ML20062G031
| ML20062G031 | |
| Person / Time | |
|---|---|
| Site: | Hatch |
| Issue date: | 06/30/1978 |
| From: | Manry M GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20062G030 | List: |
| References | |
| NUDOCS 7812260156 | |
| Download: ML20062G031 (70) | |
Text
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-;: 5r,.ca Georgia Power Edwin L Haten Nuciesr Ptant November 7, 1978 PM-78-411 PLMr E. I. HAIG Peactor Containment Building IIRE (thit 1)
Director: U.S. Nuclear Reactor Regulations c/o Distribution Services Branch.DDC, AIM U.S. Nuclear Pegulatory Conmission Washington, D.C.
20555
Dear Gentlemen:
Please find the enclosed report describing the 1978 Type A test successfully performed April 11, 1978 on the E. I. Hatch Unit 1 Primary Containment.
Mr. Floyd Cantrell (NRC I & E Principle Inspector) was notified on August 16, 1978 concerning the late submi.ttal of the report.
Plant Manager WRG/bvw xc:
H. C. Nix Floyd Cantrell (w/ enclosure - 3 copies)
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Georgia Power Company Edwin I.
Hatch Nuclear Plant Unit No. 1 Docket 1; umber 50-321 4
4 I
REACTOR CONTAINMENT BUILDING I
INTEGRATED LEAKAGE RATE TEST i
vU'IE 30, 1978
)
1 Submitted to The Uni ed States Nuclear Regulatory Commission Pursuant to Facility Operating License No. DPR-57 i
l Preparation Directed by:
(
M. Manry, Plant Manager i
Edwin I. Hatch Nuclear Plant 9
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,-,-,..,--_wys 7,.
TABLE OF CONTENTS s
I I.
INTRODUCTION 6
II.
TEST SYNOPSIS III. DISCUSSION r
IV.
TEST DATA
SUMMARY
A.
Plant Information B.
Technical Data C.
Test Results - Type A Test D.
Integrated Leakage Rate Measurement System E.
Permanent Plant Instrumentation Used during Test F.
Information Retained at Plant G.
Test Results - Type B&C Tests APPENDIX A - REPORT PRINTOUTS OF INTERIM TYPE A AND VERIFICATION TEST DATA ANALYSIS Table A-1: Summary data and Icakage rate calcula-tions during drybulb temperature measure-ment system malfunction period.
Table A-2: Summary data and leakage rate calcula-tions following correction of drybulb temperature measurement system malfunction.
i APPENDIX B - RESULTS
SUMMARY
OF TYPE BSC TESTS PERFORMED SINCE
[
LAST TYPE A TEST i
APPENDIX C - FAILED TEST REPORT - TYPE A TEST t
i L
r i
I.
pjTRODUCTION The reactor containment building Integrated Leakage Rate, Type A, Test, is performed to demonstrate that leakage through the primary reactor containment and systems and components penetrating primary containment does not exceed the allowable leakage rate specified in the Plant Technical Specifications.
The successful periodic Type A and supplemental verification tests were performed according to the requirements of the E.
I.
Hatch Nuclear Plant, Unit 1 Technical Specifications and 10CFR50, Appendix J.
The Plant Hatch Type A test method is the absolute method des-cribed in ANSI N45.4-1972, " Leakage Rate Testing of Containment Structures for Nuclear Reactors" and ANS N274, " Containment System.
Leakage Testing Requirements", Draft No.
2, Rev. 1 - April 5, 1978.
Leakage rate was calculated using formulas from ANSI N45.4-1972 and BN-TOP-1, Rev. 1. " Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants" (Total. Time) and ANS N274 (Mass-Point) modified for varying contain-ment free air volume during the Type A and verification tests.
The free air volume in calculations was varied to account for changes in reactor vessel water level, and thus changes in free air volume, caused by reactor vessel water temperature changes.
Type A and veri-fication test durations were according to the criteria of BN-TOP-1.
1 The test results are reported in accordance with the requirements of 10CFR50, Appendix J, Section V.B.3 i
II.
TEST SYNOPSIS Containment pressurization was stopped at a containment pressure of 59.5 psig at 1930, 4/6/78.
Thirty minutes later containment pres-sure dropped below 59 psig and was increased to 59.5 psig.
By 2030 the pressure had dropped below 59 psig and was again increased to 59.5 psig.
The pressure again decreased at the same high rate.
An external survey of potential leak paths was initiated due to the repeated high pressure-decrease rate.
Leak survey personnel dis-covered gross leakage through the drywell head flange, but no other significant leakage.
As the drywell head leakage could not be stopped safely with the containment pressurized, the containment was depres-surized to O psig and the head bolts were detensioned.
The drywell head bolts were then retensioned per HNP-1-6705, flange gap measure-monts were taken, and successful local leakage rate test on the dry-well head gasket was performed.
The containment was repressurized and reached test pressure at 1600 on 4/8/78.
During the required stabilization period, two of the four drywell cooler f ans modified to operate during the ILRT tripped and were not restarted.
One half hour into the Type A test, a third drywell cooler fan tripped and was not restarted.
At 0745 on 4/9/78, the Type A test was terminated with a calculated leakage rate at the 4
95% confidence level of 0.217+0.054%
per day, well below the allow-able.
The verification flow Was then started at an initial. flow rate of 0.900% per day.
The verification test commenced at 1100 on 1
.~
1 4/9/78 after completion of reactor vessel fill and cooldown operations.
(Note: During Type A and verification test data acquisition, the RHR system shutdown cooling flow was aligned to bypass the RHR heat ex-changer thus allowing a slow, relatively constant reactor vessel water heat-up.)
After five hours of test, the verification test leakage rate, 0.488%
per day, was not within the allowable limits and was also less than the average induced flow rate of 0.896% per day.
The Type A and verification test data and calculations were then rechecked, with no errors found in data entry or calculations.
(See Appendix A for Type A and verification test reports. )
Proper operation of the veri-I fication flow measurement system was verified during the data and calculation review.
A calibration check, in accordance with vendor procedure, of the twelve drybulb temperature measurement channels of the data acquisition system was then performed.
During this check, temperature channels 7 and 8 were both displaying 115 F with the system preamplifier at normal gain setting.
At half-normal gain setting the two ghannels displayed 74 and 75 representing temperatures of 148 F and 150 F respectively.
All other channels displayed the expected half-normal gain setting values.
It was therefore con-cluded, after consultation with the system vendor, that the outputs of these two temperature sensor (RTD) linear bridge networks were caturating the output of the system preamplifier at normal gain set-ting and had been doing so during most of the Type A test and all of the verification test.
Test personnel concluded that the high con-tainment temperatures at the sensor locations were due to insufficient cooling air flow caused by inoperation of three of the drywell cooler fans, and the Type A test should not continue without operating addi-tional fans.
Larger overcurrent devices were installed in the four drywell cooler fan breakers, and the four f ans were restarted.
Simul-taneous two mode (full and half-gain) temperature data acquisition continued for seven hours after fan restart.
From that time through Type A and verification test completion, two mode temperature data acquisition was used only wgen the full-gain temperature read-ing for any channel exceeded 112 F.
Following completion of reactor vessel fill and cooldown operations, the Type A test was restarted at 0530 on 4/10/78.
After eleven hours of test, the measured Type A leakage rate was steady at 1.4% per day.
As this value was 0.5% per day greater than the test allowable leakage rate, a second external survey of poten-tial leak paths was initiated.
During this survey, leakage was detected through the external containment vent path (required to subject the containment isolation valves to test differential pres-sure) for penetration No. 46, Demineralized Water.
A flowmeter type local leakage rate test on this vent yielded a leakage rate, with a 3/8" flowmeter bypass open, of at least 0.34% per day.
The vent isolation valve was shut stopping the leak.
No other leak paths were discovered.
l 2
The Type A test was restarted following reactor vessel fill and cooldown operations.
At 0715 on 4/LY78, the Type A test was term-inated with a calculated leakage rate at the 95% confidence level of 0.420+0.138% per day (Total-Time Method) and 0.427+0.029% per day (Mass-Point Method.)
Following reactor vessel fill and cool-down operations and a final calibration check of the drybulb temp-erature measurement system, a verification test flow rate of 0.917%
per day was established.
Three hours and twenty minutes into the verification test, a drywell cooler fan tripped and could not be restarted.
The verification test calculated leakage rate just prior to f an trip was 1.567% per day (Tctal-Time) and 1.509%/ day (Mass-Point), both within allowable limits.
After a forty-five minute stabilization period, the verification test was restarted with the same verification flow rate continuing through the stabilization period.
The verification test was successfully completed at 1830 on 4/11/78.
Following the verification test, the containment was de-pressurized through the standby gas treatment system.
III. DISCUSSION A.
Variable Volume Leakage Rate Calculations The residual heat removal (RHR) system could not be operated, in shutdown cooling mode, to maintain constant reactor coolant temperature.
The tests were therefore performed with RHR system flow bypassing the RHR heat exchanger allowing a slow steady reactor coolant tempera-ture increase during the data acquisition periods.
The containment free air volumg used in legkage rate calcula-tions was decreased 5.5 ft for each 1 F reactor coolant temperature rise.
Required reactor vessel fill and cool-down operations were performed prior to Type A and veri-fication test data accumulation.
The only mass transfer across the containntnt boundary including the closed RHR system extension of containment was therefore due to water or air leakage.
Both water and air leakage is accounted for in the integrated leakage rate calculations.
B.
Temperature Measurement System In Section II the malfunction of temperature measurement channels 7 and 8 during the initial Type A and verifica-tion test data acquisition periods was described with the corrective action taken to prevent a later similar occur-rence.
This malfunction resulted in the understatement of:
- 1) the containment average temperature at any given time, and 2) the rate of change of containment average temperature over the Type A and verification test data intervalc.
Both phenomena, but particularly the latter, resulted in a calculated leakage rate value that is less than the actual leakage rate.
The supplemental verification test, which is performed folicwing a Type A test to detect such a 3
system malfunction, yielded leakage rate results lower than the known imposed leakage rate.
The unacceptable verification test results thus led to detection of the temperature measurement system malfunction.
C.
Corrections to Type A Test Results Immediately following containment depressurization to atmocphere, the internal demineralized water system piping at Penetration No. 46 was inspected to determine the cause of excessive leakage during the failed Type A test.
A i
normally closed drain valve, not shown on the system P&ID, was found open.
The valve would have been closed during the test but as it was not shown on the system P&ID it was not included on the ILRT system valve lineup.
The external system was vented inboard of the outboard contain-ment isolation valve to preclude draining the demineralized water system outside containment.
This conservative line-up provided only one isolation barrier, the inboard iso-lation valve.
The open drain valve is installed inside containment between the inboard locked closed containment isolation valve and the containment penetration, thus establishing the leak path which had to be blocked to allow successful Type A test completion.
The drain valve was closed and a Type C test was performed on the penetration containment isolation valves.
The Type C leakage rate of 0.016% per day is added to the Type A test results.
Refer to Section IV.C.ll. for a tabulation of corrected Type A tact results.
No corrections to Type A or verification test calculations are required as a result of the post-test calibration verification, traceable to the National Bureau cf Standards, performed on the twelve resistance temperature detectors by the vendor.
4 s
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IV.
TEST DATA
SUMMARY
A.
Plant Information Owner Georgia Power Company Plant Edwin I.
Hatch Nuclear Plant, Unit 1 Location Baxley, Ga.
+
Containment Type Mark I, BWR 1
Date Test Completed April 11, 1978 B.
Technical Data
- 1. Containment Net Free Air Volume 257,360 cu. ft.
l
- 2. Design Pressure 56 psig
- 3. Design Temperature 281 F
- 4. Calculated Peak Accident Pressure, Pa 59 psig
- 5. Containment ILRT Average Temperature 50-135 F Limits
C.
Test Results - Type A Test
- 1. Test Method Absolute
- 2. Data Analysis Techniques Mass Point (per ANS N274) and Leakage Rate (Total-Time per BN-TOP-1)
- 3. Test Pressure 59 psig
- 4. Maximum Allowable Leak 5ge Rate, La 1.2%/ day
- 5. 75% of La 0.9%/ day 6.
Integrated Leakage Rate Leakage Rate, %/ day Test Results From Regres-At Upper sion Line 95% Confi-(Lam) dence Limit
- n. Mass point analysis 0.427 0.456
- b. Total-Time analysis 0.420 0.558 t
Leakage Rate, Li, %/ day 0.917
- 7. Verification Test Imposed i
5
)
- 8. Verification Test Results Leakace Rate,%/ day l
- a. Mass Point Analysis 1.410
- b. Total-Time Analysis 1.327
- 9. Verification Test Limits Test Limits, %/ day
- a. Mass Point Analysis
- 1) Upper Limit (Li+ Lam +0.25La) 1.644
- 2) Lower Limit (Li+ Lam-0.25La) 1.044
- b. Total-Time Analysis
- 1) Upper Limit (Li+ Lam +0.25La) 1.637
- 2) Lower Limit (Li+ Lam-0.25La) 1.037
- 10. Report Printouts The Report Printouts of the Type A and verification test calculations are provided for the Mass Point and Total-Time Analyses.
(Tables 2 thru 9)
- 11. Addition to Type A Test Leakage Rate Results based on Post-ILRT Type C Test on Demineralized Water, Pene-tration No. 46, Containment Isolation Valves.
- a. Post-ILRT Type C leakage rate to 0.016%/ day be added:
- b. Type A tect leakage rate at the upper 95% confidence limit (from 6.a.,b. )
- 1) Mass Point Analysis 0.456%/ day
- 2) Total-Time Analysis 0.558%/ day
- c. Corrected integrated leakage rate at the upper 950 confidence limit.
- 1) Mass Point Analysis 0.472%/ day
- 2) Total-Time Analysis 0.574%/ day 6
D.
