73.2894 26.6172 0.1031 22.4337 26.6114 0.0399 1 12 5.50 74.0741 26.60o0 0.0311 78.2669 26.6162 0.1334 22.4628 26.0003 0.0433 13 6.00 74.1033 26.6035 0.0839 78.2557 26.6137 0.1028 22.5664 26.6076 0.0400 14 6.50 74.0515 26.6003 0.0853 78.2331 26.6105 0.1828 22.4832 26.6046 0.0403 15 7.00 74.0333 26.5970 0.0799 78.1996 26.6072 0.1806 22.4475 26.6012 0.0412 16 7.50 74.0031 26.5967 0.0796 78.1890 26.4067 0.1028 22.3761 26.6008 0.0402 17 8.00 74.0003 26.5955 0.0820 78.1547 26.6054 0.1826 22.4391 26.5997 0.0395 e ( i *
' V
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p, 7. i maa THIS IS A CHECK Of THE INPUT D?TA maa TABLM 8.2.7 RTD HILLI-VOLT TO FAHREletEIT CutlVER510tl COEFFICIEHIS
. OPPER LOWER ICE 2.00 0.0 2.00 0.0 2.00 0.0
- HYGRottETER NILLI-VOLT TO FAHREtalEIT ConvERSlott COEFFICIENTS
? UPPER L0utR-1 0.00227 3.87667 -99.49390 0.00234 3.25672 -99.14546
{ LDHER-2 ICE 0.00277 3.83471 -98.67056 0.00192 3.90355 -99.95728 MAHONETER PRESSURE CORRECTION CDEFFICIEHIS PU-1 27.9573 27.9346 27.4580 27.4347 26.9581 26.9376 26.4596 26.4373 25.9603 25.9388 PU-2 27.9573 27.4035 27.4580 26.9099 26.9581 26.4208 26.4596 25.9277 25.9603 25.4322 PL-1 27.9573 27.8136 27.4500 27.3102 26.9581 26.8110 26.4596 26.3128 25.9603 25.8090 yh PL-t sa 27.9573 28.0288 27.4580 27.'5317 26.9531 27.0359 26.4596 26.5400 25.9603 26.0427 8 PI-1 27.9573 27.9575 27.4580 27.4606 26.9581 26.9630 26.4596 26.4614 25.9603 25.9613 PI-2 27.9573 27.2318 27.4580 26.7394 26.9581 26.2529 26.4596 25.7604 25.9603 25.2719 P-ATM 16.4746 16.1106 14.9769 14.6549 13.4792 13.1928 11.9815 11. 7310 10.483^ 3 0.2681 RTD HEIGHTING FACTORS UPPER
.0628 .1161 .0831 .0831 .0960 .0960 .0960 .0960 .0296 .0296
.0296 .0296 .4740 .0105 .0167 .0513 LDHER
.0415 .0415 .0415 .0415 .0102 .0284 .0586 .0086 .0266 .0586 .1037
.1037 .1037 .1037 .0500 .0092 .0244 .0145 .0170 .0249 .0219 .0240 .0423 .0 ECE
.0750 .0750 .0725 .0725 .2213 .2766 .2071
~~# VOLUNE HEIGHTING FACTORS UPPER LOUER ICE 2.0144 1.0000 0.3933
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$UtstART Of AVERAGES O .
