ML20058P004
| ML20058P004 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 09/30/1993 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20058P003 | List: |
| References | |
| NUDOCS 9312220359 | |
| Download: ML20058P004 (105) | |
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. . I l GENERAL PUBLIC UTILITIES NUCLEAR CORPORATION l Three Mile Island Nuclear Station !
Unit I l l i l
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I REACTOR CONTAINMENT BUILDING INTEGRATEL) i i
LEAKAGE RATE TEST REPORT l
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September, 1993 1
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t ILRT Sections Prepared By: h AA d Date: t t 4- 11 LLRT Sections Prepared By: AA M Date: n-2 4-il Reviewed By: b . = - - /W Date: h '2e 73 Approved By: '
Date: /1 ' b YJ l
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9312220359 931216 P:
, PDR P
ADOCK 05000289 f4 PDR M :
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TABLE OF CONTENTS
1.0 INTRODUCTION
AND PURPOSE Page1 2.0 GENERAL ANDTECHNICAL DATA Pace 2 l
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l 2.1 Genem! Data 2.2 Technical Data l
I 3.0 TESTINSTRUMENTATION Page 3 3.1 Integrated Leakage Rate Measurement System 3.2 Measurement System Arrangement 4.0 TEST SUMM ARY Page 6 j 4.1 Test Summary Time-Line l 4.2 Edited Test Log !
4.3 Type A Test Results Summary 4.4 Verification Test Results Summary ;
5.0. TEST DESCRIPTION Page 9 6.0 TYPE B AND C 1 OCAL LEAK AGE RATE TEST RESULTS Page 11 6.1 Local Leak Rate Test Program 6.2 Acceptance Criteria 7.0 ANALYSIS AND INTERPRETATION Page 12 7.1. Summary of Type B and C Penalties 7.2 Volume Change Corrections ,
7.3 ILRT Results l S.0 APPENDICES APPENDIX A STABILIZATION PHASE DATA Page 16 APPENDlX B ILRTTEST DATA AND PLOTS Page 28 APPENDIX C VERIFICATION TEST DATA AND PLOTS Page 45 APPENDIX DILRT COMPUTER PROGRAM DESCRIPTION Page 56 APPENDIX E SENSOR LOCATIONS Page 60 APPENDIX F INSTRUMENTATION SELECTION GUIDE VALUE Page 65 APPENDIX G LOCAL LEAKAGE R ATE TEST SUMMARIES Page 73 l
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1.0 INTRODUCTION
AND PURPOSE The Reactor Building Integrated Leakage Rate " Type A" Test is performed to demonstrate that leakage through the primary reactor containment systems and components penetrating primary reactor containment at the design basis accident pressure of 50.6 psig (Pa) does not exceed the allowable leakage rate specified in the Three Mile Island Nuclear Station Unit 1 Technical Specifications. The allowable leakage is defined by the design basis accident, applied in the safety analysis, in accordance with the exposure guidelines specified by 10 CFR 100.
The purpose of this report is to provide information pertinent to the activities related to the preparation, test performance, and reporting of the Three Mile Island Nuclear Station Unit 1 (TMI-1) Integrated Leakage Rate Test (ILRT). The maximum allowable integrated leakage rate for TMI-l is 0.10 percent by weight of the mass of air contained within the R.B. when pressurized to 50.6 psig per day (La). The measured leakage rate (Lam) at the upper 95 percent confidence levelis required by 10 CFR 50 Appendix J to be less than 75 percent of the maximum allowable leakage rate. In addition,10 CFR 50 Appendix J requires that the accuracy of the ILRT be verified by a supplemental test. The supplemental test is acceptable if the difference between the ILRT data and the supplemental test data is j within 25 percent of La.
The successful periodic Type A and verification tests were performed during the period from September 15,1993 to September 16,1993, according to the requirements of the l
Three Mile Island Nuclear Station Unit 1 Technical Specifications 4.4.1.1, TMI-l Surveillance Procedure 1303-6.1, and 10CFR50, Appendix J. The test method used was the Absolute Method as described in " ANSI N45.4-1972, " Leakage-Rate Testing of Containment Structures for Nuclear Reactors". The supplemental test was conducted by superimposing a known leakage rate on the existing containment building leakage rate.
Leakage rates were calculated using the Mass Point data analysis technique as described in ANSI /ANS-56.8-1987," Containment System Leakage Testing Requirements" The test results are reported in accordance with the requirements of 10CFR50, Appendix J, Section V.B.3.
The ILRT was performed at the beginning of the 10R refueling outage prior to any repairs or adjustments to containment isolation barriers. The duration of the ILRT was 24.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />. The 95 percent Upper Confidence Level (UCL) leakage rate was determined to be 0.0707 percent by weight per day. The supplemental test was conducted for a period of 4.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> and demonstrated a difference between the ILRT data and the supplemental test data of 19.9 percent of La. Therefore, the ILRT and supplemental test met the acceptance criteria of 10 CFR 50 Appendix J.
Most of the Local Leak Rate Testing (LLRT) was performed just prior to performing the ILRT.
About two thirds of the LLRT was performed during the ILRT pressurization and stabilization periods.
2.0 GENERAL ANDTECHNICALDATA 2,1 General Data Owner General Public Utilities Nuclear Corporation Docket No.: 50-289 Plant Three Mile Island Nuclear Station Unit 1 Location Three Mile Island, near the East Shore of the Susquehanna River in Dauphin County, Pennsylvania Containment Type Prestressed, post-tensioned reinforced concrete ,
composed of cylindrical walls, a flat foundation mat and a shallow dome roof with a 3/8 inch carbon steel liner NSSS Supplier. Type Babcock & Wilcox PWR Date Test Completed September 16,1993 2.2 Technical Data !
Containment Net Free Volume 2 x 106 cubic feet Design Pressure 55.0 psig l
Design Temperature 281oF l Calculated Peak l Accident Pressure 50.6 psig Calculated Peak l Accident Temperature 289o F l
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3.0 TESTINSTRUMENTATION The following is a description of the test instruments which comprise the Integrated Leakage Rate Measurement System. The accuracy, repeatability, and sensitivity of the instrumentation meets the requirements of ANSl/ANS-56.8-1987, " Containment System Leakage Testing Requirements".
3.1 Integrated Leakage Rate Measurement System :
- 1. Absolute Pressure i
Quantity 2 ,
Manufacturer Volumetrics Type Precision Pressure Gauge Model PPM -1000 :
i Range 0 - 100 psia Accumcy 0.015% reading plus i 0.002% Full Scale ( 0.0119 psia) l Repeatability 0.001% Full Scale 0.001 psi Resolution 0.008% Full Scale '
0.008 psi Sensor Sensitivity Error 0.001 % Full Scale I l
l 0.001 psi l
- 2. Drybulb Temperature Quantity 24 Manufacturer Yellow Spring Instruments l Type 3-wire 100 ohm platinum resistance temperature detectors (RTDs) !
l Range 60 - 1200 F l Accuracy i 0.1o F j Sensor Sensitivity Error 0.01o F 1
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- 3. Dewpoint Temperature Quantity 10 l l
l Manufacturer Foxboro Type Lithium Chloride Deweell using a 3-wire 100 ohm RTD,Model BD154WB l
Range 40 - 1000 F dewpoint i
Accuracy il.5o F l Sensor Sensitivity Enor 0.10 F
- 4. Verification Flow Quantity 2 (1 primary, I backup) :
i Manufactun r Volumetrics t
Type Thennal mass flow Model FM10 l Range 0 - 15 scfm Accuracy 1% full scale !
Sensitivity i 0.5% full scale
- 5. Readout Device l
Quantity 1
1 Manufacturer Volumetrics Type Model A-100 with sensor ,
conditioning cards :
RTD Repeatability 0.01o F
. Deweell Repeatability 0.0lo F i
l Resolution Drybulb Temp 0.001o F Dewpoint Temp 0.001o F 4
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l 3.2 Measurement System Arrangement !
The measurement system arrangement as installed for the ILRT is shown in Appendix E. The Instrumentation Selection Guide Value is calculated as shown in Appendix F. Allinstrumentation performed satisfactorily with the exception of two i dewcells. Dewcells 1 and 10 exhibited excessive fluctuations which were not evident in the other 8 deweells. The readings from these two deweells were reccrded, however they were not used in the calculations for the measured leakage rate.
i The 24 RTD and 10 dewcell sensors am located at five different levels within the l
reactor containment building. Within each le.el, the sensors are located within four different quadrants. This provides more than adequate coverage of the containment and ensures that the sensors are recording representative temperatures in all areas of .
the containment. The test readings from these sensors show a fairly uniform i temperature distribution from the basement elevation at 287 feet to the dome area elevation at 437 feet. The results from this test as well as previous ILRTs at TMI Unit I have shown no temperature stratification because:
- a. There are very few cubicles inside the Reactor Building
- b. There is free communication between all levels of the building and also between cubicles and the Reactor Building. :
- c. The air inside the Reactor Building is recirculated by the installed ventilation system.
- d. Equipment in the Reactor Building, with the exception of the ventilation system fans and required instrumentation, wa'; de-energized during the test.
This eliminated any heat producing equipment in the building which could '
cause local hot spots.
Due to the uniform temperature Qs ibution, all operable RTD's and dewcells wem assigned equal weighting factors.
i After the ILRT was completed GPUN performed a temperature survey and ,
l evaluated the results by EER 93-0434 and concluded relatively uniform temperature distribution.
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4.0 TEST
SUMMARY
4.1 Test Summary Time-Line i
Phase Time Frame Duration 1 1
Pressurization From: 1430 on 9/14/93 23.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> '
To: 1345 on 9/15/93 Stabilization From: 1345 on 9/15/93 4.50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> i To: 1815 on 9/15/93 ILRT Test From: 1830 on 9/15/93 24.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> To: 1845 on 9/16/93 Verification From: 1900 on 9/16/93 4.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> Test To: 2315 on 9/16/93 ;
Depressurization From: 0010 on 9/17/93 9.83 hours9.606481e-4 days <br />0.0231 hours <br />1.372354e-4 weeks <br />3.15815e-5 months <br /> ,
To: 1000 on 9/17/93 i 4.2 Edited Test leg '
September 14.1993 ;
1430 Hr. Pressurization of containment started.
1815 Hr. Pressurization rate approx. 2.4 psi /hr.
1935 Hr. Secured pressurization for reactor building entry.
Containment pressure is 27 psia (approx.12.3 psig).
1945 Hr. During inside RB inspection, a steady stream of water was noted from RCP coolers. Operations determined that this was not a problem.
l 1950 Hr. Pressurization restarted. ;
Scotember 15.1993 0500 Hr. Pressurization rate approx. 2.3 psi /hr.
0530 Hr. One compressor was shut down for repairs.
Pressurization rate dropped to approx.1.8 psi /hr.
i 0801 Hr. Compressor repaired and restarted. l Pressurizationrate back to approx. 2.4 psi /hr.
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l September 15.1993 0805 Hr. Industrial Cooler System shut down. Reactor Building recirculation fans will continue to run wit:.out cooling water for the ILRT.
I110 Hr. Target pressure is 51.6 psig. Barometric pressure is approx.14.58 psia.
l l 1158 Hr. One compressor shutdown at containment pressure of 64.58 psia.
l i 1218 Hr. Two additional compressors shutdown at containment pressure of 65.38 psia.
l 1335 Hr. Fourth compressor shutdown at containment
! pressure of 65.98 psia.
1345 Hr. Isolated pressurization line and secured last compressor. Started stabilization period.
Containment pressure at 66.0345 psia (51.4545 psig).
1515 Hr. Temperature stabilization criteria met.
1830 Hr. Start of Type A test. Containment pressure at 66.1000 psia (51.52 psig).
l Sentember 16.1993 1845 Hr. Mass Point UCL Lom calculated to be 0.0707 wt9/ day. Calculated leakage within 0.75 L . End of test. Test duration is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and 15 minutes.
1850 Hr. Initiated verification flow. Lo = 6.03 SCFM.
1900 Hr. Started verification test.
2315 Hr. Completed veriDeation test. Le = 0.1487 wt7c/ day.
l September 17.1993 0010 Hr. Started depressurization.
1000 Hr. Depressurization of containment completed.
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i 4.3 Type A Test Results Summary <
Test Method Absolute .
Test Pressure 51.5 psig i
Mass Point Calculated .
Leakage Rate (L.)
- 0.0684 % wt./ day l t
95 % Upper Confidence Levelleakage Rate (UCL)
- 0.0707 % wt./ day l
- Does not include penalties for nonstandard alignments and water level changes ;
(Refer to Section 7.0)
The 95 % Upper Confidence Level leakage rate was below the 10 CFR 50 ,
Appendix J criteria of 0.75 L, 4.4 Verification Test Results Summary Mass Point Calculated Leakage Rate (L ) 0.0684 % wt./ day imposed Leak (Lo) 0.1002 % wt./ day ,
(6.03 SCFM)
Lower Limit:
Lo + L. - 0.25 La 0.1436 % wt./ day Composite Leakage (Lc) 0.1487 % wtJday ,
(Le = L _ + Lo )h [
t Upper Limit:
Lo + L. + 0.25 L, 0.1936 % wt./ day l OThe computer software determines a composite leakage rate (Lc) based on the sum of the current containment building leakage rate (L._ ) and the superimposed :
leakage rate (Lo). The composite leakage rate must be within the Appendix 3 l l Supplemental (Verification) Test Acceptance Criteria of 0.25 L . The criteria is ,
mathematically represented by the upper and lower limits listed above. i The composite leakage rate (Lc) of 0.1487 wt.9/ day was within the 10 CFR 50 Appendix J criteria of 0.25 La.
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i 5.0. TEST DESCRIPTION Prior to containment pressurization at 1430, on September 14,1993, site personnel were engaged in prerequisite activities for the conduct of the ILRT. These activities included ILRT procedure review and finalization, system valve lineups, ILRT computer program checkout and linkup to the Volumetrics Data Acquisition System, and ILRTinstrumentation calibration, installation and operability checks. The ILRT test procedure was reviewed '
against the requirements of the TMI-1 Technical Specifications; 10CFR50, Appendix J; and ANSI /ANS-56.8-1987.
