ML20044G257
| ML20044G257 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/26/1993 |
| From: | Padleckas A, Schaick A V GENERAL PHYSICS CORP. |
| To: | |
| Shared Package | |
| ML20044G242 | List: |
| References | |
| GP-R-643-93-006, GP-R-643-93-6, NUDOCS 9306020241 | |
| Download: ML20044G257 (108) | |
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CAROLINA POWER & LIGHT COMPANY P
Brunswick Nuclear Project Unit 2 h
FINAL REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST REPORT Reviewed by: c
, Van Schaick Reviewed by: , .,
A.M. Padleckas April 26,1993 _ j GENERAL PHYSICS CORPORATION GP-R-643-93-006 9306020241 930518 PDR ADOCK 05000324 P pon
I CAROLINA POWER & LIGHT GEh?.RAL PHYS 1CS CORPORATION Brunrwick Nuclear Project Unit 2 ERT GP-R-643-93-006 TABLE OF CONTENTS L INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 t II. TEST SYNOPSIS ....................................... 2 A. Pre-pressurization Activities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 B. Test Summary Time-Line . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 C. Containment Pressurization ............................. 3 D. Containment Atmosphere Stabilization . . . . . . . . . . . . . . . . . . . . . . . 3 E. ILRT Test Period . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
- F. Verification Test . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 III. TEST DATA
SUMMARY
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 A. Plant Information ................................... 5 B. Technical Data . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 C. Test Results - Type A ................................ 5 D. Test Results - Type B and C Tests . . . . . . . . . . . . . . . . . . . . . . . . . 7 E. Integrated i enbge Rate Measurement System . . . . . . . . . . . . . . . . . . 7 F. Information Retained at Plant . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 IV. ANALYSIS AND INTERPRETATION . . . . . . . . . . . . . . . . . . . . . . . . . 12 A. "As-Left" Type B and C Penalties . . . . . . . . . . . . . . . . . . . . . . . . 12 B. " As-Found" Type B and C " Savings" . . . . . . . . . . . . . . . . . . . . . . 18 C. Volume Change Corrections . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 D. " As-Found" ILRT Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20 E. "As-Left" ILRT Results .............................. 20 V. REFERENCES ........................................ 21 i
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~ CAROUNA POWER & UGHT GEhERAL PHYSICS CORPORATION :
Brunrwick Nuclear Project Unit 2 H.RT GP-R-643-93-006 ,
VI. ' APPENDICES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22 l 4
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- APPENDIX A STABILIZATION PHASE DATA -
APPENDIX B ILRT TEST DATA AND PLOTS
'i APPENDIX C VERIFICATION TEST DATA - AND I PLOTS '!
APPENDIX D INSTRUhENT SELECTION GUIDE .l CALCULATION ,
APPENDIX E SENERAL PHYSICS ILRT COMPUTER PROGRAM DESCRIPTION j i
APPENDIX F LOCAL LEAKAGE RATE TEST SUMMARIES -!
APPENDIX G SENSOR LOCATIONS AND VOLUME !
FRACTIONS f a
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i CAROUNA POWER & UGHT GEhT.RAL PHYSICS CORPORATION Brunswick Nudear Project Unit 2 H.RT GP-R443-93-006 I. INTRODUCTION 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 do not exceed the allowable leakage '
rates specified in the Plant Technical Specifications.
t The purpose of this report is to provide information pertinent to the activities related to the preparadon, test performance, and reporting of the Brunswick Nuclear Project Unit 2 Integrated Izakage Rate Test (ILRT).
Highlights of activities and events which occurred prior to and during the ILRT are presented in Section II, Test Synopsis.
Section III, Test Data Summary, contains data and results necessary to demonstrate containment atmosphere stabilization, acceptable leakage rate, and a successful verification test. In addition, plots provided in Appendices B and C supply a visual i history of containment atmospheric conditions beginning with the 26.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ILRT test period and ending with the verification test.
Information in Section IV, Analysis and Interpretation, supplies the technical details associated with the ILRT computer program and its associated hardware as well as the instrumentation used during the ILRT. ,
Section V, References, lists the documents used for the conduct of the ILRT.
The successful periodic Type A and verification tests were performed according to the -
requirements of the Brunswick Nuclear Project Unit 2 Technical Specifications and 10 CFR 50, Appendix J. The test method used was the Absolute Method, as described in ANSI /ANS-56.8-1987, " Containment System Ieakage Testing Requirements".
Leakage rates were calculated using the Mass Point Analysis technique as described in ANSI /ANS-56.8-1987. Total Time Analysis equations from ANSI N45.4-1972,
" Leakage-Rate Testing of Containment Structures for Nuclear Reactors" were run concurrently for informational purposes. The test results are reported in accordance with the requirements of 10 CFR 50, Appendix J, Section V.B.3.
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i CAROLINA POWER & LIGHT GENERAL PHYSICS CORPORATION Brun.rwick Nuclear Project Unit 2 JLRT GP-R-643-93-006 II. TEST SYNOPSIS Prior to containment pressunzation at 0355 (first data point at 0359) on February 25, 1993, site personnel were engaged in prerequisite activities for the conduct of the ILRT.
The ILRT was conducted at the end of the outage. The following discussion highlights some of the activities that were essential to the success"ul and timely completion of the.
ILRT. These items are presented in chronological order.
A. Pre-pressurization Activities These activities included ILRT procedure review and finalization, ILRT computer program checkout and linkup to the Fluke Data Acquisition System, ILRT instrumentation calibration, installation, and operability checks. A containment temperature survey had been performed prior to the test in the ventilation lineup used for the ILRT.
The ILRT test procedure was reviewed against the requirements of the Plant Technical Specifications; 10 CFR 50, Appendix J; ANSI /ANS-56.8-1987; and recent plant modifications.
The ILRT instrumentation was calibrated prior to the ILRT as recommended by ANSIN45.4-1972, Sections 6.2 and 6.3. FinalILRT instrumentation operability checks and in-situ checks, as specified in ANSI /ANS-56.8-1987, Section 4.2.3.1, were performed to ensure that all instrumentation was operating correctly.
Calibration records for the ILRT instrumentation system components are retained at the plant.
B. Test Summary Time-Line Phase Time Frame Duration Pressurization From: 0359 on 2/25/93 7.77 hours8.912037e-4 days <br />0.0214 hours <br />1.273148e-4 weeks <br />2.92985e-5 months <br /> To: 1145 on 2/25/93 Stabilization From: 1200 on 2/25/93 4.00 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> To: 1600 on 2/25/93 ILRT Test From: 1615 on 2/25/93 26.50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> To: 1845 on 2/26/93 Verification Test From: 1900 on 2/26/93 4.00 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> To: 2300 on 2/26/93 j
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C4ROUNA PORT.R & UGHT GENERAL PHYSICS CORPORATION Brunswick Nuclear Project Unit 2 ERT GP-R-643-93-006 ;
C. Containment Pressurization Containment pressurization started at 0355 on February 25,1993 using two 1500 cfm diesel-driven 100% oil-free air compressors. The pressurization rate was ,
maintained at approximately 7-8 psi per hour. The pressurization rate was j
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gradually reduced as the containment pressure approached 42 psig by reducing the number of operating compressors. All compressors were stopped when the containment pressure reached 65.1 psia (50.4 psig) at 11:45, on February 25, l 1993. This was within the procedural limits of 49.0 +2, -0 psig.
During pressurization a containment walkdown was performed to identify potential leakage. No excessive measurable leakage was observed.
Pressurization was conducted without the use of the Reactor Containment Fan Cooling Units. -
3 D. Containment Atmosphere Stabilization i
The stabilization phase was started at 1200 on February 25,1993. By 1600 on February 25,1993, the temperature stabilization criteria of ANSI /ANS-56.8-1987 had been met.
E. ILRT Test Period The ILRT was officially started at 1615 on February 25, 1993 and was successfully completed at 1845 on February 26,1993. The maximum allowable leakage rate (L) for the containment is 0.5 %-wt. per day with a test acceptance limit of 0.375 %-wt. per day (0.75 LJ. The Total Time and Mass Point Analyses were run concurrently on the General Physics ILRT Computer Program.
The leakage rate results are as follows:
Total Time Mass Point Analysis Analysis
%-wtJday %-wtJday Calculated T mbge Rate 0.3173* 0.3137*
95 % Upper Confidence 0.3218' O.3180*
I.cakage rate
- Does not include penalties for nonstandard alignments and water level changes 3
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- l. i C4ROUNA POWER & UGHT GEhERAL PHYSICS CORPORATION
Brunswick Nuclear Project Unit 2 llRT GP-R-643-93-006 i F. Verification Test !
A successful verification test was conducted following the ILRT. _ At 1845 on _ ;
February 26, 1993, a leakage rate of 4.5 scfm (corrected for actual versus' .!
calibration conditions) was imposed on the primary containment. The 4.5 scfm +
leakage imposed (L.) on the existing containment leakage was slightly less than '
L (0.5 %-wt./ day) at 0.4995 %-wt. per day. The verification phase'was completed at 2300 on February 26,1993. '
The verification test results are presented below: j Total Time Mass Point- l Analysis -
Analysis ,
%-wtJday %-wtJday '
i Leakage Rate (L.) 0.3178 0.3137 Imposed Leak (I,) 0.4995 0.4995 i
Lower Limit:
I, + L,,, -0.25 L, 0.6923 0.6882 l Composite Leakage (L) 0.7427 0.7309- !