O Tants a.3 2 L RUll O E1APSED AVG 1ENP AVG FRESS AVG V FWE5S AVG 1EMP AVG PRfSS AVG V IFI53 AVG IIIIP AVG FPESS AVG V PRESS . 11ttE UPPER UPP( R UPPt R LOWER Lou 1R LOHEW ILE ICE ICE
@\ ' 1 0.0 75.7610 26.7155 0.0979 80.1140 26.7272 0.2491 21.4759 26.7200 0.040S 2 0.50 75.7181 26.7134 0.1011 80.0734 26.7255 0.2510 21.5342 26.7182 0.0339 3 1.00 75.7048 26.7127 0.0973 80.0400 26.7247 0.2502 28.6289 26.7173 0.0911 4 1.50 75.6961 26.7108 0.0976 80.0108 26.7227 0.2495 21.6616 26.7154 0.0358
(*}
's 5 2.00 75.6691 26.7088 0.0970 79.9734 26.7207 0.2485 21.6018 26.7134 0.0406 6 2.50 75.6531 26.7068 ,
0.0995 79.9292 26.7185 0.2480 21.5971 26.7113 0.0424 7 3.00 75.6328 26.7059 0.1009 79.9063 26.7174 0.2466 21.5540 76.7104 0.0417 8 3.50 75.6284 26.7045 0.0905 79.8699 26.7160 0.2452 21.6031 26.7099 0.0423 (]
' 9 4.00 75.5933 26.7031 0.0959 79.e470 26.7148 0.2434 21.5707 26.7078 0.0468 10 4.50 75.5946 26.7014 0.0981 79.8059 26.7132 0.2427 21.664: 26.7046 0.0300 11 5.00 75.5595 26.7007 0.0950 79.7439 26.7122 0.2410 21.6936 26.7052 0.0395 12 5.50 75.5405 26.6903 0.0968 79.7364 26.7099 0.2399 21.7748 26.7009 0.0391
(] 13 6.00 75.5247 26.6976 0.0945 79.7304 26.7092 0.2383 21.7477 ~26.7024 0.0408 14 6.50 75.5117 26.6967 0.0971 79.6899 26.7081 0.2366 21.8176 26.7016 0.0426 15 7.00 75.4997 26.6954 0.0953 79.6592 26.7071 0.2352 21.8200 26.7034 0.0450 r 16 7.50 75.4801 26.6945 0.0945 79.6390 26.7058 0.2334 21.0604 26.6992 0.0411 k} 17 8.00 75.4577 26.6932 0.0954 79.6056 26.7044 0.2320 21.830i 26.6931 0.0430 18 8.50 75.4392 26.6917 0.0917 79.5895 26.7026 0.2303 21.9053 26.6964 0.3133 i 19 9.00 75.4148 26.6925 0.0921 79.5628 26.7034 0.2272 21.9037 26.6972 0.0407
'>~~ 20 9.50 75.4250 26.6922 0.0953 79.5294 26.7030 0.2268 21.9795 26.6967 0.0405 21 30.00 75.3828 26.6914 0.0374 79.5315 26.70:2 0.2251 22.0417 26.6951 0.3443 22 10.50 75.3457 26.6888 0.0570 79.4914 26.6996 0.2241 20.0115 26.6915 c. 04( 0 23 11.00 75.3337 26.6864 0.0396 79.4705 26.6972 0.2216 21.9932 25.6911 0.0468 e 24 11.50 75.3260 26.6840 0.0924 79.4450 26.6947 0.2204 22.0014 26.6837 0.0446
(~) s- pa 25 12.00 75.3012 26.6829 0.0921 79.3855 26.6936 0.2183 21.9782 25.6875 0.0426 C) 26 12.50 75.3115 26.6809 0.0076 79.3979 26.6915 0.2180 21.9937 25.6855 0.0i16 C) 27 13.00 75.2391 ' 26.6794 0.0921 79.3600 26.6901 0.2368 22.6398 26.6341 0.0438
. gq ' to 13.50 75.2362 26.6767 0.0919 79.3000 26.6875 0.2147 22.0392 26.4813 0.0440 k> 29 14.00 75.2257 26.6751 0.0913 79.3011 26.6876 0.2131 22.0387 26.6837 0.0400 30 14.50 75.1803 26.6749 0.0903 79.2898 26.6658 0.2117 22.1443 26.6798 0.04c3 31 15.00 75.1792 26.6725 0.0903 79.2785 26.6839 0.2104 22.0824 26.6773 0.0400 r3 32 15.50 75.1383 26.6719 0.0905 79.2403 26.6827 0.2006 22.0926 26.6767 0.0417 C/ 33 16.00 75.1273 26.6697 0.0887 79.2190 26.6813 0.2074 22.0909 26.6737 0.0419 34 16.50 75.1233 26.6696 0.0910 79.1434 26.6811 0.2066 22.1562 26.6724 0.0398 35 17.00 75.0912 26.6698 0.0905 79.1968 26.6811 0.2054 22.1463 06.6728 0.J395 36 17.50 75.0807 26.6679 0.0912 79.1611 26.6794 0.2036 22.0964 26.6710 0.0414