T The ILRT instrumentation was calibrated prior to the ILRT as recommended by ANSI N45.4-1972, Sections 6.2 and 6.3. Final ILRT instrumentation operability checks and in-situ checks, as specified in ANSI /ANS-56.8-1987, Section 4.2.3.1. were performed in ;
accordance with TMI-I Maintenance Procedure MP 1430-Y-23 to ensure that all i instrumentation was operating correctly. Calibration records for the ILRT instrumentation system components are retained at the plant.
The Three Mile island Unit 1 ILRT (Integrated Leak Rate Test) was conducted by General t Public Utilities Nuclear Corporation personnel and others, in accordance with the :
requirements of Surveillance Procedure 1303-6.1. The ILRT test procedure was the administrative document used to set up the required plant system prerequisites and initial conditions necessary to conduct an ILRT.
The containment structure itself was isolated (i.e., plant systems penetrating the containment boundary were isolated, via closure of containment isolation valves.) The Decay Heat Removal System was in service to maintain the plant in a safe and stable condition during the test. Portions of fluid systems which under post-accident conditions l become extensions of the containment boundary valves were drained and vented. The '
Penetration Pressurization System was depressurized and manometers were installed in the manifolds to provide a means ofleak detection. Equipment within the reactor building, !
which may be subject to damage, was protected and potential pressure sources were removed or vented. All accessible liner weld channels were vented to the containment atmosphere. The accessible exterior and interior surfaces of the containment were visually !
inspected in accordance with TMl-1 Surveillance Procedure SP 1301-8.1, " Reactor Building AnnualInspection".
The pressurization system consisted of a group of five diesel driven oil-free air compressors (total capacity of 6,300 sefm), a water-cooled aftercooler, a desiccant type air dryer, and valves.
A fully automated data acquisition sptem was used to record and monitor ILRT containment-related test parameters, e.g., contamment air pressure, drybulb temperatures, and dewpoint temperatures, at fifteen minute intervals. The ILRT computer system consisted of two portable computers and floppy disk drives. The test data was processed via the General Physics ILRT software system computer program, i
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With test prerequisites and initial conditions satisfied, the containment was pressurized and externalinspections of the containment were completed. When the pressure reached 51.5 ,
psig, containment pressurization was stopped and isolated. The containment air mass system was then allowed to thermodynamically stabilize. Once stabilization was attained. l the data acquisition system and ILRT computer system recorded the test data and computed the ILRTleakage rate at fifteen minute intervals. 1 I
The Type A test and the supplemental verification test were performed according to the requirements of the Three Mile Island Unit 1 Technical Specifications and 10CFR50, Appendix J. The test method as required by the Technical Specifications is the absolute method as described in ANSI N45.4-1972, " Leakage Rate Testing of Containment Structures for Nuclear Reactors." The leakage rate was calculated using formulas from ANSI /ANS-56.8-1987, " Containment System Leakage Testing Requirements".
The ILRT containment leakage rate was then compared to the procedure acceptance criteria limit and verified satisfactory.
Prior to depressurization of the containment, a verification test was completed. The i verification test induced a known leakage rate and a calculation was made which verified i the test method and the operation of the instrumentation system.
The containment was then slowly depressurized to normal atmospheric conditions and restoration was started.
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l 6.0 TYPE B AND C LOCAL LEAKAGE RATE TEST RESULTS 6.1 Local Leak Rate Test Program 1 This section addresses the Primary Reactor Containment Local Leak Rate Testing (LLRT) Program. The LLRT program complies with containment leak test -
requirements set forth in Technical Specification 4.4.1 and 10CFR50, Appendix J.
A summary of kral leakage rate tests since the ILRT in January 1990 is included in Appendix G. ;
i 6.2 Acceptance Criteria The combined leakage rate of all penetrations and isolation valves shall not exceed .
l 0.6 L (0.060 wt.9/ day,104,846 secm) at P .
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! 7.0 ANALYSIS AND INTERPRETATION l i !
- The upper 95% confidence limit (UCL) Mass Point leakage rate calculated during the ILRT !
, were less than the test acceptance cdteria of 0.75 L. (0.075 % wtiday).- Additions to the l j calculated leakage rates must be made to account for penetration paths not exposed to the i ILRT pressure and for changes in the net free containment volume due to changes in ,
containment water levels. These additions are discussed below. '
i 7.1. Summary of Type B and C Penalties !
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l Penetration paths not exposed to the ILRT pressure and the corresponding i j minimum pathway leakage rates are as follows.
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- Penetration Number System LLRT MINPATH LEAKAGE 423 Purge AH-VIC/lD 1794 SCCM LLRT results based on the above equate to a Type B and C penalty addition of i 0.0011 wt.4 per day. This penality was conservatively taken since the purge j valve interspace was pressurized during the test, in order to equalize the interspace.
Interspace repressurization however was maintained below ILRT pressure to
) preclude any llow into the Reactor Building.
7.2 Volume Change Corrections
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i The following volumes were monitored for liquid level changes which would affect j the containment net free volume:
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i VOLUME MONITORED LEVEL CHANGE (in.) VOLUME CHANGE !
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! Pressurizer -2.7 23.9 !
Core Flood Tank B -0.1 6.8 I Containment Sump 0.2 -3.0 a
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Based on the volumes monitored, the containment net free volume increased during the ILRT by 27.7 fta. This overall increase in the containment net free volume :
during the ILRT is conservatively included in the reported containment integrated i leakage rate and no other correction is required.
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l 7.3 ILRT Results ,
I The ILRT leakage rate including the required additions is as follows:
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Mass Point 95'7e l UCL leakage Rate 0.0707 % wtiday ;
Type C Penalties 0.0011 % wtiday Volume Change 0.0000 % wtiday Final 95 % UCL Leakage Rate 0.0718 '7e wtiday !
The Final Mass Point 95 % UCL leakage rate is less than the test acceptance criteria '
value of 0.75 La (0.075 % wtiday).
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8.0 REFERENCES
A. Three Mile Island Unit 1 Surveillance Procedure, 1303-6.1, " Reactor Building Integrated Leak Rate Test".
B. Three Mile Island Nuclear Station Unit 1 Technical Specifications.
C. Three Mile Island Nuclear Station Unit 1 Updated Final Safety Analysis Report.
D. Code of Federal Regulations, Title 10, Part 50, Appendix J, " Primary Reactor Containment Ixakage Testing for Water Cooled Power Reactors".
E. ANSI N45.4-1972, " Leakage-Rate Testing of Containment Structures for Nuclear Reactors".
F. ANSI /ANS-56.8-1987, " Containment System Leakage Testing Requirements",
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APPENDIX A STABILIZATION PHASE DATA ;
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STABLIZATION MODE
SUMMARY
OPTIONS TIME = 1815 l 1 - 1ANUAL DATA ENTRY # OF DATA POINTS = 19 !
2 - PARAMATER GRAPHS MODE DURATION (IN HRS) = 4.50 !
3 - SENSOR PLOTS TOT TIME MEASURED LEAK = 0.5124 l 4 - REPRINT CURRENT DATA PT TOT TIME CALCULATED LEAK = 0.6102 ;
5 - SENSOR DIFFERENTIALS TOT TIME 95% UCL = 1.1807 :
6 - ANSI STABILIZATION CRITERIA MASS PT LEAK = 0.5087 !
7 - BN-TOP-1 STAB. CRITERIA MASS PT 95% UCL = 0.5775 i 8 - ANSI CRITERIA PRINTOUT 9 - BN-TOP-1 CRITERIA PRINTOUT ,
P - PASS WORD MENU l l
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ANSI TEMPERATURE STABLIZATION CRITERIA MET l BN-TOP TEMPERATURE STABLIZATION CRITERIA MET :
POINT
SUMMARY
- CURRENT VALUE/ DIFFERENCE FROM PREVIOUS POINT AVG TEMP: 90.558/ +0.069 AVG PRESS: 65.527 / +0.004 MASS: 642884.88 / -44.250 AVG DEW PRESS: 0.5675/ +0.0025 l TOTAL PRESS: 66.094 / +0.006 ;
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STABLE MODE Three Mile Island UNIT 1 Page 1 i TEMPERATURE STABILIZATION UNIT 1 g ,
ANSI 56.8 BN-TOP-1 l TIME TEMP 1 HR 4 HR 4HR - 1HR BN1 BN2 l
0.00 89.644 0.0000 0.0000 0.0000 0.0000 0.0000 0.25 89.598 0.0000 0.0000 0.0000 0.0000 0.0000 0.50 89.633 0.0000 0.0000 0.0000 0.0000 0.0000 ;
0.75 89.677 0.0000 0.0000 0.0000 0.0000 0.0000 '
1.00 89.717 0.0735 0.0000 -0.0735 0.0000 0.0000 1.25 89.764 0 1664 0.0000 -0.1664 0.0000 0.0000 f 1.50 89.836 0.2031 0.0000 -0.2031 0.0000 0.0000 1.75 89.881 0.2035 0.0000 -0.2035 0.0000 0.0000 2.00 89.967 0.2495 0.0000 -0.2495 0.1615 0.0000 ;
2.25 90.032 0.2682 0.0000 -0.2682 0.2173 0.2231 l 2.50 90.058 0.2220 0.0000 -0.2220 0.2125 -0.0190 l 2.75 90.145 0.2646 0.0000 -0.2646 0.2340 0.0861 3.00 90.195 0.2288 0.0000 -0.2288 0.2392 0.0206 '
3.25 90.269 0.2368 0.0000 -0.2368 0.2525 0.0533 3.50 90.319 0.2611 0.0000 -0.2611 0.2415 -0.0439 -
3.75 90.381 0.2358 0.0000 -0.2358 0.2502 0.0346 4.00 90.436 0.2403 0.1980 -0.0422 0.2345 -0.0626 r 4.25 90.489 0.2197 0.2228 0.0031 0.2283 -0.0251
! 4.50 90.558 0.2394 0.2314 -0.0080 0.2503 0.0880 r
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STABLE MODE Page 1 1 AVERAGE DATA VALUES l 1
l DATE TIME RTD DEW PT. VAP PRESS DRY PRESS MASS ,
258 0.00 89.644 82.726 0.554 65.481 6435031h 258 0.25 89.598 82.741 0.554 65.476 643514.63 ,
258 0.50 89.633 82.867 0.556 65.469 643404.88 l 258 0.75 89.677 82.944 0.558 65.466 643320.88 ,
258 1.00 89.717 82.887 0.557 65.468 643294.81 258 1.25 89.764 83.116 0.561 65.466 643216.56 !
258 1.50 89.836 83.064 0.560 65.470 643169.00 !
258 1.75 89.881 83.265 0.564 65.469 643112.94 258 2.00 89.967 83.114 0.561 65.476 643080.94 258 2.25 90.032 83.072 0.560 65.482 643061.94 !
l 258 2.50 90.058 83.175 0.562 65.484 643055.50 258 2.75 90.145 83.370 0.565 65.487 642973.75 !
258 3.00 90.195 83.301 0.564 65.494 642984.63 l 258 3.25 90.269 83.435 0.567 65.497 642932.75 l 258 3.50 90.319' 83.200 0.562 65.508 642979.44 l 258 3.75 90.381 83.345 0.565 65.511 642934.88 258 4.00 90.436 83.317 0.564 65.517 642933.06 ;
258 4.25 90.489 83.345 0.565 65.523 642929.06 '
258 4.50 90.558 83.484 0.568 65.527 642884.94 t
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Three Mile Island UNIT 1 Page 1 ;
i LEAKAGE RATE
SUMMARY
UNIT 1 TOTAL TIME MASS / POINT l
DATE TIME TTLM LMCALC SL LAM L95 258 0.00 0.0000 0.0000 0.0000 0.0000 0.0000 l 258 0.25 -0.1711 0.0000 0.0000 0.0000 0.0000 258 0.50 0.7330 0.7330 0.0000 0.7335 5.1968 258 0.75 0.9065 1.0283 3.9174 0.9793 1.7833 !
258 1.00 0.7771 1.0141 2.8804 0.9106 1.2936 -
258 1.25 0.8550 1.0393 2.3843 0.9269 1.1549 i 258 1.50 0.8308 1 0299 2.1530 0.9103 1.0640 258 1.75 0.8317 1.0182 2.0021 0.8972 1.0087 258 2.00 0.7874 0.9877 1.8869 0.8624 0.9545 ,
258 2.25 0.7314 0.9431 1.7861 0.8136 0.9029 258 2.50 0.6678 0.8881 1.6911 0.7540 0.8494 '
l 258 2.75 0.7180 0.8632 1.6144 0.7375 0.8179 258 3.00 0.6445 0.8222 1.5385 0.6981 0.7769 258 3.25 0.6545 0.7932 1.4738 0.6757 0.7466 '
9 258 3.50 0.5580 0.7456 1.4044 0.6263 0.7053 258 3.75 0.5652 0.7096 1.3431 0.5943 0.6703 !
