ML19321B171

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Reactor Containment Bldg Integrated Leak Rate Test
ML19321B171
Person / Time
Site: Quad Cities 
Issue date: 03/12/1980
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COMMONWEALTH EDISON CO.
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ML19321B170 List:
References
NUDOCS 8007280474
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{{#Wiki_filter:3 % ,~ ^^^ ID TS/D REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST QUAD-CITIES NUCLEAR POWER STATION UNIT TWO MARCH 9-12, 1980 8007280y7;F

o e i TABLE OF CONTENTS PAGE INTRODUCTION. 1 A. TEST PREPARATIONS. 2 A.1 Type A Test Procedure 2 A.2 Type A Test Instrumentation 2 'A.2.a Temperature A.2.b Pressure A.2.c Vapor Pressure A.2.d Flow A.3 Type A Test Measurement 3 A4 Type A Test Pressurization. 3 8 B. TEST METHOD. 8 B.1 Basic Technique B.2 Supplemental Verification Test 8 8 B.3 Linear Regression Analysis. B.4 Instrumentation Error Analysis - Application. 8 C. SEQUENCE OF EVENTS 10 C.1 Test Preparation Chronology 10 C.2 Test Pressurization Chronology. 10 C.3 Temperature Stabilization Chronology. 10 C.4 24-Hour Phase of Leak Rate Test 11 C.5 Induced Leakage Phase 11 C.6 Blowdown Phase 12 C.7 Post-Test Phase 12 14 D. TYPE A TEST DATA 14 D.1 24 Hour Phase Data 14 D.2 Induced Phase Data. 15 E. TEST CALCULATIONS. F. TYPE A TEST RESULTS AND INTERPRETATION 29 F.1 24 Hour Phase Test Results. 29 F.2 Induced Phase Test Results 29 F.3 Leak Rate Compensation for Non-Vented Penetrations and Change in Drywell Sump Level 29 F.4' Pre-Operational Results vs. Test Results. 30 APPENDIX A TYPE B AND C TESTS 31 41 APPENDIX B AS FOUND LEAK RATES.

11 APPENDIX C COMPUTATIONAL PROCEDURES AND INSTRUMENTATION ERROR ANALYSIS 43 TABLE ONE Instrument Spccification 4 TABLE TWO Sensor Physical Locations 5 TABLE THREE 48 psig Type A Test - 24 Hour Phase. 16 TABLE FOUR 48 psig Type A Test - Induced Leak Rate Phase. 24 TABLE A-1 Type B and Type C Test Results 32 FIGURE ONE Idealized View of Drywell and Torus Used to Calculate Free Volume 6 FIGURE TWO Measurement System Schematic Arrangement 7 8

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.g' O 1 INTRODUCTION This report present details of the Integrated Primary Containment Leak Rate Test (IPCLRT) successfully performed on March 9 through 12, 1980 at Quad-Cities Nuclear Power Station, Unit Two. The test was performed in accordance with 10CFR50, Appendix J and the Quad-Cities Unit Two Technical Specifications. j The total primary containment integrated leak rate, adjusted to include penetrations not tested during the IPCLRT, was found to be 0.4492 wt%/ day at a test pressure of 48.5 psig, which was within the 0.750 wt%/ day acceptance 1 criterion. The associated upper 95% confidence limit was 0.4587 wt%/ day. Exeluding non-testable penetrations, the supplemental induced phase leakage test result was 0.794 wt%/ day. This value should compare with the sum of the 24 hour phase result (0.445 wt%/ day) and the induced leak rate of 4 scfm (0.462 wt%/ day). The statistical value of 0.794 wt%/ day lies within the allowable tolerance band of 0.907 1 0.250 wt%/ day. e l

2 SECTION A - TEST-PREPARATIONS A.1 Type A Test Procedure The IPCLRT was performed in accordance with Procedure QTS 150-1, Revision 7, including checklists QTS 150-S1 through S4, QTS 150-S7 through S13 and QTS 150-S17. In addition subsections QTS 150-T1, T2, T3, T6, T7 and T8 were utilized. Temporary change number 1318 was maae to QTS 150-1 and QTS 150-S2 to allow the IPCLRT to be performed with the reactor water temperature limit raised. These procedures were written to comply with 10CFR50 Appendix J, ANSI N45.4-1972, and Quad-Cities Unit Two Technical Specifications. A.2 Type A Test Instrumentation Table One shows the specifications for the instrumentation used in the IPCLRT. Table Two lists the physical locations of the temperature and humidity sensors within the primary containment. Figure One is an ideal-ized view of the drywell and suppression chamber from which the primary containment free air volumes were calculated. a. Temperature Locations for RTD's were carefully chosen to avoid conflict with local temperature variation, while still satisfying sensor placement as dictated by results of the previous Unit Two IPCLRT of October. 1976. Sensors were suspended to prevent direct thermal influence from any metal surfaces. Temperature of the reactor vessel air space was based upon the reactor water temperature entering the RHR Heat Exchanger of the loop in operation for reactor shutdown cooling. Each RTD-bridge network was calibrated to yield an output of 0.0 mV to 100 mV over the range of 50 F to 150'F. Observations were made by comparison with a Montedoro-Whitney platinum resistance thermometer, Aarial number TC 7G 100B006D. The plant process computer sampled the output of each RTD-bridge network. The calibration for the thermocouple used to measure reactor water temperature was performed by comparing thermocouple output with the plantinum resistance thermometer mentioned above. b. Pressure Two precision quartz bourdon tube pressure gauges were utilized. Each gauge had a local digital readout in addition to a Binary Coded Decimal output to the process computer. Primary contai ment pressure was sensed by the pressure gauges in parallel through a 3/8" tygon tube connected to a special one inch pipe penetration. Each precision pressure gauge was calibrated over the range 45 psia to 75 psia in approximately 5 psia increments using a Volumetrics Inc. VMC 07726101 calibration standard.

o 3 c. Vapor Pressure Eight deweells were physically situated in the primary containment based upon the results of the Unit Two IPCLRT performed in October 1976. An assumption was made that the reactor vessel airspace (subvolume #11) was saturated and at the same temperature as the reactor water entering the RHR heat exchanger. A calibration curve was generated for each sensor over the range of 65 F to 85 F. Calibration constants were derived from the curve to correlate the o mV to 150 mV output of the sensor to the actual dewpoint measured by a chilled mirror dewcell standard, Volumetrics Inc. serial no. VMC 203/184. d. Flow A rotameter flowmeter, Fischer-Porter serial no. 7910A9126R1 cali-brated to within 11% by Fischer-Porter, was used for flow measurement. Tygon tubing connected the rotameter to a one inch pipe penetration into the primary containment. A.3 Type A Test Measurement The IPCLRT was performed utilizing a direct interface with the station process computer. This system consists of a hard-wired installation of temperature, dewpoint, and pressure inputs for the IPCLRT to the process computer. The interface allows the process computer to scan, calculate, ar.d print results with minimal human input. The system was constructed in accordance with modification M-4-2-76-45, and was used during the previous Unit Two IPCLRT in October 1976. A,4 Type A Test Pressurization A 3000 scfm, 600 hp electric oil-free air compressor was used to pressurize the primary containment. An identical compressor was available as a j standby. The compressors were physice'ly located outside the reactor building. The compressed air was pipeo sto the reactor building through an existing. 4 inch fire header penetration. For ease of handling a flexible 4 inch pipe was used inside of the reactor building. The drywell was pressurized through the "A" containment spray header 10 inch flange with the inboard valve MO 2-1001-26A, open during the pressuri-zation process.

