ML20082H132

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Reactor Containment Bldg Integrated Leak Rate Test. W/ .Related Info Encl
ML20082H132
Person / Time
Site: 05000000, Quad Cities
Issue date: 06/14/1976
From: Kalivianakis N
COMMONWEALTH EDISON CO.
To: Rusche B
Office of Nuclear Reactor Regulation
Shared Package
ML20082H066 List:
References
FOIA-83-384 NJK-76-216, NUDOCS 8312010034
Download: ML20082H132 (128)
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9 I 8 TABLE OF CONTENTS ABSTRACT 1 A. INTRODUCTION 2 A.1 Test Frequency and Requirements 2 A.2 Statement of Test Results 2 B. TEST PREPARATIONS........................... 3 B.1 Type A Test Procedure 3 B.2 Type A Test instrumentation 3 B.3 Type A Test Heasurement System... 3 B.4 Type A Test Pressurization System 4 C. SEQUENCE OF EVENTS 11 C.I Test Preparatton' Chronology 11 C.2 48 PSIG Leak Rate Test Chronology 12 C.3 48 PSIG Induced Leak Rate Test Chronology 13 D. INTERPRETATION OF INDUCED PHASE RESULTS................ 15 E. TYPE A TEST DATA AND CALCULATIONS 16 E.1 Type A Test Data......................... 16 E.1.a Case 1(a,b) Data 16 E.1.b Case 1(a,b) SAT Data.................. 16 E.2 Type A Test Calculations..................... 16 E.2.a Volume Weighting Factor Determination........... 16 E.2.b Statistical Technique. .................. 27 F. TYPE A TEST RESULTS AND INTERPRETATIO'! ................ 30 F.1 Saturated vs. Unsaturated Environment .............. 30 F.2 Addi tion of Subvolumes 2A and 2B................. 40 F.3 Amblent Effects on Leak Rate................... 41 F.4 TIP Leakage Effects ....................... 41 F.5 Pre-Operational Resul ts vs. Test Resul ts............. 41 F.6 Future Test Proc 2 dural improvements 44 APPENDIX A - TYPE B AND TYPE C TESTS 45 APPENDIX B - AS FOUND LEAK RATES ................... 57 APPENDIX C - TYPE A TEST INSTRUMENTATION ERROR ANALYSIS........ 58 1. Accuracy E rro r Ana l ys i s.................... 60 2. Repeatability Error Analysis ................. 61 3. Total Instrument Uncertainty 62 APPENDlX 0 - DEWCELL PROBLEM 63 I

9 i TABLES AND FIGURES INDEX PAG ( TABLE ONE INSTRUMENT SPECIFICATIONS TABLE TWO SENSOR PHYSICAL LOCATIONS 5 6 TABLE THREE 48 PSIG Type A Test - Case 1(a,b) 19 TABLE FOUR 48 PSIG Type A Test - Induced Leak Rate 21 Phase - Case 1(a,b) TABLE FIVE 48 PSIG Type A Test - Case 1(a,b) - Final CIx Hours From 22 Reference Time Zero TABLE SIX 48 PSIG Type A Test - Case 1(a,b) SAT 23 TABLE SEVEN 48 PSIG Type A Test - Induced Leak Rate Phase - Case 1(a,b) SAT 25 TABLE EIGHT 48 PSIG Type A Test - Case 1(a,b) SAT - Final Six Hours From 26 Reference Time Zero TABLE A-1 Type B and Type C Test Results 46 FIGURE ONE IDEALIZED VIEW OF DRiWELL AND TORUS USED TO CALCULATE FREE 7 VOLUMES FIGURE TWO TEMPORARY INSTRUMENT PENETRATION 8 FIGURE THREE MEASUREMENT SYSTEM SCHEMATIC ARRANGEMENT 9 FIGURE FOUR PRESSURIZATION SYSTEM SCHEMATIC ARRANGEMENT 10 FIGURE FIVE STATISTICAL LEAKAGE VS. TIME, CASE 1(a,b) 31 FIGURE SIX STATISTICAL LEAKAGE VS. TIME, CASE 1(6,b) SAT 32 FIGURE SEVEN STATISTICAL LEAKAGE FOR FINAL SIX HOURS OF THE 48 PSIG TEST 33 VS. TIME, CASE 1(a,b) FIGURE EIGHT STATISTICAL LEAKAGE FOR FINAL SIX HOURS OF THE 48 PSIG VS.34 TIME, CASE 1(a,b) SAT FIGURE NINE MEASURED LEAKAGE (HOURLY) VS. TIME, CASE 1(a,b) 35 FIGURE TEN MEASURED LEAKAGE (HOURLY) VS. TIME, CASE 1(a,b) SAT 36 FIGURE ELEVEN PRIMARY CONTAINMENT SUBVOLUME AND VOLUME WEIGHTED AVERAGE 37 TEMPERATURES VS, TIME FIGURE TWELVE PRIMARY. CONTAINMENT SUBVOLUME AND VOLUME WEIGHTED VAPOR38 PRESSURES VS. TIME FIGURE THIRTEEN PRIMARY CONTAINMENT TOTAL PRESSURE AND DRY AIR PRES 39 TIME FIGURE FOURTEEN EFFECT OF SHUT *0WN COOLING ON SUBVOLUME 2 A AND 2 B TEMPERATU FIGURE FIFTEEN REACTOR BUILDING TEMPERATURE VS. TIME 43 h 11 ,,w.. r-3- -+,e, ,m., -c- -e, ,e s.