258 4.00 0.5315 0.6731 1.2845 0.5614 0.6361 l 258 4.25 0.5038 0.6375 1.2288 0.5295 0.6030 258 4.50 0.5124 0.6102 1.1807 0.5087 0.5775 ,
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1 e e STABLE MODE Page 1 AVERAGE MASS DIFFERENTIAL DATE TIME (HOURS) MASS DIFFERENTIAL 258 0.00 0.000 258 0.25 11.438 258 0.50 -109.750 258 0.75 -84.000 258 1.00 -26.063 258 1.25 -78.188 258 1.50 -47.625 258 1.75 -56.125 258 2.00 -32.000 258 2.25 -19.000 258 2.50 -6.375 258 2.75 -81.688 258 3.00 10.813 258 3.25 -51.813 258 3.50 46.563 258 3.75 -44.500 258 4.00 -1.750 258 4.25 -4.000 258 4.50 -44.250 l
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e APPENDIX B ILRT TEST DATA AND PLOTS 28
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TEST MODE
SUMMARY
l OPTIONS TIME = 1845 1 -
MANUAL DATA ENTRY # OF DATA POINTS = 98 2 -
PARAMETER GRAPHS MODE DURATION (IN HOURS) = 24.25 3 -
SENSOR PLOTS TOT TIME MEASURED LEAK = 0.0707 4 -
REPRINT CURRENT DATA PT TOT TIME CALCULATED LEAK = 0.0702 5 -
SENSOR DIFFERENTIALS TOT TISE 95% UCL = 0.0849 l 6 -
TREND ANALYSIS MASS POINT LEAK = 0.0684 ;
P -
PASS WORD MENU HASS POINT 95% UCL = 0.0707 75 La = .075 POINT
SUMMARY
- CURRENT VALUE/ DIFFERENCE FROM PREVIOUS POINT AVG TEMP: 93.441/ +0.016 AVG PRESS: 65.825 / -0.001 MASS: 642444.06 / -32.500 AVG DEW PRESS: 0.5792/ +0.0026 i TOTAL PRESS: 66.404 / +0.001 l
l l l i
29 l
l
i TEST MODE l Page 1 l AVERAGE DATA VALUES j DATE TIME RTD ' ' 'W PT . VAP PRESS DRY PRESS MASS i
l 258 l 0.00 90.619 f ,3.305 0.564 65.536 642903.44 258 0.25 90.655 83.332 0.565 65.541 642912.31 258 0.50 90.721 83.408 0.566 65.546 642882.00 ,
258 0.75 90 767 83.136 0.561 65.556 642931.63 '
258 1.00 90.834 83.544 0.569 65.555 642835.69 258 1.25 90.888 83.651 0.571 65.559 642814.63 258 1.50 90.938 83.488 0.568 65.567 642839.25 258 1.75 90.985 83.570 0.569 65.571 642824.25 258 2.00 91.025 83.410 0.566 65.580 642860.69 258 2.25 91.076 83.479 0.567 65.584 642839.00 258 2.50 91.115 83.540 0.569 65.588 642831.00 258 2.75 91.169 83.543 0.569 65.593 642820.56 258 3.00 91.212 83.553 0.569 65.598 642817.19 258 3.25 91.275 83.697 0.571 65.600 642765.00 ,
258 3.50 91.310 83.499 0.568 65.608 642807.81 258 3.75 91.348 83.575 0.569 65.612 642797.00 258 4.00 91.392 83.615 0.570 65.616 642783.00 258 4.25 91.427 83.537 0.568 65.622 642802.44 258 4.50 91.484 83.490 0.568 65.627 642786.31 258 4.75 91.516 83.610 0.570 65.629 642774.56 258 5.00 91.559 83.630 0.570 65.634 642767.75 258 5.25 91.597 83.772 0.573 65.636 642740.81
, 259 5.50 91.631 83.648 0.571 65.642 642765.38 259 5.75 91.671 83.530 0.568 65.649 642780.56 259 6.00 91.708 83.750 0.572 65.648 642735.25 259 6.25 91.750 83.651 0.571 65.655 642747.88 1 259 6.50 91.780 83.722 0.572 65.657 642740.50 i 259 6.75 91.825 83.749 0.572 65.661 642720.31 259 7.00 91.859 83.688 0.571 65.666 642729.81 259 7.25 91.903 83.706 0.572 65.669 642712.06 259 7.50 91.937 83.834 0.574 65.670 642685.63 259 7.75 91.972 83.894 0.575 65.673 642671.75 259 8.00 92.009 83.712 0.572 65.680 642697.19 259 8.25 92.028 83.806 0.573 65.682 642679.81 259 8.50 92.076 83.840 0.574 65.685 642667.38 259 8.75 92.111 83.806 0.573 65.689 642663.19 259 9.00 92.132 83.799 0.573 65.693 642674.81
, 259 9.25 92.172 83.765 0.573 65.697 642666.63
. 259 9.50 92.203 83.690 0.571 65.702 642681.00 259 9.75 92.225 83.859 0.574 65.702 642655.94 l
30 l
TEST MODE Page 2 l
AVERAGE DATA VALUES
{
DATE TIME RTD DEW PT. VAP PRESS DRY PRESS MASS 259 10.00 92.247 83.876 0.575 65.705 642658.00 259 10.25 92.290 83.945 0.576 65.706 642626.31 l
l 259 10.50 92.320 83.890 0.575 259 65.711 642632.88 10.75 92.341 83.886 0.575 65.714 642640.69 l
259 j 11.00 92.374 83.827 0.574 65.718 642640.81 259 11.25 92.412 83.814 0.574 259 11.50 65.721 642631.00 92.447 83.765 0.573 65.725 642625.69 i 259 11.75 92.465 83.967 0.576 65.725 259 642599.81 12.00 92.495 83.858 0.574 65.729 642610.31 259 12.25 92.520 83.860 0.574 259 12.50 65.732 642610.94 92.553 83.919 0.576 65.734 642588.50 259 12.75 92.568 83.783 0.573 259 13.00 65.739 642621.13 [
92.593 83.876 0.575 65.740 642600.94 259 13.25 92.620 83.770 0.573 65.744 642613.81 t
259 13.50 92.648 )
83.930 0.576 65.745 642582.75 '
259 13.75 92.672 83.817 0.574 259 14.00 65.749- 642600.44 ?
92.686 83.994 0.577 65.748 642576.06 259 14.25 92.711 83.869 0.575 259 65.754 642597.00 !
14.50 92.739 83.867 0.575 65.756 642591.19 259 14.75 92.769 !
83.886 0.575 65.758 642576.63 259 15.00 92.790 83.974 259 0.577 65.759- 642559.00 15.25 92.812 84.054 0.578 65.760 259 15.50 92.831 642540.25 84.046 0.578 65.762 642544.31 259 15.75 92.845 84.034 259 0.578 65.765 642551.25 l 16.00 92.868 83.999 0.577 65.768 i
259 16.25 92.888 642553.56 84.178 0.580 65.767 642521.00 259 16.50 92.908 83.834 l
259 0.574 65.775 642579.88 16.75 92.930 84.039 0.578 65.774 642538.06 259 17.00 92.959 84.018 259 0.577 65.776 642531.25 i 17.25 92.978 83.896 0.575 65.781 642551.63 259 17.50 92.996 84.066 0.578 l
259 17.75 65.780 642519.56 {
93.021 83.997 0.577 65.783 642522.19 '
! 259 18.00 93.039 84.119 259 0.579 65.783 642499.44 18.25 93.056 83.930 0.576 65.788 642533.44 259 18.50 93.074 83.935 259 0.576 65.790 642529.25 18.75 93.092 83.940 0.576 65.792 642526.25 259 19.00 93.108 83.972 259 0.576 65.793 642519.75 19.25 93.124 84.110 0.579 65.792 642494.06 259 19.50 93.145 84.224 0.581 259 19.75 65.792 642466.75 93.158 84.233 0.581 65.794 642468.00 I
l 31 l
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TEST MODE Page 3 AVERAGE DATA VALUES DATE TIME RTD DEW PT. VAP PRESS DRY PRESS MASS 259 20.00 93.179 84.056 0.578 65.799 642494.69 ,
259 20.25 93.200 S4.074 0.578 65.800 642485.38 l 259 20.50 93.215 84.158 0.580 65.801 642470.50 259 20.75 93.232 84.085 0.579 65.804 642483.38 259 21.00 93.247 84.157 0.580 65.804 642470.94 259 21.25 93.271 84.072 0.578 65.808 642476.25 259 21.50 93.282 84.109 0.579 65.809 642473.69 l 259 21.75 93.303 84.114 0.579 65.810 642464.06 259 22.00 93.326 84.154 0.580 65.811 642447.69 259 22.25 93.327 84.193 0.581 65.812 642452.19 259 22.50 93.335 84.029 0.578 65.817 642489.13 259 22.75 93.359 83.984 0.577 65.819 642485.38 259 23.00 93.381 84.017 0.577 65.820 642466.88 259 23.25 93.385 84.017 0.577 65.822 642478.00 259 23.50 93.403 84.045 0.578 65.823 642466.38 259 23.75 93.405 84.178 0.580 65.821 642449.88 259 24.00 93.426 83.977 0.577 65.826 642476.56 259 24.25 93.441 84.116 0.579 65.825 642444.06 1
l l
l 32
TEST MODE Three Mile Island UNIT 1 Page 1 LEAKAGE RATE
SUMMARY
UNIT 1 TOTAL TIME MASS / POINT ;
DATE TIME TTLM LMCALC SL LAM L95 l '
258 0.00 0.0000 0.0000 0.0000 0.0000 0.0000 258 0.25 -0.1318 0.0000 0.0000 0.0000 0.0000 258 0.50 0.1598 0.1598 0.0000 0.1593 1.6045 258 0.75 -0.1403 -0.0416 2.2986 -0.0799 0.3860 i 258 1.00 0.2530 0.1634 1.1996 0.1738 0.5812 i 258 1.25 0.2653 0.2587 0.9122 0.2673 0.5345 l 258 1.50 0.1598 0.2492 0.7873 0.2316 0.4147 J 258 1.75 0.1689 0.2451 0.7082 0.2162 .0.3488 i 258 2.00 0.0799 0.2035 0.6445 0.1584 0.2769 l 258 2.25 0.1070 0.1851 0.5885 0.1384 0.2337 4 258 2.50 0.1082 0.1721 0.5437 0.1260 0.2037 l 258 2.75 0.1126 0.1636 0.5082 0.1200 0.1843 l 258 3.00 0.1074 0.1555 0.4780 0.1139 0.1680 1 258 3.25 0.1590 0.1632 0.4647 0.1296 0.1783 l i 258 3.50 0.1020 0.1543 0.4413 0.1204 0.1633 l 258 3.75 0.1060 0.1480 0.4217 0.1152 0.1530 0.1467 I l 253 4.00 0.1124 0.1443 0.4058 0.1135 l 258 4.25 0.0887 0.1361 0.3880 0.1052 0.1357 l 258 4 50 0.0972 0.1311 0.3735 0.1013 0.1288 ,
l 258 4.75 0.1013 0.1276 0.3613 0.0997 0.1244 !
258 5.00 0.1013 0.1247 0.3504 0.0981 0.1204 258 5.25 0.1156 0.1247 0.3429 0.1011 0.1215 259 5.50 0.0937 0.1209 0.3328 0.0980 0.1169 259 5.75 0.0798 0.1154 0.3218 0.0925 0.1106 259 6.00 0.1047 0.1146 0.3152 0.0936 0.1103 259 6.25 0.0930 0.1121 0.3075 0.0919 0.1073 259 6.50 0.0936 0.1099 0.3005 0.0908 0.1051 259 6.75 0.1013 0.1091 0.2951 0.0913 0.1046 259 7.00 0.0926 0.1073 0.2890 0.0904 0.1028 259 7.25 0.0986 0.1064 0.2841- 0.0906 0.1021 259 7.50 0.1085 0.1069 0.2808 0.0927 0.1037 259 7.75 0.1116 0.1077 0.2780 0.0951 0.1056 259 8.00 0.0963 0.1065 0.2736 0.0945 0.1044 l 259 8.25 0.1012 0.1061 0.2699 0.0948 0.1041
! 259 8.50 0.1037 0.1060 0.2668 0.0956 0.1044 259 8.75 0.1025 0.1057 0.2637 0.0960 0.1043 259 9.00 0.0948 0.1047 0.2600 0.0952 0.1031 259 9.25 0.0956 0.1039 0.2566 0.0947 0.1022 259 9.50 0.0874 0.1022 0.2526 0.0929 0.1001 259 9.75 0.0948 0.1015 0.2495 0.0925 0.0994 33 l
I, l i
I TEST MODE :
i Three Mile Island UNIT 1 Page 2 [
j __
+ (
LEAKAGE RATE
SUMMARY
UNIT 1 m=..
TOTAL TIME MASS / POINT DATE TIME TTLM. LMCALC SL- LAM L95
- __ _l i 259 10.00 0.0916 0.1005 0.2463 0.0917 0.09B4 259 10.25 0.1009 0.1005 0.2442 0.0925 0.0988 ?
0.0984 I 259 10.50 0.0962 0.1000 0.2417 0.0924 259 10.75 0.0913 0.0992 0.2388 0.0917 0.0975 259 11.00 0.0891 0.0982 0.2360 0.0906 0.0962 259 11.25 0.0904 0.0974 0.2334 0.0900 0.0954 ,
1 259 11.50 0.0902 0.0966 0.2309 0.0895 0.0946 259 11.75 0.0965 0.0964 0.2290 0.0898 0.0947 i e 259 12.00 0.0912 0.0958 0.2268 0.0893 0.0941 :
' 259 12.25 0.0892 0.0951 0.2245 0.0888 0.0934 !