Upper Limit:
L, + L.,, + 0.25 L, 0.9423' O.9382 j u
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I CAROUNA POnER & UGHT GEhTRAL PHYSICS CORPORATION Brunrwick Nuclear Project Unit 2 H.RT GP-R-643-93-006 III. TEST DATA
SUMMARY
A. Plant Information i
Owner Carolina Power & Light Company Plant Brunswick Unit 2 Iocation Southport, North Carolina P
Containment Type BWR Mark I NSSS Supplier, Type General Electric BWR-4 Date Test Completed February 26,1993 B. Technical Data Containment Net Free Volume 294,981 cubic feet Design Pressure 62 psig j Design Temperature 300* F Drywell, 220' F Torus Calculated Peak Accident Pressure 49.0 psig C. Test Results - Type A
- Test Method Absolute Test Pressure 50.0 psig P
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CAROUNA POWER & UGHT GENERAL PHYSICS CORPORATION Brunswick Nuclear Projea Unit 2 HRT GP-R-643-93-DO6 Integrated Ienhge Rate Total Time Analysis Test Results (Presented for '
- information only):
Calculated Leakage Rate, L., 0.3178 %-wt./ day 1:
95 % Upper Confidence Limit i, Leakage Rate 0.3218 %-wt./ day Integrated Leakage Rate Mass Point Analysis Test Results Calculated Ienbge Rate, L , 0.3137 %-wt./ day 95 % Upper Confidence Limit Leakage Rate 0.3180 %-wt./ day .
l Maximum Allowable Izakage Rate, L, 0.5 %-wt./ day I ILRT Acceptance Criteria,0.75 L, 0.375 %-wt./ day Verification Test Imposed Ieakage .,
Rate, L. 4.5 scfm or 0.4995 %-wt./ day Verification Test Total Time Analysis Results and Limits (Presented for ,
information only)
Upper Limit 0.9423 %-wt./ day (L + L , + 0.25 L.) l Calculated Composite 0.7427 %-wt./ day Leakage Rate, I, tower umit 0.6923 5-wt./ day [
(L + L., - 0.25 L.)
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i CAROUNA POWER & UGHT GENERAL PHYSICS CORPORATION Brunswick Nuclear Projea Unit 2 H.RT GP-R-643-93-006 ,
Verification Test Mass Point Analysis Results and Limits Upper Limit 0.9382 %-wtJday ,
(L + L ,, + 0.25 L.)
Calculated Composite 0.7309 %-wtJday Leakage Rate, I, Iower Limit 0.6882 % wt./ day.
(L. + L., - 0.25 L.) .
Report Printouts The report printouts of the ILRT and verification test calculations for the Total Time and Mass Point Analyses are provided in Appendices B and C. Stabilization data is provided in Appendix A.
r D. Test Results - Type B and C Tests The total acceptance criteria for Type B and C tests is 0.6L, (159.78 scfh). A summary of localleakage rate test results since the ILRT in 1991 are included in t
Appendix F.
E. Integrated Leakage Rate Measurement System
- 1. Absolute Pressure Quantity 2 Manufacturer Paroscientine Type Quartz Manometer Model 760-100A' 0 - 100 psia -l Range t
Accuracy 0.01 psia 7
i CAROUNA POWER & UGHT GENERAL PH1' SICS CORPORA 170N Brunswick Nuclear Projea Unit 2 ERT . GP-R-643-93M Repeatability 0.005% Full Scale (0.005 psia)-
Resolution 0.001 psia Sensor Sensitivity Error 0.001 psia
- 2. Drybulb Temperature Quantity 24 Manufacturer Rosemount Type Model 78-39-11, 3-wire 100 ohm platinum resistance temperature detectors (RTDs)
Range, calibrated 32 - 120* F Accuracy i 0.02* F Repeatability, Sensor i 0.090* F Scanner i 0.072* F A/D Converter i 0.005 % Input Resolution 0.001' F Sensor Sensitivity Error 0.10* F
- 3. Relative Humidity Quantity 10 Manufacturer Foxboro Type Model 2781 Dewcels with 2-Model 2712-6 Heater power units Range, calibrated 32-160* F Accuracy i 1.5* F 8
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CAROLINA POWER & LIGHT Brunswick Nuclear Project Unit 2 ERT GENERAL PHYSICS CORPORATION GP-R-643-93-006 .
l.l Repeatability, Scanner i 0.072* F A/D Converter 0.005 % Input -
Resolution 0.001* F l Sensor Sensitivity Error 0.10* F
- 4. Verification Flow I t
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.. Quantity 2 Manufacturer Brooks .i*
g Type Model 1110 Rotameter , ;
Range 0 - 10 scfm & 0 - 13.3 scfm .
,T Accuracy 1% full scale - 'fi cr
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- 5. Readout Device t
Quantity 1, plus 1 backup ;
Fluke !
Manufacturer Type Model 2285B, Model 2286A Dataloggers l l.
Repeatability I Drybulb Temp - i 0.072* F -
r Dewpoint Temp 0.072* F -l Resolution 1 i
Drybulb Temp _ 0.001* F t t
i Dewpoint Temp 0.001'F i
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CAROUNA POWER & UGHT GEhERAL PHYSICS CORPORA 110N Brunswick Nuclear Pmject Unit 21LRT GP-R-643-93-lD6 The Instrumentation Selection Guide (ISG) value from ANSI /ANS-56.8-1987 based on a 26.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> test and the above ILRT instrumentation configuration is 0.0078 %-wt./ day.
(Refer to Appendix D for calculations.) The sensor locations and volume fractions as installed for the ILRT are shown in Appendix G.
F. Information Retained at Plant The following information is available for review at the Brunswick Nuclear Project site:
- 1. A listing of all containment penetrations, including the total number, size, and function.
- 2. A listing of normal operating instrumentation used for the leakage test.
- 3. A system lineup (at time of test), showing required valve positions and status of piping systems.
- 4. A continuous, sequential log of events from the initial survey of containment to restoration of tested systems.
- 5. Documentation ofinstrumentation calibrations and standards, including a sensor failure analysis.
- 6. Data to verify temperature stabilization criteria as established by test procedure (Appendix A).
- 7. The working copy of the test procedure that includes signature sign-offs of procedural steps.
- 8. The procedure and data that verifies completion of penetration and valve testing, including as-found leak rates, corrective action, and final leak rates. ,
- 9. Computer printouts ofILRT data and automated data acquisition printouts I
along with a summary description of the computer program.
- 10. Calibration certification of the test equipment and instrumentation used for i the ILRT measurement system. :
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i CAROLINA PO%ER & LlGHT GENERAL PH131CS CORPORATION Brunswick Nuclear Project Unit 2 ERT GP-R-643-93M
- 12. A listing of test exceptions including changes in the containment system ,
boundaries.
- 13. Description of sensor malfunctions, repairs, and methods used to ,
redistribute volume weighting fractions to operating instrumentation.
- 14. A review of confidence limits of test results with accompanying computer printouts.
- 15. Description of the method of leakage rate verification.
- 16. ILRT data plots obtained during the test.
- 17. The P& ids of pertinent systems.
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t CAROUNA POWER & UGHT GENERAL PHYSICS CORPORATION Brurtrwick Nuclear Project Unit 2 JLRT GP-R-643-93-006 IV. ANALYSIS AND INTERPRETATION The 95% upper confidence limit (UCL) Total Time and Mass Point leakage rates calculated during the ILRT were less than the test acceptance criteria of 0.75 I, (0.375
%-wtdday). Additions to the calculated leakage rates must be made to account for ,
i penetration paths not exposed to the ILRT pressure and for changes in the net free containment volume due to changes in containment water levels. These additions are discussed below. .
A. "As-Left" Type B and C Penalties Penetration paths not exposed to the ILRT pressure and the corresponding minimum pathway leakage mtes are as follows:
Penetration Test Data Penetration System / Minimum Number Component Pathway Local Test Error Test Error T enkage Rate (scfh) Squared .
(sefh)
X-009A Feedwater/ 0.850 0.218 0.0475 HPCI r
B21-F032A/
E41-F006 X-009B Feedwater/ 1.514 0.284 0.0807 RCIC B21-F032B/
E51-V88 X-012 RHR 0.365 0.343 0.1176 SHUTDOWN COOLING E11-F008/
E11-F009 X-013A RHR LPCI 0.089 0.284 0.0807 INJECTION
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CAROLINA POWER & LIGHT GENERAL PHYSICS CORPORATION Brunswick Nuclear Project Unit 2 JLRT GP-R-643-93-036 Penetration Test Data i
Penetration System / Minimum Number Component Pathway Local Test Error Test Error
- I2akage Rate (sefh) Squared (scfh)
X-014 RWCU 0.089 0.284 0.0837 G31-F001 X-016A CORE SFRAY 3.763 0.284 0.0807 E21-F005A .
X 017 RHR RPV 0.045 0.284 9.0807 .
HEAD SPRAY E11-F022/
E11-F023 t X-018 DRYWELL 0.090 0.284 0.0807 DRAINS G16-F003 X-019 DRYWELL 0.090 0.284 0.0807 l DRAINS t
G16-F019 X-023/ X-024 RBCCW 2.163 0.382 0.1459 SUPPLY RCC-V28/V52 X-039A RHR 0.089 0.284 0.0807 CONTAINhENT SPRAY E11-F016A X-056E RECIRC 0.506 0.343 0.1176 B32-F019/
B32-FO20 l X-062A RECIRC 0.090 0.284 0.0807 !
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P i i CAROUNA POWER & UGHT GEhERAL PHYSICS CORPORATION Brurswick Nuclear Project Unit 2 JLRT GP-R-643-93-006 >
Penetration Test Data i
Penetration System / Minimum Number Component Pathway Local Test Error Test Error !
Leakage Rate (sefh) Squared l (sefh)
X-077B RBCCW 0.090 0.284 0.0S07 SAMPLE RCC-SV-1222B X-077C RBCCW 0.465 0.284 0.0807 SAMPLE >
RCC-SV-1222C X-078A RECIRC 0.223 0.284 0.0807 B32-V30 X-100A ELECTRICAL 0.091 0.289 0.0835 PENETRATION !
X-100B ELECTRICAL 0.091 0.289 0.0835 PENETRATION X-100C ELECTRICAL 0.091 0.289 0.0835 PENETRATION X-100D ELECTRICAL 0.091 0.289 0.0835 PENETRATION X-100E ELECTRICAL 0.091 0.289 0.0835 PENETRATION X-100F ELECTRICAL 0.091 0.289 0.0835 PENETRATION X-100G ELECTRICAL 0.091 0.2o9 0.0835 l PENETRATION l X-100H ELECTRICAL 0.091 0.289 0.0835 PENETRATION X-101A ELECTRICAL 0.020 0.222 0.0493 PENETRATION 14 !
i CAROUNA POWER & UGHT GEhT.RAL PHYSICS CORPORATION Brunswick Nuclear Project Unit 2 ILRT GP-R-613-93M Penetration Test Data Penetration System / Minimum Number Component Pathway Local Test Error Test Enor Inkage Rate (scfh) Squared (sefh)
X-101C ELECTRICAL 0.020 0.222 0.0493 PENETRATION X-101D ELECTRICAL 0.268 0.289 0.0835 PENETRATION X-101F ELECTRICAL 0.091 0.289 0.0835 i PENETRATION i
X-102A ELECTRICAL 0.092 0.289 0.0835 PENETRATION X-102B ELECTRICAL 0.092 0.289 0.0835 PENETRATION X-102C ELECTRICAL 0.091 0.289 0.0835 PENETRATION X-102E ELECTRICAL 0.091 0.289 0.0835 PENETRATION .