9 5:30 PM Five leaks of various sizes were found in the Traversing incore Probe (TIP) rocm; the total leakage was estimated to be 1.0 scfm. The leaks were through new fittings installed during this refueling outage which had not been sufficiently tightened. The fittings were tightened to correct the leakage. 6:30 PM The RCIC valves and HPCI valves were reopened after no leakage effect was determined. 3-6-76 00:18 AM Data indicated that the ILRT was satisfactory over the required 24 hour time span. However, data acquisition was continued for an additional hour in order to determine graphical tendencies of the measured and statistical leak rates. 1:00 AM The ILRT 24 hour test phase at 48 psig was completed. Radiation Protection personnel immediately obtained a drywell air sample in order to determine whether or not a possible airborne activity situation might be present in the Reactor Building during the induced leak rate portion of the ILRT. The sample resulted in a negligible activity measurement. 2:00 AM Operational Analysis and Instrument Department per-sonnel completed a humidity measurement of the drywell environment. The results indicated an 60'F dewooint at elevation 620, approximately 5*F below the dewpoint measured during the test. C.3 48 psig induced Leak Rate Test Chronology DATE TIME EVENT 3-6-76 3:00 AM The induced leak rate phase was begun with an imposed leak rate of 3.05 scfm (0.36 wt%/ day). 7:00 AM A negative leak rate, indicating a source of in-leakage into the primary containment, was indicated based on data cbtained at the console. 3:30 PM The flowmeter was found to indicate 6.1 scfm with no actual flow through the flowmeter. l l 5:30 PM A leak was again imposed on the primary containment, this time through two of the Oxygen Analyzer Rack i rotometers. This resultant imposed leak was equal to 6.0 scfm (0.713 wt%/ day). A moisture trap was Installed upstream of the rotometer in order to reduce the possibility of moisture condensation affecting .the imposed leak rate. 10:00 PM The imposed leak rate phase was completed. However, the results were unexplair,able at this time due to l 13

t 1 the lack of correlation between the 24 hour measured leakage and the induced leakage. Additional leaks of higher magnitudes were imposed on the primary containment in an attempt to determine a correlation. However, these imposed leaks were not accurately set at the rotometers and insufficient time was alloted for data collection. 3-7-76 3:00 AM Blowdown of the primary containment was begun to perform a drywell Internal investigation to determine a possible cause for the lack of data correlation. 12:15 PM Blowdown was completed and a drywell entry was made. There were no instrument or structural deficiencies discovered during this inspection. 'l t