4 TABLE ONE INSTRUMENT SPECIFICATIONS INSTRUMENT MANUFACTURER HODEL NO. SERIAL NO RANGE ACCURACY REPEATABILITY Precision Pressure Volumetrics 1309 0-100 psia 10.015 psia 10.001 psia Gauges (2) 1311 RTD's (30) Burns Engineerir.g SPIAI-5 \\-3A 44209, 44224 50-200 F 10.15 F 10.1 F Inc. 44210, 44225 44211, 44226 44212, 44227 44213, 44228 44214, 44229 44215, 44230 44216, 44231 44217, 44232 44218, 44233 44219, 44234 k 44220, 44235 44221, 44236 44222, 44237 44223, 44238 Dewcells (8) Volumetrics 07740 5835-1, 5835-5 140 F 11.0 F 10.5 F 5835-2, 5835-6 5835-3, 5835-7 5835-4, 5835-8 Thermocouple (1) Pall Trinity Micro 14T211 TE 2-1046A 0-600 F 12.0 F 10.1 F Flowmeter (1) Fischer & Porter 10A3555-S 7910A9126H1 2-17.5 scfm 10.175 scfm

'e 0 5 TABLE TWO IPCLRT INSTRUMENT PHYSICAL LOCATIONS INSTRUMENT INSTRUMENT RTD NO. JUNCTION BOX SUBVOLUME ELEVATION AZIMUTH

  • 1 2

1 670'0" 180 2 4 1 670'0" 0 3 1 2 657'0" 20 4 3 2 657'0" 200 5 6 3 634'0" 70 6 5 3 634'0" 265 7 6 4(Annular 643'0" 45 8 8 4 Ring) 615'0" 225 9 10 5 620'0" 5 10 9 5 620'0" 100 11 8 5 620'0" 220 12 10 6 608'0" 40 13 9 6 608'0" 130 14 8 6 608'0" 220 15 7 6 608'0" 310 16 14 7 598'0" 70 17 13 7 598'0" 160 18 11 7 598'0" 250 19 15 7 598'0" 340 20 15 8 587'0" 10 21 14 8 587'0" 100 22 13 8 587'0" 190 16 8 587'0" 280 24 12 9 (CRD Space) 5C6'0" 0 25 16 10 (Torus) 57b*C" o 26 16 10 (Torus) 578'0" 60 27 16 10 (Torus) 578'0" 120 28 16 10 (Torus) 578'0" 180 29 16 10 (Torus) 578'0" 240 30 16 10 (Torus) 578'0" 300 Thermocouple (RHR HX inlet) 11 INSTRUMENT INSTRLHENT DEWCELL NO. JUNCTION BOX SUBVOLUME ELEVATION AZIMUTH

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2 657'0" 160 2 7 5 620'0" 340 3 14 7 598'0" 70 4 11 7 598'0" 250 5 12 9 (CRD Space) 586'0" 0 6 16 10 (Torus) 578'0" 0 7 16 10 (Torus) 578'0" 120 8 16 10 (Torus) 578'0" 240 Thermocouple (Vessel Saturated) 11 (RHR HX Inlet)

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Idaafized View of Dry. mil end Torus ~ Used to Calculat e Free Voluines 7 -37'0" - - - i ') 681'9" ~ k -3488" 677'6" //_J 11 / 666'9" I ( 66'2'0" f/-d2'0" y / 2 // ___655'2" '/' 652'0" / // ' I~ (Grntin;;) ~ UCCit? Cd I V01L*;T.C / / 't l 2ht 'n / sf s j.' 7 cc 6.15'i"i" Vol u.m / j / s' s cyc 'c:- (croting) f, / f g,,, o '/ / . ) 5 / / / / / 614'6" /// / s;";.'"6, 6 l / 605'6" //e / 602'10' i r _. _.._ _ j ./ / / C 20 ' 0" --- 7 9 l[ 593'0" / (Gra ti n-8 / // /w/w =. A // [ 569'10n Floor) 30'o" _ 54'6" s i Figure one 7' ~-

e 7 FIGURE TWO MEASUREMENT SYSTEM SCHEMATIC ARRANGEMENT Belden Beiden 3 RTD 8616 8618 ~ 3/C (30) Local Junction Box (16) Beiden Belden Dewce11 5 9873 8616 (8) 6/C sa Dewcell Power Supply 110 Vac Junction Box (1) Drywell Terminal Box PI Volumetrics I ns t rumen t Console . ~ CT Induced Phase 40/ cable ,t T Tubing (3) RTD Bridges Transducers Flowmeter Pressure Sensing l Tubing 3 (3) Y LJ X 110 Vac D rywel l Access Hatch Bulkhead F1 (2) 40/c cable Cable pan and Computer Outlet tunnel (2) 20/c cable

8 SECTION B - TEST METHOD B.1 Basic Technique The absolute method of leak rate determination was used. The absolute method uses the ideal gas laws with measured containment temperature, dew point and air pressure to determine dry air mass in the cont einment. The leak rate can then be determined from the rate of mass loss. B.2 Supplemental Verification Test The supplemental verification test superimposes a leak of approximately the same magnitude as that measured during the 24-hour phase of the test. The degree of detectability of the combined leak rate provides a basis for resolving any uncertainty associated with the 24-hour phase of the test. B.3 Linear Regression Analysis The leak rate is assumed to be constant during the testing period, ideally yielding a straight-line plot with a negative slope. However, sampI.ng techniques and test conditions are not perfect; consequently, the measured values will deviate from the ideal straight-line situation. A least squares fit statistical analysis was performed to determine a regression line for mass versus time af ter each set of data was acquired. The slope of this regression line was designated to be the statistically averaged leak rate. This quantity was compared to the Technical Specifi-cat ion allowable operational leak rate L (0.75 wt%/ day). Associated with the statistically averaged leak rate was the upper 95% confidence limit leak rate. The calculation of this upper lisit was based upon the standard deviations from the regression line and the one-sided Students-T Distribution function. A procedural requirement specified that the upper 95% confidence limit leak rate must be less than the Technical Specification allowable operational leak rate L, (0.75 g wt%/ day). B.4 Instrumentation Error Analysis-Application An instrumentation error analysis was performed prior to the test in accordance with ANSI N45.5-1972. The instrumentation system error was calculated in two parts. The first part was to determine system accuracy and the second part was to determine system repeatability. The system err 9r analysis performed prior to the test yielded a total instrument uncertainty of 0.11298 wt%/ day. During the post-test calibration check the reliability of two RTD's was found to be questionable, consequently these RTD's (numbers 14 and 15 in subvolume 6) were considered failed and a new error analysis was performed. This post-teat error analysis yielded a total instrument uncertainty of 0.11416 wt%/dar

9 The instrumentation uncertainty is used only to illustrate the system's compatability to measure the required parameters that are necessary for calculation of the primary containment leak rate. The instrumentation uncertainty is always present in the data and is incorporated in the 95% upper confidence limit in the form of data scatter. Procedures required that the summation of the 24 hour statistical leak rate and the total instrument uncertainty be less than L, (0.75 wt%/ day).

10 SECTION C - SEQUENCE OF EVENTS C.1 Test Preparation Chronology The pretest preparation phase and containment inspection were comple'ted on March 9, 1980 with no visible structural deterioration being found. Major preliminary steps included: 1. Completion of all Type B and C tests, component repairs, and retests. 2. Completion of IPCLRT pretest valve checklist including isolation of drywell and suppression chamber pressure sensors. 3. Blocki-g cf three sets of drywell to suppression chamber vacuum breakers in the open position for pressure equalization between the drywell and suppression chamber volumes. 4. Venting of the reactor vessel to the primary containment via the manual head vent line and the drywell equipment drain sump. 5. Completion of pretest data gathering system, including computer program, instrument console, and ascoc; t e-( viring. C.2 Test Pressurization Chronology Date Time Event 3-9-80 1700 Primary Containment pressurization initiated. 1830 Found leaks on drywell personnel interlock which totaled about 10 scfh. These leaks could not be repaired. 2115 Found and repaired several small packing leaks on the oxygen analyzer valves. 2330 Repaired a small leak on one T.I.P. tube. 3-10-80 0020 Primary containment pressure reached 65 psia. Pressurization was complete. C.3 Temperature Stabilization Chronology Date Time Event 3-10-80 0640 Computer software problem with reading of containment pressure was corrected. All instruments and computer program now operat-ing properly and ready for test. 1215 Reactor vessel temperature was stabilized and vessel level was dropping approximately 1 inch per hour. Twenty-four hour test was ready to begin.