( s 37 18.00 75.0622 26.6660 0.0906 79.1325 26.6771 0.2027 22.1236 26.6606 0.0428 38 18.50 75.0134 26.6641 0.0921 79.1167 26.6756 0.2012 22.0375 26.44 72 0.0415 39 19.00 74.9931 26,6626 0.0953 79.1032 26.6717 0.2000 21.9937 26.6554 0.0423 (~ 40 19.50 74.9570 26.6614 0.0894 79.0640 26,6727 0.1985 22.0034 26.6f47 0.0402 41 20.00 74.9467 26.6601 0.0833 79.0367 26.6712 0.1973 22.0488 26.6632 C.0399 42 20.50 74.9202 26.6594 0.0873 79.0239 26.6703 0.1957 22.0847 26.6608 0.0409 43 21.00 74.9261 26.6565 0.0806 78.9790 26.6673 0.1950 22.1255 26.65$6 0.04 0 21.50 74.8857 0.ce26 78.9681 0.1937 22.1508 26.6596 C.0*07 (} x 44 45 22.00 74.6479 26.6563 26.6553 0.C873 78.9386 26.6620 26.6658 0.1927 22.2404 26.6!83 0.0394 46 22.50 74.6304 26.6534 0.0879 78.9245 26.6639 0.1921 22.1732 26.65$0 0.6416 47 23.00 74.7978 26.6518 0.0876 78.8994 26.6626 0.1910 22.1504 26.6543 0.0 e;4
/~T 48 23.50 74.7882 26.6510 0.0894 70.8722 26.6s12 0.1905 22.1128 26.6536 , 0.0412 k/ 49 24.00 74.7344 26.6491 0.0853 78.8419 26.6593 0.1893 22.2005 26.4520 0.0430 50 24.50 74.7116 24.6498- 0.0059 78.8307 26.6600 0.1891 22.2C51 26.6!!9 0.0*23 51 25.00 74.6970 to.6487 0.0e66 78.7990 26.65S8 0.1637 22.2:84 26.e510 0.0-03
'~
52 25.50 74.7079 26.6461 0.0849 78.7934 26.6543 0.1061 22.18a6 26.6435 0.0400 k 53 26.C0 74.6547 26.6437 0.C2e3 78.7660 26.6 f 41 0.1873 22.1J07 ;4.4 4!: 0.!4;9 E4 26.50 74.67e9 26.6431 0.C804 74.7394 26.f530 6.1874 22.1162 26.6475 0.0432
![1 O.
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" TABLE 8.3 2
# SunHARY OF AVER ACE S .-
I* RUH 0 ELAPSED AVG ltHP AVG PRESS AVG V PRESS AVG IEHP AVG PRESS AVG V PRESS LOld[ H ICE AVG ltHP ICE AVG l'RL55 ICE AVG V fHESS UPPER UPPER UPPER LDLIER L OllLR T1HE 6"s t < = . 0.0676 78.7068 26.6520 0.1871 22.1000 26.6464 0.0470 55 27.00 74.6119 26.6419 26.6460 0.0437 {. 26.6414 0.0350 76.6923 26.6515 0.1870 22.0341 56 27.50 74.6069 22.1403 26.6445 0.0397 g 74.535S 26.6399 0.0e63 78.6604 26.6503 0.1863 57 28.00 0.1858 22.2620 26.6426 0.0407 58 20.50 7's.5466 26.6300 0.0348 78.6501 26.6404 78.6117 26.6463 0.3661 22.2139 26.6406 0.0402 59 29.00 74.5221 26.6360 0.0643 ' 0.0843 78.5837 26.6449 0.lc54 22.2056 26.6393 0.0418 60 29.50 74.4790 26.6346 26.6320 0.0441 f j 26.6333 0.0866 78.5577 26.6436 0.1852 22.2603 61 30.00 74.4634 22.3477 26.6337 0.0423 74.4345 26.6309 0.0655 76.5369 26.e413 0.1850 62 30.50 0.1649 22.1169 26.6337 0.0394 63 31.00 74.42t7 26.6297 0.0649 78.5235 26.6402 74.4040 26.63c5 0.1049 22.1650 26.6330 0.0403 64 31.50 74.3795 26.6267 0.0848 l 8 L li ' h' C) FJ t I I. f i -
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+
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> P d c4NP6mMmOONdMOA da 4 mJ24w G. e. m. G. O. O. O. m. m. m. M. m. M. m. M. m wa M M M n N N N eard n a m m m O O O 4
- EL 0000 0 00S0000000 m N 2 mw d. e. e d. 4 4 d e. d d. e d d. e. d d e W b' * * * *
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t w & E & M >4 OOOOOOOOOOOOOOOOO Q > 3 M = G M = E > e M 4 8 4 wp W d PM M { 3 e 4= de-ecNmMOMf40eN 4 W e 44cewdOwNONOMMehm w gw mdemdemPNPPEN #P W W 2fNF Nm4MO9hdMONde a a eeM OOMuemaudes~ Qm wa NNN~~~m*~OOOOOpee w Og N e # M e d a m 44 W M f f N N w d w O Mu A& dedede@.