X-102F ELECTRICAL 0.091 0.289 0.0835 PENETRATION X-102H ELECTRICAL 0.475 0.289 0.0835 >
PENETRATION ;
X-103A ELECTRICAL 0.091 0.289 0.0835 PENETRATION X-103B ELECTRICAL 0.091 0.289 0.0835 PENETRATION '
X-104A ELECTRICAL 1.310 0.289 0.0835 i PENETRATION X-104B ELECTRICAL 0.092 0.289 0.0835 PENETRATION ,.
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. Brunswick Nuclear Project Unis 2 H.RT GP-R-643-93-006 Penetration Test Data Penetration System / Minimum Number Component Pathway Imal Test Error Test Error Leakage Rate (sefh) Squared (scfh)
X-104C ELECTRICAL 0.091 0.289 0.0835 PENETRATION X-104E ELECTRICAL 0.091 0.289 0.0835 PENETRATION X-104F ELECTRICAL 0.091 0.289 0.0835 PENETRATION X-104G ELECTRICAL 0.091 0.289 0.0835 PENETRATION X-105B ELECTRICAL 0.020 0.222 0.0493 PENETRATION X-105C ELECTRICAL 0.020 0.222 0.0493 PENETRATION X-105D ELECTRICAL 0.080 0.222 0.0493 PENETRATION X-105E ELECTRICAL 0.020 0.222 0.0493 PENETRATION X-105G ELECTRICAL 0.092 0.289 0.0835 PENETRATION X-105H ELECTRICAL 0.092 0.289 0.0835 PENETRATION X-105J ELECTRICAL 0.091 0.289 0.0835 PENETRATION X-105K ELECTRICAL 0.091 0.289 0.0835 PENETRATION i
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f CAROLINA POWER & LIGHT GENERAL PHYSICS CORPORATION Brunswick Nuclear Projea Unit 2 H.RT GP-R-643-93-006 Penetration Test Data Penetration System / Minimum Number Component Pathway local Test Error Test Error Leakage Rate (scfh) Squared (sefh)
X-211 A RHR POOL 0.089 0.284 0.0807 SPRAY E11-F027A X-232A ELECTRICAL 0.091 0.289 0.0835 PENETRATION X-232B ELECTRICAL 0.091 19 0.0835 PENETRATION X-232C ELECTRICAL 0.092 0.289 0.0835 PENETRATION X-232D ELECTRICAL 0.091 C.289 0.0835 PENETRATION Sum Totals 15.488 4.44565 15.488 i 2.108 /E(Error *)
ggy g L,=
i Lz,,,,,u7,4 1 oL z = Lz ,,,,,,,g 1 ]E (Error *)
LLRT results based on the above minimum pathway leakage rate (MNPLR) results and the conservative inclusion of measurement error equate to a Type B and C penalty addition of 17.596 scfh. This converts to an addition of 0.0292 Swt. per day.
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I CAROUNA POWER & UGHT GENERAL PHYSICS CORPORATION Brun. wick Nuclear Project Unit 2 HRT GP-R-643-93-CD6 B. "As-Found" Type B and C " Savings" The Type B and C localleak rate test (LLRT) post-repair MNPLRs are compared to the pre-repair MNPLR. If the post-repair MNPLR is smaller, a leakage savings -
has been realized. The total of the improvements, or leakage savings realized from repairs is applied to the 95 % Upper Confidence Limit (UCL) plus the Type B and C penalties listed earlier to determine the "As-Found" condition of the containment. If the post-repair MNPLR is 2 the pre-repair MNPLR, no leakage savings has been realized for that penetration and no contribution is made to the "As-Found" condition of the containment.
Penetration As-Found As-Left MNPLR Leakage- Test Test Error No. MNPLR Savings Error Squared (scB) (scfh)
X-009B 4.626 i 0.284 1.514 0.284 3.112 0.284 0.0807 0.284 0.0807 X-012 13.165 4.65 0.3645 0.343 12.8005 4.65 21.6225 0.343 0.1176 X-014 12.170 1.774 0.089 i 0.284 12.081 1.774 3.1471 0.284 0.0807 X-025 8.980 i 1.774 8.100 i 1.580 0.920 1.774 3.1471 0.020 0.218 0.218 0.0475 0.020 i 0.218 0.218 0.0475 1.580 2.4964 X-035A 0.090 0.284 0.089 0.284 0.001 0.284 0.0807
- 0.284 0.0807 X-056E 7.970 i 2.080 0.5075 0.343 7.4625 2.080 4.3264 0.343 0.1176 X-205 8.980 0.284 2.800 i 0.284 6.220 0.284 0.0807 0.020 i 0.218 0.218 0.0475 0.020 i 0.218 0.218 0.0475 0.284 0.0807 Sum Total 42.59 5.97 42.59 , 35.7 G) sefh a nm- ,
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i CAROUNA POWER & UGHT GEhT.RAL PHYSICS CORPORATION Brun.rwick Nuclear Project Unit 2 ILRT GP-R-643-93-006 >
LLRT results based on the above and the conservative inclusion of measurement error equate to a Type B and C penalty addition of 48.56 scfh. This converts to an addition of 0.0909
%-wt./ day.
C. Volume Change Corrections The following volumes were monitored for liquid hvel changes which would ,
affect the containment net free volume:
VOLUME MONITORED LEVEL CHANGE VOLUME CHANGE (ft3)
REACTOR VESSEL 13.47 Inches +34.0252 TORUS _ 0.06 Inches +48.1248 DRYWELL FLOOR 0 Gallons 0 DRAIN TANK 1 DRYWELL EQUIPMENT 0 Gallons 0 DRAIN TANK i
TOTAL 82.1500 Based on the volumes monitored,- the containment net free volume increased during the ILRT by 82.15 ft .8 Since this is a conservative representation already included in the reported ,
leakage rates, no additional penalty or correction is made.
19
i CAROLINA POWER & LIGHT GENERAL PH151CS CORPORATION ,
Brunswick Nuclear Project Unit 2 HRT GP-R-643-93-006 D. "As-Found" ILRT Results ;
The As-Found ILRT leabge rate including the required additions is as follows:
Total Time Mass Point Analysis Analysis
(% wtJday) (% wtJday) '
95 % UCLIeakage Rate 0.3218 0.3180 Type C Penalties 0.0292 0.0292 Volume Change 0.0000 0.0000 Leakage Savings 0.0909 0.0909 As-Found 95 % UCL Leakage Rate 0.4419 0.4381 '
The As-Found Total Time and Mass Point 95 % UCL leakage rates are greater i than the test acceptance criteria value of 0.75 L. (0.375 %-v4./ day).
E. "As-Left" ILRT Results The As-Ieft ILRT leakage rate including the required additions is as follows:
Total Time Mass Point Analysis Analysis
(% wtJday) (% wt./ day) 95 % UCL Leakage Rate 0.3218 0.3180 Type C Penalties 0.0292 0.0292 i
Volume Change 0.0000 0.0000 l l
As-Left 95 % UCL T nh e E Rate 0.3510 0.3472 i
The As-Left Total Time and Mass Point 95 % UCL leabge rates are less than the test acceptance criteria value of 0.75 L. (0.375 %-wt./ day). l 20
I CAROUNA POWER & LIGHT GENERAL PHYSICS CORPORATION Brunswick Nuclear Pwject Unit 2 H.RT GP-R-643-93406 i
i V. REFERENCES A. . Brunswick Periodic Test Procedure, PT-20.5, Integrated Primary Containment Ie,ak Rate Test B. Brunswick Unit 2 Technical Specifications.
C. Brunswick Unit 2 Updated Final Safety Analysis Report.
D. Code of Federal Regulations, Title 10, Part 50, Appendix J, Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors.
E. ANSI N45.4-1972, T mbge-Rate Testing of Containment Structures for Nuclear Reactors.
F. ANSI /ANS-56.8-1987, Containment System Leakage Testing Requirements.
[
21
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i VI. APPENDICES l
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9 1
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3 APPENDIX A STABILIZATION PHASE DATA s
v 9
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s b
8 9
.. .. ~
TSTABLIZATION MODE. TIME : 1600 ,
. OPE'9NS MODE
SUMMARY
AANUAL DATA ENTRY # OF DATA POINTS = 17 2 - PARAMATER GRAPHS MODE DURATION (IN HRS) = 4.00 l3 -. SENSOR PLOTS TOT TIME MEASURED LEAK = 0.2677 4 - SENSOR DIFFERENTIALS TOT TIME CALCULATED LEAK = 0.2906 -
5 - ANSI STABILIZATION CRITERIA TOT TIME 95% UCL = 0.3224-6 - BN-TOP-1 STAB. CRITERIA MASS PT LEAK = 0.2826 7 - ANSI CRITERIA PRINTOUT MASS PT 95% UCL = 0.3114 8 - BN-TOP-1 CRITERIA PRINTOUT 9 - REPRINT CURRENT DATA POINT i P - PASS WORD MENU 0 - FLASH OFF
~I ANSI TEMPERATURE STABLIZATION CRITERIA MET BN-TOP TEMPERATURE STABLIZATION CRITERIA MET POINT
SUMMARY
- CURRENT VALUE/ DIFFERENCE FROM PREVIOUS POINT AVG TEMP: 72.742/ -0.032 AVG PRESS: 64.783/ -0.006 MASS: 96879.48/ -3.391 AVG DEW PRESS: 0.1888/+0.0006 TOTAL PRESS: 64.971/ -0.006 k
I 5
STABLE MODE BRUNSWICK UNIT 2 Page 1 TEMP STABILIZATION
SUMMARY
UNIT 2 ANSI /ANS-56.8 BN-TOP-1 .