11 C.4 24-Hour Phase of Leam Rate Test Date Time Event 3-10-80 1200 Started 24 hour test phase. Data sets taken at 15 minute intervals. 1700 Blind flange on the "A" RHR loop was replaced. (This was the line used for containment pressurization). 3-11-80 0610 Computer shutdown three times between 2225 and 0555. Each shutdown was short and no data sets were lost as a result. 1020 An error was found in the calculation r subvolume number 11 (reactor vessel ait pace). This error affects the containment mass equation and therefore the leak rate. It also affect; the subvolume weighting factors which are used in calculating t'e volume weighted average temperature anc the volume weighted average vapor pressure. It was determined that the error would not signifi-cantly affect the containment leak rate and therefore the 24 hour test could still be concluded at 1200 hours. However all data will be recomputed with the error corrected. 1200 Twenty-four hour test phase completed. The 95% upper confidence limit leak rate was 0.4715 wt%/ day well below the allowable leak rate of 0.75 wt%/ day. The statistically averaged leak rate was 0.4624 wt%/ day. These numbers were subject to correction as noted above. C.5~ Induced Leakage Phase Date Time Event 3-11-80 1245 Induced leak rate 4 scfm initiated (0.4623 wt%/ day). 1320 Upper limit of induced phase was calculated to be 1.1747 wt%/ day, lower limit 0.6747 wt%/ day. The ideal valve was calculated to be 0.4624 wt%/ day (leakage of 24 hour phase) + 0.4623 wt%/ day (induced leakage) = 0.9247 wt%/ day.

12 2000 Induced leakage phase commenced at 1500 and completed at 1900. Final results of induced phase were: statistical leak rate: 0.8293 wt%/ day, upper 95% confidence leak rate: 0.8483 wt%/ day. These results are subject to correction as noted above. C.6 Blowdown Phase Date Time Event 3-11-80 2015 Blowdown was initiated through the standby gas treatment system. 3-12-80 0305 Depressurization of primary containment is complete. An initial drywell entry was made by the technical staff. No damage was observed as a result of the test. The drywell equipment drain sump was at the 4 same level as prior to the test. During the depressurization 690 gallons of water were pumped from the drywell floor drain sump. This volume change was compensated for in the final calculation of the leak rate. C.7 Post-Test Phase Date Event 3-21-80 During the post-test calibration checks, two RTD's (numbers 14 and 15) were found to have failed. A new error analysis was performed and the test data was recomputed with the information from these two RTD's eliminated. All other instruments checked out satisfactorily. 3-27-80 Leak rate was recomputed with the error in subvolume number 11 corrected. The leak rate was also recomputed with the raw data from RTD's 14 and 15 eliminated. Following is a table of the statistical leak rates and 95% upper confidence limit leak rates. 1 j

13 24 HOUR TEST INDUCED TEST Statistical 95% Upper Statistical 95% Upper Leak Rate Conf Limit Leak Rate Conf Limit With error 0.4624 0.4715 0.8293 0.8483 With error . corrected 0.4627 0.4717 0.8227 0.8417 With error corrected and RTD's-14 and 15 4 failed 0.4451 0.4546 0.7942 0.8102 i NOTE - All values are in we3ght %/ day. 1 i .i I 3 I s b l i c-r , _ l., . ~ -, ._,n

14 SECTION D - TYPE A TEST DATA D.1 24 Hour Paase Data Data for the 24 hour phase is illustrated in Table Three. Graphic record of this portion of the test is presented in graphs 1 through 6. This data has been corrected and the raw data from RTD's 14 and 15 has been eliminated. D.2 Induced Phase Data Cata for the induced phase is presented in Table Four. Graphic illustra-tion of the major parameters is presented in graphs 7 through 10. This data has also been corrected and raw data from RTD's 14 and 15 has been eliminated. i

+ t 15 SECTION E - TEST CALCULATIONS Calculations for the test were based on Quad-Cities procedures QTS 150-T3. A reproduction of this procedure is found in Appendix C. The instrument error analyses are also found in Appendix C. 4 ) 4 5 d r -rr-g u ye. r.-. --.. -, - - + +. -

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29 SECTION F - TvPE A TEST RESULTS AND INTERPRETATION -F.1-24 Hour Phase Test Results Based upon data collected during the 24 hour phase, the following results were determined: ACTUAL ACCEPTANCE LEAK RATE CRITERION (wt%/ day) (wt%/ day) Total time measured leak rate 0.4572 0.75 i . Statistically averaged leak rate 0.4451 0.75 Upper 95% confidence limit leak rate 0.4546 0.75 F.2 Induced Phase Test Results A leak of 4 scfm (0.4623 vt%/ day) was induced on the primary containment for this phase of the test. The following results were determined: ACTUAL ACCEPTANCE LEAK EATE CRITERION (wt% day) (wt%/ day) $1.1747 Total time measured leak rate 0.7802 10.6747 $1.1747 Statistically averaged leak rate 0.7942 10.6747 11.1747 Upper. 95% confidence limit leak rate 0.8102 10.6747 F.3 Leak Rate Compensation for Non-vented Penetrations and Change in Drywell Sump Level The Integrated Primary Containment Leak Rate Test was performed with the following penetzitions not drained and vented as required by 10CFR50, Appendix J. The as left leak rate of each of these penetrations, as determined by Type C testing is listed: PENETRATION FUNCTION scfh wt%/ day X-9A "A" feedwater line 0.0 0.0000 X-9B- "B" feedwater line 0.0 0.0000 X-12 RHR supply 1.75 0.0034 X-14 Rx water cleanup supply 0.20 0.0004 X-41 Primary system sample 0.0 0.0000 TOTAL 0.0038

e 30 In addition, according to our procedure the leak rate must be adjusted for any changes in drywell sump levels during the test. The following is a tabulation of these changes. VOLUME CHANGE CHANGE IN LEAK RATE Drywell floor 3 drain sump 7 ft 0.0000 wt%/ day Drywell equipment 3 drain sump 93 ft 0.0003 wt%/ day i This yields the following adjusted leak rates: Statistically averaged leak rate: 0.4492 wt%/ day Upper 95% confidence limit leak rate: 0.4587 wt%/ day F.4 Pre-operational Results vs. Test Results The successful pre-operational IPCLRT, performed August 29 to September 2, 1971, demonstrated an average measured leak rate of 0.099 wt%/ day. Although the instrument uncertainty for the pre-operational IPCLRT was calculated to be 0.096 wt%/ day, a number assumptions concerning accuracies and repeatabilities were made. Using present methods yields a revised uncertainty for the test of 0.314 wt%/ day. When this value was applied to the measured leak rate of the pre-operational IPCLRT, the result was found to be close to the current result (0.4492 wt%/ day). Although the pre-operational IPCLRT uncertainty as calculated by present analysis was larger than previously reported, the pre-operational result was still well within acceptable limits, and provides explanation for the leak variation from the present test. Normal component and seal wear coupled with periodic repair of components could readily account for the small variation in leak rate values between the pre-operational test and the current test. i

31 APPENDIX A TYPE B AND C TESTS Presented herein are the results of local leak rate tests conducted on all penetrations, double gasketed seals, and isolation valves since the previous IPCLRT in October, 1976. All valves with leakage in excess of the individual valve leakage limit were restored to an acceptable leak tightness prior to the resumption of power operation. Total leakage.for double gasketed seals and total leakage for all other penetrations and isolation valves following repairs satisfied the Technical Specification Limits. These results are listed in Table A-1. I l