Integrated Leakage Rate Measurement System i
- 1. Absclute Pressure (1 channel)
Precision Pressure Gago - Texas Instruments Model 145-02 with BCD mechanical shaft encoder kit.
1 Range:
0-100,000 counts Accuracy:
0.010% of reading &0.002% F.S.
Resolution:
0.001% F.S.
Repeatability:
0.001% F.S. or better l
Bourdon Tube Capsule for Precision Pressure Gage, Texas Instruments Tube Number 6, Type 2 Range:
0.000-100.000 psia Calibration Date:
12/3/77
- 2. Drybulb Temperature (12 channels)
Resistance Temperature Detectors - Leeds and Northrup Thermohm Model 8193-3, 3-lead, 10-ohm copper.
Thermohms conform to the resistance-versus-temperature curves e
published in Leads and Northrup Company Standard Con-version Tables for L&N Thermohm Resistance Thermometers, 77-21-0-4, Issue 4.
(L&N Thermonm Tacles 177586, Issue 1).
Range:
32-g50F Limit of error:
0.5 F Static resistance:
10 ohms @ 77 F Calibration Date:
5/4/78 Measurement System: CTE Model 35-12-10 12-channel system consisting of a 20-volt precision power supply, 12 individual RTD wheatstone bridge completion /lineari-zation/ signal conditioning networks designed for the above described RTD's.
Accuracy:
+0.1 F Repeatability:.
0.1 F Resolution:
0.01 F Output:
0.l m'! / F Calibration Date:
3/22/78 l
- 3. Dewpoint Temperature (6 channels)
Dewpoint Temperature Systems - Consolidated Test and Equipment Model 6MA-2-AH continuous tracking dewpoint analy:er with 6 VAP-AIR Model PN 26330791 dewpoint l
temperature probes.
7
=. _ -.
1 4
i Accuracy:
+1 g?
Repeatability:
0.5c Resolution:
0.1 F l
Output:
0.1 F j
Calibration Date: 12/12/77 & 4/4/78 I
- 4. Verification Flow (1 channel)
{
Flowmeter-Brooks Instrument Thermal Mass Flowmeter, Model i
5812, with Model 5821 power supply and CTE Fig. 7-26 signal conditioning circuit.
l Range:
0-10 sofm Accuracy:
1,0.1 scfm Repeatability:
0.01 scfm Output:
1 mv/sefm Calibration date:
1/4/78
- 5. Gauge Pressure (1 channel) - Not used directly in calculations.
i Transducer - Bell and Howell Model 4-326-0031 Range:
0-75 psig Accuracy:
1,0.2 psi output:
0.13 mv/ psi i
l Calibration Date: 3/29/78
- 6. Data Acquisition, Display and Printout (31 channels) i 1
Data Acquisition System - Consolidated Test and Equip-ment Model 35, consisting of a multiplexer, coupler power distribution and power supply module and the
]
following signal conditioning and display devices:
1 ea. Preston Scientific Model 8300 XWB-B differential preamplifier -
Gain Settine Parameter Rance 500 Drybulb temp.
0-230 F g
Dewpoint temp.
0-140 F 1000 Drybulb temp.
0-ll5 F g
Dewpoint temp.
0-115 F 1 ea. Hewlett Packard Model 3480A digital voltmeter with 3482A DC range unit and parallel BCD output option.
Display -
Parameter Rance Drvbulb tercerature 0.00 to 140.00 F Deipoint te' pera ture 0.00 to 140.00 F m
U Verification flow 0.00 to 10.00 scfm Gage pressure 0.00 to 75.00 psig Volts (D.C.)
0.000 to 14.000 VDC 8
i 1 ea. Hewlett Packard Model 5055A digital recorder -
i Prints thirty-one (31) channels of information on operator demand or at preset intervals determined by the digital clock.
7.
Overall Instrumentation Selection Guideline (ISG)
Value (from ANS N274) based on IL9T instrumentation and a six and one quarter hour test duration:
- 0.037%/ day
~
8.
Drybulb and Dewpoint Temperature Sensor Locations -
See Table 1.
9.
The pressure suppression chamber (torus) atmosphere was saturated during the tests.
At saturation, the atmcsphere drybulb, dewpoint and wet-bulb temperatures all take on the same value.
Therefore, the more stable and accurate torus atmosphere drybttib temperature values (frca RTD channels ll&l2) were taken as dewpoint read-ings.
The devpoint temperature channels in the torus were monitored during the test for centinued evidence of torus atmosphere saturation.
E.
pernanent Plant Instrumentation Used During Test j
Parameter MPL No.
Calibration Date 1
Reactor water temperature
- E41-R605 3/18/78 RpV water level C32-R6063 11/26/77 Torus water level T48-R607A 4/4/78 4
Torus water temperature T4 7-R611 4/4/78 I
I
=" sed to vary containment free air volume F.
Information Retained at Plant The following information is not included in the summary but is retained at the Plant available for review:
- 1. Data and Data Reduction 1
a.
Raw data sheets showing ILRT data as recorded from the instrumentation and as entered in the computer.
- b. Computer printouts showing containment atmosphere drybulb ter.peratures, total pressure and dewpoint temperatures entered from the raw dz
9's and also the time, date, average drybu12 cemperature, parH al pressure of dry air, and containment free air volume used in leakage rate calculations.
1' 9
i
Formulas used by ccmputer for calculation of leakage c.
rate, regression analyses and confidence limits.
- d. Data to verify temperature stabilization.
- 2. Systems Status (at time of ILRT)
- a. A system line-up showing valve positions and status of piping systems (drained, vented, etc.) for all plant systems associated with ILRT.
- b. Equipment protection list identifying action taken to prevent equipment damage due to high containment atmosphere pressure.
3.
Reactor Building Penetration Index
- 4. Event Log A continuous log of ILRT events.
- 5. Instrumentation Documentation Calibration data and certificates.
- 6. Test Procedure i
The working copy of test procedure including signature sign offs.
- 7. Local Leakage Rate Tests j
The procedure and data to verify completion of pene-tration and valve testing (Type B and C tests) including 1
measured leakage rates, significant problems found, and j
applicable corrective action, and total, overall leakage rate.
i
- 8. Quality Assurance The Quality Assurance audit plan or checklist that was used to monitor the ILRT.
- 9. Local Leak Survey During ILRT Identification of any leakage (into or out of contain-ment) found during ILRT and corrective action taken.
- 10. System Restoration Checklist for restoration to normal status of non-standard system or instrumentation conditions after completion of the ILRT.
10
G.
Test Results - Type B and C Tests j
(
A cu=ary of results of Type B and C tests performed since l
thelast ILRT is included as Appendix B to this sumary j
report.
l l
l 11
l TABLE 1 Elevation Aximuth Distance From Volume Dewpoint 4 (ft)
(Dec.)
Center (Ft)
Fraction 1.
120 330 28 0.110 2.
134 165 24 0.206 3.
154 330 20 0.096 4.
195 040 13 0.156 5.*
108 240 65 0.216 6.*
108 135 65 0.216 1.000 RTD u 1.
126 330 28 0.045 2.
120 180 28 0.045 3.
130 090 28 0.020 4.
134 205 24 0.103 5.
134 345 20 0.103 6.
154 035 24 0.048 7.
154 270 20 0.048 8.
195 115 13 0.078 9.
195 295 13 0.078 10.*
108 250 65 0.144 11.*
108 025 65 0.144 12.*
108 090 65 0.144 1.000
- Located in prescure suppression chamber (tcrus)
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TABLE 2 t
8 i
OUMMARY DATA E.
I. HATCH UNIT 1 59 P01G ILPT ALMAX = 1.200 o
o TIME DATE TEMP PPESCUGE VOLUME 100 411 549.926 72.8589 256931.
115 411 549.917 72.8572 256914 130 411 549.880 72.8562 256897.
146 411 549.902 72.8565 256880.
201 411 549.871 72.8564 2S6862.
216 411 549.870 72.8614 256844 231 411 549.888 72.8645 256825.
246 411 549.905 72.8675
- 256607, 301 411 549.951 72.8747 256789.
317 411 549.991 72.8825 256777.
331 411 550.039 72.8880 256766.
346 411 550.116 72.8960 256754 400 411 550.175 72.9029 256742.
416 411 550.221 72.9090 256731.
430 411 550.302 72.9126
- 256720, 445 411 550.329 72.9241 256710.
501 411 550.444 72.9336 256699.
516 411 550.486 72.9410 256667.
531 411 550.561 72.9494 256676.
546 411 550.622 72.9593 256664.
601 411 550.698 72.9685 256652.
616 411 550.764 72.9789 256646.
630 411 550.851 72.9674 256639.
645 411 550.895 72.9984 256633.
702 411 550.936 73.0099 256627.
715 411 551.003 73.0191 256612.
0 0
- 0. 0
- 0. 0
- 0. 0 4
4 w
l TABLE 3 E.
I.
HATCH UNIT 1 59 PSIG ILRT TREND REPORT LEAKAGE PATES (WEIGHT PERCENT / DAY)
BA?ED ON TOTAL-TIME CALCULATIONS TIME AND DATE AT START OF TEST:
100 0411 ELAPSED TIME:
6.25 HOURS fiO. DATA ELAPSED MEAN MEA!URED CALCULATED CHG IN CALC L/P UPPEP 95%
PDENTS TIME LEAVAGE PATE LEAKAGE PATE FPCM LAST PDINT CONF LEVEL 10 2.29 0.477 0.386 0.627 11 2.52 0.473 0.386 0.001 0.609 12 2.77 0.471 0.395 0.009 0.609 13 3.00 0.471 0.406 0.011 0.612 14 3.27 0.470 0.412 0.006 0.610 15 3.50 0.470 0.420 0.008 0,611 16 3.75 O.468 0.420 0.001 0.602 17 4.02 0.470 0.431 0.010 0.609 18 4.27 0.470 0.436 0.005 0.608 19 4.52 0.471 0.442 0.006 0.609 20 4.77 0.470 0.444 0.002 0.605 21 5.02 0.470 9.447 0.003 0.603 22 5.27 0.469 0.445
-0.002 0.596 23 5.50 0.469 0.446 0.001 0.592 24 5.75 0.467 0.440
-0,006 0.5?2 25 6.03 0.463 0.428
-0.011 0.569 26 6.25 0.460 0.420
-0.009 0.557 THE CALCULATED LEAKAGE PATE 0.420
=
4
TABLE 4 E.
I. HATCH UtiIT 1 59 P3IG ILRT LEAVAGE PATE OJEIGHT PERCENT / DAY)
BAIED ON TCTAL TIME CALCULATICNC TIME AND DATE AT OTART OF TECT:
100 0411 ELAPIED TIME:
6.25 HOURS TIME TEMP.
PPECOURE MEASUPED (R)
(PSI A)
LEAKAGE PATE 100 549.926 72.8589 115 549.917 72.8572 0.702 130 549.880 72.8562 0.412 146 549.902 72.8565 0.588 201 549.871 72.8564 0.479 216 549.870 72.8614 0.384 231 549.888 72.8645 0.422 246 549.905 72.8675 0.443 301 549.951 72.8747 0.454 317 549.991 72.8825 0.414 331 550.039 72.8880 0.428 346 550.116 72.8960 0.456 400 550.175 72.9029 0.468 416 550.221 72.9090 0.461 430 550.302 72.9186 0.470 445 550.329 72.9241 0.447 501 550.444 72.9336 0.490 516 550.486 72.9410 0.473 531 550.561 72.9494 0.481 546 550.622 72.9593 0.467 601 550.698 72.9685 0.472 616 550.764 72.9789 0.449 630 550.851 72.9874 0,460 645 500.895 72.9984 0.421 702 550.936 73.0089 0.383 715 551.003 73.0191 0.385 MEArt CF MEAIURED LEAKAGE PATES 0.460
=
o OTD. DEVIATIuri OF NEHOUF2D LEAKAGE PATEC 0,066
=
MAXIMUM ALLDI.lAELE LEAFAGE RATE 1.200
=
75 *. OF MAXIMUM ALLC1,iABLE LERMAGE RATE 0.900
=
THE CALCULATED LEAKAGE FATE 0.420
=
THE CALC. LEAK AGE PATE AT 95*. COriFIDENCE LOiEL 0.420 0.138
=
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TABLE 5 E.
I. HATCH Uri1T 1 59 PSIG ILPT LEAKAGE PATE (WEIGHT PERCENT / DAY)
MASS POINT ANALYSIS TIME AND DATE AT STAPT OF TEST:
100 0411 ELAPSED TIME:
6.25 HOURS TIME TEMP PPESCUPE CTMT. AIR MASS LOSS TOT. AVG. MASS (P)
(PSIA)
MASS (LEM)
(LBM)
LOSS (LEM/HR) 100 549.926 72.8589 91880 115 549.917 72.8572 91874 6.7 26.9 130 549.880 72.8562 91873 1.2 15.8 146 549.902 72.8565 91863 9.4 22.5 201 549.871 72.8564 91862 1.4 18.3 216 549.870 72.8614 91862
- 0. 0 14.7 231 549.888 72.8645 91856 5.9 16.2 246 549.905 72.8675 91850 5.5 17.0 301 549.951 72.8747 91845 5.0 17.4 317 549.991 72.8825 91844 1.1 15.8 1
331 550.039 72.8880 91839 5.0 16.4 346 550.116 72.8960 91882 7.1 17.4 400 550.175 72.9029 91827 5.4 17.9 416 550.221 72.9090 91823 3.9 17.6 410 550.302 72.9186 91817 5.4 18.0 445 550.329 72.9241 91816 1.2 17.1 501 550.444 72.93?6 91805 11.2 18.8 516 550.486 72.9410 91803
- 2. 0 18.1
{
531 550.561 72.9494 91797 5.9 18.4 546 550.622 72.9593 91795 2.0 17.9 601 550.698 72.9685 91790 5.4 18.1 616 550.764 72.9789 91790 0.1 17.2 610 550.851 72.9874 91783 6.3 17.6 645 550.895 72.9984 91788
-4.4 16.1 702 550.936 73.0089 91792
-4.2 14.6 715 551.003 73.0191 91788 3.7 14.7 FREE AIP VOLUME USED (MILLIONS OF CU. FT.) =
0.257 REGRESSIOrt LINE INTERCEPT (LBMS 91378
=
SLOPE (LEM/HP)
-16.4
=
MAXIMUM ALLDIlAELE LEAKAGE PATE 1.200
=
75 "; OF MAXIMUM ALLOMABLE LEAKAGE PATE 0.900
=
THE CALCULATED LEA > AGE PATE 0.427
=
THE C ALC. LEAK AGE PATE AT 95* CONFILENCE LE'.'EL 0.427 0.029
=
CTMT. FPEE RIP VOLUME AT TIME 715 =
256612.
e
, TABLE 6 OUMMARY DATA E.