o SECTION D - INTERPRETATION OF INDUCED PHASE RESULTS Although it became apparent during the test that effects not included in the analysis were present, one of these effects (shutdown cooling) was not identifled until after depressurization. Continuing investigations of the Ecst data demon-strated a direct cycling of containment pressure with operation of the shutdown cooling system. Temperature changes in the immediate vicinity of the vessel, inside the biological shield, resulted in primary containment pressure changes not accounted for in the initial data analysis model. The two foot thick cylindrical concrete wall of the biological shield,, capped at the top, separates the enclosed volume from the other subvolumes except for openings for pipe pene-trations. This separation is not air tight but is sufficiently thermodynamica11y removed from the other subvolumes that additional subvolumes 2a and 2b, described in Section B.2, were added to the analysis to account for the separation. Because the vessel shell temperature had been computer trended during the test, it was possible to use a calculated heat transfer relationship for subvolume 2b. Additionally, normal vessel and drywell temperature recorders were available for furhter temperature information to support the calculated temperature distri-bution used in the analysis madel. During the 24 hour test, the shutdown cooling system was cycled sufficiently that the end result would have been acceptable. However, since the Induced phase was expected to take only six hours, it was decided not to run the shutdown cooling system. However, with the shutdown cooling system off, the increase in temperature inside the biological shield (approximately 4.4% of the total containment volume) resulted in an indicated increase in mass that offset the calculated leak rate until the analysis model was improved. l t I 1 l l 1 l [ l 15 l n w n s e-m' e y

SECTION E - TYPE A TEST DATA AND CALCULATIONS This section demonstrates the methods used in determining the calculated data presented in the Tables herein. Graphical representations of these results are presented in Section F. E.1 Type A Test Data The test data was analyzed for two cases of primary containment relative humidity to illustrate the conservative effect of complete saturation. The data was analyzed for each case in its entirety. E.1.a Case 1(a,b) Data This case uses complete saturation throughout the entire primary contain-ment except for humidity subvolume 1,2. Since complete saturation (100% R.H.) is used, the dewpoint temperature is by definition equal to the dry bulb temperature as registered by the RTD's. The dewpoint for humidity subvolume 1,2 is taken to be the actual measured dewpoint tem-perature. The 48 psig and induced leak rate test data are given in Tables Three and Four, respectively. Table Five shows the results of negating the TlP leakage by eliminating the data for this period of time, but measuring the leak rate from reference time zero. E.1.b Case 1(a,b) SAT Data This case uses complete saturation (100% R.H.} for each s'ibvolume in the primary containment. Again, the dewpoint is taken to be equal to the dry bulb temperatures as registered by the RTD's. The 48 psig and induced leak rate test data are given in Tables Six and Seven, respectively. Table Eight again demonstrates the result of negating the TIP leakage by eliminating the data for this period of time, but measuring the leak rate from reference time zero. E.2 Type A Test Calculations E.2.a Volume Weighting Factor Determination As previously mentioned, a volume fraction weighting factor was applied to each temperature and humidity sensor reading in order to obtain primary containment volume weighted averages for these values. The volume frac-tions of the drywell and torus were calculated as follows: 2 V= Th (R -r2) 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 3 Therefore, V = 1437 ft. 16

Additionally, for the purposes of this test, the torus internal vent pipe and vent header volumes were subtracted from the torus free air volume since the air volume enclosed by the header is essentially Independent of the remainder of the torus free air volume. Since this volume was found to be equal to 14,714 ft3, the actual torus subvolume was found to be equal to: 117,245 - 1,437 - 14,714 - 101,094 ft3 Drywell Since the drywell was divided inte eight separate volumes for the calcula-tions, the FSAR numbers served as a comparison to the volumes calculated. Initially, the drywell was idealized into easily calculable volumes (see Figure Threc). The total volume of the components was calculated to be: V = 198,429 ft3 this compared with the FSAR volume of the drywell of V - 198,440 ft3 Calculation of the volumes represented by the shaded areas in Figure Three gave the calculated occupied volume of the drywell. This occupied volume was: OV = 44,079 ft3 This, again, was compared to the FSAR occupied of 40,204 ft3, in this analysis, it was necessary to assume that internal drywell equip-ment such as pumps, piping, valves, etc. occupied an even volumetric distribution throughout the drywell such that the volume ratios were equal to the ratios of the free volumes calculated, i l The following volumes were free volumes, but are not included in the sub-volume fractions because of their isolated characteristics: Vent Pipe Volume between Torus 3 and Drywell 5,596 ft Volume Enclosed by the Main Steam Lines between the Reactor Vessel and the inboard MSIV's 648 ft3 l Utilizing all of these factors, the total primary containment free air volume was found to be: l 154,350 Drywell free air volume l 101,094 Torus free air volume 14,714 Torus internal vent header volume l 5.596 Torus-Drywell vent pipe volume 648 Main steam line enclosed vo?ume 276,402 ft3 Total Free Air Voiume 17