32 TABLE A-1 TYPE B AND C TEST RESULTS VALVE (S) OR MEASURED LEAK RATE (SCFH) PENETRATION TEST VOLUME AS FOUND DATE AS LEFT DATE A0 203-1A Main Steam Line 30.0 11-26-79 0.6 2-25-80 Isolation Valves 46.5 1-15-78 6.7 2-26-78 A0 203-2A 47.2 11-26-79 0.6 2-25-80 57.3 1-15-78 5.8 2-26-78 AO 203-1B 32.3 11-26-79 1.8 2-14-80 6.3 1-15-78 6.3 1-15-78 A0 203-2B 24.2 11-26-79 1.8 2-14-80 6.8 1-15-78 6.8 1-15-78 A0 203-1C 5.2 11-25-79 5.2 11-25-79 43.7 1-15-78 9.3 2-27-78 A0 203-2C 5.2 11-25-79 5.2 11-25-79 4.3 1-15-78 4.3 1-15-78 A0 203-1D 4.6 11-26-79 4.6 11-26-79 9.9 1-15-78 9.9 1-15-78 A0 203-2D 9.2 11-26-79 9.2 11-26-79 4.1 1-15-78 4.1 1-15-78 1.7 MO 220-1 Main Steam Line Drains 26.0 11-26-79 8.5 1-23-80 MO 220-2 6.6 1-15-78 6.6 1-15-78 AO 220-44 Primary Sample 0.0 12-28-79 0.0 12-28-79 A0 220-45 0.0 2-28-78 0.0 2-28-78 Unable to CV 220-58A Feedwater Inlet determine 12-26-79 7.8 1-16-80 Loop "A" Inboard 1.6 2-3-78 1.6 2-3-78 CV 220-62A Feedwater Inlet 12-26-79 0.0 1-16-80 Loop "A" Outboard 5138 2-6-78 9.5 2-14-78 CV 220-58B Feedwater Inlet 0.0 11-26-79 0.0 11-26-79 Loop "B" Inboard 696.7 1-17-78 1.0 3-2-78 CV 220-62B Feedwater Inlet 406.8 11-27-79 14.9 1-28-80 Loop "B" Outboard 1-17-78 16.5 3-2-78 MO 1001-20 RHRS to Radwaste 0.0 2-12-80 0.0 2-12-80 MO 1001-21 0.0 2-22-80 0.0 2-22-80

o e 33 TABLE A-1 TYPE B AND C TEST RESULTS VALVE (S) OR MEASURED LEAK RATE (SCFH) PENETRATION TEST VOLUME AS FOUND DATE AS LEFT DATE MO 1001-23A RHRS Containment Spray - 5.1 1-29-80 5.1 1-29-80 MO 1001-26A System I 5.2 1-23-78 5.2 1-23-78 MO 1001-29A RHRS Return Loop "A" 1.5 1-28-80 1.5 1-28-80 2.1 1-23-78 2.1 1-23-78 MO 1001-34A RHRS Suppression Chamber 7.3 1-29-80 7.3 1-29-80 MO 1001-36A Spray - System I 5.7 1-23-78 5.7 1-23-78 MO 1001-37A MO 1001-23B RHRS Containment Spray - 3.7 11-29-79 3.7 11-29-79 MO 1001-26B System I 5.4 2-9-78 5.4 2-9-78 MO 1001-29B RHRS Return Loop "B" 2.1 11-29-79 2.1 11-29-79 0.0 2-9-78 0.0 2-9-78 MO 1001-34B RHRS Suppression 27.9 11-30-79 3.0 2-11-80 MO 1001-36B Chamber Spray 15.3 2-9-78 15.3 2-9-78 MO 1001-37B System II MO 1001-47 RHRS Shutdown 7.0 2-6-80 7.0 2-6-80 MO 1001-50 Cooling Suction 3.5 2-14-78 3.5 2-14-78 MO 1001-60 RHRS Head Spray 0.2 2-6-80 0.2 2-6-80 MO 1001-63 0.0 1-31-78 0.0 1-31-78 MO 1201-2 Clean-up System 0.8 12-28-79 0.8 12-28-79 MO 1201-5 Suction

6. 4 ' 2-13-78 6.4 2-13-78 M0 1301-16 RCIC Steam Supply 76.7 11-26-79 0.9 2-28-80 17.5 1-15-78 17.5 1-15-78 MO 1301-17 5.6 11-20-79 5.6 2-28-80 17.5 1-15-78 17.5 1-15-78 CV 1301-40 RCIC Condensate Drain 4.5 11-26-79 4.5 11-26-79 4.6 1-16-78 4.6 1-16-78 CV 1301-41 RCIC Turbine Exhaust 16.6 11-26-79 16.6 11-26-7S 1.2 1-16-78 1.2 1-16-78 AO 1601-21 Drywell and Suppression 136.1 12-3-79 14.5 1-17-80 AO 1601-22 Chamber Purge A0 1601-55 Unable to AO 1601-56 determine 1-19-78 4.1 3-6-78 A0 1601-20A Suppression Chamber 11.5 12-3-79 11.5 12-3-79 CV 1601-31A Vent Lines #1 7.3 1-18-78 7.3 1-18-78

34 TABLE A-1 TYPE B AND C TEST RESULTS VALVE (S) OR MEASURED LEAK RATE (SCFH) PENETRATION TEST VOLUME AS FOUND DATE AS LEFT DATE A0 1601-20B Suppression Chamber 0.8 12-3-79 0.8 12-3-79 CV 1601-31B Vent Lines #2 110.7 1-18-78 0.7 2-15-78 A0 1601-57 Drywell and Suppression 0.5 11-28-79 0.5 11-28-79 A0 1601-58 Chamber Supply Air 0.1 1-19-78 0.1 1-19-78 A0 1601-59 Purge A0 1601-23 Drywell and Suppression 27.0 12-5-79 18.0 2-12-80 A0 1601-24 Chamber Exhaust 12.5 2-25-78 12.5 2-25-78 A0 1601-60 A0 1601-61 A0 1601-62 A0 1601-63 A0 2001-3 Drywell Floor Drain 0.1 12-4-79 0.1 12-4-79 AO 2001-4 Sump Discharge 1.6 1-24-78 1.6 1-24-78 A0 2001-15 Drywell Equipment 4.2 12-4-79 4.2 12-4-79 A0 2001-16 Drain Sump Discharge 1.2 1-24-78 1.2 1-24-78 MO 2301-4 HPCI Steam Supply 3.5 11-25-79 3.5 11-25-79 MO 2301-5 16.2 1-15-78 16.2 1-15-78 CV 2301-34 HPCI Condensate Drain 6.0 11-26-79 6.0 11-26-79 8.2 1-16-78 8.2 1-16-78 CV 2301-45 HPCI Steam Exhaust 16.9 11-26-79 16.9 11-26-79 1.6 1-16-78 1.6 1-16-78 A0 4720 Drywell Pneumatic 4.3 12-6-79 4.3 12-6-79 Suction 1.0 1-24-78 1.0 1-24-78 A0 4721 Drywell Pneumatic 4.3 12-6-79 4.3 12-6-79 Suction 1.0 1-24-78 1.0 1-24-78 A0 8801A 0 Analyzer Suction 0.0 12-6-79 0.0 12-6-79 2 0.0 1-18-78 0.0 1-18-78 AO 8802A 0 Analyzer Sueti n 0.0 12-6-79 0.0 12-6-79 2 0.0 1-18-78 0.0 1-18-78 AO 8801B 0 Analyzer Suction 0.0 12-6-79 0.0 12-6-79 2 0.0 1-18-78 0.0 1-18-78 A0 8802B 0 Analyzer Suction 0.0 12-6-79 0.0 12-6-79 2 0.0 1-18-78 0.0 1-18-78