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= 4 w 5O0000000000000 CD NNNNNNNNNNNNNNNNN g3 4 e e e e e e e e e e e e e e a I gm ,
t wJ W Q 4 L d U e d d S MO%dM4dOCMMM@MMMM g 4 Ek eme=CtJueemMfemMMO m = ww eMPe-Mo*4mMNOmMOO
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- O O O ase THIS IS A CHECK OF lilE IllPUT DATA Wa#
?
I _TAllI.E 8. 3 5 RTD HILLI-VOLT TO FAHREtSt(171"0INERSIOtt C0tFFICIEllT3 ICE 2.00 UPPER 0.0 2.00 LOWER 0.0 2.00 0.0 ( HTGROMETER HILLI-VOLT TO FAHREtelE*T CONERSION CotFFICIENTS UPPER LOWER-1 0.00227 3.87667 -99.49390 0.00234 3.86472 -99.14546 LOWER-2 ICE 0.00277 3.83471 -98.67056 0.00192 3.90155 -99.95728
!O (
#1At10t1ETER PRESSURE CORRECTIDH COEFFICIEt4TS PU-1 O '''''"""*'''''''''''''5"''55" (
PU-2 27.9573 27.4035 27.4530 26.9999 26.9581 26.4208 26.4596 25.9277 25.9603 25.4122 PL-1
, a 27.9573 27.8136 27.4580 27.3102 26.9581 26.8110 26.45 % 26.3128 25.9603 25.8090 F8 70 PL-2 (
T 27.9573 28.0288 27.4580 27.3317 26.9531 27.0359 26.45 % 26.5400 25.9603 26.0427 PI-1 27.9573 27.9575 27.4580 27.4604 26.9581 26.9630 26.45 % 26.4614 25.9603 25.9613 ( i PI-2 i 27.9573 27.2318 27.4580 26.73*4 26.9581 26.2529 26.4596 25.7604 25.9603 25.2719 P-ATit 16.4746 16.1106 14.9769 14.6549 13.4792 13.1928 11.9815 11.7310 10.4838 10.2661 RIO leEIGHTING FACTORS
"""'" (
O .0628 .1161 .0831 .0831 .0960 .0960 .0 % 0 .r960 .0296 .0296
.02 % .0296 .0740 .0105 .0167 .0513 g
LOWER
*g .0415 .0415 .0415 .0415 .0102 .4284 .0584 .0086 .0264 .0586 .1937
.1937 .1937 .1037 .0500 .0092 .0244 .0145 .0170 .0:49 .0219 .0240 .0423 .0
- e ICE
.g .0750 .0750 .0725 .0725 .2213 .2766 .2071 VOLUt1E WEIGHTING FACTORS UFPER LOMER ICE f 2.0144 1.0000 0.4818 '
0
1 l l *~ 9.0 LCCAL LEAK TEST PROGRAM A local leak test program was conducted in accordance with guide-lines specified in 10CFR 50 Appendix'J', FSAR, and Technical l Specifications, under AEPSC written and I&M approved procedures, L 2 PO-033-330 "contain=ent Penetration and Personnel Lock (Type 'B') Leak Test" and 2 Po-033-332 " containment Isolation valve (Type 'C') . 1 e
\
Leak Test". These tests were conducted as a prerequisite to the l Integrated Leak Rate Test to systematically verify acceptable leakage across each containment penetration and pressure centaining boundary. The progra= consisted of Type '3' tests designed to determine leakage through the containment penetrations, air lock door seals,
, lock cover flange seal, ring body flange seal and overall air lock \
t leakage, as well as Type 'C' tests designed to' determine leakage across isolation valves. l
,, The leakage detection instrumentation used in the conduct of the i Type '3' and 'C' tests were calibrated prior to the tests and are certified traceable to NES. These instruments (Volumetries Leak Rate Monitor) are self contained mass flow leak test systems capable