i The temperature and humidity subvolume volume fractions were found to be: Free Volume (Ft3) Volume Fraction Subvolume #1 7,778 0.03045 Subvolume #2 20,146 0.07887 Subvolume #2A 7,573 0.02965 Subvolume #2B 3,748 0.01467 Subvolume #3 23,353 0.09142 Subvolume #4 31,067 0.12162 Subvolume #5 26,591 0.10410 Subvolume #6 34,094 0.13347 Subvolume #7 101,094 0.39575 It can be seen that the calculated free volume of the drywell and tS)rus 3 (276,402 ft ) was in good agreement with the FSAR value (275,481 ft The effect of this difference on the induced leak rate in scfm was insig-nificant when converted to wt%/ day. 18

TABLE THREE UNIT ONE 48 PSIG TYPE. A TEST Case 1(a,b) Lm L 95% LOWER 95$UFPER TIME CONTAINMENT CONTAihMENT CONTAINMENT CONTAINMENT CCNTAINMENT TOTAL TIME STATISTICALLY COMFIDEUCE C0';F102HCE s i . PRESSURE AVG. VAPOR DRY Alh AVERAGE CliY A IR MEASURE 0. AVERAGED LEVEL LEAK LEVEL LEA' f (PSIA) PRESSURE PRESSURE TEMPERATURE PASS (LBm) LEAK RATE LEAK RATE RATE RATE (PSI) (PSIA) (OF) (%/ DAY) (%/ DAY) (%/ DAY) (t/ DAY) 0000 63.955 0 705 63.289 92.539 85,519.49 0030 64.001 0.709 63.291 92.732 85,486.34 1.524 I 0100 63.999 0.706 63.293 92.844 85,471.42 1.181 1.181 0.049 2 312 0130 63.994 0 705 63.289 92.892 85',458.86 1.022 1.004 0.593 1.414 4 0200 63.991 0 704 63.287 92.944 85,948.14 0 917 0.888 0.638 ' l.138 0230 63 989 0 702 63.287 92.961 85,145.01 0.869 0.753 0.529 0 977 0300 63.990 0.702 63.287 93.060 85,430.52 0.776 0 711 0.554 0.868 1 0330 63.984 0.701 63.283 92.482 85,514.09 -0.005 0.244 -0.298 O.786 0400,63 967'. 0.700 63.267 91.830 85,592.99 -0.558 -0.286 -0 999 0.427 0430 163 954 0.698 63.256 91.811 S5,581.22 -0.422 -0.504 -1.109 0.101 0500 63 944 0.697 63.247 91.843 C5,564.30 -0.285 -0.557 -1.046 .0.067 0530 63 937 0.697 63.241 92.034 85,526.01 -0.064 -0.483 -0.893 -0.074 + 0600 63 932 0.696 63.237 92.213 85,f92 98 0.096 -0.362 -0.727 0.004 i l 0630 63 919 0.695 63.224 91.828 85,535.13 -0.093 -0.343 -0.653 -0.032 0700 63.895 0.691 63.204 91.261 85,596.25 -0 332 -0.407 -0.683 -0.168 0730 63.876 0.690 63.186 91.287 85,563.71 -0.207 -0.408 - -0.647 -0.168 0500 63.860 0.688 63.172 91.362 85,537.29 -0.083 -0 365 -0.580 -0.092 l 0830 63.845 0.687 63.159 91.472 85,S02.64 0.036 -0.295 -0.498 -0.092 i 0900 63.830 0.687 '63.143 91.646 85,454.59 0.184 -0.197 -0.403 i 0.008 0930 63.817 - 0.683 63.135 91.765 85,424.29 0.264 -0.099 -0.308 0.110 i 1000 63.806 0.683 63.122 91 955 85.378.57 0.379 0.008 -0.209 0.225 1030 63.800 0.680 63.!20 91.987 85,369.92 0.384 0.094 -0.120 0.309 1100 63.790 0.679 63.111 91.962 85,362.05 0 386 0.164 -0.043 0.371 I i 1130 63.746 0.683 63.062* 90.653 85,499.14 0.036 0.139 -0.052 0.33a i 1200 63.716 0.673 63.043 90.515 85,493.95 0.0f 6 0.120 -c.056 0.297-1230 163.697 0.670 63.027 90.425 85,478.12 0.059 0.108 -c.054 0.271 i 1300 63.681 0.668 63.012 90.472 85.659.31 0.117 0.110 -0.040 0.261 1330 63.666 0.668 62 998 90,604 85,419.26 0.196 0.128 -0.013 0.268 i 1400 63.650 0.666 62.984 90.765 85,375.13 0.277 0.158 0.024 0.292 1430 63.638 0.663 62 974 90.897 85,341.59 0 333 0.194 0.064 0.324 g' 1500 63.622 0.662 62 959 91.083 85,232 75 0.413 0.413 c.238 0.367 1530 63.61'3 0.661 62 551 91.045 85,237.85' O.409 0.409 c.i49 0.l:01 1600 ,63.592 0.659 62 933 90 927 85,230.63 0.408 c.307 0.184 0.429 1630 63.571 0.659 62 912 90 710 85,206.72 0.386 0.329 0.212 0.446 1700 63.551 0.657 62 900 90.475 85,'> 05. 83 0.343 0 342 0.231 0.453 19 8 I I