35 TABLE A-1 TYPE B AND C TEST RESULTS VALVE (S) OR MEASURED LEAK RATE (SCFH) PENETRATION TEST VOLUME AS FOUND DATE AS LEFT DATE A0 8801C 0 Analyzer Suction 11.0 12-6-79 11.0 12-6-79 2 10.5 1-18-78 10.5 1-18-78 A0 8802C 0, Analyzer Suction 0.6 12-6-79 0.6 12-6-79 > 30.0 1-18-78 0.1 2-9-78 A0 8801D 0 Analyzer Suction 0.2 12-6-79 0.2 12-6-79 2 0.0 1-18-78 0.0 1-18-78 A0 8802D 0 Analyzer Suction 0.4 12-6-79 0.4 12-6-79 2 0.0 1-18-78 0.0 1-18-78 A0 8803 0 Analyzer Return 0.0 12-26-79 0.0 12-26-79 2 0.0 1-30-78 0.0 1-30-78 A0 8804 0 Analyzer Return 2.9 12-6-79 2.9 12-6-79 2 3.9 1-30-78 3.9 1-30-78 733-1 Automatic TIP Ball V1v 0.9 12-5-79 0.9 12-5-79 0.2 1-26-78 0.2 1-26-78 733-2 Automatic TIP Ball Vlv 0.6 12-5-79 0.6 12-5-79 0.1 1-26-78 0.4 2-10-78 733-3 Automatic TIP Vall Viv 7.0 12-5-79 7.0 12-5-79 8.0 1-26-78 8.0 1-26-78 733-4 Automatic TIP Ball Vlv 0.0 12-5-79 0.0 12-5-79 0.0 1-26-78 0.0 1-26-78 733-5 Automatic TIP Ball Viv 0.1 12-5-79 0.1 12-5-79 0.8 1-26-78 0.8 1-26-78 700-743 TIP Purge Check Viv 4.6 12-5-79 4.6 12-5-79 >30.0 1-26-78 5.1 2-7-78 SO 2499-1A CAM-Drywell 0.0 2-29-80 0.0 2-29-80 SO 2499-2A SO 2499-3A CAM-Suppression Chamber 0.0 2-29-80 0.3 2-29-80 SO 2499-4A SO 2499-1B CAM - Drywell 0.0 2-29-80 0.0 2-29-A0 SO 2499-2B SO 2499-3B CAM - Suppression 0.0 2-29-80 0.0 2-29-80 SO 2499-4B Chamber

36 TABLE A-1 TYPE B AND C TEST RESULTS VALVE (S) OR MEASURED LEAK RATE (SCFH) PENETRATION TEST VOLUME AS FOUND DATE AS LEFT DATE FCV 2599-1A ACAD Isolation 0.0 2-29-80 0.0 2-29-80 FCV 2599-1B ACAD Isolation 0.6 2-29-80 0.6 2-29-80 A0 2599-2A ACAD to Drywell 0.0 2-29-80 0.0 2-29-80 CV 2599-23A i AC 2599-3A ACAD to Suppression 0.1 2-29-80 0.1 2-29-80 CV 2599-24A Chamber 0.0 2-29-80 0.0 2-29-80 A0 2599-2B ACAD to Drywell 0.0 2-29-80 0.0 2-29-80 CV 2599-23B A0 2599-3B ACAD to Suppression 0.0 2-29-80 0.0 2-29-80 CV 2599-24B Chamber A0 2599-4A ACAD Drywell Bleed to 0.' 2-29-80 0.7 2-29-80 FCV 2599-5A SBGTS 0.1 2-29-80 0.1 2-29-80 A0 2599-4B ACAD Drywell 0.0 2-29-80 0.0 2-29-80 FCV 2599-5B Bleed to SBGTS X-1 Drywell Equipment Hatch 0.0 11-23-79 0.3 3-9-80 0.0 3-8-78 0.0 3-8-78 0.1 9-25-77 0.1 9-25-77 3.3 12-5-76 3.3 10-5-76 X-2 Drywell Personnel 13.7 1-16-80 13.7 1-16-80 Airlock 9.5 3-3-78 9.5 3-3-78 X-4 Drywell Head Access 0.0 1-15-80 0.0 1-15-80 Hatch 0.0 2-27-80 0.0 2-27-80 X-6 CRD Removal Hatch 0.0 11-21-79 0.0 3-4-80 0.0 4-29-79 0.0 4-29-79 0.0 6-8-78 0.0 6-8-78 0.0 1-17-78 0.0 1-17-78 0.0 9-25-77 0.0 9-25-77 0.0 3-4-77 0.0 3-4-77 X-35A TIP Flux Mon. Flange 0.0 12-4-79 0.0 12-4-79 0.0 1-25-78 0.0 1-25-78 i X-35B 0.0 12-4-79 0.0 12-4-79 0.0 1-25-78 0.0 2-10-78

37 TABLE A-1 TYPE B AND C TEST RESULTS VALVE (S) OR MEASURED LEAK RATE (SCFH) PENETRATION TEST VOLUME AS FOUND DATE AS LEFT DATE X-35C 0.0 12-4-79 0.0 12-4-79 0.0 1-25-78 0.0 1-25-78 X-35D 0.0 12-4-79 0.0 12-4-79 0.0 1-25-78 0.0 1-25-78 X-35E 0.0 12-4-79 0.0 12-4-79 0.0 1-25-78 0.0 1-25-78 X-35F 0.0 12-4-79 0.0 12-4-79 0.0 1-25-78 0.0 1-25-78 X-35G 0.0 12-4-79 0.0 12-4-79 0.0 1-25-78 0.0 1-25-78 X-200A Suppression Chamber 0.0 11-21-79 0.0 3-9-80 Access Hatch 0.0 3-8-78 0.0 3-8-78 0.0 3-12-77 0.0 3-12-77 X-200B 0.0 11-21-79 0.0 3-9-80 0.0 2-11-79 0.0 2-11-79 0.0 6-13-78 0.0 6-13-78 0.0 6-12-78 0.0 6-12-78 0.0 6-8-78 0.0 6-8-78 0.0 5-28-78 0.0 5-28-78 0.0 5-20-78 0.0 5-20-78 0.0 3-8-78 0.0 3-8-78 0.0 11-8-77 0.0 11-8-77 0.0 9-25-77 0.0 9-25-77 0.0 5-30-77 0.0 5-30-77 0.0 3-15-77 0.0 3-15-77 0.0 3-11-77 0.0 3-11-77 Drywell Head Drywell Head Flange 0.7 11-25-79 0.0 3-9-80 0.2 3-8-78 0.2 3-8-78 SL-1 Shear Lug Inspection 0.0 12-7-79 0.0 12-7-79 Hatches 0.0 1-25-78 0.0 1-25-78 SL-2 0.0 12-7-79 0.0 12-7-79 0.0 1-25-78 0.0 1-25-78 SL-3 0.0 12-7-79 0.0 12-1-79 0.0 1-25-78 0.0 1-25-78 SL-4 0.0 12-7-79 0.0 12-7-79 0.0 1-25-78 0.0 1-25-78