I. HATCH UNIT 1 ILET VERIFICATION ALMAX = 1.200 VRATET = 1.337 VRATEM = 1.344 o
TIME DATE TEMP PPESCUPE VOLUME 1516 411 550.871 72.9999 256628.
1530 411 551.066 73.0118 256619.
1545 411 551.159 73.0240 256610.
1600 411 551.294 73.0360 256601.
1615 411 551.407 73.0445 256588.
1630 411 551.562 73.0555 256575.
1646 411 551.715 73.0657 256562.
1701 411 551.834 73.0777 256549.
1716 411 551.969 73.0967 256536.
1731 411 552.074 73.0976
- 256522, 1746 411 552.220 73.1079 256497.
1800 411 552.341 73.1168 256472.
1815 411 552.401 73.1290 256447.
1830 411 552.545 73.1391 256421.
0 0
- 0. 0
- 0. 0
- 0. 0 s
I I
/
E TABLE 7 r
L i
i f
r I
E.
I.
HATCH UNIT 1 ILPT VEPIFICATION i
4 TREftD PEPDFT
[
LEAKAGE PATEI (WEIGHT PEF. CENT / DAY)
SASED Oli TOTAL-TIME CALCULATIOHe i
TIME AND DATE AT STAPT OF TETT:
1516 0411 ELAP5ED TIME:
3.23 HOUPS
[
riO. DATA ELAPIED MEAN MEAIUFED CALCULATED CHG IN CALC L/P i
POINTE tit 1E LEAKAGE PATE LEAKAGE PATE FPDM LAST POINT
(
10 2.25 1.401 1.232 11 2.50 1.402 1.264 0.032 12 2.73 1.407 1.304 0.040 13 2.98 1.403 1.308 0.003 14 3.23 1.405 1.357 0.019 o
THE CALCULATED LEAKAGE PATE 1.327
=
b I
k r
i i
r 5
l
I
(
TABLE 8 E.
I. HATCH UNIT 1 ILPT VERIFICATION LEAKAGE PATE GIEIGHT PEPCENT/ DAY)
BA!ED ON TOTAL TIME CALCULATIONO TIME AND DATE AT STAFT OF TEST:
1516 0411 ELAPIED TIME:
3.23 HOUPS TIME TEMP.
PPEMUPE MEASUPED (P:)
(POIA;'
LEAKAGE PATE 1516 550.871 72.9999 1530 551.066 73.0118 2.183 1545 551.159 73.0240 1.236 1600 551.294 73.0360 1.193 1615 551.407 73.0445 1.230 1630 551.562 73.0555 1.333 1646 551.715 73.0657 1.397 1701 551.634 73.0777 1.337 1716 551.969 73.0867 1.377 1731 552.074 73.0976 1.325 1746 552.220 73.1079 1.405 1800 552.341 73.1168 1.456 1815 552.401 73.1290 1.365 1830 552.545 73.1391 1.426 MEAN OF MEAEUPED LEAFAGE FATES 1.405
=
STD. DEVIATIDH OF MEACUFED LEAKAGE PATEI 0.247
=
VEPIFICATION TEST LEAKAGE PATE UPPEP LIMIT =
1.637 VEPIFICATION TEIT LEAKAGE PATE LOWER LIMIT =
1.037 THE CALCULATED LEARAGE PATE 1.327
=
(
TABLE 9 E.
I. HATCH Uf4IT 1 ILRT VERIFICATION LEAKAGE RATE (WEIGHT PERCEriT/ DAY)
MASO POIllT Af4ALYSIS TIME AfiD DATE AT START OF TEST:
1516 0411 ELAPSED TIME:
3.23 HOUR $
TIME TEMP PPEIOUPE CTMT. AIR MA!! LDSO TDT. AVG. MAEC (R)
(PSIA)
MASS (LEM)
(LEM)
LDSS (LEN/HP
)
1516 550.871 72.9989 91791 1530 551.066 73.0118 91771 19.5 83.5 1545 551.159 73.0240 91763 3.4 47.3 i
1600 551.294 73.0360 91757-10.6 45.6 1615 551.407 73.0445 91744 12.8 47.0 1630 551.562 73.0555 91728 16.6 51.0 1646 551.715 73.0657 91711 17.3 53.4 1701 551.834 73.0777 91701 9.4 51.1 1716 551.969 73.0667 91685 15.8 52.6 1731 552.074 73.0976 91677 8.8 50.7 1746 552.220 73.1079 91656 20.3 53.7 1500 552.341 73.1168 91638 17.9 55.7 1915 552.401 73.1290 91635 3.6 52.2 1830 552.545 73.1391 91614 20.5 54.5 FFEE AIR VOLUME UIED (MILLIONS OF CU. FT.)
0.257
=
FEGFESSIDff LIfiE IllTERCEPT (LBM) 91793
=
SLDPE (LEM HP)
-53.9
=
VEPIFICATIDri TEST LEAKAGE RATE UPPER LIMIT =
1.644 VEFIFICATIDri TEST LEAVAGE PATE LOWEP LIMIT =
THE CALCULATED LEAEAGE PATE 1.044, 1.410
=
CTMT. FFEE AIP VOLUME AT TIME 1830 =
256421.
APPENDIX A REPORT PRINTOUTS OF INTERIM TYPE A AND VERIFICATION TEST DATA ANALYSIS t
4
+
TABLE A-1 (Sheet 1)
IUf1MAPY DATA E. I. HATCH UNIT 1 59 P!IG ILPT ALMAX = 1.200
+
+
TIME DATE TEMP PPES3UPE VOLUME 2231 408 550.198 73.0170 257913.
2245 408 550.091 72.9937 257904 2300 408 549.965 72.9756 257876.
2315 408 549.879 72.9581 257863.
2330 408 549.804 72.9451 257849.
2345 408 549.749 72.9364 257840.
0 409 549.717 72.9336 257817.
15 409 549.696 72.9237 257817.
30 409 549.667 72.9133 257817.
46 409 549.630 72.9034 257808.
100 409 549.595 72.8945 257795.
116 409 549.507 72.8932 257790.
130 409 549.485 72.8879 257786.
146 409 549.466 72.8876 257772.
201 409 549.450 72.8841
- 257767, 216 409 549.451 72.8793 257765.
f 231 409 549.435 72.8798 257754<
246 409 549.437 72.8805 257749.
l 300 409 549.439 72.8865
- 257740, 315 409 549.444 72.8908 257731.
331 409 549.466 72.8901
- 257727, 346 409 549.486 72.8907 257718.
401 409 549.502 72.9081 257741.
416 409 549.506 72.9084 257732.
431 409 549.520 72.9114 257704 445 409 549.544 72.9121 257699.
501 409 549.568 72.9155 257695.
516 409 549.596 72.9198 257681.
531 409 549.647 72.9256 257677.
545 409 549.676 72.9281 257672.
600 409 549.717 72.9336 257663.
616 409 549.746 72.9415 257659.
631 409 549.801 72.9492 257654.
646 409 549.868 72.9649 257619.
701 409 549.915 72.9851 257589.
716 409 549.934 72.9941 257580.
731 409 549.987 73.0010 257580.
745 409 550.025 73.0077 257580.
0 0
- 0. 0
- 0. 0
- 0. 0 i
l l
i y
-,.+
TABLE A-1 (Sheet 2 59 P.IIG )ILF T E.I. HHi n vote 1 LEAKAGE PATE O.lEIGHT PEPCENT/ DAY)
MAS! PDIriT ANALYSIS TIME Arid DATE AT OTART OF TEST:
9.23 HOUP!
TIf1E TEMP PFE!!UFE CTf1T. AIR MAIO LOOO TUT. AVG. t1A*!
(Py (P S I A)
MA:~ (LBfD (LBPD LDIO (LBM HP) 2231 550.198 73.0170 92386 2245 550.091 72.9937 92371 14.7 63.2 2300 549.965 72.9756 92360 11.8 54.9 2315 549.879 72.9581 92347 12.4 53.0 2330 549.804 72.9451 92338 8.9 48.6 2345 549.749 72.9364 92333
- 5. 0 42.8 0
549.717 72.9336 92327 6.4 39.9 15 549.696 72.9237 92318 9.0 39.3 30 549.667 72.9133 92310 8.3 38.6 46 549.630 72.9034 92300 9.5 38.2 100 549.595 72.8945 92290 10.0 38.7 116 549.507 72.8932 92301
-11.3 30.8 130 549.485 72.8879 92297 4.4 29.9 146 549.466 72.8876 92295 2.2 28.1 201 549.450 72.8841 92291
- 3. 5 27.1 216 549.451 72.8793 92283 7.7 27.4 l
231 549.435 72.8798 92284
-0.1 25.6 246 549.437 72.8805 92282 1.2 24.4 i
300 549.439 72.8865 92286
-4.0 22.2 315 549.444 72.8908 92288
-1.4 20.8 331 549.466 72.8901 92282 6.0 20.9
/
346 549.486 78.8907 92276 5.8 21.0 401 549.502 72.9081 92303
-27.6 15.0 416 549.506 72.9084 92300 3.5 15.0 431 549.520 72.9114 92291 8.6 15.8 445 549.544 72.9121 922'26 4.9 16.0
=. n.1
=.4 4.. es. o
-:< m. c. 1 E. =.
c.
So c.
- 1. m>
1e.=
516 549.596 72.9198 92281 4.3 15.6 531 549.647 72.9256 92278 2.7 15.4 545 549.676 72.9281 92275 3.5 15.4 e. t, e a a... 1.
n-
-. o. #o e
- c. : 3. :.
31 1e. 3
<c.
616 549.746 72.9415 92275
-3.7 14.3 631 549.801 72.9492 92274 1.3 14.0 646 549.868 72.9649 92270 3.9 14.0 n.1 sa o.. o.1 e
..o_, o p e.,1
- c. :-:..
- g.. o.
i c..o
(
716 549.934 72.9941 92282
-5.0 11.9 r
731 549.987 73.0010 92282 0.2 11.6 745 550.025 73.0077 92284
-2.1 11.0 FFEE AIP VOLUME USED (MILLIDri: OF CU. FT.)
0.258
=
l FEGGE!!!Dri lit!E I:iTEF C EPT (LEri) 92338
=
?LDPE (LEMeHF)
-8.3
=
MAXIMUM ALLDI..AELE LEM AGE PATE 1.200
=
?S 7 OF MAXIMUri ALLDtlAELE LEAKAGE FATE 0.900
=
THE CALCULATED LEAtAGE FATE 0.217
=
THE CALC. LEALAGE PATE AT 95N CDriFILEtiCE LEVEL 0.217 0.054
=
1 1
1 CTMT. FREE AIP VOLUME AT TIME 745 =
257580.
t TABLE A-1 (Sheet 3)
IUMMAPY DATA HATCH UNIT 1 59 PSIG ILPT VEFIFICATIDM ALMPX = 1.200 VPATET = 1.019 VRATEM = 1.113 TIME DATE TEMP FPESCUFE VOLUME 110 ft 409 550.45.
73.1212 257219.
1116 409 550.376 73.1100 25719e.
1130 409 550.359 73.1057 257173.
1145 409 550.370 73.1039 257150.
1201 409 550.400 73.1040 257127.
1216 409 550.401 73.1039 257104 r
1831 409 550.445 73.1100 257081.
1245 409 550.486 73.1155 257058.
1300 409 550.542 73.1217 257035.
1315 409 550.577 73.1318 257021.
13?0 409 550.592 73.1397 257021.
1345 409 550.614 73.1502 257007.
1400 409 550.717 73.1596 256998.
1415 409 550.809 73.1690 256993.
1410 409 550.586 73.1809 256988.
1445 409 550.918 73.1928 256955.
1500 409 550.995 73.2045 256926.
1515 409 551.065 73.2161 256897.
1530 409 551.154 73.2270 256859.