{ of measuring small gaseous leak rates. The monitor pressurized the 4 test volume to a predetermined setpoint (12.0 PSIG). After test m pressure is attained precise pressure regulators, internal to the instrument, maintain the pressure setpoint by adding air through a l thermal flow sensor. Since the test volume pressure remains i constant during the test the amount of air leakage is equal to the i amount of air added. This leak rate is electronically converted and { displayed on a digital rate meter.
, -104-k.
_ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ A_ _ _ _ _ . _ _ _
90 LOCAL LEAK TES? FROGRAM (Cont'di The following Type 'B' and 'C' penetrations were tested in the nanner described above with the neasured leakage rates as listed below: Measured Acceptance Leakare Criteria p 9.1 Fersonnel Air Lock (612) 9 1.1 No sinulated pressure force. Inner Seal 0.0 La $ O.5 L a Outer Seal , 0.0 L a j O.5 L a J 9.1.2 With si=ulated f pressure force. ( Inner Seal O.O La - 0.0005 L a
~
Outer Seal O.0 L a 0.0005 L a 913 overall leak rate o.oL,jfic.05L, 92 Personnel Air Lock (650) [ 9 2.1- No simulated pressure force. ( I Inner Seal O.0 L a l$[0 5 L, f Outer Seal 0.0 L a l$ic.5 L, 1 s 9 2.2 With sinulated pressure
)t. force.
Inner Seal 0.0 L a 0.0005 L a ( Outer Seal O.0 L a l$O.0005L a 923 overall Leak Rate o.o L, :5LO.oSL, 9 2.4 Cover Flange 1.0 SCCM N/A 9 2.5 Ring Body Flange 0.0 SCCM N/A
-105-
9.0 LOCAL LEAK TEST FROGRAM (Cert'd' l Measured Acceptance Leakare Criteria 93 Contain=ent penetrations O.0 L a d50157La f 9.4 Contain=ent Isolation
- [ Valves (Iotal Leakage) 0.178L,dEO.L43L a 1i Initial Type '3' testing of the contain=ent penetration pressuriza-tion syste=, Ite
- 9 3 above, resulted in a leakage rate of 5,330 SCCM (0.048 La ) which is well within the allotted allowable leakage rate. The origin of this leak was traced to containment penetrations
, CPN-6 and CpH-51. Exa=ination of these penetrations revealed the ( expansion bellows, located outside the containment, were cracked in p. each case. Upon repair, both contain=ent penetrations were re-( tested by the local Type '3' test method and found to have zero l leakage. It should be noted that, while repair and re-test of the i i i, damaged expansion bellows was performed after perfor ance of the
; contain=ent ILRT, no action was taken to isolate the affected pene- ' b trations from the containment ILRT test pressure. Moreover, it is i a prerequisite of the ILRT procedure to vent to containment atmo-L sphere all interval zones of the containment veld channel system.