38 TABLE A-1 TYPE B AND C TEST RESULTS VALVE (S) OR MEASURED LEAK RATE (SCFH) PENETRATION TEST VOLUME AS FOUND DATE AS LEFT DATE SL-5 0.0 12-7-79 0.0 12-7-79 0.0 1-25-78 0.0 1-25-78 SL-6 0.0 12-7-79 0.0 12-7-79 0.0 1-25-78 0.0 1-25-78 SL-7 0.0 12-7-79 0.0 12-7-79 0.0 1-25-78 0.0 1-25-78 SL-8 0.0 12-7-79 0.0 12-7-79 0.0 1-25-78 0.0 1-25-78 X-7A Primary Steam 0.0 11-29-79 0.0 11-29-79 0.0 1-18-78 0.0 1-18-78 X-7B 0.0 11-29-79 0.0 11-29-79 0.0 1-18-78 0.0 1-18-78 X-7C 0.0 11-29-79 0.0 11-29-79 0.0 1-18-78 0.0 1-18-78 X-7D 0.0 11-29-79 0.0 11-29-79 0.2 1-18-78 0.2 1-18-78 X-8 Primary Steam 0.0 11-29-79 0.0 11-29-79 Drain Line 0.0 1-18-78 0.0 1-18-78 X-9A Reactor Feedwater 0.0 11-29-79 0.0 11-29-79 0.0 1-18-78 0.0 1-18-78 X-9B 0.4 11-29-79 0.4 11-29-79 0.2 1-18-78 0.2 1-18-78 X-10 Steam to RCIC 0.0 11-29-79 0.0 11-29-79 0.0 1-18-78 0.0 1-18-78 X-11 HPCI to Steam Supply 0.0 11-29-79 0.0 11-29-79 0.0 1-18-78 0.0 1-18-78 X-12 RHRS Supply 0.2 11-29-79 0.2 11-29-79 0.0 1-18-78 0.0 1-18-78 X-13A RHRS Return 0.0 11-29-79 0.0 11-29-79 0.0 1+18-78 0.0 1-18-78 -X-13B 0.0 11-29-79 0.0 11-29-79 0.0 1-18-78 0.0 1-18-78

e 39 TABLE A-1 TYPE B AND C TEST RESULTS VALVE (S) OR MEASURED LEAK RATE (SCFH) PENETRATION TEST VOLUME AS FOUND DATE AS LEFT DATE X-14 Cleanup Supply 1.1 11-29-79 1.1 11-29-79 1.0 1-18-78 1.0 1-18-78 X-23 Cooling Water Supply 0.0 11-29-79 0.0 11-29-79 0.0 1-18-78 0.0 1-18-78 X-24 Vent from Drywell 0.0 11-29-79 0.0 11-29-79 0.0 1-18-78 0.0 1-18-78 X-26 ' lent to Drywell 0.8 11-29-79 0.8 11-29-79 0.1 1-18-78 0.1 1-18-78 X-36 CRD Hydraulic 0.0 11-29-79 0.0 11-29-79 System Return 0.0 1-18-78 0.0 1-18-78 ~ X-47 Standby Liquid 0.0 11-29-79 0.0 11-29-79 Control 0.0 1-18-78 0.0 1-18-78 X-17 Reactor Vessel 1.2 11-29-79 1.2 11-29-79 Head Spray 0.2 1-18-78 0.2 1-18-78 X-16A Core Spray Inlet 4.7 11-29-79 4.7 11-29-79 5.0 1-18-78 5.0 1-18-78 j X-16B 10.5 11-29-79 10.5 11-29-79 5.6 1-18-78 5.6 1-18-78 X-1008 CRD Position Indication 0.0 12-5-79 0.0 12-5-79 0.0 1-20-78 0.0 1-20-78 X-100C Neutron Monitor 0.0 11-30-79 0.0 11-30-79 ] 0.0 1-20-78 0.0 1-20-78 X-100E CRD Position Indication 0.0 11-30-79 0.0 11-30-79 0.0 1-20-78 0.0 1-20-78 .X-100F Power 0.0 12-4-79 0.0 12-4-79 0.0 1-25-78 0.0 1-25-78 X-100G CRD Position 0.0 12-4-79 0.0 12-4-79 Indication 0.0 1-25-78 0.0 1-25-78 X-101A Recirc Pump Power 0.0 11-30-79 0.0 11-30-79 0.0 1-19-78 0.0 1-19-78 X-101B Recire Pump Power 0.0 11-30-79 0.0 11-30-79 0.0 1-20-79 0.0 1-20-79

o 40 TABLE A-1 TYPE B AND C TEST RESULTS VALVE (S) OR MEASURED LEAK RATE (SCFH) PENETRATION TEST VOLUME AS FOUND DATE AS LEFT ') ATE X-101D Power 0.0 12-4-79 0.0 12-4-79 0.0 1-25-78 0.0 1-25-78 X-102B Neutron Monitors 0.0 11-30-79 0.0 11-30-79 0.0 1-20-78 0.0 1-20-79 X-103 Neutron Monitors 0.0 11-30-79 0.0 11-30-79 3.0 1-20-78 0.0 1-20-78 X-104A Power 0.0 12-5-79 0.0 12-5-79 0.0 1-20-18 0.0 1-20-78 X-104B Drywell Coolers 0.0 12-5-79 0.0 l'.-5-79 L 0.0 1-20-78 0.0 1-20-78 I X-104C CRD Position Indication 0.0 11-30-79 0.0 11-30-79 0.0 1-20-78 0.0 1-20-78 X-104D CRD Position Indication 0.0 11-30-79 0.0 11-30-79 0.0 1-20-78 0.0 1-20-78 .-104F Recirc Pump Power 0.0 12-4-79 0.0 12-4-79 0.0 1-25-78 0.0 1-25-78 1 X-105C Neutron Monitors 0.0 11-30-79 0.0 11-30-79 0.0 1-20-78 0.0 1-20-78 X-106A CRD Position Indication 0.0 12-5-79 0.0 12-5-79 0.0 1-20-78 0.0 1-20-78 X-106B Thermocouples 0.3 11-30-79 0.3 11-30-79 0.0 1-20-78 0.0 1-20-78 X-107A Neutron Monitor 0.0 11-30-79 0.0 11-30-74 0.0 1-20-78 0.0 1-20-78 X-107B Recirc Pump Power 0.0 12-4-79 0.0 12-4-79 0.0 1-25-78 0.0 1-25-78 4 4

41 APPENDIX B AS FOUND LEAK RATES The as found leak rate for the primary containment isolation valves, excluding the main steam isolation valves and leakages identified during the IPCLRT, was unable to be determined due to excessive leakage in the "A" feedwater line. The total leak rates prior to and after the outage are summarized as follows: AS FOUND AS LEFT TECHNICAL LEAK RATE LEAK RATE SPECIFICATION ITEM (SCFH) (SCFH) LIMIT (SCFH) Isolation Valves Unable to determine 132.4 110.18 Testable o Penetrations 19.2 19.2 Double Gasketed Seals 0.7 0.7 36.73 Main Steam Isolation Valves (tested at 25 psig) A0 203-1A 30.0 0.6 11.5 A0 203-2A 47.2 0.6 11.5 A0 203-1B 32.3 11.5 A0 203-2B 24.2 1.8 11.5 A0 203-1C 5.2 5.2 11.5 A0 203-2C 5.2 5.2 11.5 A0 203-ID 4.6 4.6 11.5 A0 203-2D 9.2 9.2 11.5 Total through leakage @ 25 psig 64.0 12.2 Total adjusted through leakage @ 48 psig 122.9 23.4 Total through leakage @ 48 psig Unable to determine 175.7 Complete details of these local leak rate test results are contained in LER/RO-79-27/03L.

i 42 Based on the above, the total as found leak rate of the primary containment was greater than the Technical Specification criteria of I wt%/ day. If only the leakage paths found during the IPCLRT are taken into account, the as found leak rate is 217.9 scfh (.445 wt%/ day) falling within the Technical Specification acceptance criteria of 1 wt%/ day. 4 e d 4 l l f I I 1 ~

43 APPENDIX C The following are the computations made to determine the instrument error of the instruments used during the IPCLRT. Also included is a reproduction of the computational procedures used during the IPCLRT. i i I } i 4 1 4 J I 1 T l .__.., _. - _ _ _ - - - - - - - = - - - - -, -