259 12.50 0.0941 0.0948 0.2227 0.0889 0.0933 i 259 12.75 0.0827 0.0937 0.2202 0.0877 0.0921 ,
259 13.00 0.0869 0.0930 0.2181 0.0870 0.0913 i 259 13.25 0.0816 0.0919 0.2156 0.0858 0.0901 259 13.50 , 0.0887 0.0914 0.2138 0.0855 0.0897 259 13.75 0.0823 0.0905 0.2117 0.0847 0.0887 259 14.00 0.0873 0.0900 0.2099 0.0844 0.0883
- 259 14.25 0.0803 0.0890 0.2078 0.0834 0.0873
! 259 14.50 0.0804 0.0882 0.2057 0.0825 0.0864 259 14.75 0.0827 0.0875 0.2039 0.0819 0.0856 259 15.00 0.0857 0.0870 0.2024 0.0817 0.0853 '
259 15.25 0.0889 0.0868 0.2011 0.0817 0.0852 r 259 15.50 0.0865 0.0865 0.1997 0.0817 0.0851 259 15.75 0.0835 0.0860 0.1982 0.0812 0.0846
. 259 16.00 0.0816 0.0854 0.1966 0.0807 0.0840 I
259 16.25 0.0879 0.0852 0.1954 0.0808 0.0840 ,
259 16.50 0.0732 0.0841 0.1935 0.0796 0.0829 259 16.75 0.0814 0.0836 0.1920 0.0793 0.0825 i 259 17.00 0.0817 0.0832 0.1907 0.0790 0.0821 l 259 17.25 0.0761 0.0824 0.1891 0.0782 0.0813 259 17.50 0.0819 0.0820 0.1878 0.0780 0.0810 259 17.75 0.0802 0.0816 0.1865 0.0777 0.0807 i 259 18.00 0.0838 0.0813 0.1855 0.0777 0.0806 259 18.25 0.0757 0.0807 0.1840 0.0770 0.0799 259 18.50 0.0755 0.0800 0.1826 0.0764 0.0793 1 259 18.75 0.0751 0.0794 0.1812 0.0759 0.0787 259 19.00 0.0754 0.0788 0.1799 0.0753 0.0782 s 259 19.25 0.0794 0.0785 0.1788 0.0751 0.0779 l 259 19.50 0.0836 0.0783 0.1780 0.0753 0.0780 :
259 19.75 0.0823 0.0782 0.1771 0.0753 0.0780 i
3
{
34
t s TEST MODE Three Mile Island UNIT 1 Page 3 l
LEAKAGE RATE
SUMMARY
UNIT 1 TOTAL TIME MASS / POINT DATE TIME TTLM LMCALC SL- LAM L95 l __ ;
259 20.00 0.0763 0.0777 0.1760 0.0750 0.0776 259 20.25 0.0771 0.0773 0.1749 0.0746 0.0772 259 20.50 0.0789 0.0770 0.1739 0.0746 0.0770 259 20.75 0.0756 '
,.0765 0.1728 0.0741 0.0766 259 21.00 0.0769 0.0762 0.1718 0.0739 0.0763 259 21.25 0.0750 0.0758 0.1708 0.0736 0.0760 259 21.50 0.0746 0.0753 0.1698 0.0732 0.0755 259 21.75 0.0754 0.0750 0.1688 0.0729 0.0752 259 22.00 0.0773 0.0747 0.1679 0.0728 0.0751 259 22.25 0.0757 0.0744 0.1670 0.0725 0.0748 259 22.50 0.0687 0.0738 0.1659 0.0719 0.0742 259 22.75 0.0686 0.0732 0.1647 0.0712 0.0735 259 23.00 0.0709 0.0727 0.1637 0.0708 0.0731 259 23.25 0.0683 0.0721 0.1626 0.0702 0.0725 259 23.50 0.0694 0.0716 0.1616 0.0697 0.0720 259 23.75 0.0713 0.0712 0.1607 0.0694 0.0716 259 24.00 0.0664 0.0706 0.0854 0.0687 0.0710 259 24.25 0.0707 0.0702 0.0849 0.0684 0.0707 l
35 1
TEST MODE Three Mile Island UNIT 1 Page 1 LEAKAGE RATE TREND
SUMMARY
UNIT 1 TOTAL TIME MASS POINT DATE TIME TTLM LMCALC CHANGE LAM CHANGE 258 0.25 -0.1318 0.0000 0.0000 0.0000 0.0000 258 0.50 0.1598 0.1598 0.1598 0.1593 0.1593 258 0.75 -0.1403 -0.0416 -0.2015 -0.0799 -0.2392 258 1.00 0.2530 0.1634 0.2050 0.1738 0.2537 258 1.25 0.2653 0.2587 0.0953 0.2673 0.0935 258 1.50 0.1598 0.2492 -0.0095 0.2316 -0.0358 258 1.75 0.1689 0.2451 -0.0041 0.2162 -0 0154 258 2.00 0.0799 0.2035 -0.0416 0.1584 -0.0578 258 2.25 0.1070 0.1851 -0.0184 0.1384 -0.0200 258 2.50 0.1082 0.1721 -0.0130 0.1260 -0.0125 258 2.75 0.1126 0.1636 -0.0085 0.1200 -0.0060 258 3.00 0.1074 0.1555 -0.0081 0.1139 -0.0061 258 3.25 0.1590 0.1632 0.0077 0.1296 0.0157 258 3.50 0.1020 0.1543 -0.0089 0.1204 -0.0093 258 3.75 0.1060 0.1480 -0.0063 0.1152 -0.0051 258 4.00 0.1124 0.1443 -0.0037 0.1135 -0.0017 258 4.25 0.0887 0.1361 -0.0082 0.1052 -0.0083 258 4.50 0.0972 0.1311 -0.0051 0.1013 -0.0039 258 4.75 0.1013 0.1276 -0.0035 0.0997 -0.0016 258 5.00 0.1013 0.1247 -0.0029 0.0981 -0.0016 ,
258 5.25 0.1156 0.1247 0.0000 0.1011 0.0029 258 5.50 0.0937 0.1209 -0.0037 0.0980 -0.0030 .
259 5.75 0.0798 0.1154 -0.0055 0.0925 -0.0055 259 6.00 0.1047 0.1146 -0.0009 0.0936 0.0011 1 259 6.25 0.0930 0.1121 -0.0025 0.0919 -0.0017 259 6.50 0.0936 0.1099 -0.0021 0.0908 -0.0011 259 6.75 0.1013 0.1091 -0.0008 0.0913 0.0006 259 7.00 0.0926 0.1073 -0.0019 0.0904 -0.0009 259 7.25 0.0986 0.1064 -0.0009 0.0906 0.0002 259 7.50 0.1085 0.1069 0.0005 0.0927 0.0021 259 7.75 0.1116 0.1077 0.0008 0.0951 0.0024 l 259 8.00 0.0963 0.1065 -0.0011 0.0945 -0.0006 1 259 8.25 0.1012 0.1061 -0.0004 0.0948 0.0004 259 8.50 0.1037 0.1060 -0.0001 0.0956 0.0008 l 259 8.75 0.1025 0.1057 -0.0002 0.0960 0.0004 l 259 9.00 0.0948 0.1047 -0.0010 0.0952 -0.0008 259 9.25 0.0956 0 1039 -0.0009 0.0947 -0.0006 259 9.50 0.0874 0.1022 -0.0016 0.0929 -0.0018 259 9.75 0.0948 0.1015 -0.0007 0.0925 -0.0003 259 10.00 0.0916 0.1005 -0.0010 0.0917 -0.0008 36
h i
TEST MODE Three Mile Island UNIT 1 Page 2 f LEAKAGE RATE TREND
SUMMARY
UNIT 1 j l _ _ _ _ .
l TOTAL TIME MASS POINT DATE TIME TTLM LMCALC CHANGE LAM CHANGE 259 10.25 0.1009 0.1005 -0.0000 0.0925 0.0008 !
259 10.50 0.0962 0.1000 -0.0005 0.0924 -0.0002 259 10.75 0.0913 0.0992 -0.0009 0.0917 -0.0007 i 259 11.00 0.0891 0.0982 -0.0010 0.0906 -0.0011 !
259 11.25 0.0904 0.0974 -0.0008 0.0900 -0.0006 !
259 11.50 0.0902 0.0966 -0.0008 0.0895 -0.0006 !
259 11.75 0.0965 0.0964 -0.0002 0.0898 0.0003 l 259 12.00 0.0912 0.0958 -0.0006 0.0893 -0.0005 l 259 12.25 0.0892 0.0951 -0.0007 0.0888 -0.0005 !
259 12.50 0.0941 0.0948 -0.0003 0.0889 0.0001 259 12.75 0.0827 0.0937 -0.0011 0.0877 -0.0012 !
259 13.00 0.0869 0.0930 -0.0007 0.0870 -0.0007 !
259 13.25 0.0816 0.0919 -0.0011 0.0858 -0.0012 !
259 13.50 0.0887 0.0914 -0.0005 0.0855 -0.0003 259 13.75 0.0823 0.0905 -0.0009 0.0847 -0.0009 ;
259 14.C3 0.0873 0.0900 -0.0005 0.0844 -0.0003 [
259 14.25 0.0803 0.0890 -0.0010 0.0834 -0.0010 l 259 14.50 0.0804 0.0882 -0.0009 0.0825 -0.0008 259 14.75 0.0827 0.0875 -0.0007 0.0819 -0.0007 259 15.00 0.0857 0.0870 -0.0004 0.0817 -0.0002 259 15.25 0.0889 0.0868 -0.0002 0.0817 0.0000 ,
259 15.50 0.0865 0.0865 -0.0003 0.0817 -0.0000 259 15.75 0.0835 0.0860 -0.0005 0.0812 -0.0004 259 16.00 0.0816 0.0854 -0.0006 0.0807 -0.0005 l 259 16.25 0.0879 0.0852 -0.0002 0.0808 0.0001 l 259 16.50 0.0732 0.0841 -0.0010 0.0796 -0.0011 259 16.75 0.0814 0.0836 -0.0005 0.0793 -0.0003 259 17.00 0.0817 0.0832 -0.0005 0.0790 -0.0004 l 259 17.25 0.0761 0.0824 -0.0008 0.0782 -0.0007 l 259 17.50 0.0819 0.0820 -0.0004 0.0780 -0.0002 l 259 17.75 0.0802 0.0816 -0.0005 0.0777- -0.0003 259 18.00 0.0838 0.0813 -0.0002 0.0777 0.0000 259 18.25 0.0757 0.0807 -0.0007 0.0770 -0.0007
! 259 18.50 0.0755 0.0800 -0.0006 0.0764 -0.0006 l 259 18.75 0.0751 0.0794 -0.0006 0.0759 -0.0005 259 19.00 0.0754 0.0788 -0.0006 0.0753- -0.0005 259 19.25 0.0794 0.0785 -0.0004 0.0751 -0.0002 259 19.50 0.0836 0.0783 -0.0001 0.0753 0.0002 259 19.75 0.0823 0.0782 -0.0C02 0.0753 0.0000 259 20.00 0.0763 0.0777 -0.0005 04 0750 -0.0004 37 l
l l
\. , - - -. - -- - . _ _ . . - . . . . -- - ., - .- -
l l
TEST MODE Three Mile Island UNIT 1 Page 3 l l
LEAKAGE RATE TREND
SUMMARY
UNIT 1
- - - = - . . - - ,
TOTAL TIME MASS POINT
- 1 DATE I TIME '
TTLM LMCALC CHANGE LAM CHANGE l
____]
l 259 20.25 0.0771 0.0773 -0.0004 0.0746 -0.0003 259 20.50 0.0789 0.0770 -0.0003 0.0746 -G.0001 l 20,75 0.0765 -0.0004 0.0741 -0.0004 l 259 0.0756 259 21.00 0.0769 0.0762 -0.0004 0.0739 -0.0002 l 259 21.25 0.0750 0.0758 -0.0004 0.0736 -0.0003 259 21.50 0.0746 0.0753 -0.0004 0.0732 -0.0004 l 259 21.75 0.0754 0.0750 -0.0004 0.0729 -0.0003 l 259 22.00 0.0773 0.0747 -0.0003 0.0728 -0.0001 J 259 22.25 0.0757 0.0744 -0.0003 0.0725 -0.0003 259 22.50 0.0687 0.0738 -0.0006 0.0719 -0.0007 )
259 22.75 0.0686 0.0732 -0.0006 0.0712 -0.0007 i 259 23.00 0.0709 0.0727 -0.0005 0.0708 -0.0005 1 259 23.25 0.0683 0.0721 -0.0006 0.0702 -0.0006 0.0697 -0.0005
]
259 23 50 0.0694 0.0716 -0.0005 l 259 23.75 0.0713 0.0712 -0.0004 0.0694 -0.0003 l 259 24.00 0.0664 0.0706 -0.0006 0.0687 -0.0006 l 259 24.25 0.0707 0.0702 -0.0004 0.0684 -0.0003 i 20 POINT MEAN TOTAL TIME CALCULATED LEAKAGE = 7.458624E-02 20 POINT MEAN TOTAL TIME MEASURED LEAKAGE = 7.415611E-02 20 POINT MEAN MASS POINT LEAKAGE = 7.241055E-02 MASS POINT INTERCEPT = 642855.4 MASS POINT SLOPE =-18.3333 I
1 l
38
24 HOUR ILRT MASS POINT LEAK RATE VS TIME -
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,3 24 HOUR ILRT PRESSURE VS TIME .
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i APPENDIX C i i
VERIFICATION TEST DATA AND PLOTS f
T I
1 I
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i 45
1 I I
)
VERIFICATION MODE
SUMMARY
OPTIONS TIME = 2315 1 -
MANUAL DATA ENTRY # OF DATA POINTS = 18 2 -
PARAMETER GRAPHS MODE DURATION (IN HOURS) = 4.25 l 3 -
SENSOR PLOTS TOT TIME MEASURED LEAK = 0.1248 J 4 -
REPRINT CURRENT DATA PT TOT TIME CALCULATED LEAK = 0.1604 5 -
SENSOR DIFFERENTIALS MASS PT LEAK = 0.1487 6 -
TREND ANALYSIS IMPOSED LEAK = 0.1002 P -
PASS WORD MENU TOT TIME UPPER LIMIT = 0.1954 TOT TIME LOWER LIMIT = 0.1454 MASS PT UPPER LIMIT = 0.1936 1 MASS PT LOWER LIMIT = 0.1436 1 TOT TIME VERIFICATION CRITERIA HAS BEEN MET
, MASS PT VERIFICATION CRITERIA HAS BEEN MET j POINT
SUMMARY
- _ CURRENT VALUE/ DIFFERENCE FROM PREVIOUS POINT AVG TEMP: 93.646/ +0.010 AVG PRESS: 65.833 / +0.000 MASS: 642283.44 / -6.375 AVG DEW PRESS: 0.5783/ -0.0003 TOTAL PRESS: 66.411 / +0.000 4
)
i 1
l 1
I 46 l
1 i l
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(
VERF MODE Page 1 i AVERAGE DATA VALUES l DATE TIME RTD ~ DEW PT. VAP PRESS DRY PRESS MASS 4
{
259 0.00 93.455 84.194 0.581 65.825 642425.44 259 0.25 93.460 84.262 0.582 65.824 642414.00 ;
259 0.50 93.480 83.897 0.575 65.831 642460.81 l' 259 0.75 93.484 84.037 0.578 65.829 642434.00 259 1.00 93.502 84.020 0.577 65.830 642422.69 f 259 1.25 93.510 84.128 0.579 65.828 642397.00 l 259 1.50 93.528 84.022 0.577 65.831 642399.81 l 259 1.75 93.525 84.099 0.579 65.829 642392.19 i 259 2.00 93.551 83.912 0.575 65.833 642400.56 259 2.25 93.559 84.201 0.581 65.828 642340.75 .
259 2.50 93.577 84.098 0.579 65.831 642343.88 l 259 2.75 93.581 84.009 0.577 65.832 642355.38 !
259 3.00 93.587 84.128 0.579 65.831 642331.13 1 259 3.25 93.597 84.206 0.581 65.829 642307.25 1 259 3.50 93.619 84.054 0.578 65.832 642312.31 ;
259 3.75 93.627 84.083 0.579 65.832 642297.94 l 259 4.00 93.636 84.085 0.579 65.832 642289.81 !
259 4.25 93.646 84.070 0.576 65.833 642283.44 i i
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47 l ?