r - 1 , Table 9.4.1 is provided for an individual accounting of the i containment isolation valve leak rates reported as total leakage in , t Item 9.4 above. In this table each valve is identified by tag
,f number, valve diameter, allowable leakage and actual leakage as measured during the pre-operation leak test. The individual i i s
allowable leakag'e values were determined by allocating a portion of
/
p
- 106-m a
m . , = A-. ,. .,
-+e4 y.- , y - - i--.-- -t--r, ,,9 t- .gy--9
90 LOC AL IEAK TEST 2900? At' f r o - t ' d '> [ the total allowable leakage based on valve size (diameter). The allowable leakage values were determined as a guideline to enable the test engineer to decide which valves should be repaired, if r necessary, to =eet the total allowable leakage value of 48,827
' SCCM (0.LL3 La )*
( i Referring to Table 9.4.1 it can be seen that for sc=e instances the
- " actual leakage" measured has exceeded its asscelated guideline t
" allowable leakage" li=it. The 1ccal leak rate test, however, was I considered acceptable because as per 10CFR 50, Appendix 'J', the cerbired leakage for all Type '3' and 'C' tests cust be less than the allowable limit of 0.6 L a. A review of the test results ,
indicates that the total actual leakage measured for both Type '3'
\
l and 'C' leak rate tests was equal to 0.178 L a r nly 29 7 per cent r of the allowable limit.
- In addition to the valves and penetrations subjected to the Type r
'3' and 'C' local leak rate tests as required in 10CFR 50; Appendix i 'J', the spray header check valves associated with the Containment u.
Spray System were leak tested in accordance with FSAR Question 022.15 (4). As specified by the NRC, the acceptance criteria for each chec'k valve is such that the water inventory normally resident i in the associated spray header shall not leak out within a thirty
-(30) day period. In response to this requirement, the volume of
, } water resident in the spray headers was calculated from isometric j drawings and the leak tests performed with the following results: . s
?
l -107-
90 LOC AL LFAK TEST PROGR AM (cer.:'d 3 r Measured Leakage Allowable Leakage C. neck Valve cM3/Mn:. cM3/ x n, CTS 127U 16.00 21.88 CTS 127E 5.co ?3 38 ( CTS 131'<' l.37 3.co , CTS 1313 1.53 3 73 1 t \ ( f i ' ( l i { l - ( ( ( ( ( l. i l (~ 108- ' L
0.0 LOC AL LE;E TEST PROGR A5' TAPLE G.L.1 i VALVE ALLOWABLE ACTUAL DIAMETF3 LEA'GGE LELU GE VALVE I . D. (INCHEST (SCCM) (SCCMS l7 CPN-1 (Blind Fige.) 20.0 1240 100
' CS 442-1 2.0 124 540 f CS 442-2 2.0 124 204 CS 442-3 2.0 124 145 CS 442 L 2.0 124 157
. SI-189 4.0 248 657 WCR-901 6.0 372 0
[ NSW 415-1 6.0 372 500 i WCR-902; WCR-903 6.0 744 1 [ WCR-905 I 6.0 372 74 NSW-415-2 6.0 372 1581 WCR-906; WCR-907 6.0 744 49 WCR-909 6.0 372 3 h. NSW 415-3 6.0 372 516 ( WCR-910; WCR-911 6.0 744 8 t WCR-913 6.0 372 100 NSW 415-4 6.0 372 - 45 WCR-914; WCR-915 6.0 744 13 WCR-921 30 372 77 NSW 419-1 30 372 2 1 WCR-922; WCR-923 30 744 78 l ? { WCR-945; WCR-951 30 744 114 L l I i l l I
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g . - , ,, - -
I l i 0.0 ECC AL EEAK TEST PROGR AM i TAELE o.4.1 l VALVE ALLCUABLE ACTUAL
- DIAMETER LEAKAGE LEAKAGE VALVE I.D. ( NCHES) (SCCMT (SCCMT WCR-955; NSW 24L-1 3.o 744 612
[' t WCR-925 30 372 3 NSW 419-2 30 372 2 , i
, WCR-926; WCR-927 30 7L4 153 WCR-946; WCR-932 30 7k4 60 WCR-936; NSW 244-2 30 744 308
[~ XCR-102; XCR-103 0.75 93 265 PA 243 2.0 248 106 f NPX 151-V1 0.5 31 7
! DCR-203; DCR-207 0.75; 1.0 93 10 e DCR-201; N 160 0.75; 1.0 124 231 DCR-610; DCR-611 25 310 10
{ DCR-620; DCR-621 1.0 124 6 i SM-1 1.0 62 742 GCR-314 1.0 62 12
'IlO2 1.0 62 159 I. ECR-31; ECR-32 1.O' 124 183 SI 171; SI 172; SI 194 0 75 139 5 1
{ NCR-252 30 186 21
! PW 275 3.o 186 9 CS 321 3.o 186 34
/
[ QCR-300 2.0 124 5 l . 1
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___-____---.'~'_'"** * '"-*T #
* ~
1 0.0 LOC AL I T AE TES* FROGR AM TABLE C.L.1 r VALVE ALLOWABLE ACTUAL DI.sMETER LEAKAGE LEnKAGE
.. VALVE I.D. (INCHEST (SCCM) ( SCCM '.