[
TIME TEMP 1HR F/HR 4HR F/HR 4-1 HR BN dT BN dT2 0.00 73.622 0.0000 0.0000 0.0000 0.0000 0.0000 O.25 73.510 0.0000 0.0000 0.0000 0.0000 0.0000 '
0.50 73.414 0.0000 0.0000 0.0000 0.0000 0.0000 O.75 73.331 0.0000 0.0000 0.0000 0.0000 0.0000 1.00 73.258 0.3640 0.0000 -0.3640 0.0000 0.0000 l 1.25 73.192 0.3187 0.0000 -0.3187 0.0000 0.0000 1.50 73.130 0.2839 0.0000 -0.2839 0.0000 0.0000 1.75 73.074 0.2572 0.0000 -0.2572 0.0000 0.0000 2.00 73.025 0.2332 0.0000 -0.2332 -0.2986 0.0000 ,
0.2105 2.25 72.981 0.0000 -0.2105 -0.2646 0.1360 2.50 72.938 0.1920' O.0000 -0.1920 -0.2379 0.1066 I 0.0937-2.75 72.902 0.1719 0.0000 -0.1719 -0.2145 3.00 72.865 0.1605 0.0000 -0.1605 -0.1969 0.0705 3.25 72.829 0.1524 0.0000 -0.1524 -0.1815 0.0617 3.50 72.801 0.1367 0.0000 -0.1367 -0.1644 0.0684 -
3.75 72.774 0.1282 0.0000 -0.1282 -0.1500 0.0574 ,
4.00 72.742 0.1222 0.2200 0.0978 -0.1414 0.0346 [
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1 a
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STABLE MODE Page 1 I AVERAGE DATA VALUES DATE TIME RTD DEW PT. VAP PRESS DRY PRESS MASS ;
56 0.00 73.622 49.963 0.178 64.919 96922.73 '
56 0.25 73.510 50.146 0.179 .64.905 96922.67 :
56 0.50 73.414 50.286 0.180 64.893 96922.30 56 0.75 73.331 50.366 0.180 64.883 96921.85 i 56 1.00 73.258 50.521 0.181 64.872 96919.46 ;
56 1.25 73.192 50.629 0.182 64.863 96917.66 1 56 1.50 73.130 50.685 0.183 64.854 96916.36
- 56 1.75 73.074 50.826 0.184 64.845 96913.02 56 2.00 73.025 50.863 0.184 64.838 96910.46 56 2.25 72.981 51.032 0.185 64.829 96906.11 56 2.50 72.938 51.060 0.185 64.822 96903.37 l 56 2.75 72.902 51.138 0.186 64.815 96899.68 :
56 3.00 72.865 51.213 0.186 64.808 96896.02 56 3.25 72.829 51.366 0.187 64.801 96891.76 56 3.50 72.801 51.434 0.188 64.795 96887.30 56 3.75 72.774 51.512 0.188 64.789 96882.88 56 4.00 72.742 51.592 0.189 64.783 96879.48 .
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STABLE MODE '
BRUNSWICK UNIT 2 Page 1 i
LEAKAGE RATE
SUMMARY
UNIT 2 .
TOTAL TIME MASS / POINT DATE TIME TTLM LMCALC SL LAM L95 ;
56 0.00 0.0000 0.0000 0.0000 0.0000 0.0000 56 0.25 0.0056 0.0000 0.0000 0.0000 0.0000 -
56 0.50 0.0210 0.0210 0.0000 0.0217 0.1002 56 0.75 0.0289 0.0301 0.0603 0.0297 0.0485 56 1.00 0.0810 0.0692 0.1462 0.0733 -0.1325 ,
56 1.25 0.1004 0.0973 0.1470 0.1000 0.1486 [
56 1.50 0.1050 0.1132 0.1557 '
0.1132 0.1490 56 1.75 0.1373 0.1364 0.1712 0.1368 0.1736 56 2.00 0.1518 0.1560 0.1866 0.1552 0.1898 56 2.25 0.1829 0.1799 0.2072 0.1796 0.2174 ;
56 2.50 0.1917 0.1986 0.2246 0.1978 0.2334 ;
56 2.75 0.2075 0.2163 0.2418 0.2138 0.2479 56 3.00 0.2204 0.2325 0.2588 0.2287 0.2612 !
56 3.25 0.2359 0.2483 0.2752 0.2435 0.2751 56 3.50 0.2506 0.2637 0.2913 0.2581 0.2891. i 56 3.75 0.2632 0.2784 0.3069 0.2721 0.3024 ;
56 4.00 0.2677 0.2906 . 0.3224 0.2826 0.3114 i
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e ILRT TEST DATA AND PLOTS 1 ;
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t TEST MODE PI 5E SELECT THE OPTION f YL WISH TO USE: TEST DATA 1845 I 1 -
MANUAL DATA' ENTRY # OF DATA POINTS = 104 ;
2 -
PARAMETER GRAPHS MODE DURATION (IN HOURS) = 26.50 3 -
SENSOR PLOTS TOT TIME MEASURED LEAK =- 0.3140 !
4 -
TREND ANALYSIS TOT TIME CALCULATED LEAK = 0.3178 5 -
REPRINT CURRENT DATA PT TOT TIME 95% UCL = 0.3218
- 6 -
SENSOR DIFFERENTIALS MASS POINT LEAK = 0.3137 MASS POINT 95% UCL = 0.3180 75% La = .375 P -
PASS WORD MENU MASS = 96539.50 -
SELECTED OPTION =
l POINT
SUMMARY
~
CURRENT VALUE/ DIFFERENCE FROM PREVIOUS POINT AVG TEMP
- 71.970 / -0.003 AVG PRESS: 64.461 / -0.002 MASS: 96539.50 / -3.070 AVG DEW PRESS: 0.2305 / +0.0004 TOTAL PRESS: 64.692 / -0.002 l 5
t 6
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TEST MOiE '
Page 1 i i
AVERAGE DATA VALUES l
DATE TIME RTD DEW PT. VAP PRESS DRY PRESS MASS f 56 0.00 72.713 51.705 0.190 64.776 96875.36 56 0.25 72.684 51.748 0.190 64.771 96872.27 56 0.50 72.661 51.871 0.191 64.765 96867.66 56 0.75 72.635 51.923 0.191 64.759 96864.44 l 56 1.00 72.614 52.033 0.192 64.754 96860.10 !
56 1.25 72.592 52.120 0.192 64.749 96855.99 !
56 1.50 72.570 52.192 0.193 64.743 96852.25 !
56 96847.87 1.75 72.549 52.316 0.194 64.738 i 56 2.00 72.535 52.367 0.194 64.733 96843.59 !
56 2.25 72.511 52.418 0.195 64.728 96840.81 r 56 2.50 72.499 52.484 0.195 64.724 96835.59 I 56 2.75 72.481 52.575 0.196 64.719 96831.87 I 56 3.00 72.464 52.638 0.196 64.714 96827.84 56 3.25 72.451 52.683 0.197 64.710 96823.62 i 56 3.50 72.436 52.818 0.198 64.705 96818.93 !
56 3.75 72.420 52.880 0.198 64.701 96815.65 ;
56 4.00 72.408 52.956 0.199 64.696 96811.06 !
56 4.25 72.395 53.002 0.199 64.692 96806.84 56 4.50 72.382 53.040 0.199 64.688 96803.41 !
, 56 4.75 72.372 53.158 0.200 64.684 96799.05 i 56 5.00 72.358 53.213 0.200 64.679 96794.43 ;
56 5.25 72.348 53.241 0.201 64.676 96792.05
- 56 5.50 72.335 53.373 0.202 64.672 96788.02 i 56 5.75 72.328 53.441 0.202 ' 6 668 96783.64 '
56 6.00 72.321 53.504 0.203 d4.664 9G778.82 56 6.25 72.315 53.581 0.203 64.661 96774.90 -
56 6.50 72.305 53.574 0.203 64.658 96772.29 56 6.75 72.296 53.700 0.204 64.653 96767.58 ;
56 7.00 72.290 53.737 0.204 64.650 96763.71 i 56 7.25 72.282 53.756 0.204 64.648 96761.46 56 7.50 72.273 53.912 0.206 64.644 96757.26 i 57 7.75 72.268 53.895 0.205 64.641 96754.64 r
-57 8.00 72.259 54.010 0.206 64.638- 96751.38 ,
4 57 8.25 72.248 54.011 0.206 64.635 96748.17 l 57 8.50 72.247 54.067 0.207 64.632 96743.63 ;
57 8.75 72.240 54.116 0.207 64.628 96740.35 !
57 9.00 72.229 54.165 0.208 64.625 96737.81 i 57 9.25 72.226 54.267 0.208 64.622 96733.42 57 9.50 72.223 54.307 0.209 64.619 96729.73 }
57 9.85 72.209 54.360 0.209 64.615 96726.20 r i
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d 29 00669 l 215 46 422 0 142 65 840 27 52 02 75 80 40669 515 46 322 0 091 65 250 27 00 02 75 05 60669 615 46 322 0 451 65 450 27 57 91 75 31 01669 915 46 322 0 411 65 450 27 05 91 75 58 11669 125 46 222 0 280 65 850 27 52 91 75 60 51669 325 46 222 0 460 65 260 27 00 91 75 87 61669 525 46 222 0 220 65 660 27 57 81 75
- 61 91669 725 46 122 0 459 55 170 27 05 81 75 28 22669 035 46 122 0 519 55 270 27 52 81 75 28 42669 235 46 122 0 219 55 970 27 00 81 75
! 03 82669 435 46 022 0 118 55 280 27 57 71 75 44 03669 635 4S 022 0 928 55 580 27 05 71 75 80 43669 935 46 022 0 177 55 680 27 52 71 75 32 63669 145 46 022 0 267 55 290 27 00 71 75 *
~
32 04669 445 46 912 0 756 55 390 27 57 61 75 37 24669 645 46 912 0 226 55 790 27 05 61 75 53 54669 845 46 812 0 255 55 101 27 52 61 75 '
85 84669 155 46 812 0 325 55 501 27 00 61 75 33 15669 355 46 812 0 615 55 701 27 57 51 75 i 83 45669 555 46 712 0 244 55 111 27 05 51 75 71 75669 755 46 812 0 064 55 111 27 52 51 75
- 22 06669 065 46 712 0 543 55 913 27 00 51 75 88 36669 365 46 612 0 192 55~ 911 27 57 41 75 18 66669 565 46 612 0 952 55 321 27 05 41 75 l 57 86669 765 46 612 0 032 55 231 27 52 41 75 89 17669 075 46 612 0 422 55 331 27 00 41 75 76 57669 275 46 512 0 041 55 531 27 57 31 75
- 77 77669 575 46 512 0 511 55 441 27 05 31 75 87 08669 775 46 412 0 560 55 741 27 52 31 75 32 48669 085 46 412 0 120 55 051 27 00 31 75 49 68669 185 46 412 0 069 45 741 27 88 21 75 59 29669 685 46 312 0 809 45 251 27 05 21 75 89 39669 885 46 312 0 458 45 161 27 52 21 75 06 89669 195 46 212 0 457 45 361 27 00 21 75 38 00769 395 46 212 0 567 45 961 27 57 11 75 05 11 75 16 40769 795 46 212 0 396 45 571 27 44 70769 995 46 112 0 756 45 871 27 52 11 75
! 93 01769 206 46 112 0 556 45 681 27 20 11 75 l 97 02769 116 46 012 0 844 45 202 27 52 01 75 i 87 32769 316 46 902 0 893 45 702 27 00 01 75 l SSAM SSERP YRD SSERP PAV .TP WED DTR EMIT ETAD l SE'LLAV ATAD EGAREVA
- 2 egaP EDOM TSET I
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i TEST MODE ;
Page 3 '
AVERAGE DATA VALUES DATE TIME RTD DEW PT. VAP PRESS DRY PRESS MASS
, 57 20.50 72.045 56.235 0.224 64.510 96599.16 .