TABLE THRI:E UNIT ONE 48 PSIG TYPE A TEST ~ Case 1(n,b) Lm L 95% LOWER 955UPER s TIME CONTAlHMENT CONTAINMENT CONTAINMENT CONTAINMENT CONTAlHMENT TOTAL TIME STATISTICALLY CONFICENCE CONFIDENCE PRESSURE AVG. VAPOR . DRY AIR AVERAGE CRY AIR MEASURED AVERAGED LEVEL LEAK LEVEL LEAF (PSIA) PRESSURE PRESSURE TEMPERATURE l'. ASS (LBm) LEAK RATE LEAR RATE RATE RATE (PSI) (PS'I A) (OF) (%/ DAY) (%/ DAY) (3/ DAY) (%/ DAY) 1730 63.552 0.657 62.895 90.636 85,774 36 0.333 0.359 0.253 0.465 1800 63.559 0.656 62 902 90.832 85.254.31 0.404 0 376 0.275 0.478 1830 63.565 0.657 62.908 91.094 85.221.49-0.443 0.397 0.299 '0.496 - 1900 63.563 0.656 62 907 91.320 85,185.26 0.485 0.421 0 325 0.518 1930 63.571 0.659 62 912 91.580 85,152.23 0.520 0.447 0 353 0.542 2000 63.579 0.657 62 923 91.782 85,135.02 0.531 0.472 0 379 0.565 2030 63.588 0.658 62.931 91.522 85,185.88 0.448 0.481 0 392 0.570 2100 63.570 0.657 62 913 91.235 85,199.03 0.420 0.486 0.401 0.57) 2130 63.556 0.657 62.599 90.970 85,227.99 0.373 0.484 0.403 0.565 2200 63.552 0.656 62.895 90.819 85,;46.79 0.340 0.477 0 399 0.555 2230 63.550 0.657 62.893 90.945 85,223.92 0.361 0.474 0 399 0.548 2300 63.550 0.656 62.e93 9i.082 85.103.56 0.378 0.472 0.40i 0.544 2330 63.551 0.657 62.893 91.323 85,165.96 0.415 0.475 0.407 0.544 2400 63.551 0.656 62.895 91.481 85.143.78 0.432 0.480 0.414 0.545 2430 63.548 0.656 62.891 91.659 85,111.56 0.460 0.487 0.424 0.550 2500 63.552 0.657 62.895 91.828 85,090.44 0.475 0.495 0.434 0.556 s l t 20