VERF MODE Three Mile Island UNIT 1 Page 1 LEAKAGE RATE
SUMMARY
UNIT 1 TOTAL TIME , MASS / POINT DATE TIME TTLM LMCALC SL LAM L95 l
259 0.00 0.0000 0.0000 0.0000 0.0000 0.0000 259 0.25 0.1703 0.0000 0.0000 0.0000 0.0000 259 0.50 -0.2643 -0.2643 0.0000 -0.2640 1.8858 259 0.75 -0.0430 -0.1523 2.4420 -0.1076 0.3161 259 1.00 0.0101 -0.0706 1.0148 -0.0209 0.2076 259 1.25 0.0850 0.0123 0.7431 0.0615 0.2309 259 1.50 0.0639 0.0443 0.5964 0.0799 0.1951 259 1.75 0.0709 0.0653 0.5173 0.0904 0.1741 259 2.00 0.0465 0.0676 0.4567 0.0810 0.1451 259 2.25 0.1405 0.1041 0.4514 0.1200 0.1857 259 2.50 0.1218 0.1221 0.4356 0.1340 0.1889 259 2.75 0.0951 0.1260 0.4149 0.1304 0.1758 i 259 3.00 0.1175 0.1349 0 4031 0.1358 0.1742 l 259 3.2: 0.1358 0.1462 0.3971 0.1456 0.1797 l 259 3.50 0.1207 0.1506 0.3880 0.1464 0.1758 259 3.75 0.1270 0.1552 0.3811 0.1484 0.1740 l 259 4.00 0.1266 0.1585 0.3746 0.1492 0.1717 259 4.25 0.1248 0.1604 0.3684 0.1487 0.1686 i
48
VERF MODE '
Three Mile Island UNIT 1 Page 1 LEAKAGE RATE TREND.
SUMMARY
UNIT 1 TOTAL TIME MASS POINT w-DATE TIME TTLM LMCALC CHANGE LAM CHANGE 259 0.25 0.1703 0.0000 0.0000 0.0000 0.0000 259 0.50 -0.2643 -0.2643 -0.2643 -0.2640 -0.2640 259 0.75 -0.0430 -0.1523 0.1120 -0.1076 0.1564 l 259 1.00 0.0101 -0.0706 0.0817 -0.0209 0.0867 259 1.25 0.0850 0.0123 0.0830 0.0615 0.0824 259 1.50 0.0639 0.0443 0.0319 0.0799 0.0184 t 259 1.75 0.0709 0.0653 0.0211 0.0904 0.0105 259 2.00 0.0465 0.0676 0.0023 0.0810 -0.0093 259 2.25 0.1405 0.1041 0.0365 0.1200 0.0390 259 2.50 0.1218 0.1221 0.0181 0.1340 0.0140 259 2.75 0.0951 0.1260 0.0038 0.1304 -0.0036 259 3.00 0.1175 0.1349 0.0089 0.1358 0.0054 l
259 3.25 0.1358 0.1462 0.0113 0.1455 0.0098 259 3.50 0.1207 0.1506 0.0044 0.1464 0.0008 259 3.75 0.1270 0.1552 0.0046 0.1484 0.0020 259 4.00 0.1266 0.1585 0.0033 0.1492 0.0008 259 4.25 0.1248 0.1604 0.0020 0.1487 -0.0005 20 POINT MEAN TOTAL TIME CALCULATED LEAKAGE = 0 20 POINT MEAN TOTAL TIME MEASURED LEAKAGE = 0 20 POINT MEAN MASS POINT LEAKAGE = 0 MASS POINT INTERCEPT = 642451.8 MASS POINT SLOPE =-39.80461 l
l 49
VERIFICATION TEST DRESSURE VS TIME 6 6 . 411-~
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. . ,e 66.405- 7' ,
1900/ 259 TIME 2315/ 259
VERIFICATION TEST DEWPOINT TEMPERATURE VS TIME
- 84. 262-~ ,1/
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. VERIFICATION TEST TEMPERATURE VS TIME
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1 I
APPENDIX D l ILRT COMPUTER PROGRAM DESCRIIrrlON ,
l 1
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t 56
DESCRIPTION OF ILRT COMPUTER PROGRAM The following paragraphs describe the various features and attributes of the General Physics ILRT Computer Program and the process used to certify it for each ;
application. !
REDUNDANCY 1
1 The General Physics ILRT team was equipped with two fully operational IBM l compatible microcomputers during the ILRT and for on site data reduction and analysis. The computer software and hardware interfaced directly with the ILRT ,
Measurement System Volumetries A-100 Datalogger.
Two computers were brought on site for 100% redundancy, as each computer and its l software is capable of indepen.lently performing the ILRT. The General Physics ILRT !
Computer Softw.'re is also capable of accep !ng manual input of raw sensor data and l performing all required 2.cnsor data converFbns if the data logger should cease to !
function. Each computer was equipped with back-up disks in the unlikely event of a disk " crash." .
SECL'RITY l 1
The General Physics 11 RT Computer Program is written in IBM's BASICA. BASICA l is a high level programming language which comhines programming ease with user oriented command functions to create an easy to use and understand program. In l order to increase speed of operation the program was then compiled into an executable !
command Gle. Compiling was accomplished using the IBM Basic Compiler. In j addition to execution speed this had the added benent of making the program more secure as compiled programs cannot be edited or changed. The program requires a l password to change moder. of operation, start times, or enter the data editing routine to
! safeguard the integrity of the raw data files.
l l FEATL'RES l l l
l The program itself is designed to be a menu driven program consisting of Gve l l separate. menu driven operating modes. These are the: l l 1. Pressurization Mode 4. Veri 0eation Mode l l 2. Stabilization Mode 5. Depressurization Mode j
- 3. Test Mode '
l 1
1 l
57 l
l
l These modes also correspond to the phases of the ILRT, Menu driven means that the j user is presented with a list of options that the program can perform and from which the user can choose. It allows for interactive infonnation exchange between the user and the computer and prevents invalid information or user mistakes frorn crashing the program. Program organization consists of a master menu which controls access to the seven operating modes chained to the individual menus which control these modes. l The data processing, information display capabilities and function of each mode is as l follow s: l l i
{ l. Pressurization Mode: All data reduction, graphic displays of average l temperature, dewpoint, and corrected pressure, )
- 2. Stabili7ation Mode: All data reduction, automatic comparison of data against ANSI 56.8 and BN-TOP-1 temperature stabilization criteria, notification when criteria is met, graphic displays of average temperature, dewpoint, and corrected pressure.
i
- 3. Test Mode: All data reduction, calculation of leakage rates using mass point, !
total time and point-to-point analysis techniques, display of trend report information required by BN-TOP-1, graphic display of average temperature, dewpoint, pressure and mass, as well as graphic display of mass point !
measured leakage,95% UCL; total time measured and calculated leakage and _
the total time leakage rate at the 95% UCL (as calculated by BN-TOP-1), i including a superimposed acceptance criteria line). !
i I
- 4. Veritication Test Mode: With input of imposed leakage in SCFM :
automatically calculates and displays on graph and trend report the acceptance !
criteria band, plus all graphics displays available in test mode. ;
- 5. Depressurization Mode: All data and graphics capabilities of Pressurization Mode. In programs for BWR units, this mode also includes a Drywell to {
Suppression Chamber Bypass Test routine.
Other reduction and aaalysis capabilities of the General Physics ILRT computer ,
program include:
- 1. Containment total pressure conversion from counts to psia (if required), and :
averaging. ;
- 2. Containment drybulb temperature weighted averaging and conversion to ;
absolute units. l
- 3. Containment dewpoint temperature weighted averaging (conversion from Foxboro deweell element temperature to dewpoint temperature if required) and conversion to panial pressure of water vapor (psia).
58
- 4. Data storage of ILRT measurement system inputs for each data point.
- 5. Weight (mass) point calculations using the ideal gas law.
- 6. Automated Data Acquisition and/or Manual Data Entry.
j 7. Sensor performance and deviation information for sensor failure criteria.
l graphie display of individual sensor performance for selected operating mode.
l l l I
S. Calculation of ISG formula at beginning of test; acceptance criteria based on l l
l number of sensors remaining and actual test duration. I L i
- 9. Computer System Error Functions automatically checks for error in incoming l data, printer or disk drive faults.
The computer program used by General Physics has been previously certified for six ;
tests at the San Onofre Nuclear Generating Station and over a dozen other ILRTs.
The initial certification required verification of the program through hand calculations ,
l l and an independent review by Bechtel Power Corporation. After certification was completed, a calibration set of raw data was used to verify software of the program piior to usap Additionally, once the computer was linked to the data acquisition system and a complete data stream was available, the input function'of each mode of .
the program was verified by comparing the data acquisition system output to the l computer printout data point summary.
c i
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59
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i APPENDIX E SENSOR LOCATIONS P
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?
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60 t
APPENDIX E ,
l SENSOR LOCATIONS :
t i
SENSOR ELEV. SENSOR NUMBER (FEET) LEVEL TYPE QUADRANT !
TE-655R 2S7 1 RTD I {
1 TE-655S 287 1 RTD 111
{
TE-655T 287 1 RTD IV ,
TE-655U 287 1 RTD 11 TE-655V 287 1 RTD IV -
l TE-6541 287 1 DEWCELL Ill :
i TE-654J 287 1 DEWCELL l' TE-655M 314 2 RTD 1 to
?
321 i
i TE-655N 314 2 RTD 111 l
to 321 TE-6550 314 2 RTD IV r to 321 i
! I TE-655 P 314 2 RTD 11 ;
l to 321 TE-6550 314 2 RTD 11 l to ;
321
~ ,
TE-654G 314 2 DEWCELL I ;
to i 321 TE-65411 314 2 DEWCELL 111 to 321 TE-655A 352 3 RTD ;
to ,
365
- - . ^ ' ~ ~
6T'
_~ ._ . -
APPENDIX E SENSOR LOCATIONS SENSOR ELEV. SENSOR NUMBER (FEET) LEVEL TYPE QUADRANT TE-655K 352 3 RTD III to 365 TE-654D 352 3 DEWCELL II to 365 TE-655E 352 3 DEWCELL IV ,
to l 365 TE-655D 365 4 RTD I j to 405 )
TE-655J 365 4 RTD I
, to l 405 TE-655L 365 4 RTD I i to 405 l TE-655W 365 4 RTD 11 to !
405 l TE-655X 365 4 RTD IV '
to 405 TE-655B 365 4 RTD I '
l to 405 TE-654 B 365 4 DEWCELL I to 405 TE-654C 365 4 DEWCELL III to 405
! TE-654F 365 4 DEWCELL II to 405 l TE-655C 437 5 RTD I l TE-655E 437 5 RTD II TE-655H 437 5 62 RTD III l
l
_ . . -. .1
I l
APPENDIX E SENSOR LOCATIONS SENSOR ELEV.. SENSOR NUMBER (FEET) LEVEL TYPE QUADRANT TE-655F 437 5 RTD IV TE-654A 437 5 DEWCELL I The trend of deweell temperature sensors TE-654A and TE-654J during the ILRT did not reflect the trend of the other dewcell temperature sensors. All ILRT calculations were redone with the input from deweell temperature sensors TE-654A and TE-654J removed.
l l
l l
63
,e ,f 10 ff ELEV. 437' ;* .f;*t a' ~ *"
. INSTHUW N TAllON SURCHART m ,, . , i m .r , n,s.,.... ..e==
- ', .m..,
set tMkt H n.m 14 MSP
,s, TI EL EV. 405' -- .T+$E
- e +=~~ '
', o.-,ns
"*a* +o . *n
=
=
6h ~~..
~ m
_. _ m -_ ,, _ . . .._..
.% @% MS EL EV. 385' -- o a
- no .. ;;;,i s. .~
c)
A ,, n
.. .n .n ~
c %. .% +
= = "
1o AT MOSPHC HE
,+ ts h
ELEV. 365'-- ~ ~
A l h
ELEV. 352' --
e.s s
~
X X 9 V
p3 tv 8 E
,, ,, n n n n X !
0
_ .n, m n, m - .
ELEV. 314* -- a
- o a " ' "
8 " " " ' "
- oNsif t
- ; PEHSONAL y COMPUT LH n n ,, ,, u ,, 24 RTD's m, m, es .nw ow me - - - - - ------ -~
10 DEWCELLS ELEV. 28 7* -- m. - a 5 " ' ' '
nrcono m m n av ev
- i PHIN T L R INSi nUME N T CONSOlL
-_ a 6 a ~ e.-- -a mm , =_. +.una ---. .- a n a ~.u ,a. , + -g--
O O 1
l l
1
)
l I
i I
1 l
APPENDIX F INSTRUMENTATION SELECTION GUIDE VALUE ;
1 l
I f
i 65 l
l
1 l
I l'
INSTRUMENTATION SELECTION GUIDE CALCULATION PRE-TEST ISG A. TEST PARAMETERS
- 1. Test Pressure: 50.6 psig = 65.3 psia
- 2. Containment Avg. Drybulb Temperature (T): 70 F = 529.67 R
- 3. Containment Avg. Dewpoint Temperature (Tdp): 65 F B. Instrument and Measurement System Errors
- 1. Definitions
- a. e= the error associated with the measurement of change in a given parameter.
- b. E= the error associated with the sensitivity of the sensor.
- c. e= the error associated with the measurement system readout and signal conditioning (excludes sensor), including resolution and repeatability.
- 1) Instrumentation errors (e.g., repeatability and resolution) are combined using a root-sum-square formula (per ANSI /ANS-56.8-1987, Appendix G).
- 2) In cases where repeatability is tested and specified for both the sensor and the readout device, the largest source of error is used to calculate c.