57 20.75 72.044 56.284 0.224 64.509 96596.63 l 57 21.00 72.039 56.376 0.225 64.506 96593.82 57 21.25 72.037 56.361 0.225 64.504 96590.99 l 57 21.50 72.033 56.452 0.225 64.502 96588.22 !
57 21,75 72.029 56.465 0.226 64.499 96585.37 !
57 22.07 72.027 56.509 0.226 64.497 96582.21 !
57 22.25 72.026 56.534 0.226 64.496 96581.16 57 22.50 72.020 56.565 0.226 64.493 96578.12 57 22.75 72.018 56.586 0.227 64.492 96575.89 l 57 23.00 72.017 56.649 0.227 64.490 96573.00 57 23.25 72.016 56.677 0.227 64.488 96569.98 '
57 23.50 72.014 56.713 0.228 64.485 96567.44 ,
57 23.75 72.007 56.752 0.228 64.484 96565.84 ;
57 24.00 72.004 56.776 0.228 64.482 96563.51 l 57 24.25 72.003 56.813 0.228 64.480 96561.27 57 24.50 71.999 56.831 0.229 64.478 96558.70 !
57 24.75 71.995 '56.854 0.229 64.476 96556.13 !
57 25.00 71.990 56.872 0.229 64.474 96554.34 !
57 25.25 71.990 56.968 0.230 64.471 96550.74 57 25.50 71.984 56.954 0.230 64.469 96548.62 96544.41 57 26.00 71.979 56.955 0.230 64.466 57 26.25 71.973 57.019 0.230 64.464 96542.57 ,
57 26.50 71.970 57.062 0.231 64.461 96539.50 P
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i TEST MODE i BRUNSWICK UNIT 2 Page 1 f
LEAKAGE RATE
SUMMARY
UNIT 2 l TOTAL TIME MASS / POINT DATE TIME TTLM LMCALC SL LAM L95 f
56 0.00 0.0000 0.0000 0.0000 0.0000 0.0000 56 0.25 0.3059 0.0000 0.0000 0.0000 0.0000 56 0.50 0.3815 0.3815 0.0000 0.3830 0.7542 56 0.75 0.3607 0.3768 0.7576 0.3704 0.4306 56 1.00 0.3781 0.3859 0.5345 0.3805 0.4113 56 1.25 0.3838 0.3925 0.4910 0.3860 0.4060 56 1.50 0.3816 0.3940 0.4742 0.3873 0.4006 56 1.75 . 0.3891 0.3979 0.4656 0.3917 0.4024 "
56 2.00 0.3935 0.4018 0.4612 0.3956 0.4049 56 2.25 0.3803 0.3990 0.4571 0.3911 0.3998 56 2.50 0.3940 0.4016 0.4547 0.3938 0.4016 3 56 2.75 0.3917 0.4025 0.4525 0.3950 0.4015 56 3.00 0.3924 0.4032 0.4506 0.3957 0.4012 56 3.25 0.3944 0.4042 0.4493 0.3968 0.4016 56 3.50 0.3994 0.4060 0.4489 0 3994 0.4042 >
56 3.75 0.3944 0.4062 0.4478 0.3990 0.4032 ,
56 4.00 0.3982 0.4071 0.4472 0.4000 0.4039 56 4.25 0.3994 0.4081 0.4468 0.4012 0.4048 56 4.50 0.3961 0.4081 0.4460 0.4011 0.4043 i 56 4.75 0.3980 0.4084 0.4454 0.4013 0.4041 ;
56 5.00 0.4010 0.4091 0.4452 0.4022 0.4049 56 5.25 0.3932 0.4083 0.4442 0.4011 0.4039 ;
56 5.50 0.3934 0.4076 0.4433 0.4003' O.4030 56 5.75 0.3952 0.4073 0.4425 0.4001 0.4026 56 6.00 0.3986 0.4075 0.4420 0.4002 0.4026 -
56 6.25 0.3982 0.4076 0.4415 0.4005' O.4026 56 6.50 0.3928 0.4069 0.4406 0.3997 0.4019 :
, 56 6.75 0.3956 0.4066 0.4399 0.3993 0.4014 ,
56 7.00 0.3951 0.4063 0.4392 0.3990 0.4010 56 7.25 0.3892 0.4052 0.4382 0.3975 0.3998 56 7.50 0.3901 0.4043 0.4372 0.3965 0.3988 57 7.75 0.3859 0.4030 0.4361 0.3951 0.1978 '
57 8.00 0.3840 0.4016 0.4348 0.3932 0.3963 57 8.25 0.3819 0.4001 0.4335 0.3916 0.3950 57 8.50 0.3839 0.3989 0.4323 0.3903 0.3938 57 8.75 0.3822 0.3977 0.4310 0.3889 0.3924 57 9.00 0.3786 0.3962 0.4296 0.3872 0.3909 57 9.25 0.3802 0.3949 0.4283 0.3858 0.3896 t 57 9.50 0.3798 0.3938 0.4271 0.3849 0.3886 57 9.85 0.3751 0.3923 0.4257 0.3831 0.3870 t
TEST MODE ;
BRUNSWICK UNIT 2 Page 2 i i l LEAKAGE RATE
SUMMARY
UNIT 2 i
= l TOTAL TIME MASS / POINT ,
i DATE TIME TTLM LMCALC SL LAM L95 l 57 10.00 0.3755 0.3909 0.4242 0.3816 0.3855 1 57 10.25 0.3736 0.3895 0.4228 0.3801 0.3341 '
57 11.02 0.3710 0.3880 0.4215 0.3782 0.3824 i
57 0.3862 11.25 0.3698 0.4198 0.3765 0.3807 57 11.50 0.3678 0.3845 0.4180 0.3745 0.3789 57 11.75 0.3680 0.3829 0.4164 0 3732 0.3775 !
57 12.00 0.3649 0.3812 0.4147 0.3714 0.3758 57 12.25 0.3668 0.3798 0.4131 0.3699 0.3744 ;,
57 12.50 0.3615 0.3781 0.4114 0.3684 0.3729 57 12.88 0.3623 0.3765 0.4097 0.3668 0.3713 ,
57 13.00 0.3642 0.3754 0.4084 0.3656 0.3701 57 13.25 0.3638 0.3742 0.4070 0.3647 0.3691 t 57 13.50 0.3626 0.3730 0.4056 0.3638 0.3681 ,
57 13.75 0.3598 0.3717 0.4041 0.3624 0.3667 !
5 14.00 0.3599 0.3705 0.4027 0.3614 0.3657 ,
57 14.25 0.3592 0.3694 0.4014 0.3605 0.3647 57 14.50 0.3563 0.3681 0.3999 0.3592 0.3635 57 14.75 0.3552 0.3668 0.3985 0.3581 0.3623 !
57 15.00 0.3555 0.3656 0.3971 0.3569 0.3612 -
57 15.25 0.3545 0.3644 0.3958 0.3559 0.3601 :
57 15.50 0.3532 0.3633 0.3944 0-.3547 0.3589 i 57 15.75 0.3524 0.3621 0.3931 0.3537 0.3579 57 16.00 0.3511 0.3609 0.3918 0.3527 0.3569 57 16.25 0.3507 0.3598 0.3905 0.3516 3.3558 57 16.50 0.3493 0.3587 0.3892 0.3506 0.3548 57 16.75 0.3478 0.3575 0.3878 0.3495 0.3537 i 57 17.00 0.3485 0.3564 0.3866 0.3485 0.3527 l t 57 17.25 0.3465 0.3553 0.3853 0.3475 0.3517 i 57 17.50 0.3467 0.3543 0.3841 0.3466 0.3507 57 17.75 0.3448 0.3532 0.3828 0.3456 0.3498 57 18.00 0.3448 0.3521 0.3816 0.3447 0.3488 57 18.25 0.3428 0.3510 0.3803 0.3437 0.3478 57 18.50 0.3431 0.3500 0.3791 0.3428 0.3469 !
57 18.75 0.3416 0.3490 0.3779 0.3418 0.3459 I 57 19.00 0.3394 0.3479 0.3767 0.3407 0.3448 -
57 19.25 0.3391 0.3468 0.3754 0.3399 0.3440 f 57 19.50 0.3370 0.3457 0.3742 0.3388 0.3429- !
57 19.75 0.3372 0.3446 0.3730 0.3379 0.3420 :
57 20.00 0.3360 0.3435 0.3718 0.3368 0.3410 i 57 20.25 0.3358 0.3425 0.3706 0.3359 0.3401 i l
k P
TEST MODE- !