1545 409 551.224 73.2421 256654 1600 409 551.272 73.2530 256654
TABLE A-1 (Sheet 4)
HATCH UttIT 1 59 PIIG ILRT VERIFICATIuri LEAKAGE PATE (f.IEIGHT PEPCEriT/ DAY)
MA;5 POIfiT AfiALYSIS TIME Arid DATE AT ITAPT OF TEIT:
1100 0409 ELAP*ED TIME:
5.00 HOUPS TIME TEMP PPEi!UPE CTMT. AIP MACO LDSI TOT. AVG. MA!C (P)
(P5IA)
MAO! (LBM)
(LEM)
LOSS (LEM/HP) 1100 550.459 73.1212 92225 1116 550.376 73.1100 92217 8.5 31.7 1130 550.359 73.1057 92206 10.8 38.6 1145 550.370 73.1039 92194 12.4 42.2 1201 550.400 73.1040 92180 13.1 44.1 1216 550.401 73.1029 92172 8.5 42.1 1231 550.445 73.1100 92164 7.9 40.4 1245 550.486 73.1155 92156 8.2 39.7 1300 550.543 73.1217 92146 10.0 39.7 1315 550.577 73.1318 92148
-2.0 34.4 1330 550.592 73.1397 92155
-7.4 28.0 1345 550.614 73.1502 92160
-4.5 23.8 1400 550.717 73.1596 92151 8.6 24.7 1415 550.809 73.1690 92146 5.3 24.4 1430 550.886 73.1809 92146
-0.3 22.6 1445 550.938 73.1928 92141 5.5 22.6 1500 550.995 73.2045 92135 5.2 22.5 1515 551.068 73.2161 92127 8.0 23.0 1530 551.154 73.2270 92113 14.3 24.9 1545 551.224 73.2421 92119
-5.5 22.4 1600 551.272 73.2530 91124
-5.7 20.2 FPEE AIF. VOLUME UOED (MILLIGtC GF CU. FT.) =
0.257 FIGFE;01Cri LIriE IriTEPCEFT (LEM) 92205
=
OLDPE (LEM/HP)
=
-18.8 VEPIFICATIDft TECT LEAFAGE FATE UFPEP LIMIT =
1.413 VdPIFICATIDri TELT LEALAGE F ATE LUI.JEP LIMIT =
0.813 THE CALCULATED LEAKAGE PATE 0.488
=
C T!)T. F:'EE AIF VOLUME AT TIME 1600 =
256854 Average verification flow rate during test = 0.8961 per day I
I 1
l
j TABLE A-2 (Sheet 1)
~UMMARY DATA E.I. HATCH UNIT 1 ILPT 59 PSIG ALMAX = 1.200 TIME DATE TEMP PPE55UPE VOLUME 530 410 548.908 73.2451 257087.
545 410 548.757 73.2244 257077.
600 410 548.666 73.2084 257067.
615 410 548.596 73.1927 257056.
631 410 548.562 73.1808 257046.
646 410 548.496 73.1687 257036.
716 410 548.598 73.1498 257015.
730 410 548.459 73.1410 257005.
746 410 548.464 73.1339 256994.
800 410 548.410 73.1251 256984 816 410 548.426 73.1208 256974.
830 410 548.463 73.1136 256963.
845 410 548.498 73.1073 256951.
900 410 548.460 73.1034 256943.
915 410 548.569 73.0962 256932.
931 410 548.497 73.0947 256922.
946 410 548.497 73.0921 256912.
1001 410 548.593 73.0874 256901.
1015 410 548.759 73.0841 256891.
1030 410 548.864 73.0829 256881.
1045 410 549.011 73.0821 256870.
1100 410 548.844 73.0815 256860.
'1115 410 548.917 73.0788 256850.
1130 410 548.963 73.0797 256839.
1145 410 549.029 73.0788 256829.
1200 410 549.128 73.0773 256819.
1215 410 549.170 73.09G2
- 256808, 1230 410 549.236 73.0810 256798.
I I
I
I, TABLE A-2 (Sheet 2) 1245 410 549.346 73.0813 256788.
1300 410 549.409 73.0834 256777.
1316 410 549.532 73.0874 256767.
1331 410 549.515 73.0890 256757.
1346 410 549 640 73.0920 256746.
1400 410 549.651 73.0964 256736.
1415 410 549.786 73.0995 256726.
1430 410 549.855 73.1036 256715.
1445 410 549.896 73.1083 256705.
l 1500 410 549.960 73.1138 256695.
1515 410 550.040 73.1159 256688.
1530 410 550.210 73.1195 256681.
1545 410 550.302 73.1254 256674 l
1600 410 550.432 73.1297 256668.
I 1615 410 550.504 73.1352 256661.
1630 410 550.554 73.1416 256654.
1645 410 550.610 73.1489 256647.
1700 410 550.589 73.1271 256733.
1715 410 551.554 73.0869 256519.
1730 410 551.395 73.0458 256905.
1745 410 551.057 73.0218 256592.
1800 410 551.082 73.0049 256579.
4 1815 410 550.988 72.9981 256866.
1831 410 550.786 72.9936 256853.
1845 410 550.688 72.9914 256840.
1900 410 550.741 72.9903 256:527.
1916 410 550.801 72.9889 256814 1936 410 550.872 72.9872 256802.
1945 410 550.844 72.9910 256789.
2000 410 550.910 72.9946 256776.
2015 410 550.900 72.9972 256764 2030 410 551.172 73.0023 256751.
2046 410 551.234 73.0072 256738.
2100 410 550.007 73.0208 256725.
TABLE A-2 (Sheet 3)
E.I. HATCH UNIT 1 ILPT 59 PSIG LEALAGE PATE OJEIGHT PEPCENT/ DAY)
MAir POINT ANALYSIS l
TIME AND DATE AT STAPT OF TECT:
530 0410 ELAP5ED TIME:
15.50 HOUPO TIME TEt1P PPE10VRE CTNT. AIP MASG LOSS TOT.AVC 17 TIS (P=
(Pila)
MA55 (LBM)
(LEM)
LOSS (Li.s hP) 530 548.908 73.2451 92595 545 548.757 73.2244 92591 4.3 17.2 600 548.666 73.2084 92582 8.5 25.6 615 548.596 73.1927 92570 12.0 33.0 l
631 549.562 73.1808 92557 12.9 37.1 646 548.496 73.1687 92549 7.8 35.9 716 5-5.598 73.1498 92501 48.7 53.3 730 548.459 73.1410 92510
-8.7 42.7 746 548.464 73.1339 92496 13.8 43.8 800 548.410 73.1251 92490 5.6 41.9
/
816 548.426 73.1208 92478 11.7 42.1 830 548.463 73.1136 92459 19.3 45.3 845 548.498 73.1073 92442 17.5 47.2 900 548.460 73.1034 92439 2.1 44.4 915 548.569 73.0962 92408 31.4 49.8 931 548.497 73.0947 92415
-6.6 44.9 946 548.497 73.0921 92408 6.9 43.9 1001 548.593 73.0874 92382 26.1 47.2 1015 548.759 73.0841 92346 35.7 52.4 1030 548.864 73.0829 92323 22.8 54.3 1045 549.011 73.0821 92294 29.7 57.4 1100 548.844 73.0815 92317
-23.7 50.5 l
1115 548.917 73.0788 92298 19.3 51.6 1130 548.963 73.0797 92287 10.5 51.2 1145 549.029 73.0789 92272 15.8
- 51. 7 1200 549.128 73.0773 92250 22.1 53.1 1215 549.170 73.0802 92242 7.3 52.3
.,.. vw. i o
- c. e r t o.
1.o..
- s. o..
1 :.e n.
e.,a.:,. -:. ->
i 1245 549.346 73.0813 92207 21.7 53.5 1300 54?.4n9 73.0834 92195 11.9 53.3
!?ls 549.532 73.0874 92176 19.2 54.0 i.. i e.,a c.. e.,1 e.,
.. tw. o. n.
- c. : t..
- 3. m.
er.1 l
{
a TABLE A-2 (Sheet 4) 1346 549.640 73.0920 92156 21.1 53.1 1400 549.651 73.0964 92156
-0.1 51.6 1415 549.786 73.0995 92134 22.3 52.7 1430 549.855 73.1036 92123 10.3 52.4 1445 549.896 73.1083 92119 4.5 51.5 1500 549.960 73.1138 92111 7.4 50.9 1515 550.040 73.1159 92098 13.3 50.9 1530 550.210 73.1195 92072 26.4 52.3 1545 550.302 73.1254 92061 10.5 52.1 1600 550.432 73.1297 92043 18.5 52.6 1615 550.504 73.1352 92025 7.6 52.1 1630 550.554 73.1416 92032 2.8 51.1 1645 550.610 73.1489 92030 2.7 50.2 1700 550.589 73.1271 92037
-6.9 45.5 1715 551.554 73.0869 91856 180.8 62.9 1730 551.395 73.0458 91861
-5.6 61.1 1745 551.057 73.0218 91883
-21.5 58.1 1800 551.082 73.0049 91853 30.1 59.4 1815 550.986 72.9991 91855
-2.5 58.0 1831 550.786 72.9936 91879
-23.4 55.0 1845 550.688 72.9914 918?8
-8.9 53.4 1900 550.741 72.9903 91873 14.9 53.5 1916 550.801 72.9889 91856 16.4 53.7 l
1936 550.872 72.9872 91838 18.3 53.7 l
1945 550.844 72.9910 91843
-4.8 52.8 2000 550.910 72.9946 91872 11.1 52.6 2015 550.900 72.9972 91832
-0.6 51.7 j
2030 551.172 73.0023 91789 43.6 53.7 4
2046 551.234 70.0072 91780 8.8 53.4 2100 550.007 73.0208 91997
-217.2 38.6 FFEE AIF VOLUME UIED (MILLIDrG OF CU. FT.)
0.258
=
REGREi!IOri LIriE 92610 litTEPCEPT (LEM)
=
]
OLDPE (LEft/HP)
-54.3
=
1.200 MAXIMUM ALLOIAAELE LEAKAGE RATE
=
75 % OF IIAXIMUM ALLDidAELE LEALAGE PATE 0.900
=
1.407 THE CALCULATED LEAFAGE FATE
=
1.407 0.060 THE CALC. LEAKAGE PATE AT 95% CCriFIDENCE LEVEL
=
CTMT. FFEE AIP VOLUr:E AT TIME 2100 =
256725.
APPE!! DIX B RESULTS
SUMMARY
OF TYPE B&C TESTS PERFORMED SI!!CE LAST TYPE A TEST i
l l
l l
I) 6EEENDIZ_B TABLE OF CONTENTS I. GEtiERAL II. DISCUSSION III. DETERMINING TOTAL CONTAINMENT LEAKAGE IV. ACCEPTANCE CRITERIA V. LLRT PROGRAM RESULTS ATTACHMENT 1 Type D LLRT Summary ATTACHMENT 2 Type C LLRT Summary ATTACHMENT 3 Failed LLRT Summary i
?
1 e,
I.
GENERAL m
C.1e of the conditions of all operating licenses for water-cooled power reactors is that primary reactor containments shall meet the ccntainment leakage test requirements set forth in the Appendix J to ICCFR50 and the project tech specs.
The purposes of the tesis (Type A, B, and C) are to assure that (a) the leakage through the primary reactor containment and systems and components penetrating primary containment shall not exceed allowable leakage rate values as specified in the tech specs or associated bases and (b) periodic surveillance of reactor containment penetrations and isolation valves is performed so that proper maintenance and repairs are made during the service life of the containment,.and systems and components penetrating primary containment.
The satisfactory completion of Type B and C leak rate tests allows the discovery and elimination of leak paths thru the containment without pressurizing the entire containment
' structure as is done in an Integrated Leak Rate Test (ILRT).
Three Type 8 and C local leak rate test (LLRT) programs were satisfactorily performed during the time inter. val between the pre-operational ILRT and the first ' periodic ILRT.
Due to the long duration of the first operating. cycle, one LLRT program had to be performed prior to the first refueling shutdown in order to comply with the 2 year surveillance frequency set forth in Tech Specs.
The second and third LLRT programs were completed during.the first and second R/F Dutages respectively.
II. DISCUSSION The procedure used to perform local leak rate tests (LLRT's) on primary containment boundary components employs the air flow method.
This method determines the leakage rate by measuring the amount of makeup flow required to keep the test volume at a pre-set pressure which is maintained by a pressure regulator.
Following the completion of an LLRT, the measured leakage rate is
'he test adjusted as required to account for any differences between t
Pressure and/or temperature and the pressure and tempera ture at which the instrumentation was calibrated.
The following equations are used to determine the pressure and temperature correction factors:
O e
(
Wh'er e :
1/2 f
= Temperature correction factor f*=[Tc+T,snh t
1 T
= Flowmeter calibration temperature Te+ Tabs /
c T
= Test temperature 1/2 t
f fp yPT+Pam T
= Absolute temperature conversion (460)
(Pe t Patm abs
\\
f
= Pressure correction factor P
P
= Flowmeter calibration pressure C
~ P'
= Test pressure t
P
= Atmospheric pressure (14.7) atm Rotameters are used to determine Type B and C leakage rates and are calibrated to i 1% (Full Scale) accuracy traceable to the National Bureau of Standards.
The rotameters used are of the following ranges:
22-220 ACCM, 220-2200 ACCM and 4-40 SCFH.
Efforts are made to measure leakages with the correct range rotameters to prevent obtaining inaccurate leakage rate readings.
Occasionally during the performance of a Type C LLRT it is difficult to determine which valve is leaking in a two or more valve boundary.
One method for determining this is by checking vents on the outboard side of each boundary valve as this is helpful in directing maintenance activities.
III. DETERMINING TCIAL CONTAINMENT LEAKAGE In order to detor-s.c3 atal containment leakage, it is initially required to detesmine t..e TYPE B and C leakages for each penetration.
Once penetration leakages are determined, the overall leakage for components penetrating the primary containment may'be determined by summing the Type B and C penetration leakages.
Penetration leakage is determined as follows:
Type B penetration leakages are determined directly from the test leakages when the penetration invoives only one test.
Wiien the penetration involves an inboard and an outboard component; however, the penetration leakage is equal to the greater of the two test values.
I
4 I
Type C penetration leakages include three types of tests:
~
a.
For containment isolation valves in series, tested individually, the renetration leakage is equal to tire i
measured test leakage of the isolation valve with the highest leak rate.
b.
For containment isolation valves tested simultaneously, the penetration leakage is equal to the total leakage measured.
c.
For containment isolation valves tested individually that are in parallel, the penetration leakage is the sum of the individually measured test leakages.
IV.
ACCEPTANCE CRITERIA The acceptance criterion for Type B and C local leak rate tests is set forth in 10CFR50 Appendix J and the project Tech Specs as being 60% La for all containment penetrations and isolation valves subject to Type B and C testing.