i s DW 211; Ud 212 2.0 248 4 i SF 152; SF 154 1.5 186 L7 QCM-250; QCM-350 l L.0 l L96 l 56 7 CCM-458; CCM-L5'" ; 8.0; 4.0
, CCM-452 8.0 12LO 3CL i CCM-459; CCM-453 8.0; 4.0 CCM-451 8.0 1240 56 r
' DCR-205; DCR-206 4.0 496 18 DCR-600; DCR-601 30 372 100 i
I SF 159; SF 160 30 372 19 r TCM-265 4.0 248 165 i ICM-305 18.0 168 75 ICM-306 18.0 168 85 VCR-10; VCR-ll 30 372 145 h VCR-20; VCR-21 30 372 58
, CPN-57 (Blind Fige.) 4.0 496 100
' VCR-105; VCR-205 30.0 3720 0 VCR-106; VCR-206 24.0 2976 0 lt -
VCR-101; VCR-201 14.0 1736 2 VCR-102; VCR-202 14.0 1736 100 ! l VCR-104; VCR-204 30.0 3720 100 if t. JCR-103; VCR-203 24.0 2976 0 [ VCR-107; VCR-207 12.0 1488 0 L (~ l
-111-
- - - ~ . . -
, ,,-_g-. _,__-- .,,
~
- I~
f 1 c.o tocAt tr s Trs? =ac.caAta r T" ELE 4 '*1 l VALVI ' ALLCW4BLE ACThL r- DIAMETER LEAKAGE LEAKAGE ( VAtVT T.D. (IficurS T ( SCCM'- (SCCMT NCR-109; NCR-110 0.5 62 1 1 NCR-107; NCR-108 05 62 l 2 NCR-105; NCR-lC6 0.5 62 2 WCR-961; WCR-963 2.0 248 274 i i t WCR-965; WCR-967 2.0 248 6 NSW-417-4; WCR-962 2.0 248 900 NSW-417-3; '.lCR-966 2.0 248 586
- f. XCR-100; SCR-101 O.75 93 4 N-159 0 75 46 5 l 8 L GCR-301 0.75 46 5 30 t CCR-460; CCR-462 30 372 105 CPN-76 (Blind Flge.) 8.0 992 129 5 CPN-80 (Blind F1ge.) 6.0 744 100 L
RCR-LOO; RCR-lOl O.375 46 5 7 DCR-202; DCR-204 0 75 93 30 ICR-3; ICR-6 05 62 1 { L CCR-457; CCW-135 2.0 - 248 94 CCR-455; CCR-456 2.0 248 37 CA-181n 0.5 31 El CA-181s o.5 31 64 WCR-948; WCR-954 30 372 1500 j fu WCR-958; NSW-244-4 30 372 298 [ -112-c. t . . . - . .
G.0 LOCAL leg? TEST PROGRAM r T.BLE o.L.l_ VALVE ALLOUaELE ACTUAL DIAMETER LEAKAG" ' EAKAGE VALVE I.D. (INCHEST (SCCM' ( SC C"'.