BRUNSWICK UNIT 2 Page 3 t
LEAKAGE RATE
SUMMARY
UNIT 2 l i
TOTAL TIME MASS / POINT -l t
DATE TIME TTLM LMCALC SL LAM L95 'l 57 20.50 0.3338 0.3414 0.3694 0.3350 0.3391
- 57 20.75 0.3328 0.3403 0.3682 0.3339 0.3381 57 21.00 0.3321 0.3393 0.3670 0.3330 0.3371 ;
57 1:. 25 0.3315 0.3382 0.3658 0.3320 0.3362 i 57 21.50 0.3309 0.3372 0.3646 0.3310 0.3352 57 21.75 0.3303 0.3362 0.3635 0.3301 0.3343 i 57 22.07 0.3291 0.3350 0.3621 0.3291 0.3333 l j 57 22.25 0.3276 0.3342 0.3611 0.3282 0.3324 57 22.50 0.3273 0.3332 0.3600 0.3273 0.3315 f
! 57 22.75 0.3261 0.3321 0.3589 -0.3263 0.3305 i j 57 23.00 0.3257 0.3311 0.3577 0.3254 0.3296 t 57 23.25 0.3254 0.3302 0.3566 0.3245 0.3287 l 57 23.50 0.3246 0.3292 0.3555 0.3236 0.3278 -
57 23.75 0.3229 0.3282 0.3544 0.3227 0.3269- -
57 24.00 0.3219 0.3272 0.3316 0.3218 0.3261 ,
57 24.25 0.3209 0.3263 0.3305 0.3209 0.3251 57 24.50 0.3202 0.3253 0.3295 0.3200 0.3242 !
57 24.75 0.3195 0.3243 0.3285 0.3191 0.3233 57 25.00 0.3181 0.3233 0.3275 0.3181 0.3224 57 25.25 0.3185 0.3224 0.3265 0.3173 0.3216 l 57 25.50 0.3174 0.3214 0.3255 0.3164 0.3207 i 57 26.00 0.3153 0.3197 0.3238 0.3155 0.3197 :
57 26.25 0.3141 0.3187 0.3228 0.3146 0.3189 !
57 26.50 0.3140 0.3178 0.3218 0.3137 0.3180 ;
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I APPENDIX C ;
VERIFICATION TEST DATA AND PLOTS a
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VERIFICATION MODE TIME = 2300 OPTIONS: TEST
SUMMARY
1 MANUAL DATA ENTRY # OF DATA POINTS = 19 PARAMETER GRAPHS MODE DURATION (IN HOURS) = 4.00 .
SENSOR PLOTS TOT TIME MEASURED LEAK = 0.7291 4 -
TREND ANALYSIS TOT TIME CALCULATED LEAK = 0.7427 5 -
REPRINT CURRENT DATA PT MASS PT LEAK = 0.7309 6 -
SENSOR DIFFERENTIALS IMPOSED LEAK = 0.4995 TOT TIME UPPER LIMIT = .0.9423 P -
PASS WORD MENU TOT TIME LOWER LIMIT = 0.6923 MASS PT UPPER LIMIT =' O.9382 SELECTED OPTION = MASS PT LOWER LIMIT = 0.6882 TOT TIME VERIFICATION CRITERIA HAS BEEN MET- i MASS PT VERIFICATION CRITERIA HAS BEEN MET POINT
SUMMARY
- CURRENT VALUE/ DIFFERENCE FROM PREVIOUS POINT .
AVG TEMP: 71.895/ +0.000 AVG PRESS: 64.369 / -0.006 i MASS: 96414.01/ -9.758 AVG DEW PRESS: 0.2350/ +0.0005 '
TOTAL PRESS: 64.604 / -0.006 i
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l VERF MODE BRUNSWICK UNIT 2 Page 1 LEAKAGE RATE
SUMMARY
UNIT 2 i t
TOTAL TIME MASS / POINT c
DATE TIME TTLM LMCALC SL LAM L95 I 57 0.00 0.0000 0.0000 0.0000 0.0000 0.0000 f 57 0.25 0.5585 0.0000 0.0000 0.0000 0.0000 ;
57 0.50 0.6292 0.6292 0.0000 0.6298 0.9791 57 0.75 0.6598 0.6665 0.8248 0.6651 0.7447 i 57 0.85 0.6781 0.6819 0.7409 0.6833 -0.7364 57 1.00 0.6729 0.6915 0.7603 0.6875 0.7222 57 1.10 0.6800 0.6957 0.7572 0.6905 0.7168 57 1.25 0.6701 0.6977 0.7679 0.6875 0.7079 57 1.50 0.6848 0.7074 0.7791 0.6921 0.7085 57 1.75 0.7022 0.7178 0.7855 0.7043 0.7214 57 2.00 0.7005 0.7223 0.7893 0.7099 0.7241 57 2.25 0.6992 0.7238 0.7910 0.7106 0.7220 57 2.50 0.7216 0.7320 0.7950 0.7216 0.7350 !
57 2.75 0.7181 0.7362 0.7974 0.7262 0.7382 57 3.00 0.7093 0.7365 0.7983 0.7252 0.7354 r 57 3.25 0.7134 0.7374 0.7990 0.7257 0.7343 57 3.50 0.7190 0.7394 0.7998 0.7278 0.7355
- 57 3.75 0.7129 0.7393. 0.7999 0.7268 0.7335 57 4.00 0.7291 0.7427 0.8014 0.7309 0.7380 1
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Page 1 '
AVERAGE DATA VAL'IES DATE TIME RTD DEW PT. VAP PRESS DRY PRESS MASS !
t 57 0.00 71.965 57.117 0.231 64.455 96531.30 '
57 0.25 71.958 57.126 0.231 64.451 96525.69 57 0.50 71.950 57.144 0.231 64.445 96518.65 57 0.75 71.943 57.194 0.232 64.439 96511.40 57 0.85 71.939 57.221 0.232 64.437 96508.11 l' 57 1.00 71.936 57.208 0.232 64.434 96504.24 57 1.10 71.935 57.231 0.232 64.432 96501.22 57 1.25 71.932 57.243 0.232 64.429 96497.61 f 57 1.50 71.929 57.260 0.232 64.424 96489.98 t 57 1.75 71.926 57.325 0.233 64.418 96481.88 ,
57 96474.95 2.00 71.922 57.345 0.233 64.413 57 2.25 71.916 57.344 0.233 64.407 96468.03 57 2.50 71.915 57.427 0.234 64.401 96458.74 57 2.75 71.911 57.464 0.234 64.396 96451.88 57 3.00 71.909 57.422 0.234 64.191 96445.71 57 3.25 71.904 57.493 0.234 64.386 96438.05 '
57 3.50 71.901 57.523 0.234 64.380 96430.09 57 3.75 71.895 57.533 0.234 64.375 96423.77 57 4.00 71.895 57.593 0.235 64~.369 96414.01 5
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APPENDIX D ;
INSTRUMENT SELECTION GUIDE CALCULATION
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-i lnstrument Selection Guide Calculition (ISG) Date - 02-Apr.93 -
for -;CP&L Brunswick Nuclear Project i Unit # : 2 :
. Page 3 of 4 ,
- 11. Post-Test ISG A. Test Pararneters ,
La = 0.500 wt-%! day,'.
T= 71.970 Deg. Fahrenheit = 1 531.640] Deg. Rankine ,
t= 26.50 Hours P= 49.000 psig = l 63.7l psia T dewpt= l 57.0621 Deg. Fahrenheit B. Instrument Parameters .
- 1. Total Absolute Pressure :
Number of Sensors 2 ;
Range O. 100 psia Sensitivity &ror (Ep) 0.00100 psia ( 0.001% ) FS Measurement System Error (Cp) t l
- a. Resolution 0.001 psia
- b. Repeatability of 0.000500 psia ( _ 0.0005%) FS Precision Pressure Gage Paroscientisc
- c. Repeatability of l Olpsia ( 0.005% ) Input..
Fluke 228CA-161 (Not used w/ RS-232) 63.7 psia A/D Converter Cp=[( 0.000001 )+( 0.0000CD25 )+( 0 )]".5
_ Cp = [(a.*2)+(b.*2)+(c.*2)] *.5 .I Cp = l 0.001118034 l psia i ep = [(Ep)*2+(Cp)*2)".5/(No. Instruments)".5 op = 1 0.0010006601 psia
- 2. Water Vapor Pressure ,
Number of Sensors 1 101 ,
' PSIA Deg.F- '
At dewpoint temperature of 57.062 Dog. F Above' O.23842 ~
58 the egivalent water vapor pressure change is Below 0.22999- . 57 l 0.0084300 l psia /Deg. F Delta PSIA / Delta Dog. F = psla/Deg. F Sensitivity Error (Epv) 1 0.01 IDog. F -
Epv= 0.01 Degrees F x 0.00843 poin/Deg.F= 0.0000843 psia Converted to psia is 1 0.0000843) pois - l
' Measurement System Error (Cpv)
- a. Resolution - 0.001 Dog.F !
- b. Repeatability of 0.072 Dog. F ( - 0.04 ) Dog. C - l Fluke 22808-163 !
i RTD/Resestance Scanner
- c. Repeatabihty of l 0.0040250lDeg. F ( 0.005% ) input. ,
Fluke 228CA-161 57.062 Dog. F ND Corwerter '
1 4
u 4
)
n ,
instrument Selection Guide Calcul: tion (ISG) D te 02-Apr-93 for CP&L Brunswick Nuclear Project Unit # -2 >
Page 4 of 4 Cpv = [(a.*2)+(b.*2)+(c.*2)] *.5 Cpv= l 0.072119349] Deg. F i Cpv= 0.072119 Degrees F x 0.00843 psia /Deg.F= 0.0006079 psia .
Converted to psia is l 0.000607966 l psia !
epv = [(Epv)*2+(Cpv)'2]".5/(No. Instruments)*.5 epv= 1 0.000194095l psia
- 3. Temperature Number of Sensors l 24l Sensitivity Error (Et) 1 0.10 l Deg. F i Measurement System Bror (Ct)
- a. Resolution 0.001 Deg.F
- b. Repeatability of 0.090 Deg. F ( 0.05) Deg. C Rosemount 78-39-11 RTD's
- b. Repeatability of l 0.072 l Deg. F ( 0.04 ) Dog. C Fluke 2280B-163 RTD/ Resistance Scanner
- d. Repectability of l 0.0035985lDeg. F ( 0.005% ) input Fluke 2280A-161 71.9695 Deg. F A/D Converter Ct = ((a."2)+(b.*2)+(c.*2)+(d.*2)] *.5 Ct = .1 0.115316733IDog. F i
et = [(Et)*2+(Ct)*2]*.5/(No. Instruments)" 5 et = 1 0.031156827 l Deg. F
-[-+-+- ]
t [ (P)'2 (T)*2 (P)*2 ]
0.5545027 6.8691336 1.8568658 2400[( 5.55E-10 )+( 6.87E-09 )+( 1.86E-11 )]^.5
= +/-
26.5 7.442204
= +/- 90.56603 ( 7.44E-00 ) *.5
= +/- 90.56603 ( 8.63E-05 )
8.626821 ISG = +/- l 0.0078130]Wwt/ day Which is / is not <.25 La ( 0.125 ) %-wt./ day (circle one) tru5aTs ,
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V APPENDIX E GENERAL PHYSICS ILRT COMPLTTER PROGRAM DESCRIPTION P 0
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DESCRIIrrION OF GENERAL PIIYSICS 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 The General Physics ILRT team was equipped with two fully operational IBM 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 Fluke Datalogger.