C. Instrument Errors
- 1. Total, Absolute Pressure
- a. Ep = 10.001 psia (per manufacturer spec.) l
- b. ep = [(0.001 psia)2 + (0.008 psia)2 1/2 3
cp= i[1.0 x 104 + 6.4 x 10-5 jl/2 E
p = 1[6.5 x 10-5 31/2 c p = i8.062 x 10-3 psia )
66 l
i
- c. ep = [(Ep)2, (,p)2)lp/[no. of sensors]IN ep = [(0.001)2 + (8.062 x 10-3)2 31/2/ (2)l/2 t ep = 1[1 x 104 + 6.5 x 105 )l/2j),434 e
p
= 1[6.6 x 10-5)1/273,434 e
p
= i5.7454 x 10-3 psia
- 2. Drybulb Temperature
- a. F-3, = 0.01 F
- b. eT = i[(0.01)2 + (0.001)231/2 j
E T = i[1.0 x 10" + 1 x 104]I/2 E7= [1.01 x 10 ]I/2 1.005 x 10-2 op ET=
eT = 1[1.0 x 10 + 1.010025 x 10d]I/2/4.899 1 '
l eT = 1[2.010025 x 10d]I/2j4,ggg i i eT = 11.4177 x 10-2/4.899 eT = 12.89396 x 10-3 op
- 3. Water Vapor Pressure l
- a. Epy = 0.1 F
- b. c py =
[(0.01)2 + (0.001)2)W E
py = 1[1 x 10" + 1 x 10-6)l/2 c py = i[1.01 x 10-4]I/2 e py = 1.005 x 10-2 op l l
l 67 l
l
- c. At a 65 F dewpoint, water vapor pressure change?F is 0.0106450 psiaPF (from the General Physics ILRT Data Management Computer Program)
- d. e =z[(F ps r' + (rpy)-]1/',(no. of sensors)1/'
gy e
gy = e[(0.1)~ + (l .005 x 10 -)-]l/(10)1/'
l e p = [1.0101 x 10-2]I/2 /3.1623 e
ps. = 10.1005,3.1623 e
ps. = eo.0317S"F x 0.0106450 psiaFF e = z3.383 x 10'4 psia py D. Instrumentation Selection Guide Formula (24 hr. Test)
/ x2 f 12 / $2 1 er en e ISG = + 2400
~
2 -
+2 -
+2 -r t 8 ,P, <P, ,T, l
- - - :, n .- _-...-. .-- -w n ,- nun, nn .
r 12 r 12 r 42 2400 , 5.7454x10 3 3.383 x 10 4 2.893% x 10-3
=: +2 +2 24 N. <
65.3 , 1 65.3 , s 529.67 ,
1
~
= 2 100 / (1.5483 x 10~8) + (5.3680 x 10~") 4 (8.9336 x 10 i)
ISG = 2100 /1.562637 x 10'8 4
ISG = 2100 (1.25 x 10 )
l
/SG = 10.0125 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> F. ISG Acceptance Criteria 1.
ISG must be < 25?E L i
- 2. 25Ch (0.1 wt."h/ day) = 0.025 w t.Ch. day
- 3. ISG = 0.0125 < 0.125 w t.%24168 s
.l l
POST-TEST ISG l t
A. TEST PARAMETERS >
l'. Test Pressure: 51.52 psig = 66.1 psia
- 2. Containment Avg. Drybulb Temperature (T): 90.62 F= 550.29 "R :
- 3. Containment Avg. Dewpoint Temperature (Tdp): 82.86 F
. B. Ins:rument and Measurement System Errors
- 1. Definitions j
- a. e= the error associated with the measurement of change in a given l
parameter,
- b. E= the error associated with the sensitivity of the sensor.
- c. e= the error associated with the measurement system readout and l signal conditioning (excludes sensor), including resolution and repeatability.
- 1) Instrumentation errors (e.g., repeatability and resolution) are combined using a root-sum-square formula (per ANSI /ANS-56.8-1987, Appendix G).
- 2) in cases where repeatability is, tested and specified for both the sensor and the readout device, the largest source of error is used I to calculate t.
I C. Instrument Errors
- 1. Total, Absolute Pressure
- a. Ep= 20.001 psia (per manufacturer spec.)
- b. r p
= e[(0.001 psia)2 + (0.008 psia)2]U r p = =[1.0 x 10-6 + 6.-l x 10-5)l/2 tg = [6.5 x 10-5)1/2 op = 8.062 x 10-3 psia 69 I I i
J
, _ , _ . . . ...m. ,..,._ ,-.-,_ ...- .-
l l . .
- c. e = m[(Ep)2 + (tp)2]1/2 /[no. of sensors]1/2 p
e = z[(0.001)2 + (8.062 x 10~3)2]I/2 / (2)l/2 p
5 e = z{1 x 1(f6 + 6.5 x 10 ]I/27j ,4 34 p
e p
= z[6.6 x 10-5]I'2/1,414 e = 15.7454 x 10-3 psia p
- 2. Drybulb Temper:iture
- a. Fp= 0.01"F i b.
rT * *[(U UI) +(UUUI)}'
4 IX I E
T " *{I U X III IU~^)!
I rT"*[IUIXIU~4}l!
l (T = 21.005 x 10' F
- c. eT = 1[(E T ) +(f T) ]I/2/ (24)1/2 I j
eT = 2[(0.01) + (1.005 x 10-2)2)1/2 (74)1/2 eT = 2[1.0 x 10' + 1.010025 x 10'4]I/2/-1.899 i
/4.899 j eT = [2.010025 x 10-4]I/2 j4,399 eT = z1.4177 x 10-2 1 eT = 2.89396 x 10~3 "F
- 3. Water Vapor Pressure
- a. E , = 20.1"F g
- b. r p = z[(0.01)2 + (0.001)2)l/2 r py = 2[1 x 10-4 + 1 x 10-6)1/2 r py =
[1.01 x 10-4J I/2 r py = 1.005 x 10-2 op 70 i
f
_ . _ _ . , , __ p_ , _, _ __
- c. At a 82.86"E dew point, water vapor pressure change /"F is 0.01797 psiaPF (from the Gener:d Physics ILRT Data Management Computer Program) 7 , /9 = r,
- d. e gy = 1[(Egy)-
+
(r py)-])' /(no. of sensors)"-
e gy
= z[(0.1) + (l.(HIS x 10')-]3 p-/(8) g p-eP '. = m[1.0101 x 10' ]1/'/2.8284 e = 20.1005 '2.S2S4 e , = 20.03553"E x 0.01797 psiaPF e = z6.3847 x 10~4 psia gy D. Instnnnentation Selection Guide Formula (24 hr. Te.st) r 12 / s2 r 32 e
+2 e' 7400 e ISG = 1 2 1 + 2 2 t \ P, s P, T, ,
- -g-. - ... -- - -
. - .- __,,,_.,,,_,,;,,_.,_..,,,.,_j j f 1 32 r 32 4
2400 5.7454x10 32 6.3847 x 10 2.89396 x 10-3 l 7
+2 +2 ;
= 2 24- T s 66.1 ; i 66.1 ; s 550.29 , !
~ ~
=
1 100 y]1.ilI~x~1IE8) 4 (1.866 x 10-1 ) 4 (8.2766 x 10-")
1 l
8 l ISG = f 100 V'l.5379 x 10 l
l d
ISG = 2100 (1.24 x 10 )
1 af.%
ISG = 2 0.0124 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> F. ISG Acceptance Criteria
- 1. ISG must 1,c < 25"h L;1
- 2. 25"b (0.1 w t."b/d:ty) = 0.025 w t." Hay
1 r
?
I
. l
- 3. ISG = 0.0124 < 0.125 wt.fc/24 hours .
k A
4
?
I t
i 9
f P
t t
t I
l-f
?
t h
h f
I' t
i
+
'l r
i i
e l'
t i
1 i
.t l
L i
+
h i
?
r 5
1 l
72 ;
l l
F k
4 8 APPENDIX G LOCAL LEAKAGE RATE TEST SUMMARIES .
i l
l j
l r
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4 l
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73
APPDOIX G
'IEREE MILE ISIAto UNIT 1 1991 REACIOR BUTIDITU LOCAL LEAK RATE Tr'STIIC REPORP (Includes 9R Refueling Outage Test Data and 8R Operating Cycle 1990 ' Dest Data)
SP 1303-11.18 APPDOG 74
. ~
If0EX - 1991 REACIDR EUILDIfG IDCAL LEAK RATE TESTITG REPORT
- 1. PURPOSE
- 2. SUFARY OF VORK ACDCIPLISHED 2.1 Valve Testing / Repairs / Modifications 2.2 Access Hatches
- 3. IEIMODS OF TESTIIG 3.1 Valves 3.2 Access Hatches
- 4. TEST EQUIPl W T USED 4.1 Valves 4.2 Access Hatches
< 5. SGFARY ATO INTERPRETATIGi OF DATA 5.1 Valves 5.2 Access Hatches
- 6. ERROR ANALYSIS 6.1 Valves 6.2 Access Hatches 7.
LESSONS LEARNED /IIGROVEVINPS/ DEGRADATION
- 8. t<t.tutt1CES
- 9. IDCAL LEAK RATE TEST SUFARY APPDOG 75
i l REACTOR BUIIDIIG IOCAL IEAK RATE TESTIIG REPORT l
l 1991 REFUELIIC FRECUEPCY ,
t
- 1. PURPOSE l 1.1 3b provide analysis to the Nuclear Regulatory Conntission on the l Twelfth Periodic Type B and Type C leakage tests performed on the l
Three Mile Island, Unit 1, Reactor Building.
l This report is in accortlance with Title 10, Code of Federal
( Regulations, Part 50, AppeMix J, " Primary Reactor Containment Irakage Testing for Water Cooled Power Reactors". This regulation required the contents of this surmary report to becane part of the Type A test report along with the details of any other Type B and l Type C testing performed since the pmvlous Type A test (also required per Technical Specification 4.4.1.1.8).
- 2.
SUMMARY
OF WORK ACCCIPLISHED 2.1 Valve Testino/ Repairs / Modifications I
Appendix J, Type B and C leak tests were performed on the components as listed in 3MI, Unit 1, FSAR, Update Number 9, Table 5.7-2 and 5.7-3, respectively. In addition the folloaing canponents were leak l tested though not yet listed in the FSAR (will be added during Update i Number 10).
I
- 1. NI-V26 l Repairs or modifications were initiated on the 9R following canponents due to higher than desirable leakage during 10R or during previous outages.
- 1. CA-V13 motor operator gear ratio was increased by BA # 123265.
- 2. CM-V4 repaired due to leakage by actuator solenoid valve.
Actuator solenoid valve was repaired. The CIV was not disassembled or refurbished.
l
- 3. West side fuel transfer tube PP line had leaking pipe fitting i repaired.
- 4. IC-V2 adjusted packing.
l S. MU-V2B yoke bushing replaced. l 1
- 6. NI-V26 adjusted packing. l i
- 7. Spare penetration 221 and 222 roodified. " Blind" flanges were installed tc make the penetrations usable for tanporary routing of wires and hoses.
i
- 8. WDL-V304flushedlineahlappedseats. Did not significantly improve leak rate.
APPENDG l
l
2.2 Access Hatch Testino/ Repairs 2.2.1 Access Hatch Door Seals, SP 1303-11.25 (Reference 8.5)
Access Hatch Door seal leak tests were performed as regaired by Technical Specification 4.4.1.2.5.
2.2.2 Overall Hatch Test SP 1303-11.18 (Reference 8.2)
Semi-annual integrated type leak tests were performed as required by Technical Specification 4.4.1.2.5.
l l
1 l
l 77 APPENDG
t
- 3. Vf1EODS OF 'IESTIIU 3.1 Valve Test Methods Testing was perfonred in accordance with SP 1303-11.18 Reactor Building local Isak Rate Testing. This procedure gives detailed guidance on the test equipnent and methods to be used for each penetration / valve. 'Ihe following general philosophy is contained in the surveillance procedure.
3.1.1 Use air or nitrogen to establish a pressure differential across the valve greater than Pa (50.6 psig - calculated accident pressure).
3.1.2 Assure that the pressure is exerted in the accident test direction unless it can be demonstrated that pressurizing in the non-accident direction provides equal or conservative leak rate data. Butterfly valves AH-VlB/lC, and globe valves ,
WDG-V4, DH-V64, SA-V3, IA-V20, and WDL-V534 (gate valve) were tested in the reverse direction.
3.1.3 Assure that the test volume is drained of liquid so that air or nitrogen test pressure is against valve seats.
3.1.4 Assure that the test verifies valve packing integrity in those cases where the packing would be a Reactor Building leakage boundary.
3.1.5 Assure adequate time period for stabilization of test conditions. !
3.1.6 Assure test equipnent is calibrated and used in a manner consistent with the data accuracy desired (weekly meter i standardization was performed during the test program to i verify meters accurate within i 4% full scale (Reference 8.1). ll 3.1.7 Assure valves to be tested are closed by the normal method prior to testing.
3.1.8 Document As-Found conditions (prior to adjustments / repairs) and As-Inft conditions.
3.1.9 Record test instrument scale leadings prior to doing any data corrections.
3.1.10 Assure that system drains and vents which could serve as containment isolation valves, are closed and capped and tagged after completion of the test program.
A training program prior to the refueling outage was performed to assure that the above philosophy was understood by the l personnel involved in the testing.
78 APPDOG
- t I, !
i i i
! 3.2 Access Hatch Test Methods 3.2.1 Access Hatch Seal Isak Tests-Method !
{
a a Access Hatch Door seal leak tests were perfonned in accordance l with SP 1303-11.25 (Reference 8.5). This procedure provides i detailed guidance on the test equipment and methods to be !
used, i i !
'Ihe Access Hatch Door seal tests are performed by pressurizing the interspace between the double seals on each Access Hatch with metered air at the manufacturers reu==eMed test ,
pressure of 10 psig. After stabilization, the air rotameter l j indicates the rate of air input required to maintain the test j
- pressure. 1 l
3.2.2 Overall Access Hatch Leak Test - Semi-annual overall hatch !
leak testing was performed in accordance with SP 1303-11.18, i Reactor Building local Isak Rate Testing. This procedure :
provides detailed guidance on the test equipnent and methods .i to be used. The overall integrated leak test verified the integrity of all of the following barriers: .
1 !
l 1. Hatch shell/ welds !
- 2. Rubber door seals l
- 3. Teflon operating shaft packing j t'
- 4. Bulkhead electrical penetrations
- 5. Penetration pressurization check valves l
t
, 6. Emergency air flange and associated "O" rings on i J
outer bulkhead e
~
i i
- 7. Bulkhead equalizing ball valves and associated '
mounting flanges /"0" rings The overall leak test was performed by pressurizing the hatch ,
to greater than calculated accident pressure and observing the rate of pressure drop on a high accuracy (Heise) pressure Pressure corrections were made by reference to a barometer.
! Mininum test duration was 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> stabilization prim.