, WCR-933 30 186 33 NS4-419-4 30 186 1 , ICM-260 4.0 , 2L8 45 L
WCR-93'; WCR-935 30 372 11C0
, WCR-929 30 186 1 NSW-419-3 30 186 84 I
I WOR-930; WCR-931 30 372 114 WCR-947; WCR-953 30 372 2100 {.- WCR-957; NSW-2 "-3 30 372 157 l SM-8; SM-lO O.5 62 2 l PPF-302 05 31 3 r
, PPP-301 c.5 31 l 3 7
SM-4; SM-6 05 62 2 b ECR-ll; ECR-21 05 62 3 ECR-12; ECR-22 0.5 62 3 ECR-13; ECR-23 0.5 62 o ECR-15; ECR-25 05. 62 ( 6 ECR-14; ECR-24 05 62 2 ECR-16; ECR-26 05 62 2 t i ECR-17; ECR-27 0.5 62 1 I ECR-18; ECR-28 0.5 62 47 4 (. ECR-19; ECR-29 0.5 62 3 l [ l ( L
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? !
.-J
r s a e 0.0 ECC.-l EE AK TEST PROGR.O' 'r I _..m.- ct
.L.1 vasvs s 7 LC1
.4 .
ensL-. - c.u t.b. a
.L l
vinnaiss LsaanG-s usn .nus
't VALVE I.D. (INCHES) (SCCM' ( SCC
f 0.5 62
; ECR-lo; Ica-20 7 ._
???-300 05 31 5
! PPF-303 0.5 31 23
,r ??A-310; ??a-311 0.5 62 7 r
FFA-312; ??A-313 0.5 62 29 f ICM-250 4.0 248 63 ICM-251 L.0 246 264 i CPU-67 (Blind Flge.) -2.0 124 ! 1 100 ICR-33 0 75 46 5 1600 7 3 s
?
e 0 6 t [ - i t l
- 114-i
-*-"*"O'&g4-M wNMN '"
%#. -r-- g_ , , ,,
p.- 10.0 REFERE: ICES i 10.1 D. C. Cook I;uclear :-lant Final Safety Analysis Report i 1C.1.1 Initial Leakage 3 ate Testing of Containment. r ( Section 5.2.1 10.1.2 Initial Containment (Fre-Operational) Leakage Rate Test. Section 5 7 2 4 10.1 3 Contain=ent Leakage Test Progra=. 1 I l FSaR Questien 5 93 10.1.4 Containment Integrated Leak Rate (Type 'A') F, Test Program and Surveillance Requirements. r FSAR Appendix 'Q' Question 022.6 { ! 10.1 5 Local Leak Rate (Type 'B' and 'C') Tese [ t Frogram and Surveillance Requirements. FSAR Appendix 'Q' Question 022.7 f~ ( 10.1.6 Containment Integrated Leak Rate (Type'A')
, Testing.
L FSAR Appendix 'Q' Question 022.14 10.1 7 Local Leak Rate (Type 'B' and 'C') Testing. FSAR Appendix 'Q' Question 022.15 10.2 D. C. Cook Nuclear Plant - Unit No. 2 Technical Specifications. 10.2.1 Containment Systems - Containment Leakage g Specification: 3.6.1.2 l Surveillance: Requirement 4.6.1.2 i L -115-
- q. _ _ . . . - -
_ j
T e I
/
/
10.0 REFE?,ENCES (Cert'c' U 10.2.2 Containment Syste=s - Centain=ent .41r Locks.
, Specification: 3 6.1 3 Surveillance Require =ent: 4.6.1 3 ) 10 3 American National Standard - ANSI, NL5.4-1972 Leakage-r Rate Testing of Centainment Structures for Nuclear I
Reac crs.
! 10.4 10CyR 50, Appendix 'J' I
. Frimary Reactor Containment Leakage Testing for i ater-Cooled Power Reactors.
,r .
t 10 5 Basic Statistical Methods for Engineers and Scientists - A. M. Neville J. 3. Kennedy 10.6 Hygrc=etric and Psychrometric Tables Smithsonian Institution f
- . 10 7 D. C. Ccok Nuclear Flant - Unit No. 2
, Fre-Operational Test Frecedures.
10 7 1 Containment Fenetration and Personnel Lock (Type 'B') Leak Test. l-2 Fo-033-330 ( I. . 10 7 2 Containment Isolation Valve (Type 'C') Leak Test. l 2 FO-033-332 g 10 7 3 Containment Integrated (Type 'A') 1 ' Leak Rate Test. f-2 FO-033-334 t . I L i i
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