Two computers were brought on site for 100% redundancy, as each computer and its software is capable of independently performing the ILRT. The General Physics ILRT Computer Software is also capable of accepting manual input of raw sensor data and performing all required sensor data conversions if the data logger should cease to function. Each computer was equipped with back-up disks in the unlikely event of a disk
" crash."
SECURITY The General Physics ILRT Computer Program is written in Microsoft's Quickbasic version 4.5. BASIC is a high level programming language which combines programming ease with user oriented command functions to create an easy to use and understand program. In order to increase speed of operation the program was then compiled into an executable command file. Compiling was accomplished using the IBM Basic Compiler.
In addition to execution speed, this had the added benefit of making the program more secure as compiled programs cannot be edited or changed. The program requires a password to change modes of operation, start times, or enter the data editing routine to safeguard the integrity of the raw data files.
FEATURES The program itself is designed to be a menu driven program consisting of five separate, menu driven operating modes. These are the:
- 1. Pressurization Mode 4. Verification Mode
- 2. Stabilization Mode 5. Depressurization Mode
- 3. Test Mode These modes also correspond to the phases of the ILRT. Menu driven means that the user is presented with a list of options that the program can perform and from which the us'er can choose. It allows for interactive information exchange between the user and the computer and prevents invalid information or user mistakes from crashing the program.
Program organization consists of a master menu which controls accea to the seven operating modes chained to the individual menus which control these modes. The data processing, information display capabilities and function of each mode is as follows:
- 1. Pressurization Mode: All data reduction, graphic displays of average temperature, dewpoint, and corrected pressure.
- 2. Stabilization Mode: All data reduction, automatic comparison of data against i ANSI 56.8 and BN-TOP-1 temperature stabilization criteria, noti 6 cation when criteria is met, graphic displays of average temperature, dewpoint, and corrected pressure. ,
- 3. Test Mode: All data reduction, calculation ofleakage 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), including a superimposed acceptance criteria line).
- 4. Verification Test Mode: With input of imposed leakage in SCFM automatically i 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 analysis 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.
- 3. Containment dewpoint temperature weighted averaging (conversion from Foxboro dewcell element temperature to dewpoint temperature if required) and conversion to partial pressure of water vapor (psia). ,
- 4. Data storage ofILRT 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.
- 7. Sensor performance and deviation information for sensor failure criteria, graphic display of individual sensor performance for selected operating mode.
I
- 8. Calculation of ISO formula at beginning of test; acceptance criteria based on number of sensors remaining and actual test duration. !
- 9. Computer System Error Functions automatically checks for error in incoming 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 c.ther ILRTs. The initial certi5 cation required verification of the program through hand calculations and an independent review by Bechtel Power Corporation. After certi5 cation was completed, a calibration set of raw data was used to verify software of the program prior to usage.
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 computer printout data point summary.
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UNIT TWO "AS FOUND MNPLR SUMMATION AND "AS FOUND" SAVINGS REPORT
- AS FOUND* SAVING TOTAL 48361 SCFH OUTAGE # B210F6
'AS FOUND* MNFtR TOTAL 78.062 SCFH*
- SFF FNP-18 8 (SFCTION 5 0) IF MNPL R TOTAL OR A PFNETRATIONS MNPt.R EXCFFDS 159 78 SCFH
~
Peetodio *As Foun# .EquiPe *Ae Foune *As Leff . Equip *As Left* 'Ae Leff . As
- Founts Beele ' Test Date Pen f Teet# - - Componentf teenene Error ' MNPLR
- Leekone Ener MNPLR MXPLH ' Bevina Code FT-20.3-57 B21 -F0328,E51 -V88 9.958 1.774 1.514 0.288' ~1.5* 4 20- Dec-92 PT-20.3-105 G31-F042 E51-F013 4.832 0284 1.974 0 284 0.000 26-Nov-92
-W X8
~_ -
myj4MMMMJWC PT-20.3-5M B21 -F016 M&% 2 Q3Zhegi 0.020 0.218 1 1 wj 0.020 k.h _MZ3%sQMb 0.020
_sw
- eg , ^m .%>q 0.000 C 29- Nw-92 PT-20.3-588 B21 -F019 WNP 0219 0.284 0219 19- An-93 QiC.74(%..W 4.g!]ii[li@ W" MWS&i&fG ggggisidig/@MGWpW f@@kg gg* gpx 31 qs :
X62A PT-20.3-5M B32-V22 5212 0284 0.090 0.284 0.090 0.000 C 24- An-93 PT-20.3-61 B32-V24 0.089 0.284 0.089 0.468 0284 0.468 0.000 30-Jan-93 F4$'fT4*@*? i j $ k[ W V M Ws-M T si 1.0455W*$WfMM jdjLjljjM;jMM ilj,i.A'ii. Nig;yQ ,
X7BA PT-20.3-62 332-V32 0284 0.7 91 0284 0.791 C 30-Jan-93 PT20.3-598 B32-V30 0.091 02S4 0.091 0223 ' O.284 0.223 0.000 09- Dec-92 g:- -
g:9511-me-es rmrM&c! hiMEMMim;gge&;w:2 & t., z.M@ ;mm;i% Ogt . < , u .
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X56E PT-20.3-60 B32-F019,F020 15.940 2.0fa 7.970 1.015 ~0.343 0.506 0.508 7.463 E 15- Feb-93 g4 M% %ww w gam m mi:> 'My M% , ;xg% i su Me% +Rumf , ::a .;w ,; ;g4x : ,
X42 PT-20.3-63 C41-F006 3.690 0284 1.150 0284 1.150 C 05- Fe b-93 PT-20.3-64 C41-F007 0 089 0284 0.089 0,089 0.000 31- Oct-92 Ek;;: e *$MM i yt a neb 5MM&lA wh i132iMWEMmw&MRC?iL%'Wi l WkM&
- M ~ .2t;M M3QQj e;&jl% ;, m M* 4:
X400 FT-20.3-73 CAC-SV-1200B 0.090 0.284 0.090 0.090 C 08- Dec-92 PT-20.3-74 CAC-SV-1261 0.090 0284 08- Dee-92 m J@gqAm-- - - - - - -
~Nha i-
. -emNXM& W M h cu EMR Lsch/dC +se g jn3 am&w. ^ e +
X73C PT-20.3-79 CAC-SV-1260 0.089 0284 0.05 0.089 C 07- Dec-92 PT-20.3-77B CAC-SV-1227C 0.089 0.284 08- Dec-92 M :m NdW^ MWMMXM2MHM S'M&% MIMA %dO&3%h .nY ': . . W:MiiEY ~ - MV :w \ - MbML d " NM X76B PT-20.3-81 CAC-SV-3440 0.089 0.284 0.089 0.089 C 07- Dec-92 PT-20.3-82 CAC-SV-12258 0.089 0284 07- Dec-92
+
Hi&L: nbW&MMMiiM& MHiGMhM i > 331MitMOGi O&d3 yed$ * &Eh> @Wkw 42 DON' NEG.MM - *'L a ~ X54F PT-20.3-83 CAC-SV-1211 F 0.090 0284 0.090 0.090 C 03- Dec-92 PT-20.3-84 CAC- SV-1262 0.090 0.284 03- Dec-92 <. 40 %MMMM4ktiGE#inWim h o@DF ECA?%e ddC W.l ic h e " W+v nn # '
%: ds 46$ S$i .
X54E PT-20.3-89 CAC-SV-1211 E 0.090 0284 0.090 0.090 C 02- Dec-92 PT-20.3-90 CAC-SV-3439 0.090 0.284 02- Dec-92 MM g 59MM .gMt@p 5 ~ , edg 4 > JM ?Q x q g3 , - 4 ,y gg g.m.m eqq ggg pjg@ ggpg X12 PT-20.3-100 E11-F008.F009 26.330 4.650 13.165 0.729 - 0.343 0.365 0.365 12.801 E 10- Feb-93
. ' nefF dh!.h?MWNinM ^ " >
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N% ~ ~ +1 s M$ # X13A PT-20.3-111 A E11-F015A 3.727 0284 0.089 0.284 - 0.089 0.009 0.000 C 10- Nov-92 PT-20.3-112A E11-F017A ' O.089 0.284 0.089 0.089 14- Oct-92 Page 3 19- Apr-93
_ _ - - . _ _ ___- ._= . . . ._.m _ _ .- _ i UNIT TWO "AS FOUND MNPLR SUMMATION AND "AS FOUND" SAVINGS REPORT j I
%S FOUND* SAVING TOTAL 48.561 SCFH OUTAGE # B210F6 l 'AS FOUND* MNFtR TOTAL 78.062 SCFH* ,
*SEE ENP-18 8 (SECTION 5 0) (F MNPt R TOTAL OR A PENETRATION'S MNPL R EXCFEDS 159 78 SCFH Pededio 'As Found' Equip 'Ae Foun# 'Ae Leff Equip . "As Left" *As Left" 'As Found Basie Test Date l
P( n f Test # Componente teekene Enor MNPL R
- teekene Enor MNPL R MXPtR Savino Code l
wwm :wwww:1 m im.rmsw"'^ ' ""mani wtg c :.nu . mwy.w.nse ngw myya :n w < st3: n s , .. m X13B M-20.3-111B E11-F015B 14.370 1.774 0.090 0284 0.090 0 000 C 19- Feb-93 PT-20.3-1128 E11-F017B 0.090 0284 0.090 0.090 09- Feb-93
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i , X39A M-20.3 -113 E11-F021 A 0.550 0284 0.550 C 09- Nw -92 PT-20.3-113A E11-F018A 0.089 0284 0.089 0.264 0.089 09- Nw-92 c%.(y xv --- .. J' N
} Wn- ?v y wg*tNli MigQ ggQ j g :q X398 PT-20.3-114 EU-F0218 0.089 0284 0.089 C 09- Feb-93 PT-20.3-114A E11-F018B 0.090 0284 0.090 09- Feb-93 g ueg 7 1 - : .. q = : pg " Mygt yn : w + y Mgg QQQ{ g.gg , . ,
X17 PT-20.3-117 E11-F022.F023 0.089 0284 0.045 0.284 0.045 0.045 E 12- Feb-93 pgm . : pie %g ::e .- g +: u - . p ;ig y .p ;;@W; aq:w gp M . g ; y __,_y, X210A PT-20.3-118A E11-F024Af028A 2288 0284 1.143 1.143 E 08- Nw-92
- qyi 9%Mw.a w.-.--- --<-~M (1] lTBmmaw=nQ% hiR%:n . G44WOTA W Qt n n M , #8% W: - n % , H:
X211 A/B PT-20.3-118B E11-F027A. F02TB 0.089 0284 0.080 0.264 0.089 0.089 A 10- Feb-93 gg me n:1&smun% --- m m m m m m m w w-wam-mM& mwgy .& q.w u wmumwMs %My pay %y wgag kX2100 PT-20.3 -119A E11-F0248,F0288 1.080 0284 0.530 0.530 E 10- Feb-93
$.fMf4@%W$R D @nnif M
- W # @ -C ' NN ~ #
- WM.i n?/sRBddi ljEL&alsa g ,
sl3Ms M3L mhj, , _ . . . . ' . , _ . . , X16A PT-20.3-142A E21-F005A 3.853 - 0284 3.653 3.763 0.284 3.763 0.000 C 21 - Aug-92 PT-20.3-143A E21-F004 A 15.400 3.874 0284 3.874 21- Aug-92 j:;: pag _ yg M y yppfy g.g
^
y C . n g ym pmagpig.;; y t,5; 9 , X168 PT-20.3-142B E21-F005B 0.089 0284 0.089 1280 0218 1280 0.000 C 12- Nw-92 PT-20.3-143B E21-F0048 0.089 0284 0.089 01 - Nw-92 g pgg% ' . 4p2 :y.4 ergypaggay; ggqpteggMygg gjggg gjg .