N 4
79 APPENDG 1
l
I l . .
l
- 4. 'IEST EQUIPMDir USED 4.1 valve Test Eculment
- a. Rotameters - Sets of 3 l Mfgr. - Brooks Inst. Co. 1 Model - 1114 Full View I l
Ranges: 1 F] oat Mat'1. Tube No. Range Pyrex R-2-15D 8-1,120 SOCM l l
Sapphire R-2-15C 100-12,200 SCCM Carboloy R-6-15B 1,000-142,000 SOCM Accuracy 1 2% full scale industrial accuracy .
l
- b. Tanperature Indicators (as follows or similar) '
Mfgr. - Ashcroft Model - Di or AH / 3" or 5" Dial Range - 30 to 130 F Accuracy - 1 2 F
- c. Pressure Indicators (as follows or similar)
Mfgr. - Ashcroft Model - 1279 1/2" Dial Range - O to 60 or 0 to 100 psig Accuracy - 1 2 psig
- d. Pressure Regulator (as follows or similar)
Mfgr. - Union Carbide Corp.
Model - UPG 3-75-580 Range - 0 to 100 psi output / 0 to 3000 psi input ;
- e. Calibration Rotaneters (Set of 2)
Mfgr. - Brooks Inst. Co.
Models - 1110-05K2B1Z49, 1110-08K2B1Z06 Ranges - 20 to 16,000 SOCM, 3,600 to 234,000 SOCM Repeatability - 1 1/4% of instantanecras Accuracy - 1 1% instantaneous
- f. Flow rate Calibrator Mfgr. - Brooks Inst. Co.
Model - 1056A Range O to 2,400 SOCM Accuracy-10.2%ofingtedvolume APPDOG
I 4.2 Access Hatch Test Ecuirment l
- a. Precision Pressure Gage (as follows or similar)
Mfgr. - Heise Model - CM Range - O to 60 psig Resolution - 0.25 psig h w acy - 0.1% of instrument span
- b. Barometer (as follows or similar)
Mfgr. - Pennwalt Model - FA185260A Range - 10.8 to 15.5 psia Resolution - 0.005 psia Accuracy - 0.1% of instrument span I
l l
l i
i i
.I APPENDG 81 l
- 5. SLMGRY NO INiun'H1iATION OF DATA 5.1 Valve Test Results As-Found/As-Inft Ioakage to this date:
Total Tech. Spec. % 'Ibch. Spec.
Ihae Limit Limit As-Found MAXPAni(MINPAD1) 17,737(8767) SOCM 104,846 SOCM <16.9%(8.4%)
.i As-Inft MAXPADi(MINPADI) 17,377(8839) SCCM 104,846 SC04 <16.6%(8.4%)
1991 Reactor Buildina Purae Valve Data Mi-V1A/1B NI-VIC/1D FREQUDCY LEAKAGE RESULTS IEAKAGE RESULTS (SocM) (SocM)
AS FOUND 24844 FIRST CUARTER AS IEPT 2184 2379 SEoOND OUARTER 1365 819 UIIRD OUARTER 683 410 FUJRDi OUARTER 546 1599
- Adjust AH-VlB seat.
1990 Reactor Buildina Purne Valve Data NI-VIA/1B AH-VIC/1D FREQUDCY LEAKAGE RESULTS LEAKAGE RESULTS (SCCM) (SOCM)
FIRST OUARTER 5885 1599 SECOt0 CUARTER 351 1053 i
THIRD OUARTER 624 2379 ,
FOURDi OUARTER 468 1560 l l
82 APPENDG
5.2 Access Hatch Test Results 5.2.1 Overall sani-annual access hatch leakage test results in accordance with SP 1303-11.18 (Reference 8.2):
1991 Reactor Buildino Access Hatch Data FIRST HAIE TEST SECOND HAIF TEST OCI@CNENP LEAKAGE RESULTS LEAKAGE RESUL'IS (SOCM) (SCDf)
PERSQt@EL ACCESS HATCH 1057 1638 EQUIPMENT AnrFRS HA'IUI 1931 1337 1990 Reactor Buildino Access Hatch Data FIRST HALF TEST SECOND HAIF TEST '
OCI@ONENT LEAKAGE RESULTS LEAKAGE RESULTS-(SOCM) (SOCM)
PERSONNEL ACCESS HA'IDI 1420 925 EQUIPIENT ACCESS HA'IOi 2154 2302 l
l 5.2.2 Door Seal Leakage Test in accordance with SP 1303-11.25 l (Reference 8.5).
l l
'Ihe Personnel and Equipnent Hatch Door seals had been
! satisfactory leak tested throughout 1992 and 1993 resulting in l
leakage from each door seal to be less than 3 SCFH.
l l
I 83 APPENDG
l
- 6. EPJOR ANALYSIS l
6.1 valve Testina Errors (For purge valves see Section 6.2)
The flow meters used in the field have normal industrial accuracies of f 2% full scale in the 10-100% (15-150 m) scale range. Prior to use, m versus sem graphs were developed for the meters by 10 point calibrations using high accuracy (1 1% instantaneous) lab ,
rotameters. During the leak test program, weekly 3 point standardizations were performed on the field rotameters to verify continued accuracy. The acceptance criteria for these standardizations was a variance of no more than 4% fr m the calibration graphs. If meters were repaired or the 3 point standardization exceeded the inaccuracy limit, a new 10 point calibration was performd. Scale readings on the leak rate procedure (SP 1303-11.18) data sheets were evaluated and corrected for l temperature. Conservative bias was introduced into the results by j assuming 15 m (10% of scale) as the minimum scale. ;
6.2 Access Hatch and Purce Valve Testina Errors The measured pressure drops were corrected by adding the minimum i scale increment of the gage used for both the Heise gage and the barmeter. This conservatively corrected for the resolution and repeatability errors. Gages used were recently calibrated. A minimum one hour temperature / pressure stabilization period was used prior to each pressure drop test. The access hatches and purge valves are not instrumented to allow t mperature corrections.
- 7. LESSONS 1 EARNED /IMPRO'EMENTS/DEGRAIRTION 7.1 The As-Found MAXPATH leakage was 16.9% of the Technical Specification limit of 104,846 SOCM.
The material condition of the containment isolation valves were I
considered excellent.
l APPENDG
! 84 l
, 1 l i l
=
l
- 8. REFERErm 8.1 1430-Y-22, Standardization of Flcw Rotamters 8.2 SP 1303-11.18, Rector Building IIx:al Imk Rate Testing 8.3 Three Mile Island, Unit 1, Technical Specification 4.4.1
- ce File (Records stored in CARIRS, DatJa Base AA60 8.5 SP 1303-11.25, Reactor Building local Isakage Access Hatch Door Seals I
i i
1 l
APPENDG 85
\
l l
1 19919R OUTAGE LOCAL LEAK RATE TEST RESULTS COWONENT AS-FOUND AS-LEFT EMERGENCYACCESSHATCH 1931 1931 ,
1 PERSONNELACCESSHATCH 1057 1057 l EOUlPMENT FLANGE 109 109 AH-V1 A/1 B 546 546 i AH-V1 C/1 D 1599 1599 CA-V1 117 117 i CA-V3 46 161 CA-V13 46 46 f
! CA-V2 150 150 l CA-V4A 44 44 f i
CA-VSA 44 44 j l CA-V4B 33 33 I CA-V5B 1762 1762 l CA-V192 98 98 l CA-V189 1558 1558 l CF-V2A 28 28 CF-V20A 1086 1086 ;
CF-V2B 28 28 f 1 ,
j CF-V208 585 585 l CF-V12A 62 62 l CF-V19A 28 28 i CF-V12B 62 62
- CF-V19B 28 28 CM-V1 62 62 CM-V2 61 61 CM-V3 61 61 CM-V4 816 61 DH-V69 56 56 DH-V64 56 56 FTT EAST 105 105 i
FTTWEST 105 gg 105 HM-V1 A 64 64 l
h HM-V1 B 43 43 HM-V2A 64 64 .
i HM-V2B 43 43 j HM-V3A 64 64 ;
HM-V3B 43 43 HM-V4A 46 46 f HM-V48 43 43 ,
H P-V1 198 198 ,
HP-V6 47 47 !
HR-V22A/228 61 61 H R-V2A/28 62 62 HR-V23A 61 61 H R-V238 61 61 i HR-V4 A/4 B 75 62 t I A-V20/6 103 103 IC-V2 62 62 IC-V3 62 62 IC-V18 61 61 f IC-V4 332 332 IC-V16 62 62 i
IC-V6 28 28 :
MU-V2A 48 48 MU-V2B 18 144 M U-V3 48 48 M U-V 18 171 171 MU-V116 143 143 MU-V20 61 61 MU-V25 155 155 MU-V26 65 65 NI-V26 65 65 NI-V27 89 89 NS-V11 156 156 NS-V15 28 28 NS-V35 38 38 NS-V4 694 694 l
t
}
PENET 104 55 55 PENET 105 127 127 l 4 .
- PENET 106 56 56 l 4 i j PENET 210 56 56 j i PENET 211 55 55 1
PENET 241 104 104 !
I t PENET 414 54 54 PENET 417 60 55 l PENET 221 62 62 i
62 ;
! PENET 222 56 l
i PP-V210 INCLUDEDIN AH LEAKAGE INCLUDEDIN AH LEAKAGE l 1 PP-V211 INCLUDEDIN AH LEAKAGE INCLUDED IN AH LEAKAGE l
j PP-V212 INCLUDEDIN AH LEAKAGE INCLUDEDIN AH LEAKAGE
! PP-V213 INCLUDEDIN AH LEAKAGE INCLUDEDIN AH LEAKAGE RB-V2A 60 60 t RB-V7 60 61 ,
SA-V3/2 56 56 SF-V23 165 165
~
WDG-V3/4 99 99 WDL-V303 154 154 I
WDL-V304 2014 2208 I WDL-V534/535 162 162 MAX PATH TOTAL 17737 17377
]
MIN PATH TOTAL 8767 8839 l
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APPENDIX G
'IEREE MILE ISIRO UNIT 1 1993 REACIOR BlJIIDIfG IOCAL LEAK RATE TESTING REPORT (Includes 10R Refueling Outage Test Data and 9R Operating Cycle 1992 Test Data)
SP 1303-11.18 l
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APPETOG l
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l If0EX - 1993 REACIOR BUIIDItG LOCAL LEAK RATE TESTIIG REPORP
- 1. PURPOSE
- 2. SL1 WARY OF WORK ACCat@LISHED 2.1 Valve Testing / Repairs /l&xilfications 2.2 Access Hatches
- 3. FEIHODS OF TESTI!G 3.1 Valves 3.2 Access Hatches
- 4. TEST EQUIPMENT USED 4.1 Valves 4.2 Access Hatches
- 5.
SUMMARY
ATO INiuwt<t.TATION OF DATA 5.1 Valves 5.2 Access Hatches
- 6. ERROR ANALYSIS 6.1 Valves l 6.2 Access Hatches I
- 7. LESSONS LEARNED /IMPROVEGNIS/ DEGRADATION
- 8. REFEREtCES
- 9. IOCAL LEAK RATE TEST SlWARY j l
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l 90 APPDOG l
i REACIOR BUILDItG LOCAL LEAK RA'IE TESTI!G REPORT 1993 REFUELIfG FREOLEICY
- 1. PURPOSE 1.1 'Ib provide analysis to the Nuclear Regulatory Cmmission on the
- 'IWelfth Periodic Type B and Type C leakage tests performed on the Three Mile Island, Unit 1, Reactor Building.
This report is in accordance with Title 10, Code of Federal
! Regulations, Part 50, Appendix J, " Primary Reactor Containment Irakage 'Ibsting for Water Cooled Power Reactors". This regulation !
required the contents of this sunmary report to become part of the Type A test report along with the details of any other Type B and Type C testing performed since the previous Type A test (also required per Technical Specification 4.4.1.1.8).
i A majority of the local leak rate testing was performed during the IIRI' when the plant was shutdown for the 10R Refueling Outage.
Testing began on September 11, 1993 and was completed October 16, 1993. The LLRT during a refueling nor m lly requires approximately 1800 manhours. By ccabining the IIRT and LLRT, the LLRT was reduced to approximately 600 manhours.
- 2. SLM GRY OF WORK ACCO@LISHED 2.1 Valve Testino/ Repairs / Modifications Appendix J, Type B and C leak tests were perforned on the ccxuponents as listed in 'IMI, Unit 1, FSAR, Update Number 9, Table 5.7-2 and 5.7-3, respectively. In addition the following ccxnponents were leak tested though not yet listed in the FSAR (will be added during Update Ntznber 10) .
- 1. NI-V26
- 2. Industrial Cooling System Closed loop Pipe f I
Repairs or nodifications were initiated on the following components l due to higher than desirable leakage during 10R or during previous outages. Also listed are valves which were retested due to F0 VATS testing of notor operators.
- 1. CA-V1, CA-V3, and CA-V13 were reconfigured by Engineering Modification T1-MM-412616-229 due to notor operator concerns.
The valves have always performed well for seat leakage tests.
CA-V13 is now the only inner containment isolation valve.
- 2. During 9R Operating Cycle a bonnet to body leak was repaired !
on CA-V2. CA-V2 had high but acceptable leakrate during 10R ]
and will be replaced with a globe valve by end of 1993. )
i
- 3. The Industrial Cooling sed Icop piping in the Reactor I Building had high but a c>ptable leakage during 10R and I repairs will be scheduled for associated valve packing and bonnet gaskets. !
l APPENDG l
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- 4. Equipnent Hatch Equalizing Ball Valve Seats were repaired, replaced inner Reactor Building door seal, and tightened
, handwheel packing.
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- 5. Retested after20 VATS:
U-V2A Torque setting increased 135.3%
U-V2B Torque setting increased 65% ,
WDL-V-303 Torque setting increased 59.4% j l
Indicated leakage rate slightly increased after 10 VATS, but it's due to the fact that pressure rotameter vs. vent rotameter method was used. Actual leakage rate remained essentially identical, j 2.2 Access Hatch Testina/ Repairs l 2.2.1 Access Hatch Door Seals, SP 1303-11.25 (Reference 8.5) '
Access Hatch Door seal leak tests were performed as required ;
by Technical Specification 4.4.1.2.5.