Specific acceptance criteria exist only for Main Steam Isolation Valves (11.5 SCFH/ valve) and the Drywell Airlock Inner Space (5% La).
Due to the fact that the 60% La is an overall limit, the possibility exists in that the majority of the containment leakage could be leaking through one highly degraded valve and still be within the 60%
limit.
Although the uniformity of leakage through the containment penetrations is relatively unimportant, it is not desirable lo have a case where the majority of containment leakage is being emitted through one penetration.
Because of this, an effort is made to limit the leakage through penetrations by assigning an expected value for each test.
This value is not a limit but serves as a guideline to prevent the aforementioned condition.
k t
i i
l 1
V.
LLRT PROGRAM RESULTS 11 RT PROGE6d CONI 61NMENI_LEaEaGE 1975-1976 Type B - 641 ACCM Type C Simultaneous - 11786 ACCM Parallel - 5150 ACCM Series - 2238 ACCM IDIeL - 19 S15_eCCd 2
1977 R/F Outage.
Type B - 980 ACCM Type C Simultaneous - 11648 ACCM Parallel - 3648 ACCM Series - 631 ACCM IQI6L - 15190I_eCCd 1978 R/F Outage Type B - 884 ACCM Type' C Simultaneous - 12142 ACCM Para 11e'l - 5394 ACCM l
. Series - 818 ACCM IDI6L - 192233_eCCd Allowable leakage (60% La) is derived as follows:
'60% 11.2%_cnniainm2ni_ftce_ait_2clummi Allowable Leakage
=
1 day
.60 (.012) (257.360 cu ft.)/24 hr
=
77.21 cfh or HErdde_6CCd
=
9
ATTACHMENT 1 TYPE B Test Summary Penetration Test Test
__Numhet Eeneitalinn_Descciation Rain Intal (AccM) 1A Equipment Hatch "O"
Rings 5-5-74 0
4-13-76 0
5-14-77 0
4-5-78 0
18 Equipment Hatch "O" Rings 5-5-74 0
12-23-75 0
4-21-76 0
5-14-77 0
1 4-5-78 O
2 Personnel Airlock-Inner Space 5-01-74 420 l
11-04-74 0
11-17-74 210 3-11-75 0
9-11-75 300 3-19-76 1400 9-01-76 1639 2-14-77 2300 5-15-77 504 11-05-77 1707 4-03 650 2
Personnel Airlock (Interior) 11-17-74 O
Door Seals (Exterior) 200 12-2-74 0
0 2-12-75 250 0
2-19-75 220 0
2-22-75 480 0
2-23-75 440 0
2-24-75 420 0
3-11-75 O
O 5-06-75 500 120 5-14-75 300 O
5-19-75 225 0
6-17-75 180 5
7-7-75 250 20 3
ATTACHMENT 1 TYPE B Test Summary Penetration Test Test
__Numher Enneicatinn_Desccialian Dais In121 (ACCM) 2 (Con't)
Personnel Airlock (Interior) 7-1G-75 170 Door Seals (Exterior) 760 7-14-75 120 600 8-1-75 335 560 8-12-75 205 260 9-8-75 75 210 9-15-75 130 1700 10-1-75 195 1800 11-04-75 140 2110 12-24-75 O
O 1-14-76 O
~
O 2-12-76 10 20 2-14-76 O
O 2-24-76 O
O 4-22-76 32 69 4-23-76 9
41 5-02-76 19 52 5-11-76 41 46 6-6-76 51 80 6-09-76 23 74 11-22-76 73 87 1-04-77 50 175 1-10-77 32 110 2-01-77 0
220 3
I
\\
ATTACHMENT'.1 TYPE B Test Summary i
Penetration Test Test
__Numher Eeneltatinn_Qaenciation Qain Inlal (ACCM) 2 (Con't)
Personnel Airlock (Interior) 2-14-77 291 Door Seals (Exterior)
O 3-1-77 108 232 5-18-77 27 23 5-18-77 O
O 6-19-77 O
O 12-4-77 360 360 4
Top Head Manway 12-17-75 0
5-11-77 0
4-02-78 O
6 CRD Removal Hatch 4-11-76 O
5-11-77 O
6-19-77 0
4-03-78 0
7A Main Steam Inboard Bellows 3-30-76 0
Outboard Bellows O
3-19-77 O
O 3-09-78 O
O 78 Main Steam Inboard Bellows 3-30-76 O
Outboard Bellows O
3-19-77 O
O 3-09-78 O
O 7C Main Steam Inboard Bellows 3-30-76 O
Outboard Bellows O
3-19-77 0
O i
l 3-09-78 O
I O
ATTACHMENT 1 TYPE B Test Summary Penetration Test Test Numhgr P_RD21Calinn_QE1CCiElinD DaiC 12121 (ACCM) 7D Main Steam Inboard Bellows 3-30-76 O
Outboard Bellows O
3-19-77 O
O 3-09-78 0
O 8
Condensate Drain Inboard Bellows 3-30-76 O
Outboard Bellows O
3-19-77 O
O 3-09-78 O
O
.9A Feedwater Inboard Bellows 3-30-76 O
Outboard Bellows O
3-19-77 0
O 3-09-78 O
O 98 Feedwater Inboard Bellows 3-30-76 O
Outboard Bellows
'O 3-19-77 O
O 3-09-78 0
20 10 Steam to RCIC Inboard Bellows 3-30-76 0
Outboard Bellows O
3-19-77 O
O 3-09-78 0
0 11 Steam to HPCI Inboard Bellows 1-27-7E.
O Outboard Bellows O
4-07-77 O
O 3-12-78 0
O e
ATTACHMENT 1 TYPE B Test Summary Penetration Test Test
__Uumhet Eeneitalinn_Descciallan Dais Inlal (ACCM) 12 RHR Shutdown Cooling Inboard Bellows 1-27-76 0
Outboard Bellows O
4-07-77 0
0 3-12-78 0
0 13A RHR LPCI to Reactor Inboard Bellows 1-27-7E.
O Outboard Bellows O
4-07-77 0
O 3-12-78 O
O 138 RHR LPCI to Reactor Inbcard Bellows 1-27-76 0
Outboard Bellows 17 4-07-77 0
0 3-12-78 0
0 14 RWCU Inboard Bellows 4-2-76 0
Outboard Bellows O
4-05-77 22 0
3-25-78 0
0 1 E.A Core Spray "A"
Inboard Bellows 4-2-76 0
Outboard Bellows O
4-05-77 0
0 3-09-78 O
O 168 Core Spray "B"
Inboard Bellows 4-2-76 0
Outboard Bellows O
4-08-77 0
0 3-11-78 0
0
ATTACHMENT 1 TYPE B Test Summary i
Penetration Test Test 1
Numhgr E2DEitali2D_Q2iCEiElinn Da12 12101 (ACCM) 17 RPV Head Spray Inboard Sellows 1-27-76 O
Outboard Bellows O
4-08-77 0
0 3-13-78 O
O 25 T48-F103 Shaft O Rings 1-28-76 220 Flange O Rings O
8-31-77 O
O 2-25-78 0
0 25 T48-F307 Shaft O Rings 1-28-76 O
Flange O Rings O
8-31-77 O
s O
2-25-78 O
O 25 T48-F308 Shaft O Rings 1-28-76 O
Flange O Rings O
8-31-77 O
O 2-24-78 0
2-25-72 0
25 T48-F303 Shaft O Rings 1-28-76 O
Flange O Rings O
8-30-77 O
O 2-22-78 O
O 25 T48-F324 Shaft O Rings 1-28-76 O
l Flange O Rings O
l 8-30-77 43 0
2-22-78 72 0
D
O ATTACHMENT 1 TYPE B Test Summar y Penetration Test Test
__dumher E2n21talinn_QEiiciatinD Qaim Icial (ACCM) 26 T48-F319 Shaft O Rings 1-27-76 0
Flange O Rings O
8-29-77 O
O 2-26-78 O
O 26 T48-F320 Shaft O Rings 1-27-76 O
Flange O Rings O
8-29-77 0
0 2-26-78 O
O 35A Tip Drive O-Ring 4-25-75 O
S-11-77 0
3-14-78 0
358 Tip Drive 0-Ring 4-25-75 0
5-11-77 0
3-14-78 0
35C Tip Drive 0-Ring 4-25-75 0
5-11-77 0
3-14-78 0
35D Tip Drive 0-Ring 4-25-75 0
5-11-77 0
3-14-78 0
35E Tip Drive 0-Ring 4-16-76 0
5-11-77 0
3-14-78 0
43 Drywell Test 0-Ring 4-2-76 0
5-5-77 0
3-23-78 0
100A Electrical Penetration 1-30-76 0
4-14-77 0
E-8-78 0
1008 Electrical Penetration 1-30-76 0
4-14-77 0
2-7-78 0
1000 Electrical Penetration 4-4-76 0
4-20-77 0
3-1-78 0
100E Electrical Penetration 4,5-76 0
4-20-77 0
3-1-78 0
ATTACHMENT.1 TYPE B Test Summary Penetration Test Test
__Uucher Eeneltalinn_Resccie.linn L' ale Inlai ( ACCm 101A Electrical Penetration 3-30-76 0
5-5-77 0
2-8-78 0
1018 Electrical Penetration 3-30-76 0
5-5-77 O
2-6-78 0
101C Electrical Penetration 3-30-76 O
5-5-77 0
2-8-78 0
1010 Electrical Penetration 1-30-76 0
4-22-77 0
2-9-78 0
101E Electrical Penetration 1-30-76 0
4-22-77 0
2-9-78 0
101F Electrical Penetration 1-30-76 0
4-22-77 0
2-9-78 0
102A Electrical Penetration 3-30-76 0
4-15-77 0
2-8-78 O
103A Electrical Penetration 3-30-76 0
5-5-77 0
2-7-78 O
iO4A Electrical Penetration 1-30-76 0
4-15-77 0
2-7-78 0
1048 Electrical Penetration 4-02-76 0
4-15-77 O
2-8-78 0
104C Electrical Penetration 4-2-76 0
4-19-77 0
2-8-7S 0
104F Electrical Penetration 4-5-76 0
4-20-77 O
2-27-78 0
104G Electrical Penetration 4-5-76 0
'4-20-77 0
2-27-78 0
104H Electrical Penetration 4-6-76 0
4-20-77 0
~
3-1-78 O
105A Electrical Penetration 3-30-7E.
O 5-5-77 0
2-7-78 0
e
. et, e
ATTACHMENT 1 TYPE B Test Summary Penetration Test Test Numhet__
E2Deitali2C_Q21r.,EiEii2D QQ12 121dl (ACCN 105C Electrical Penetration -
1-30-76 0
4-22-77 O
2-9-78 0
1068 Electrical Penetration 4-4-76 0
4-20-77 0
3-1-78 0
2OOA Torus Hatch O-Ring 12-7-75 O
Northwest 5-4-77 0
4-5-78 0
2008 Torus Hatch O-Ring 4-10-76 O
Southwest 4-20-76 0
6-5-76 0
5-11-77 0
4-5-78 0
201A Dcwncomer Inboard Bellows 4-2-76 O
Outboard Bellows O
4-8-77 O
O I
2-10-78 0
0 2018 Downcomer J
Inboard Bellows 4-15-7E.
O I
Outboard Bellows 5
4-8-77 O
O 2-9-78 0
10 201C Downcomer Inboard Bellows 4-15-76 O
Outboard Bellows O
4-12-77 O
O 2-11-78 O
O 201D Downcomer Inboard Bellows 4-15-76 0
Outboard Bellows O
4-12-77 0
0 2-11-78 O
O 3
O
ATTACHMENT 1 TYPE B Test Summary Penetration Test Test Numhar E2D21CalinD_Q21ECiEliSD Dait 121al (ACCM) 201E Downcomer Inbcard Be11ows 4-15-76 O
Outboard Bellows 37 4-12-77 O
O 2-11-78 O
O 201F Drwncomer Inboard Bellows 4-02-76 O
Outboard Bellows O
4-12-77 O
O 2-14-78 O
O 201G Downcomer Inboard Bellows 4-02-76 O
l 0
Outboard Bellows 4-09-77 O
O
(
2-14-78 0
O 201H Downcomer Inboard Bellows 4-15-76 O
Outboard Bellows O
4-E-77 144 4-10-77 0
2-14-78 0
0 202 Electrical Penetration 1-22-76 0
5-18-77 0
2-9-78 0
205 T48-F310 Shaft 0-Ring 1-2S-76 0
Flange O-Ring O
8-30-77 O
O 2-22-78 0
0 205 T48-F311 Shaft 0-Ring 1-28-76 O
Flange 0-Ring O
8-30-77 0
0 2-23-7S O
O O
ATTACHMENT 1 TYPE B Test Summary Penetration Test Test Numhgr EgDR1CaliQn_Q25EniEli2D Qaig Inlal (ACCM) 218-A Torus Drain 0-Ring Seal 12-2-75 0
5-4-77 0
3-5-78 0
218-8 Torus Drain 0-Ring Seal 12-2-75 0
5-4-77 0
3-5-78 0
220 T48-F318 Shaft 0-Rings 1-28-76 300 Flange O-Rings O
8-29-77 0
8-31-77 0
2-24-78 0
O l
220 T48-F326 Shaft 0-Rings 1-28-76 300 Flange O-Rings O
8-31-77 0
107 2-23-78 0
0 9
C'
)
..m.