44 INSTRUMENTATION ERROR ANALYSIS PPG RTD THERMOCOUPLE DEWCELL +.02 psia +.15 F +2. F +1. F Accuracy +.001 psia +.1 F +.1 F +.5 F Repeatability 11 RTD Accuracy 6(T) = I (VF ) ( ) g j=1 N (PPG Accuracy) 11 Dewcell Accuracy 6(ri = (( )2 + (I (VF ) ( ))']g d (# of PPG's) j=1 N 6(P)) + 2(6(5) 6(L) = 100 [2(, T )) P P = 63.0 psia i = 92 F = 551.7 R Dewpoint = 80 F ACCURACY .15 .15 .15 .15 6(5) = (.03486)( ) + (.03174)( ) + (.03634)( ) + (.01251) ( ) di di di di .15 .15 .15 .15 +(.07979)( - ) + (.10670)( ) + (.09134)( ) + (.08624) ( ) 45 45 44 44 i .15 .15 .2 i +(.03083)( ) + (.46689)( ) + (.02276)( ) di 48 Ji l 6(T) =.11921 F With an average dewpoint of 80 F, an accuracy of +1 F egrresponds to +.017 psi. The thermocouple in subvolume #11 has an accuracy of +2 F.

45 .02 .017 .017 .017 6(P) = [( i ) + ((.0666)( ) + (.19804)( -) d di ) + (.12864)( i di d .017 .017 .034 ) + (.46689)( ) + (.02276)( )) ]b + (.11707)( i 45 41 d 6(P) =.01924 pata 6(L) = 100 (2 ( )2 + 2 '( ) ]b 63 551.7' =.05291 wt%/ day REPEATABILITY l .1 .1 .1 .1 6(T) = (.03486)( ) + (.03174)( ) + (.03634)( ) + (.01251) ( - ) + 45 di di di .1 .1 .1 .1 .(.07979)( ) + (.10679)( ) + (.09134)( ) + (.08624) ( )+ 45 44 44 44 .1 .1 .1 (.03083)( ) + (.46689)( ) + (.02276)( ) ) di di di 6(T) =.05140 F .001 .009 .009 .009 6(P) =-[( ) + ((.0666)( ) + (.12864)( ) + (.19804)( ) 45 Ji di di i .009 .009 .002 + (.11707)( ) + ( 46689)( ) + (.02276)( }) ] 41 45 41 i =.00658 psi

  • D 46 6(L) = 100 [2 (

)2 + 2( )2)\\ 63 551.7 =.01979 wt%/ day O(L) TOTAL = [.05291 +.01979 ) =.05649 wt%/ day i 2a(L) TOTAL** ' " %! *Y 1 ]- With RTD's 14 and 15 failed in subvolume #6. ACCURACY .15 .15 .15 .15 6(T) = (.03486)( ) & (.03174)( ) + (.03634)( - ) + (.01251) (-) 45 di di di .15 .15 .15 .15 +(.07979)( ) + (.10670)( ) + (.09134)( ) + (.08624) ( ) 45 Ji di 44 J .15 .15 .15 +(.03083)( ) + (.46689)( ) + (.02276)( - ) i di di di 6(T) =.12253 F i .02 .017 .017 .017 6(P) = [(, ) + ((.0666)( ) + (.12864)( ) + (.19804)(, ) 42 4,1 4,1 42 .017 .017 .034 + (.11707)( ) + (.46689)( ) + (.02276)( ))2) Ji 45 di 6(P) =.01924 psi' 6(L) = 100 [2 ( )2 + 2( )2)\\ 63 551.7 -=.05340 wt*./ day

47 REPEATABILITY .1 .1 .1 .1 6(f) = (.03486)(---) + (.03174)(, ) + (.03634)(, ) + (.01251) ( )+ J2 42 J2 42 .1 .1 .1 .1 (.07979)(---) + (.10670)(, ) + (.09134)( ) + (.08624) (, )+ 43 42 44 44 .1 .1 .1 (.03083)( ) + (.46689)( ) + (.02276)( ) di 45 Ji 6(T) =.05361 F .001 .009 .009 .009 6(P) = [(, )2 + ((.0666)( ) + (.12864)(, ) + (.19804)(, ) 42 4,1 41 42 .009 .009 .002 + (.11707)( ) + (.46689)( ) + (.02276)( ))2) JI /3 JI =.00658 psi .00658 .05361 6(L) = 100 [2 ( ) + 2(-- )2) 63 551.7 =.02017 wt%/ day c(L) TOTAL = [(.05340)2 + (.02017) ]b =.05708 wt%/ day 20(L) TOTAL ** " %# '*Y t i-l I i

48 DATA SHEETS USED AND CALCULATIONS MADE TO OBTAIN HOURLY LEAK RATES Calculations of Free Volumes and Weighting Factors Torus The calculated free volume of the torus is 116,937 ft This free volume was calculated assuming a water height in the torus of +2.0 inches. For the IPCLRT, the water height should be 0.0 inches, which will add free air volume to the torus. This additional free volume can be calculated from: ' 2 V = nh (R~-r ) where V= the added free volume of the torus h= the height change of the water in feet R= the major radius of the torus in feet r= the minor radius of the torus in feet Therefore, V = +1437 ft For the purposes of this test, the torus internal vent pipe and vent header volumes have been subtracted from the torus free air volume s,ince the air volume enclosed by the header is essentially indepesdent of the remainder 3 of the torus free air volume. This volume is found to be equal to 14,714 ft The actual torus subvolume is found to be equal to: 3 116,937 + 1437 = 118,374 fc, Drywell Since the drywell and torus were divided into twelve separate subvolumes for the calculations, the FSAR numbers will serve as a comparison to the volumes calculated (see Figure 3). The total volume of the drywell was calculated to be: V = 197,913 ft this compared with the FSAR volume of the drywell of 3 V = 198,440 ft Calculation of the shaded areas in Figure 4 gives the calculated occupied volume of the drywell. This occupied volume is 3 OV = 45,370 ft this again, was compared to the FSAR volume. The FSAR volume for the occupied volume of the drywell is OV = 40,204 ft

. D 49 In this analysis, it is necessary to assume that internal drywell equipment such as pumps, piping, valves, etc. occupy an even distribution in the drywell such that the ratios are equal to the ratios of the free volumes calculated. This assumption eliminates this component from the occupied-drywell volume calculation. The free volume of each of the twelve regions in Figure 4 was then calculated according to the following volume formuli: 1. Volume of a sphere 3 V = 4/3nr 2. Volume of a right circular cylinder V = nr h 3. Volume of a spherical segment V = 1/2nh (3r-h) The free volumes calculated are: Free Volume #1 = 10,066 ft3 Free Volume #2 9,165 ft = 3 Free Volume #3 = 10,494 ft3 Free Volume #4 3,612 ft = 3 Free Volume #5 = 23,039 ft3 Free Volume #6 = 30,808 ft3 Free Volume #7 = 26,373 ft3 Free Volume #8 = 24,900 ft3 Free Volume #9 8,901 ft = 3 Free Volume #10 =134,808 ft3 d Free Volume #11 = 7,340 ft The volume.weignting factors are then found to be VF(1) = 0.03477 VF(2) = 0.03166 VF(3) = 0.03625 VF(4) = 0.01248 VF(5) = 0.07958 VF(6) = 0.10642 VF(7) = 0.09110 VF(8) = 0.08601 VF(9) = 0.03075 VF(10) = 0.46565 VF(11) = 0.02533