, TABLE FCult UN!T ONE 48 PSIG r PE TEST Case i(t.,6) 1 Induced Leak _R 3e Phase 7 Lm L 95% LOWER 954 UPPER s TIME CONTAINMENT CONTAINMENT CONTAINMENT CONTAINMEf!T CC11/ i Nf'ENT TOTAL TIME STATISTICALLY CONFI DE*4CE C0!!F I CE!!CE PRESSURE AVG. VAPOR DRY AIR AVERAGE GRY AIR MEASURED AVERAGED LEVEL LEAK LEVEL LEAK (PSIA) PRESSURE PRESSURE TEMPERATURE l'ASI (LBm) LEAK RATE LEAK RATE RATE RATE (PSI) (PSIA) (OF) (t/ DAY) (t/ DAY) (%/ DAY) (t/ DAY) 3 1730 63.538 0.656 62.882 93.450 8i,321.93 l 1800 63.535 0 659 62.876 93.593 84,792.91 1.642 1830 63.534 0.658 62.876 93.690 84,778.73 1.222 1.222 -0.290 2 735 1900 63.537 0.659 62.877 93.888 84,750.16 1.354 1.299 c.915 - 1.682 1930 63.541 0.661 62.E80 94.083 84,723.38 1.394 1.357 1.162 1.553 2cco 63.549 0.661 62.088 94.261 I 0':,737.53 1.295 1.308 1.178 1.439 2030 63.558 0.661 62.696 94.431 84,692.57 1.220 1.241 1.124 1.359 2l00 63 569 0.663 62.906 94.637 S4,674.23 1.194 1.196 1.098 1.295 2130 63.58; 0.662 62.920 94.830 84,663.27 1.122 1.137 1.038 1.236 l 2200 63.597 0.663 62.934 95.012 84.654.15 1.055 1.073 0 969 1.177 I 4 e i I i i i l l i 1

TABLE FIVE ~ UlllT ONE 48 PSIG TiPE A TEST Case 1(o,t-) Final Six Hours From Reference Time Zero Lm L 95% LOWER 954 UPPEP. s TIME CONTAINMENT CONTAINMENT CONTAINMENT CONTAINHENT C0:!TAIHMENT TOTAL TIME STATISTICALLY COM.lDEHCE CONFIDEl:CE PRESSURE AVG. VAPOR DRY AIR AVERAGE ORY AIR MEASURED AVERAr.ED LEVEL LEAX LEVEL LEA' (PSIA) PRESSURE PRESSURE TEMPERATURE l'ASE (LBm) LEAK RATE LEAK ?. ATE RATE 3 ATE (PSI) (PSIA) (OF) (0/ DAY) (2/Pf,Y) (%/2AY) !j};~5f.;) 0000 63.995 0.705 63.289 92.539 85,51?.49 1 ~ ~ 1900 63 563 0.656 62.907 91 320 85,185.26 0.485 1930 63.571 0.659 62.912 91.580 85.152.23 0.520 0.503 0.330 0.677 2000 63.579 0.657 62.923 91.782 85,135.02' O.531 0.514 'O.430 0.598 2030 63 588 0.658 62.931, 91.522 85,185.88 0.449 0.494 0.391 0.598 21C0 63.570-0.657 62.913 91.285 85,199.03 0.420 0.474 0 360 0.587 2130 63 556 0.657 62.899 90 970 85,227.99 0.373 0.447 0.312 0.583 2200 63.552 0.656 62.895 90.819 85,246.79 0.340 0.419 0.267 'O.571 2230 63.550 0.657 62.893 ,90.945 85,223.92 0.361 0.401 0.256 0.547 23C0 63.550 0.656 62.393 91.082 85,203.56 0.378 0.391 0.256 0.525 2330 63.551 0.657 62.893 91.323 85,155.96 0.415 0 390. 0.268 0.512 2400 63.551 0.656 62.895 91.431 85,143.73 0.432 0 393 0.281 0.505 2430 63.548 0.656' 62.891 91.659 85,111.56 0.460 0.403 0.297 0.509 2500 63.552 0.657 62.395 91.828 85,c90.44 0.475 0.415 0.313 0.517 - e 9 22 l