n
ATTACHMENT'2 TYPE C Test Summary Penetration Test Test Test Numhgr Q21CCiElinn Qa12 I21a1 (SCFH)
N212111 7A MSIV Inboard 821-F022A 12-24-75 Greater than 80 1,4 4-22-76 4
1 3-22-77 4
1 3-27-78 4
1,6 (As found greater than 80) 7A MSIV Outboard B21-F028A 12-21-75 4
4-18-76 0
3-16-77 4
3-27-78 4
78 MSIV Inboard 821-F0228 11-21-75 6
3-15-77 4
3-16-78 4
i 7B MSIV Outboard 821-F028B 11-21-75 6
3-15-77 0
3-16-78 4
1,6' (As found greater than 80) 7C MSIV Inboard B21-F022C 11-21-75 Less than 4 3-16-77 0
3-05-78 8.5 7C MSIV Outboard 821-F028C 11-19-75 Less than 4 3-1E.-77
'O 3-05-78 8.5 s
70 MSIV Inboard B21-F022D 11-21-75 Less than 4 l
3-12-77 0
3-06-78 4.5 7D MSIV Outboard 821-F028D 12-10-75 Less than 4 1
3-13-77 4
3-06-78 4.5 s
~
I ATTACHMENT 2 TYPE C Test Summary Penetration Test Test Test
__Uumber Deictlatinn Qain Inial (ACCM)
Unleini 8
Condensate Drain B21-FOl6, F019 4-14-76 481 3-22-77 0
1 3-23-78 0
1.6 (As found greater than 2200 ACCM) 9A FW-Outboard Check B21-F0108,F0328,E41-FOO6 11-23-75 35 3
3-22-77 0
3 3-14-78 50 3
9A FW-Inboa'rd Check B21-F0108, F0118 11-23-75 390 3
3-21-77 93 3
3-13-78 0
3 9A FW-HPCI E41-FOO6, FOO7, FOOS 3-29-76 0
i 3-23-77 0
3-11-78 O
98 FW-Outboard Check B21-FO10A, F032A E51-F013, G31-F042 3-31-76 40 3
4-03-77 48 3
3-13-7S 360 3
98 FW-Inboard Check B21-F010A, F011A 3-31-76 124 3
4-03-77 113 3
3-13-78 372 3
98 FW-RCIC E51-F012,F013,F022 4-1-76 256 4-5-77 0
3-31-78 520 1,6 (As found greater than 2200 ACCM) 10 Steam to RCIC Drain vivs E51-F025, F026 12-20-75 60 4-3-77 109 1,7 10 Steam to RCIC 1 sol Vivs E51-FOO7, FOOS 4-24-75 0
5-04-75 0
3-24-77 247 3-20-78 454 1,6
)
(As found greater than 2200 ACCM) w
l ATTACHMENT 2 TYPE C Test Sum.nar y Penetration Test Test Test
_Uumkar Q21EtiE112D DA12 12121 (ACCM)
U212111 11 Steam to HPCI Drn Vivs E41-F028, F029 12-07-75 10 3-27-77 0
1,7 11 Steam to HPCI Isol Vivs E41-FOO2, FOO3 12-14-75 200 4-02-76 0
3-22-77 0
3-12-78 604 12 RHR suction from Recirc E11-FOOS', FOO9 4-14-76 499 4-11-77 414 4-02-73 300 13A RHR Return E11-F015A, F017A 3-31-76 1810 1
3-23-77 1030 3-24-78 1450 138 RHR Return E11-F0158, F0178 11-25-75 1950 5-17-77 1704 1
3-12-73 1074 1,6 (As found greater than 2200 ACCM) 14 RWCU G31-FOO1,FOO4 4-1-76 225 4-2-77 0
3-25-78 0
16A Core Spray Injection E21-FOO4A, FOOSA 12-14-75 40 3-25-77 0
3-E-78 0
168 Core Spray Injection E21-FOO48, FOO58 12-15-75 35 3-23-77 0
3-11-7S O
17 RPV Head Spray E11-F022,F023 4-09-76 10 4-29-77 0
3-04-78 O
18 Equipment Drain Disch.
i G11-FO19,F020 4-02-76 0
4-15-77 793 3-16-73 O
l l
?
ATTACHMENT 2 TYPE C Test Summary Penetration Test Test Test
.__Uumhet__
Resntiation Q212 Inial Unicial 19 Floor Drain Pump Disch.
G11-FOO3, FOO4 12-15-75 110 4-15-77 9
3-16-78 O
21 Service Air P51-F513,F514 12-13-75 0
4-04-77 0
3-21-78 0
22 DW Pneum.atic Supply P70-FOO4,FOO5,F022,F024 12-13-75 0
4-05-77 0
3-15-78 0
25 Purge Supply T48-F103,F307,F308, F324,F303 12-11-75 110
(
'4-1-77 20 3-3-78 204 25 Purge Supply Einer g enc y Makeup T48-F113, F114 12-11-75 0
4-5-77 0
3-6-78 0
25 Purge Supply Emergency Makeup T48-F321, F322 12-11-75 7
4-5-77 0
3-5-78 20 25 Purge Suppl, Emergency Makeup T48-F104, F118A F1188 12-12-75 27 3-29-77 0
3-6'-78 0
26 Purge Exhaust T48-F319, F320 12-20-75 450 1
4-17-77 242 1
3-5-78 E.6 26 Purge Exhaust Emergency T48-F334A, F335A 12-12-75 0
3-25-77 0
3-5-78 40 3
O ATTACHMENT 2 TYPE C Test Summary Penetration Test Test Test
__Uumhet___
Qescnialinn Qain Inial (ACCM)
Unic121 26 Purge Exh. Emergency T48-F3348, F3358 12-12-75 45 3-25-77 0
3-5-78 30 26 Purge Exh. Normal T48-F340, F341 12-12-75 0
3-25-77 0
3-6-78 0
26 Purge Exh. Hydrogen and Oxygen Analyzer P33-FOO2, F010 3-12-75 0
4-6-77 9
3-13-78 O
28F Hydrogen and Oxygen Analyzer P33-FOO3, FOli 12-10-75 0
,4-6-77 0
g 3-13-78 0
310 Hydrogen and Oxygen Analyzer P33-FOO4, F012 3-28-76 0
4-6-77 3
3-13-78 0
36 CRD Return C11-FOB 6,F087 4-1-76 81 5
36 CRD Return C11-FOB 3,F087 4-1-76 582 5
39A Cont. Spray Cooling E11-FOl6A, F021A 12-6-75 180 3-31-77 80 3-20-78 60 398 Cont. Spray Cooling E11-FOl68, F0218 4-9-76 0
4-29-77 0
3-4-78 0
40C-F Drywell Pneu. Outlet l
P70-FOO2, FOO3 12-14-75 O
l 4-5-77 36 1
3-16-78 0
I l
- bo ATTACHMENT 2 i
TYPE C Test Summary Penetration Test Test Test
__Uumher Desctiatinn Dain Inial (ACCM)
Unicisi 28A Recirc Loop Sample B31-F019, F020 12-9-75 0
4-5-77 O
3-23-78 0
42 Standby Liquid Control C41-FOO6, FOOB 3-28-76 100 3-28-77 178 3-21-78 18 42 Standby Liquid Control C41-FOO7, FOO8 12-8-75 750 3-30-77 0
3-21-78 18 46 Demin' Water P21-F353,F406 3-28-76 180 5-3-77 357 I
~4-12-78 400 45E Pres. Inst /ILRT Panel Manual Vlvs 4-16-78 0
4-8-77 21 4-3-78 0
45F ILRT verification flow i
T23-FOO4, FOO5 12-13-75 0
4-7-77 0
3-23-78 0
203 RCIC Pump Suction E51-FOO3, F031 11-24-75 0
3-31'77 4
3-15-78 0
204A RHR Pump Suction E11-F065A, FOO4A 3-30-76 467 1
3-24-77 13 3-23-78 488 2
2048 RHR Pump Suction E11-F065B, FOO4B 4-09-7E.
1030 5-12-77 3560 1
3-9-78 1050 2
N'
^
'p \\
ATTACHMENT 2 i
'l TYPE C Test Summary Penetration Test Test Test Numhgr Q21CCiEli2D Da12 12ial (ACCM)
Unici:1 204C RHR Pump Suction E11-F065C, FOO4C 3-30-76 1354 1
j 3-25-77 0
3-19-78 30 2
204D RHR Pump Suction E11-F065D, FOO4D 4-9-76 42 4-30-77 456 3-7-78 545 2
205 Vacuum Relief T48-F310, F328A 12-12-75 115 3-30-77 446 3-9-78 424 205 Emergency Nitrogen Makeup T48-F115, F116 12-13-75 0
4-9-77 5
3-9-78 10
(
205 Vacuum Relief T48-311, F3288 12-12-75 75 3-30-77 198 3-9-78 20 205 Emergency Nitrogen Makeup T48-F325, F327 12-13-75 8
4-9-77 22 3-9-78 10 206C,0 Torus Level Switch Vivs E41-F107, F108 2-10-75 0
4-6-77 78 3-11-78 O'
206A,B Torus Level Switch Vivs E41-F109, F110 2-10-75 0
4-6-77 18
[
3-12-78 0
207 HPCI Pump Suction E41-F042, F051 3-27-76 0
3-29-77 O
3-10-78 0
i
7 Il ATTACHMENT 2 ll TYPE C Test Summary Penetration Test Test Test Numher D2iCCiElinD Qa12 121C1 (ACCM)
N2idial 208A Core Spray Pump Suction E21-F019A, FOO1A 3-29-76 194 3-26-77 0
3-8-78 692 2088 Core Spray Pump Suction E21-F0198, FOO18 12-15-75 0
3-29-77 0
3-9-78 634 210A RHR Pump Min. Flow E11-FOO7A, F046A,C 12-9-75 800 4-1-77 20 1
3-20-78 1130 210B RHR Pump Min. Flow E11-FOO78, F046 B,0 4-9-76 81 5-6-77 520 1
3-13-78 26 1,6
(
(As found' greater than 2200 ACCM) 210A Jockey Pump Min Flow E21-F063A, F044A 12-8-75 0
4-1-77 0
3-8-78 0
2108 Jockey Pump Min Flow E21-F0638, F0448 12-8-75 0
4-1-77 0
3-9-78 0
210A RCIC Pump Min Flow E51-F019, F021 12-8-75 600 3-31-77 35-3-20-78 79 1,6 (As found greater than 2200 ACCM) 210B R.B. Floor Drain Pump Discharge G11-FOO7A, FOOBA 12-15-75 0
4-16-77 30 3-25-78 34 1,6 (As found greater than 2200 ACCM) 2108 HPCI Min Flow l
E41-F012, F046 12-8-75 181 4-1-77 247 3-10-78 600 j
l l
e ATTACHMENT 2 TYPE C Test Summary Penetration Test Test Test
__Uumhet___
Qasctialian Rain Inial (ACCM)
Unic121 210B R. B. Floor Drain
, Pump Discharge G11-FOO7B, FOOSB 12-15-75 0
4-16-77 0
3-28-78 150 210A RHR Test Line E11-F024A,F027A,F028A 12-18-75 1500 1
3-28-77 227 1
3-19-78 581 2108 RHR Test Line E11-F0248, F0278, F02SB 4-4-76 930 1
5-4-77 1188 1
3-31-78 400.
1,6 (As found greater than 2200 ACCM) 210A C.S. Pump Min Flow
/
E21-F010A, F031A 4-7-76 55 3-28-77 277 1
3-8-78 112 2108 C.S. Pump Min Flow E21-F0108, FO318 4-7-76 71 4-6-77 150 1
~
3-15-78 114 1,6 (As found greater than 2200 ACCM) 212 RCIC Turbine Exh.
E51-FOO1, F040 3-31-76 2050 1
3-25-77 481 1
3-16-78 2125 213 RCIC Turb. Exh. Drains E51-FOO2, F028 12-7-75 70 4-4477 196 3-15-78 10 l
214 HPCI Turbine Exh.
E41-F021, F049 4-13-76 1059 1
3-23-77 1969 1
3-22-78 2630 1,6 (As f ound grea ter than 2200 ACCM)
(
215 HPCI Turb. Exh. Drain E41-F'022, F040 12-7-75 0
4-2-77 22 3-12-78 0
l
ATTACHMENT 2 TYPE C Test Summary Penetration Test Test Test
__Uumher Descciation Dale Inial (ACCM)
U21cisl 217 Hydrogen and Oxygen Analyzer P33-FOO7, F015 12-10-75 0
4-5-77 12 3-13-78 0
220 Hydrogen and Oxygen Analyzer P33-FOO6, FO14 12-10-75 0
4-5-77 12 3-14-78 O
1,6 (As found greater than 2200 ACCM) 220 Purge Exhaust T48-F318, F326 12-11-75 95 3-25-77 0
3-9-78 O
220 Purge Exhaust Emergency T48-F332A, F333A 12-11-75 0
/
3-24-77 0
3-7-78 0
220 Purge Exhaust Emergency T48-F3328, F3338 12-11-75 0
3-24-77 0
3-5-78 0
220 Purge Exhaust Normal T48-F338, F339 12-11-75 0
3-25-77 0
3-9-78 42 220 Pressure Inst. ILRT Panel T23-Manual Vivs 4-14-76 0
4-7-77 0
4-3-78 0
221C RCIC Turb. Exh. Vac.
Relief E51-F105, F104 2-10-75 0
3-18-77
'348 3-17-78 260 1.o (As f ound grea ter tnan 2200 #CCMe
(
222A HPCI Turb Exh.
Vac. Relief E41-F111, F104 2-10-75 0
4-28-77 44 1
3-11-78 0
I TYPE C_IESI_Sudd6EY NOIES 1.
Valves required corrective maintenance prior to satisfactory LLRT.
2.
Test performed with waterfilled test volume pressurized with air at 1.10 Pa.
l 3.
Test perhormed with waterfilled test volume pressurized with air I
at Pa.
4.
MSIV failed to pass LLRT after repetitive corrective maintenance attempts.
NRC. permission was granted to operate with 821-FO22A and 821-F02SA taken out of service.
Unit operated at reduced power until valve was fixed during a subsequent scheduled outage in April 1976.
5.
CRD return isolation valves were deleted as part of the CRD return line modification.
6.