. pg , p X11 M-20.3-148A E41-F002 2.540 0.218 2.540 C 30- Nw-92 PT-20.3-1488 E41-F003 1.820 0.218 1.820 01 - Dec-92 R.1si?)REW- NM&l&O ==mAWEFi?!f as< % E M e:#s Fa;dM ^ 'mf L Ww ettW Aht:L Wi $ siqhr X218 PT-20.3-153A E41-F079 0.089 0284 0.089 0.089 C 18- Nw-92 PT-20.3-153B E41-F075 0.019 0284 18- Nw-92
@nMM3h2-'- ^*"~fshisW!nki ' - PMGGWM/B4?fn@ n@pNi @OA t _ +
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- 2NM X10 PT-20.3-156A E51-F007 0.089 0284 0.089 0.089 C 30- Dec-92 PT-20.3-156B E51-F008 0.089 0284 30- Dec-92 f +
- u. ' iMWFA Mf @@ h " W W/M ' 4V:6 _ <
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- J + M2 4 X216 PT-20.3-161 A E51-F066 0.089 0284 0.089 0.089 0.000 C 18-Nw-92 PT-20.3-161 B E51-F062 13.400 1.580 1280 0218 1280 01 - Dec-92 1.j g > -
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Page 4 19- Apr-93
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4 UNIT TWO "AS FOUND MNPLR SUMMATION AND "AS FOUND' SAVINGS REPORT 48.561 SCFH OUTAGE # B210F6 '
'AS FOUND* 8AVING TOTAL
'AS FOUND' MNPLR TOTAL - 78.002 SCFH+
'SEE f-16 8 p 5.0l IF MNFLR TOTAL OR A PEETRATION'S MNPLR EXCEEDS 159.78 SCFH 4 ~.s.
Pede Se gg'mp lAs Foun#ciEgulpw:'Ae Fount c *As Ler g Equip w?As Lee fAe Lor;. 'Ae Found Beelei oot c v. v T Date - 0.000 0284 0.000 0.217 0204 0217 0217 - 0.000 D- 16-Feb-93 X38C PT-20.3-te1 -- lTIP V3 M-20.3-191 A RINGS X35C 0.085 0284 0.04; 0.045 04-Oct-92 ,
.; . c .; .: _ry: .y .
l PT-20.3-1sI2 -- TIP V4 ' O.0m 0204 0.085 0.000 D 16-Feb-93 X350 OJoe 0.284 0.046 0.046 04-Oct-92 PT 20.5-182A O' RINGS X2O 0.000 0.204 0.50 0.000 D 04-Dec-92 XmE PT-20.3-183 1TIP N2 CHECK 0.000 0.204 0.046 C.045 04-Oct-92 PT 20.3-183A O' RINGS X35E '
.y..-
^
4 _ SA-V440 0.089 ' 0204 0.000 C 03-Oct-92 X21 - PT-20.3-104 0.2m 0.208 03-Oct-92 PT-20.3-1 SA-V448
- ry -
,s :q prl%g.
E 14- Apr-93 , N/A PT-20.38 PERSONEL AIR.OCK 220D 0218 . TOTAL 7s 0s2 es.524 4s.561 l
~
a17.80) Penoty for LRT . 48.56 'As found" Lee kego Savings MS* A MNPLR = LeekeGe 8elo ' B MNPLR = Leeke0* Rate Past the bestvelve(s) of the foRowing two bordere: 521-F0108 or B21-Fos 28,E51-Ves C MNFLR = Leskage Rote poetthe boetvelve of the two lookege barriere D MNPLR = Leekage Rete poetthe valve + 1/2 of the O' Ring Leskoge , E MNPLR = 1/2 Lenksgo Rote.' . The MNPLR may be reduced by repeldng one of the two volves and rotesting. Aitor the reteet, the MNftR een be the 'ne loff Leekage Rate or the *es foune leakage rate, wNchever le smaller. F N no repelre are modo, tw MNPLR le equel to the *ee foune leakage rate poet
. CAC-V5, V16. V17, V100, V182, V170 of CAC-V4,V15,X3DA,X208 and CAC-V55,V-56 ' .
1 . whichever group hoo thelowest leakege, if repelre are made,the MNILR may be roweiusted by repelring one of he valves and reteeting. G If no repaire are made, tw MNPLR la equel to the 'ee foune leakage rate past ' CAC-VG, V161,V163,V171 or ' CAC-V4,V15,X20A,X206 and CAC-V55,V-56 , whlehever aroup hee the lowest leakene. If repaire are made. the MNR.R may be reerolueled by repelrina one of the vahtee e nd retestinc Pages 19- Apr-93
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i I
.i APPENDIX G 1ENSOR LOCATIONS AND VOLUME FRACTIONS o
P G s l 1 3 i a
El. (ft.)/Dio. (ft.) 40 30 20 10 0 e r , , ,
-117_, I 90- .
-110_ g]gglao ,O' 1%~ gj f rs._ )
90_ M3Qf[dQM ' T- j? Zone 1 93 ft. i 80_ . , ] _. G
, 2 %[
< Q,._._!.C Zone 2 78 ft. '
70_ , E17 E Zone 3 ' 66 ft. 60-
- \ ~
50 C , .- 5 l' 3 Zone 4 54 ft. Zone 5 46 ft.
, grg \ i O' Zone 6 33 ft.
30_ Q^ 20_, , i 10-
"- 2 E 2
A- - Zone 7 16 ft. 8 17 ! M l S O_ kd
^
\ (N2 S b
i")
/
Va
, Zone 8 8ft. l
(- a V li
-10_ \ E) ---a ,
e _ _ --m
-20_'
l i t F
4 QW
-~ ,
w=.z , c
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=
wa 's /*~.E :
=
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ese.9ge -
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=
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$ X -
hl s I / d f $ \ O (4 Qai s t ' 5 l s s s 3 ,g, S ' s W e ~S-m S N'N I o 1 o = :s_g
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g E[IlaV ' U$W\ X g. e
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X !NCo j x-X i s 9 8 - a _ e w s- g y 53 e a- ; g g- s > E l
CAROLINA POWER & LIGHT COMPANY BRUNSWICK NUCLEAR PROJECT ILRT INSTRUMENTATION CROSS REFERENCE FLUKE CHANNEL NO. Temperature Element SHOP ID NO. VOLUME NO. FRACTION C1 TE-1 RTD-4 0.0264 C2 TE-2 RTD-8 0.0264 C3 TE-3 RTD-10 0.0187 C4 TE-4 RTD-12 0.0187 C5 TE-5 RTD-13 0.0115 C6 TE-6 RTD-14 0.0115 C7 TE-7 RTD-15 0.0136 C8 TE-8 RTD-16 0.0136 C9 TE-9 RTD-17 0.0194 C10 TE-10 RTD-18 0.0194 C11 TE-11 RTD-20 0.0194 C12 TE-12 RTD-21 0.0500 C13 TE-13 RTD-23 0.0500 C14 TE-14 RTD-24 0.0500 C15 TE-15 RTD-25 0.0577 C16 TE-16 RTD-26 0.0577 C17 TE-17 RTD-27 0.0577 C18 TE-18 RTD-28 0.0577 C19 TE-19 RTD-30 0.0701 C21 TE-20 RTD-38 0.0701 C22 TE-21 RTD-32 0.0701 C23 TE-22 RTD-34 0.0701 ; C24 TE-23 RTD-35 0.0701 C25 TE-24 RTD-36 0.0701 cw I "$hj @S7s )$'; j'#@$" [ Sum (I) 1.0000
CAROLINA PCWER & LIGHT COMPANY BRUNSWICK NUCLEAR PROJECT , ILRT INSTRUMENTATION CROSS REFERENCE FLUKE CHANNEL NO. Dewpoint Element SHOP ID NO. VOLUME NO. FRACTION -> C29 DPE-1 DC-1 0.0527 C30 DPE-2 DC-2A 0.0489 i C31 DPE-3 DC-4 0.0386 C32 DPE-4 DC-5 0.0583 L C33 DPE-5 DC-6 0.1502 C34 DPE-6 DC-9A 0.2309 ' C35 DPE-7 DC-11 0.1051 ; C36 DFE-8 DC-13 0.1051 C37 DPE-9 DC-15 0.1051 i C38 DPE-10 DC-16 0.1051
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- lb! ?I?j Sum (I) 1.0000 "l
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