50 From Figure 4, the subvolume #1 free volume is defined to be the air space above the "essel-drywell flange. The subvolume #2 free volume is the airspace between elevations 652'8" and 666'9". The subvolume #3 free volume is the ' airspace external to the biological shield between elevations 628'8" and 652'8". The subvolume #4 free volume is defined to be the annular airspace between the reactor vessel and the biological shield. The subvolume #5 free volume is the airspace external to the biological shield between elevations 614'6" and 628'8". The subvolume #6 free volume is the airspace external to the biological shield between elevations 602'10" and 614'6". The subvolume #8 free volume is the airspace external to the biological shield between elevations 593'0" and 602'10". The subvolume #7 free volume is the airspace external to the biological shield betwen elevations 579'10" and :.4 3'0" in the drywell basement. The subvolume #9 free air volume is the airspace in the CRD pit below the reactor vessel. The subvolume #10 free air volume is the volume enclosed by the drywell-torus vent pipes, vent spheres, downcomers, torus internal vent header, and the torus airspace above 0". The subvolume #11 free air volume is the reactor vessel airspace above 35" minus the steam dryer volure and one-half of the moisture separator volume. 9 i o ynn-- n-

51 CALCULATIONS PERFORMED FOR IPCLRT DATA Data collected from pressure sensors, dew cells and P.TD's located in the containment are processed using the following calculations. A. Average Subvolume Temperature and Dewpoint. I(all RTD's in the jth subvolume) T = Number of RTD's in Jth subvolume F I(all dew cells in jth subvolume) D.P. u Number of dew cells in jth subvolume F where T average temperature of the jth subvolume = D.P. = average dewpoint of the jth subvolume B. Average Primary Containment Temperature and Dewpoint. T= FL cvF.) * (r ) F J:1 J j D.P. = b (VF ) * (D.P.j) F J:1 3 where T = average containment temperature D.P. = average containment dewpoint l VF = volume fraction of the jth subvoleme NVOL = number of subvolumes If T is undefined then T = T for 1 1 j i (NVOL - 2) 3 j T. l for j = NVOL - 1 T = J-T = estimate for j = NVOL If D.P.. is undefined J D.P. = D.P. for 1 1,1 1 (NVOL - 2) D.P. = D.P. for j = NVOL - 1 D.P., = estimate for j = NVOL J

e :. 52 C. Calculation of Dry Air Pressure. D.P.( K) = 273.16 + D.P.( F) - 32 1.8 X = 647.27 - D.P.( K) EXPON = X * (Y + Z

  • X + C
  • X )

(D.P.("K))*(1 + D

  • X)

P = (218.167) * (14.696) y (pgys e(EXPON

  • In(10))

P = I(all absolute pressure gauges) ,pv (,,) Number of absolute pressure gauges where Y = 3.2437814 -3 Z = 5.86826 x 10 -8 C = 1.1702379 x 10 D = 2.1878462 x 10" P = volume weighted containment vapor pressure y P = containment dry air absolute pressure C, D, X, Y, Z, and EXPON are dewpoint to vapor prassure conversion constants and coefficients. D. Containment Dry Air Mass. W = (28.97) * (144) * (P) * (289506 - 25 * (LEVEL - 30)) 1545.33 * (T + 459.69) where W = con.ainment dry air mass LEVEL = reactor water level i l 289506 = primary containment volume i NOTE This volume is the summation of the subvolumes calculated in QTS 150-T2. These subvolumes were calculsted using QTS 150-18. Since the measured leak rate is a difference in air masses, this number is just as conservative as using'the FSAR number.

. s 53 E. Measured Leak Rate. L,(TOTAL) = (WBASE i %/ LAY ~ i BASE L,(POINT) = (W - W )

  • 2400

,3 j %/ DAY (t - t,g)

  • W,

g where W = c n ainment ry air mass a =0 BASE t = time from start of test at ith data set g t, = time from start of test at (1-1)th data set g W = dry air mass at ith data set W = dry air mass at (1-1)th data set g,g L,(TOTAL)= measured leakage from the start of test to ith data set L,(POINT)= measured leakage between the last two data sets F. Statistical Leak Rate sad Confidence Limit. LINEAR LEAST :>QUARES FITTING THE IPCLRT DATA The method of "Least Squares" is a statistical procedure for finding the best fitting regression line for a set of measured data. The criterion for the best fitting line to a set of data points is that the sum of the squares of the deviations of the observed points from the line must be a minimum. When this criterion is met, a unique best fitting line is obtained based on all of the dr.ta points in the ILRT. The value of the leak rate based on the regression is called the statistically average leak rate. Since it is assumed that the leak rate is constant during the tecting period, a plot of the measured containment dry air mass versus time would ider1]y yield a straight line witF negativ slope (assuming a non-zero lesx rate). Obviously, samplin, tec 'iques ad test conditions are not perfect and consequently the wasurec ; alues will deviate from the ideal st raight line situation. Based on this statistical process, t e calculated leak rate is obtained from the equation: W = At + B where W = contained dry air mass at time t

.4 54 B = calculated dry air mass at time t = 0 A = calculated leak rate t = test duratica B N09 Dry Air Mass (lbs)

  • 4 Test Duration (hrs)

The values for the Least Squares fit constants A and B are given by:

  • IW } = I(t - t) * (W - 0)

A = {N

  • I(tg) * (W ) - It1 1

g g 1 {N

  • I(t ) - (It )}

1(t - E) g B = IW, - A

  • It = {I(t )
  • Z(W }} - {I(t ) * (W )}

g g g g N N

  • I(ti)' - (It.)'

i where t = the average time fe,r all data sets O = the average air mass for all data sets The second formulas are used in the process computer program to reduce round-off-error. By definition, leakage out of the containment is considered positive leakage; therefore, the statistically average leak rate is given by: bs " (~^ (weight %/ DAY) B STATISTICAL UNC11TAINTIES In order to calculate the 957 confidence limits of the statistically average leak rate, the standazd di vie'. ion of the least squares slope and the student's TDistribution function are used as follows. 1 N

  • I(W )' - (IW )~

g g 1 (N-2) N

  • I(t )2 - (It )2) - A'}

a={

  • (

g g When gerforming these calculations on the process computer, 2(W )' and g (IW.) become so large that they overflow. To avoid this problem AW is substi-g tt.ted for W. AW is the difference between W and W 1 g BASE

  • 55 The single sided T-Distribution with 2 degrees of freedom is approximated by the following formula from NBS Handbook 91:

T.E. = 1.646698 + 1.455393 + 1.975971 (N-2) (N-2) The upper-confidence limit (UCL) is give,by flCL = L + o * (TE)

  • 2400 s

(weight %/ DAY) B 4 l r 4 J 4 h

....o 56 IPCLRT DEFINITIONS (48 PSIG TEST PRESSURE) Maximum Allowable Leakage. Rate (L ) L = 1.0% of containment volume per day p 3 = (0.01)(275,481 ft )/24 hrs. (FSAR) = 2754.81 ft /24 hrs. = 114.784 ft /hr. 3 = (114.764 ft /hr)(48 + 14.7) = 489.59 scfh 14.7 Maximum Allowable Operational Leakage Rate (L ) L = 75% of Maximum Allowable Leakage Rate 3 3 = 0.75 (114.784 ft /hr) = 86.088 ft /hr = 0.75 (489.59 scfh) = 367.2 scfh Maximum Allowable Leakage Rate for Double Gasketed Seals (0.10)(367.2 scfh) = 36.72 scfh Maximum Allowable Leakage Rate for Testable Penetrations & Isolation Valve (0.30)(367.2 scfh) = 110.16 scfh Maximum Allowable Leakage Rate for Any One Penetration or Isolation Valve except Main Steam Isolation Valves (367.2 scfh)(5%) = 18.36 scfh Maximum Allowable Leakage for any one Main Steam Isolation Valve 11.5 scfh @ 25 PSIG test pressure NOTE 275,481 ft is the primary containment volume as calculated in the FSAR. This number is lower than the sum of the subvolumes calculated in QTS 150-T2 and therefore is a more conservative number to use in calculating the maximum allowable leakage. i ...}}

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