The recording of " As Found" Type B and C LLRT results contmenced with 1978 R/F Outage per a recent interpretation of 10CFR50 Appendix J.
/
7.
NRC permission granted to delete these valves from LLRT program as they do not serve a containment isolation function.
6
6II6CBdEbI_3 E/F QUI 6GE_E_1192H1 Pen.
MPL No./
Maint.
Nh Valre_Desctinilan Irae: Site danufaciutat Encintmed 7A B21-F022A/MSIV Inboard Globe-24" Atwood-Morrill Lapped seats 79 B22-F0288/MSIV Outboard Glo'be-24" Atwood-Morrill Lapped seats 8
821-F019/Cond. Drain Gate-3" Crane Clean seat ring 2108 E11-FOO78/RHR Pump Minimum Flow Gate-4" Walworth Replaced gate Repaired seat ring 138 E11-FO178/RHR Return Globe-24" Wm. Powell Replaced operator 210B E11-FOR48/RHR Test Line Globe-16" Wm. Powell Lapped seat rings 2108 E11-F0278/ Torus Spray Globe-6" Wm. Powell Lapped seat rings 2108 E11-F0288/RHR Test
. alworth Lapped seat rings Line.
Gate-24" W
210B E11-F0318/C.S. Pump Gate-3" Walworth Lapped seat rings Minimum Flow Rep 1' aced gate 214 E41-F049/HPCI Turbine Swing Wm. Fowell Replaced flapper, Exhaust Check-24" Lapped seat' ring 5 10 E51-FOOS/ Steam to RICI Gate-4" Crane Added vat king Turbine 210A E51-F019/RCIC Pump Min Globe-2" Velan Replaced Valve.
Flow Stem 221C E51-F105/RCIC Turbine Ga t e-a" Velan Lapped seat rings Exh. Vac. Br.
210B Gil-FOOSA/Rx. Bldg.
Swing Ck -
Drain Sump Pump Disch 2 1/2" Crane Cleaned seat 220 P33-F014/ Hydrogen &
Air Oper.-
Oxygen Analyzer 1"
Fisher AdJustee pac: tn; 98 E51-F012/RCIC Injection Gate-4"
' Crane Replaced motor
(
)
6II6CddENT b cnn111
(
R/F OUT6GE_1-(192Z1 Pen.
MPL No./
Maint.
Un.
Vaixe_Desctiatina Irae: Size danufaciutet Entintmed 7A B21-F022A/MSIV Inboard Globe-24" Atwcod and Stroke ad justmen t Morrill 8
821-F019/Cond. Drain Gate-3" Crane Torque switch adjustment Lapped seat, cleaned seat ring 10 E51-F025/ Steam to Diaph.-
Fisher Re9 laced 9askets RCIC Turbine Drain 1"
and lapped seats 10 E51-F026/ Steam to Diaph.-
Fisher Replaced gaskets RCIC Turbine Drain 1"
and lapped seats 212 E51-F040/RCIC Turbine Swing Ck-Powell Lapped flapper Exhctst 10" seat 11 E41-F028/HPCI Turbine Diaph.-
Fisher Replaced gaskets Exhaust Drain 1"
and lapped seats 11 E41-F029/HPCI Turbine Diaph.-
" Fisher Replaced gaskets Exhaust Drain 1"
and lapped seats 214 E41-F049/HPCI Turbine Swing Ch-Powell Replaced seat Exhaust 24" ring Lapped f lap p ei-seat seat 222A E41-F104/HPCI Turbine Gate-2"-
Velan Polished seats &
Exhaust Vac. Relief gates 26 T48-F319/ Purge Exh.
Butterfly-Fisher Replaced 0-Ring 18" gaskets 26 T48-F320/ Purge Ex'h.
Butterfly-Fisher Replaceo 0-Ring 18" gaskets 210A E21-F031A/ Core Spray Gate-3" Walworth Cleaned seats Pump Minimum Flow 2108 E21-F0318/ Core Spray Gate-3" Walwor th Lapped sco tc Pump Minimum Flow 210A E11-FOO7A/RHR Gate-4" Walworth Lapped seats Pump Minimum Flow l
P 6II6CUMENI_bcnn.'.11 8/F QUI 6GE_1_li3221 Pen.
MPL No./
Maint.
Una.
Mal 22_Q2ictiE11cn IXE2:Sila danufaClutat Entf2tm2d 2108 E11-FOO78/RHR Gate-4" Walworth Replaced gate Pump Minimum Flow 138 E11-F0158/RHR Return Gate-24" Crane Adjust torque switch, lapped seats l
138 E11-F0178/RHR Return Angle Powell Adjust torque Globe-switch, lapped 24" seats 210A E11-F027A/RHR Test Globe-6" Powell Cleaned seats Line 2108 E11-F02B8/RHR Test Globe-24" Walworth Repaired operator Line Cleaned gate and seat 2048 E11-FOO48/RHR Pump Gate-24" Walworth Lapped gate &
Suction seat, adjusted torque switch s
1 8 '
e s.
- _ = - _ -
7 i
i i
.aII6CBUENI_3_1 con 111 4
19IE_1Eicil_Qacca11on_Crcini Pen.
MPL No./
Maint.
Un.
Valve _Descciallan Irae: Sire Manut.
Encincmed 214 E41-F049/HPCI Turbine Swing Ck-Powell Maintenace revealed that Exhaust 20" operation of the valve had warped the disc.
The disc was inachined on the lathe and polished.
The body seat was also lapped.
214 E41-F021/HPCI Turbine Stop Ck-Atwood Inspection of the valve Exhaust 12" Morrill revealed that the stem l
clevis had broken from i
fatigue.
The clevis 4
was replaced and the seat and disc lapped.
212 E51-FOO1/RCIC Turbine Stop Ck-Powell Inspection revealed Exhaust 10" that the guide pin on the valve plug had broken off.
The pin l
was reweled to the plus
(
and body seat lapped.
212 E51-F040/RCIC Turbine Swing Ck-Powell Disc and seat ring woro Exhaust 10" lapped.
13A.E11-F015A/RHR Return Gate-24" Crane Reset torque switch.
13A E11-FO17A/RHR Return Angle -
Powell Reset torque switch.
Globe-24" 204A E11-FO65A/RHR Suction Butterfly-Fisher Reset stops on Robotprm 24" actuator.
204A E11-FOO4A/RHR Suction Gate-24" Walworth Tightened valve packing.
204C E11-F065C/RHR Suction Butterfly-Fisher Reset stops on Robotarm 24" actuator.
204C E11-FOO4C/RHR Suction Gate-24" Walworth Tightened valve
- packing, 2108 E11-F0248/RHR Test Globe-16" Powell Reset torque swttches.
Line t
7 6II6Cdt3ENT_ i (cQDI.11 1976 (Finsi_QERCA1 QD_CrE121 Pen.
MPL No./
Maint.
U22 MalER_QE1EC.iEli20 IXERISHS E! angi.
Perfotmg31 2108 E11-F0278/RHR Test Globe-6" Powell Reset torque swi tchec.
Line 2108 E11-F0288/RHR Test Grte-24" Walworth Lapped seat.and wedge.
Line 7A B21-F022A/MSIV Angle Extensive lapping performed on Globe-24" the valve body seat.
The valve poppet was machined on the lathe several times and the seat on the main poppet was finally replaced and lapped.
~
(
S I
~
1 j
eIIeCBdENI_3_idan111 l
t-1925_(Eicsi_Qaetalinn_CXc121 i
Pen.
MPL No./
Maint.
Un.
Valre_Desctiallan Irae:Siin,danuf.
Entfs.cmed 7A B21-F022A/MSIV Globe-24" Atwood Lapped poppet Morrill
. extensively.
70 821-F02BD/MSIV Globe-24" Atwood Lapped body seat, Morrill checked trueness of stem, makchined inner poppet, checked main Poppet for true seat.
210A E11-F028A/RHR Test Gate-24" Walworth Lapped defect out of Line seat surface.
26 T48-F319/ Purse Exhaust Butterfly-Fisher Removed and adjusted 18" butterfly valve seats.
26 T48-F320/ Purge Exhaust Butterfly-Fisher Reinoved and adjusted 18" butterfly valve seats.
e P
J 1
- l
.1 l
i l
l
1xe a_--
-u
--e 9e'M a
S 9
-m 1
A a
BL A a
A, 9
e i
4 APPENDIX C FAILED TEST REPORT - TYPE A TEST c
e d
4
INTRODUCTION Section V.B.3. of 10CFR50, Appendix J requires a summary report of Type A test leakage rate results that failed to meet test acceptance criteria, which includes an analysis and interpretation of test data, the instrumentation system error analysis and a description of con-tainment conditions causing test failure.
The following information is reported in response to this requirement.
DISCUSSION The initial Type A test f ailed because of excessive leakage through two separate leaku, the drywell head flange and an open drain valve in the demineralized water system inside containment, between the containment penetration and the inboard containment isolation valve.
The drywell head leakage was the result of insufficient torque ap-plied to the head bolts during installation just prior to the start of the Type A test.
A Type B test, indicating no leakage, had been performed following drywell head installation and prior to contain-ment pressurization for the Type A test.
The drywell head leak was detected during an external containment leak survey performed after initially reaching test pressure in the containment.
The leakage was excessive enough to cause containment pressure to decay at a 1 psi per hour rate.
No leakage rate calculations were performed due to the obvious excessive leakage and the high pressure decay rate.
No other leaks were detected during this initial survey.
The containment was depressurized to atmospheric pressure and the head bolts were detensioned.
The drywell head bolts were then tensioned por the drywell head ins tallation procedure, HNP-1-6705.
The pro-cedure included applied torque measurements and head flange gap measurements.
A Type B test was again performed,. indicating no leakage following the head bolt tensioning procedure.
The contain-ment was repressurized to test pressure anc no leakage was detected through the drywell head flange.
The open drain valve in the demineralized water system was not shown on the system P&ID and resultantly was not included in the system lineup for the Type A test.
The valve would have been shown closed on the valve lineup and therefore positioned and tagged ac-cordingly.
The actual valve lineup which contributed to initial Type A test failure is shown in Sketch 1 below.
- 3F407 46
>1 N
^/
L.C.
L.C.
M C*
ORC \\g}RC F353 F372 F406 F343
[F3002
- Vent to atmosphere Sketch 1 C-1
-=. --
=
i c
The system containment isolation valves are locked closed valves P406 inside containment rnd F353 outside containment.
The system was drained inboard of F353 and vented to containment and outside atmospheres through valves F343 and F407 respectively.
This con-servative lineup, which includes the use of only one (F406) of the two available containment isolation valves for containment isolation, was used for the Type A test to preclude draining the external de-mineralized water system.
Drain valve F3002 was the open valve which provided the leakage path from containment atmosphere through the penetration and valve F372 to outside atmosphere through external system vent at valve F407.
The leakage was stopped.by closing valve F407.
The final lineup with F407 closed included the use of F353 as the only isolation barrier but did not provide an external system vent.
The leakage rate from a Type C test performed on the pene-tration after Type A test completion, with valve F3002 closed, was therefore added to the successful Type A test results.
This leakage rate was 800 ACCM at a test pressure of 59 psig or 0.016% per day.
The Type A test data and data analysis showing the excessive leakage rate prior to finding and stopping the leak are shown in Table C-1.
Valve F3002 has been added to system drawings to prevent a similar ruture occurrence.
The instrumentation system error analysis is based on the Instru-4 I
montation Selection Guide (ISG) formula from ANS N274, Draft No.
2, Revision 2 - May 15, 1973 " Containment System Leakage Testing i
Raquirements".
The formula is:
1/2 py)2-2 e
2 e
ISG = + 2400 r
7 2 (p) 2 (7) 2( p
+
+
i The symbols are defined in Appendix G of ANS N274.
Based on the followine test conditions:
t Test duration:
6.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> Containment tetal pressure:
73.7 psia containnent wacar vapor pressure:
0.5j6 psia Containmcnt temperature:
550 R h
The error acacciated with the instrumentation system, ISG, is
+ 0.037% per day.
A::S N274 requires that the ISG shall not exceed i
D.25 La.
The comparison below shows the ISG is much less than the l
AMS N274 critorion.
4 ISG
=
- 0.037 i per day La
= T.2~t per day 0.25 La - 0.30 t pc
'ay C-2 i
c _._.,
As stated in ANS N274 the ISG forrtula is not based on a statistical analysis of the actual leakage rate data and is not added to the leakage rate value.
The ISG value is used only for instrument selection and loss of sensor criteria.
It is reported per the speci-fic requirements of 10CFR50, Appendix J, Section V.B.3.
C-3
4 l
?
l f
I l
TA3LE C-1 (Sheet 1) i r
i.
I "UMMARY LATA 1
E.I. HATCH UNIT 1 ILRT 59 PSIG ALMAX = 1.200 a
i TIME DATE TEMP PRESSUFE VGLUMc 530 410 548.908 73.2451 257.087.
545 410 548.757 73.2244 257077.
600 410 548.666 73.2084 257067.
615 410 548.596 73.1957 257056.
I 631 410 548.562 73.1808 157046.
646 410 548.496 7?.1687 257036.
I Tis 410 548.598 73.1498 257015.
730 410 548.459 73.1410 257005.
746 410 548.464 73.1339 256994 800 410 548.410 73.1251 256934 816 410 548.426 73.1208 256974 i
4 830 410 548.463 73.1136 256963.
545 410 548.498 73.1073 25695?.
900 410 548.460 73.1034 256943.
915 410 548.569 73.0962 256932.
931 410 548.497 73.0947 256922.
946 410 548.497 73.0921 256912.
.i 1001 410 548.593 73.0874
- 256901, 1015 410 548.759 73.0841 256891.
1030 410 548.564 73.0829 256581.
1045 410 549.011 73.0521 256570.
1100 410 548.844 73.0815 256660.