1 2.2.2 Overall Hatch Test SP 1303-11.18 (Reference 8.2)
Semi-annual integrated type leak test.s were performed as ,
required by Technical Specification 4.4.1.2.5. 1 l
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- 3. FEI110DS OF 'IESTIIG 3.1 Valve Test Methods Testing was performed in accordance with SP 1303-11.18 Reactor Building local Irak Rate Testing. This procedure gives detailed guidance on the test equiptent and methods to be used for each penetration / valve. The following general philosophy is contained in the surveillance procedure.
3.1.1 Use air or nitrogen to establish a pressure differential across the valve greater than Pa (50.6 psig - calculated accident pressure).
3.1.2 Assure that the pressure is exerted in the accident test direction unless it can be demonstrated that pressurizing in the non-accident direction provides equal or conservative leak rate data. Butterfly valves AH-V1B/1C, and globe valves WDG-V4, DH-V64, SA-V3, IA-V20, PP-V211, PP-V212, and WDL-V534 (gate valve) were tested in the reverse direction.
3.1.3 Assure that the test volume is drained of liquid so that air or nitrogen test pressure is against valve seats.
3.1.4 Assure that the test verifles valve packing integrity in those cases where the packing would be a Reactor Building leakage boundary. i l
3.1.5 Assure adequate time period for stabilization of test conditions.
3.1.6 Assure test equipnent is calibrated and used in a mnner consistent with the data accuracy desired (weekly meter standardization was performed during the test program to l verify meters accurate within f 4% full scale (Reference 8.1). ;
3.1.7 Assure valves to be tested are closed by the normal method prior to testing.
3.1.8 Document As-Found conditions (prior to adjustments / repairs) and As-Irft conditions. l 3.1.9 Record test instrument scale readings prior to doing arry data corrections.
3.1.10 Assure that system drains and vents which could serve as containment isolation valves, are closed and capped and tagged after completion of the test program.
A training program prior to the refueling outage was performd to assure that the above philosophy was understood by the personnel involvM in the testing.
3.1.11 As much LIRI' as possibgp done using the ILRT pressure in the Reactor Building and utilizing the valve lineups and drains accmplished for ILRI'.
APPENDG
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l 3.2 Access Hatch Test Methods 3.2.1 Access Hatch Seal Leak Tests-Method Access Hatch Door seal leak tests were performed in accordance with SP 1303-11.25 (Reference 8.5). This procedure provides detailed guidance on the test equipnent and methods to be used.
The Access Hatch Door seal tests are performd by pressurizing l
the interspace between the double seals on each Access Hatch l with metered air at the manufacturers rec.umerded test pressure of 10 psig. After stabilization, the air rotameter indicates the rate of air input required to maintain the test I
- pressure.
3.2.2 Overall Access Hatch Ioak Test - Semi-annual overall hatch leak testing was performed in accordance with SP 1303-11.18, Reactor Building Incal Inak Rate Testing. This procedure provides detailed guidance on the test equipnent and methods j to be used. The overall integrated leak test verified the integrity of all of the following barriers:
- 1. Hatch shell/ welds
- 2. Rubber door seals
- 3. Teflon operating shaft packing
- 4. Bulkhead electrical penetrations l l
- 5. Penetration pressurization check valves
- 6. Emergency air flange and associated "O" rings on I outer bulkhead j l 7. Bulkhead equalizing ball valves and associated l mounting flanges /"O" rings l
The overall leak test was performed by pressurizing the hatch to greater than calculated accident pressure and observing the I rate of pressure drop on a high accuracy (Heise) pressure )
gage.
Pressure corrections were made by reference to a barometer.
Minimum test duration was 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> stabilization period.
94 APPENDG
- 4. TEST EQUIPIENI' USED I 4.1 Valve Test Eauitment
- a. Rotameters - Sets of 3 ;
Mfgr. - Brooks Inst. Co.
Model - 1114 Full View Ranges:
Float Mat'l. Tube 16. Rance Pyrex R-2-15D 8-1,120 SOCM Sapphim R-2-15C 100-12,200 SC04 Carboloy R-6-15B 1,000-142,000 SC04 ,
Accuracy f 2% full scale industrial accuracy
- b. Temperature Indicators (as follows or similar)
Mfgr. - Ashcroft Model - EH or AH / 3" or 5" Dial l Range - 30 to 130 F l Accuracy - f 2 F
- c. Pressure Indicators (as follows or similar)
Mfgr. - Ashcroft >
Model - 1279 1/2" Dial Range - 0 to 60 or 0 to 100 psig Accuracy - f 2 psig
- d. Pressure Regulator (as follows or similar)
Mfgr. - Union Carbide Corp. i Model - UPG 3-75-580 Range - O to 100 psi output / 0 to 3000 psi input
- e. Calibration Rotameters (Set of 2)
Mfgr. - Brooks Inst. Co.
Models - 1110-05K2B1Z49, 1110-08K2B1Z06 Ranges - 20 to 16,000 SCD!, 3,600 to 234,000 SOCM l Repeatability - f 1/4% of instantaneous l Accuracy - 1 1% instantaneous
- f. Flow rate Calibrator Mfgr. - Brooks Inst. Co.
Model - 1056A Range O to 2,400 SOCM Accuracy - 1 0.2% of i g ted volume APPDOG
l 4.2 Access Hatch Test Ecuirrnent
- a. Precision Pressure Gage (as follows or similar)
Mfgr. - Heise Model - 04 Range - O to 60 psig Resolution - 0.25 psig Accuracy - 0.1% of instrument span
- b. Barcaneter (as follows or similar)
Mfgr. - Pennwalt Model - FA185260A Range - 10.8 to 15.5 psia Resolution - 0.005 psia Accuracy - 0.1% of instrument span 1
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6 l 5.2 Access Hatch Test Results l 5.2.1 Overall smti-annual access hatch leakage test results in accordance with SP 1303-11.18 (Reference 8.2):
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i 1993 Reactor Buildina Access Hatch Data FIRST HAIE TEST SEWND HAIE 'IEST CO@ONETE IEAKAGE RESULTS IEAKAGE RESULTS
, (SOCM) (SCD4) l PERSOtE L ,
AnrERS HA'IU1 463 859 EQUIPMENT AnrFRS HA'IGI 1634 1782 1 1992 Reactor Buildina Access Hatch Data f
l FIRST HAIE TEST SETND HAIE TEST 00@ONENT LEAKAGE RESULTS IEAKAGE RESULTS fSOCM) fSOCM)
PERSOtE L ACCESS HA'IUi 1057 2444 EQUIHerr AS mund 8986 ACCESS HA'IDI 4040 *AS LEPP 6832
- Repaired equalizing ball valve seats, replaced inner RB door seal, tightened inner door handwheel packing. ;
5.2.2 Door Seal Isakage Test in accordance with SP 1303-11.25 I (Reference 8.5). l l
The Personnel and Eqaignent Hatch Door r-eals had been satisfactory leak tested throughout 1992 arri 1993 resulting in leakage frun each door seal to be less than 3 SCHi.
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97 APPENDG
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- 5.
SUMMARY
AIO INIERPRETATION OF DATA 5.1 Valve Test Results As-Found/As-Inft Inakage to this date:
Total Tech. Spec. % Tech. Spec.
Irakaoe Limit Limit As-Found MAXPA W (MINPAE ) 61,379(9650) SOCM 104,846 SCCM <58.5%(9.2%)
As-left MAXPADi(MINPADI) 61,379(9844) SCCM 104,846 SCCM <58.5%(9.4%)
l 1993 Reactor Buildina Purae Valve IMta AH-V1A/1B AH-V1C/1D FREQUEICY IEAKAGE RESULTS LEAKAGE RESULTS (SCCM) (SOCM) l FIRST GIARIER 254 2379 I l
SFm0 GIARTER 1638 624
'IMIRD OUARTER 761 1794 POURIH CUARTER l
1992 Reactor Buildina Purae Valve Data AH-VIA/1B AH-V1C/1D FREQUEICY LEAKAGE RESfJLTS LEAKAGE RESULTS (SoCM) (SOCM)
FIRST OUARIER 819 1989 SEIIFO GIARTER 819 4017 311RD GIARIER 1521 1443 FURIE OUARTER 975 3939 l
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i 98 APPEtOG l
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- 6. ERROR ANALYSIS 6.1 valve Testina Errors (For purge valves see Section 6.2)
The flow meters used in the field have normal industrial accuracies of f 2% full scale in the 10-100% (15-150 nm) scale range. Prior to j use, um versus sem graphs were developed for the meters by 10 point calibrations using high accuracy (f 1% instantaneous) lab rotameters. During the leak test program, weekly 3 point standartilzations were performed on the field rotameters to verify continued accuracy. The acceptance criteria for these -
standardizations was a variance of no more than 4% from the calibration graphs. If meters were repaired or the 3 point standartilzation exceeded the inaccuracy limit, a new 10 point calibration was performed. Scale readings on the leak rate procedure (SP 1303-11.18) data sheets were evaluated and corrected for temperature. Conservative bias was introduced into the results by assuming 15 nm (10% of scale) as the minimum scale.
l 6.2 Access Hatch and Pume Valve Testina Frrors The measured pressure drops were corrected by adding the minimum scale increment of the gage used for both the Heise gage and the barmeter. This conservatively corrected for the resolution and repeatability errors. Gages used were recently calibrated. A minimum one hour temperature / pressure stabilization period was used prior to each pressure drop test. The access hatches and purge valves are not instrumented to allow tmperature corrections. i
- 7. LESSONS LEARNED /IMPROVEMENPS/ DEGRADATION 7.1 The As-Found MAXPATH leakage was 58.5% of the 'Ibchnical Specification t
limit of 104,846 SCCM. Of this total 38,527 SOCM was attributed to .
! CA-V2 seat leakage and industrial cooling R.B. closed loop piping I
syst m joint / packing leakage.
CA-V2 was scheduled to be replaced during the 10R Refueling Outage.
l However, due to manufacturing scheduling, the valve was unavailable
! during the 10R Refueling Outage. The valve is scheduled to be replaced by the end of 1993. Repairs to minimize leakage of the R.B.
closed cooling loop piping will be performed during 11R Outage.
7.2 leakage noted on the outlet side of the Industrial Cooling Closed Ioop will be minimized by scheduling maintenance on packing and bonnet gaskets for the valves inside the Reactor Building on that loop.
APPEt0G 99
7.3 'IMI-l perfonned a combination IIRT/ILRT at the beginning of the refueling outage. About two-thirds of the ILRT was perfonned just prior to the IIRT test. The inner valves were tested using IIRT building pressure while the outer valves wem tested by pressurizing the interspace using IIRT pmssure rigs. Considerable man hours and radiation exposure wem reduced since the IIRT line up also supported the ILRT. .,
- 8. ut.tne2CES 8.1 1430-Y-22, Standardization of Flow Rotameters i
8.2 SP 1303-11.18, Reactor Building Incal Irak Rate Testing i 8.3 Three Mile Island, Unit 1, Technical Specification 4.4.1 ,
8.4 DiI Surveillance File (Records stored in CARIRS, Data Base AA60 [
REC. TYPE 018-12) ,
l 8.5 SP 1303-11.25, Reactor Building Local Irakage Access Hatch Door Seals l
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100 APPD4DG j
199310R OUTAGE LOCAL LEAK RATE TEST RESULTS
$ i COMPONENT AS-FOUND AS-LEFT EMERGENCYACCESSHATCH 1634 1634 i i
- PERSCtNELACCESS1%TCH 463 463 !
- EOUIPMENT FLANGE 90 90 AH-V1 A/1B 1248 1248 AH-V1 C/1 D 1794 1794 CA-V1/3/13 16 (SEE CA-V13)
.; CA-V13 (SEE CA-V1/3/13) 67 CA-V2 18634 18634 CA-V4A 17 17
\ ;
CA-V5A 86 86 ;
l 1 CA-V4B 11 11 '
CA-V5B 1916 1916 I CA-V192 23 23 1
CA-V189 1264 1264 I
, CF-V2A 15 67 l l
CF-V20A 68 68 l CF-V2B 44 67 CF-V20B 2232 2232 CF-V12A 55 55 CF-V19A 1246 1246 CF-V12B 262 262 CF-V198 1139 1139 CM-V1 17 17 CM-V2 85 85 j CM-V3 85 85 CM-V4 31 31 DH-V69 15 15 DH-V64 281 281 FTT EAST 67 67 FTT WEST 67 67 HM-V1 A 79 79 g,
HM-V1 B 85 85
. . .. _= __ - -- - .
i i HM-V2A 79 79 HM-V2B 85 85 HM-V3A 16 16 HM-V3B 16 16 HM-V4A 16 16 HM-V4B 16 16 HP-V1 17 17 i
i HP-V6 113 113 H R-V22A/22B 59 59 HR-V2A/2B 70 70 j HR-V23A 59 59 1
l HR-V23B 59 59 1
i H R-V4 A/4 B 70 70 l l A-V20/6 85 85 IC-V2 16 16 IC-V3 67 67 IC-V18 49 49 IC-V4 68 68 :
lC-V16 360 360 l
IC-V6 319 319 MU-V2A 16 16 MU-V2B 16 16 ;
! MU-V3 67 67 [
l M U-V18 276 276 4 M U-V116 1476 1476 MU-V20 79 79 MU-V25 13 13 MU-V26 90 90 Ni-V26 16 16 NI-V27 16 16 NS-V11 16 16 NS-V15 290 290 i NS-V35 16 16 NS-V4 303 3g9 303 PENET 104 56 56
PENET 105 69 69 PENET 106 67 67 PENET 210 56 56 PENET 211 56 56 PENET 241 67 67 PENET 414 55 55 PENET 417 67 67 PENET 221 67 67 PENET 222 67 67 P P-V210 INCLUDED IN AH LEAKAGE INCLUDED IN AH LEAKAGE P P-V211 INCLUDED IN AH LEAKAGE INCLUDED IN AH LEAKAGE PP-V212 INCLUDED IN AH LEAKAGE INCLUDED IN AH LEAKAGE PP-V213 INCLUDED IN AH LEAKAGE INCLUDED IN AH LEAKAGE RB-V2A 85 85 RB-V7 376 376 RB CLOSED LOOP 19893 19893 SA-V3/2 86 86 S F-V23 63 63 WDG-V3/4 67 67 WDL-V303 16 84 WDL-V304 3470 3470 WDL-V534/535 67 67 MAX PATH TOTAL 61379 61379 MIN PATH TOTAL 9650 9844 103