1115 410 548.917 73.0788 256650.
. 1130 410 548.963 73.0797 256339.
1145 410 549.029 73.0788 256229.
1200 410 549.128 73.0773
- 256G19, i
i 1215 410 549.170 73.0802 25630s.
1250 410 549.236 73.0810 256798.
1 l
r w
f I
l l
k
.. ~,,
, ~.
c-n. -.,,,,,- --- + -
TABLE C-1 (Sheet 2) 1245 410 '54;.2.346 73.0813 256788.
1300 410 549.409 73.0834 256777.
1316 410 549.532 73.0874 256767.
1331 410 549.515 73.0890 256757.
1 1346 410 549.640 73.0920 256746.
1400 410 549.651 73.0964 256736.
1415 410 549.786 73.0995 256726.
1430 410 549.855 73.1036 256715.
1445 410 549.896 73.1083 256705.
1500 410 549.960 73.1138 256695.
1515 410 550.040 73.1159 256688.
1530 410 550.210 73.1195 256681.
1545 410 550.302 73.1254 256674 1600 410 550.432 73.1297 256668.
161" 410 550.504 73.1552 256661.
1630 410 550.554 73.1416 256654 1645 410 550.610 73.1489 256647.
1700 410 550.589 73.1271 256733.
1715 410 551.554 73.0869 256819.
1730 410 551.395 73.0458 256905.
1745 410 551.057 73.0218 256892.
1800 410 551.082 73.0049 256879.
1815 410 550.988 72.9961 256866.
i 1831 410 550.786 72.99~6 256453.
1845 410 550.688 72.9914 256840.
1900 410 550.741 72.9903 256827.
1916 410 550.801 72.9889 256814 i
1936 410 550.872 72.9872 256802.
l 1945 410 550.844 72.9910 256789.
2000 410 550.910 72.9946 256776.
2015 410 5500900 72.9972 256764 2030 410 551.172 73.0023 256751.
2046 410 551.234 73.0072
- 256738, 2100 410 550.007 73.0208 256725.
E.I. HATCH Uti!T 1 ILPT 59 PSIG
'I'A3LF C-1 (Sheet 3)
TPEND FEPCPT LEAKAGE PATE3 (WEIGHT PEPCENT/ DAY)
BASED ON TOTAL-TIME CALCULATIONS TIME AND DATE AT OTAPT CF TEST:
530 0410 ELAPIED TIME:
15.50 HOUP!
NO. DATA ELAP!ED MEAN MEA 5UFED CALCULATED CHG IN CALC LeP UPFER 95%
POINT!
TIME LEAKAGE PATE LEAKAGE PATE FACM LAST POINT CCNF LEVEL 10 2.50 0.952 1.272 1.732 11 2.77 0.966 1.263
-0.003 1.723 12 3.00 0.995 1.276
- 0. 01 P.
1.703 13 3.25 1.005 1.300 0.024 1.707 14 3.50 1.016 1.299
-0.001 1.701 15 3.75 1.036 1.331 0.032 1.711 16 4.02 1.044 1.328
-0.003 1.709 17 4.27 1.050 1.317
-0.011 1.702 13 4.52 1.060 1.325 0.008 1.699 19 4.75 1.077 1.355 0.030 1.714 20 5.00 1.094 1.391 0.036 1.736 21 5.25 1.114 1.434 0.044 1.769 22 5.50 1.123 1.440 0.006 1.772 23 5.75 1.133 1.450 0.009 1.777 24 6.00 1.141 1.456 0.006 1.780 25 6.25 1.150 1.462 0.006 1.7S4 26 6.50 1.159 1.473 0.010 1.739 27 6.75 1.166 1.479 0.006 1.793 29 7.00 1.173 1.453 0.005 1.795 29 7.25 1.181 1.491 0.008 1.800 30 7.50 1.188 1.497 0.006 1.803 31 7.77 1.195 1.505 0.008 1.808 32
- 8. 02 1.200 1.505
-0.000 1.809 33 S.27 1.205 1.507 0.003 1.811 l
34 8.50 1.210 1.504
-0,003 1.SO9 l
35 8.75 1.214 1.505 0.001 1.310 l
36 9.00 1.218 1.505
-0.000 1.810 37 9.25 1.221 1.502
-0.003 1.809 33 9.50 1.224 1.498
-0,004 1.307 39 9.75 1.227 1.494
-0.004 1.305 40 10.00 1.230 1.493
-0.000 1.304 41 10.25 1.233 1.492
-0.001 1.802 42 10.50 1.236 1.492 0.000 1.801 43 10.75 1.239 1.491
-0.001 1.799 44 11.00 1.241 1.467
-0.004 1.796 45 11.25 1.242 1.482
-0.005 1.793 i
46 11.50 1.243 1.473
-0,009 1.783 1
47 11.75 1.251 1.496 0.023 1.810 48 12.00 1.258 1.513 0.017 1.824 49 12.25 1.2i3 1.523 0.010 1.530 50 12.50 1.26?
1.514 0.011 1.538 51 12.75 1.274 1.542 0.005 1.842 52 13.02 1.277 1.544 0.002 1.543 53 13.25 1.279 1.541
-0.003 1.541 54 12.50 1.251 1.519
-0.001 1.840 55 13.77 1.293 1.539
-0.001 1.839 56 14.10 1.265 1.540 0.001 1.640 57 14.25 1.lis 1.513
-0.007 1.834 53 14.50 1.238 1.510
-0.003 1.822 59 14.75 1.239 1.526
-0.005 1.?29 60 15.00 1.290 1.525
-0.001 1.823 61 15.27 1.291 1.524
-0.001 1.826 62 15.50 1.257 1.4??
-0.026 1.S27
t TABLE C-1 (Sheet 4)
E.I. HATCH UNIT 1 ILRT 59 PSIG LEAKAGE PATE G:EIGHT PERCENT / DAY)
EASED ON TOTAL TIME CALCULATIONS TIME AND DATE AT START OF TEST:
530 0410 ELAPSED TIME:
15.50 HOUPS TIME TEMP.
PPESCUFE MEASUPED (R)
(PS I A)
LEAKAGE PATE 530 548.908 73.2451 545 548.757 73.2244 0.446 600 548.666 73.2084 0.662 615 548.596 73.1927 0.857 631 548.562 73.1808 0.961 646 548.496 73.1687 0.930 716 548.598 73.1498 1.381 730 548.459 73.1410 1.107 746 548.464 73.1339 1.134 800 548.410 73.1251 1.087 816 548.426 73.1208 1.092 830 548.463 73.1136 1.174 845 548.498 73.1073 1.223 900 548.460 73.1034 1.151 915 548.569 73.0962 1.292 931 548.497 73.0947 1.163 946 548.497 73.0921 1.137 1001 548.593 73.0874 1.223 1015 548.759 73.0841 1.358 1030 548.864 73.0829 1.408 1045 549.011 73.0821 1.488 1100 548.844 73.0815 1.308 1115 548.917 73.0788 1.338 1130 548.963 73.0797 1.328 l
1145 549.029 73.0788 1.341 1200 549.128 73.0773 1.377 1215 549.170 73.0802 1.355 1230 549.236 73.0810 1.357 1245 549.346 73.0213 1.387 1300 549.409 73.0834 1.382
=.
TABLE C-1 (Sheet 5) 1316 549.532 73.0874 1.399 1331 549.515 73.0890 1.351 1346 549.640 73.0920 1.376 1400 549.651 73.0964 1.338 1415 549.786 73.0995 1.366 1430 549.855 73.1036 1.358 1445 549.896 73.1083 1.334 1500 549.960 73.1138 1.319 1515 550.040 73.1159 1.320 1530 550.210 73.1195 1.356 1545 550.302 73.125*.
1.349 1600 550.432 73.1297 1.363 1615 550.504 73.1352 1.350 1630 550.554 73.1416 1.32G 1645 550.610 73.1489 1.302 1700 550.589 73.1271 1.258 1715 551.554 73.0869 1.630 1730 551.395 73.0458 1.534 1745 551.057 73.0218 1.507 1800 551.082 73.0049 1.539
(
1815 550.988 72.9931 1.504 1831 550.786 72.9936 1.426 1845 550.688 72.9914 1.384 1900 550.741 72.9903 1.387 1916 55.801 72.9589 1.391 1936 550.872 72.9872 1.391 1945 550.844 72.9910 1.368 2000 550.910 72.9946 1.364 2015 550.900 72.9972 1.340 2030 551.172 73.0023 1.393 2046 551.234 73.0G72 1.384 2100 550.007 73.0208 1.000 r1EArt CF MEASURED LEAK AGE PATE:
1.287
=
STD. DEVTATIOri 0F MEAIUFED LEAKAGE PATES 0.202
=
r!AXIMUM ALLCidABLE LEAKAGE PATE 1.200
=
75 *: CF MAXIMUrd ALLCLABLE LEAKAGE FATE 0.900
=
THE CALCULATED LEAKAGE FATE 1.497
=
THE CALC. LEAK AGE FATE AT 95% CCriF1:ENCE LEVEL 1.497 0.330
=
.=.
('
TABI.E C-1 (Sheet 6)
E.I. HATCH UNIT 1 ILRT 59 PSIG LEAKAGE RATE 04EIGHT PEPCENT/ DAY)
MASS POINT ANALY3IS TIME AND DATE AT OTART OF TEST:
530 0410 ELAPSED TIME:
15.50 HCURO TIME TEMP PRESSUPE CTMT. AIR MASS LOSS TOT. AVG. MASO W
(PSIA)
MASS (LBM)
(LBM)
LDSS (LBM/HR) 5?0 548,908 73.2451 92595 545 548.757 73.2244 92591 4.3 17.2 600 548.666 73.2084 92582 8.5 25.6 615 548.596 73.1927 92570 12.0 33.0 631 548.562 73.1808 92557.
12.9 37.1 646 548.496 73.1687 92549 7.8 35.9 Tis 548.598 73.1498 92501 48.7 53.3 730 548.459 73.1410 92510
-8.7 42.7
(
746 548.464 73.1339 92496 13.8 43.8 S00 548.410 73.1251 92490 5.6 41.9 816 548.426 73.1208 92473 11.7 42.1 830 548.463 73.1136 92459 19.3 45.3 S45 548.498 73.1073 92442 17.5 47.2 900 548.460 73.1034 92439 2.1 44,4-915 548.569 73.0962 92408 31.4 49.8 931 548.497 73.0947 92415
-6.6 44.9 946 548.497 73.0921 92408 6.?
43.9 1001 548.593 73.0874 92382 26.1 47.2 1015 548.759 73.0841 92346 35.7 52.4 1030 548.364 73.0829 92223 22.8 54.3 1045 549.011 73.0821 92294 29.7 57.4 1100 548.844 73.0815 92317
-23.7 50.5 1115 548.917 73.0788 92298 19.3 51.6 l
1130 548.963 73.0797 92287 10.5 51.2 1145 549.029 73.0738 92272 15.8 51.7 1200 549,129 73.0773 92250 22.1 53.1 1215 549.170 73.0802 92242 7.3 52.3 1230 549.2:16 73.0810 92229 13.7 52.3 1245 549.346 73.0813 92207 21.7 53.5 1300 549.409 73.083a 92195 11.9 53.3 1316 549.522 73.0874 92176 19.2 54.O I
1331 549.515 73.0890 92177
-1.3 52.1
(
t i
f' TABLE C-1 (Sheet 7) i 1346 549.640 73.0920 92156 21.1 53.1 1400 549.651 73.0964 92156
-0.1 51.6 1415 549.786 73.0995 92134 22.3 52.7 1430 549.855 73.1036 92123 10.3 52.4 1445 549.896 73.1083 92119 4.5 51.5 1500 549.960 73.1138 92111 7.4 50.9 1515 550.040 73.1159 92098 13.3 50.9 i
1530 550.210 73.1195 92072 26.4 52.3 1545 550.302 73.1254 92061 10.5 52.1 1600 550.432 73.1297 92043 18.5 52.6 1615 550.504 73.1352 92035 7.6 52.1 1630 550.554 73.1416 92012 2.8 51.1 1645 550.610 73.1489 92030 2.7 50.2 1700 550.589 73.1271 92037
-6.9 48.5 1715 551.554 73.0869 91856 180.8 62.9 1730 551.395 73.0458 91861
-5.6 61.1 1745 551.057 73.0218 91883-
-21.5 58.1 1800 551.082 73.0049 91853 30.1 59.4 1815 550.988 72.9981 91855
-2.5 58.0 1831 550.786 72.9936 91879
-23.4 55.0
(
845 550.688 72.9914 91888
-8.9 53.4 1900 550.741 72.9903 91873 14.9 53.5 1916 550.801 72.9889 91856 16.4 53.7 1936 550.872 72.9872 91838 18.3 53.7 1945 550.844 72.9910 91843
-4.8 52.8 2000 550.910 72.9946 91832 11.1 52.6 2015 550.900 72.9972 91832
-0.6 51.7 2030 551.172 73.0023 9178?
43.6 53.7 2046 551.234 73.0072 91780 8.8 53.4 2100 550.007 73.0208 91997
-217.2 38.6 FFEE AIR VOLUf1E USED ':MILLICri? CF CU. FT.)
0.258
=
REGREI510tt wIttE 92610 IfiTERCEP1 (LBM)
=
- -54.3 SLDPE (LEiWHP)
=
t MAXIMUM ALLOldAFLE LEAK AGE F ATE 1.200
=
75 *. OF MA:-;IMUM ALLCWAELE LEAKAGE FATE 0.900
=
1.407 THE CALCULATED LEAKAGE FATE
=
i 1.407 e 0.060 THE CALC. LEAkAG7 PATE AT 95% CCriFIDEliCE LEVEL
=
CTNT. FPEE AIP VCLUME AT TIME 2100 =
256725.
l
(
l
_ _ _ _ _ _. _