TAELE S1:( U'llT ONE 48 PSIG T(PC A TEST Case 1(c,b) g. s Lm L 95% LOWER 95dUPPER i s TIME CONTAINMENT CONTAINMENT C0!iTAINMENT CONTAINMENT CCNTAi!! MENT TOTAL TIME STATISTICALLY CCFFIDENCE CCNFIDENCI PRESSL'RE AVG. VAPOR DRY AIR AVERAGE CI'.Y A I P. MEASURED AVERAGED LE*.EL LEAK LEVEL LEA: (PSIA) PRESSURE PRESSURE TEMPERATURE l' ASS (LBm) LEAK RATE LEAK RATE P.Al E

  • F. ATE i(2/ DAY)

(PSI) (PSIA) (cF) (%/ DAY) (%/ DAY) (%/ DAY) l 0000 63 995 0.786 63.209 92.539 85.405.13 0030

64. col 0.791 63.209 92.732 85.375.53 1.66

-- ~ 0100 63 999 0.793 63.206 92.844 G3 354.20 1.431 1.4313 0.665 '2.198 0130 63.994 0.794 63.201 92.892 85.339.36 1.232 1.229 0.830 1.628 0200 63.991 0.795 63.196 92.944 83.324.72 1.130 1.107 0.856 1.358 0230 63 989 0.798 63 191 92.961 85.315.37 1.009 0 989 0.780 1.198 0300 63.990 0.801 63.188 93.060 85.236.96 1.013 0.952 0.806 .l.098 0330 63 984 0.804 63.180 92.482 83.374.57 0.245 0.494 -0.037 1.024 0400 63.967 0.801 63.166 91.830 85,456.84 -0.363 -0.061 -0.793 0.670 0',30 63 954 0.801 63.152 91.811 85,441.32 -0.226 -0.293 -0 917 0.331 0500 63 944 0.803 63.141 91.843 85.420.88 -0.039 -0.354 -0.859

0. 152 0530 63 937 0.806 63.132 92.034 85,378.69 0.135

-0.284 -0.706 0.138 l 0600 63 932 0.806 63.126 92.213 89.343.57 0.288 -0.167 -0.541 0.206 0630 63.919 0.814 63.105 91.828 8.);374.66 0.132 -0.139 -0.450 0.179 0700 63.895 0.807 63.088 91.261 85,439.15 -0.137 -0.208 -0.491 0.075 0730 63.876 0.807 63.069 91.287 85,410.17 -0.019 -0.214 -0.460 0.032 0800 63.860 0.809 63.051 91.362 85,373.56 0.111 -0.173 -0.393 0.047 0830 63.845 0.811 63.035 91.472 85.334.37 0.234 -0.103 -0.310 0.104 0900 63.830 0.816 63.015 91.646 85,280.35 0.390 -0.003 -0.213 0.207 0930 63.817 0.815 63.002 91.765 85,245.51 0.472 0.098 -0.116 0.312 1000 63.806 0.821 62 985 91.955 85,192.99 0.596 0.209 -0.013 0.432 1030 63.800 0.828 62.972 .91 987 85,169.81 0.630 0.306 0.083 0.530 1100 63.790 0.873 62 917 91 962 85,099 17 0.782 0.420 0.187 0.653 1130 63.746 0.824 62.922 90.653 85,308.75 0.236 0.385 0.i70 0.601 1200 63.716 0.807 62.909 90.515 85,3'2.27 0.218 0.353 0.152 0.554 1230 63.697 0.803 62.894 90.425 85,305.82 0.223 0.328 0.141 0.514 I 1300 63.681 0.805 62.876 90.472 85,273.86 0.284 0.319 0.147 0.492 1330 63.666 0.808 62.858 90.604 85,229.48 0.366 0.328 0.168 0.489 1400 63.650 0.811 62.839 90.765 85,179.16 0.454 0.353 -0.202 0.504 1430 63.638 0.813 62.825 90.897 85,138.79 0.516 0.386 0.241 0.530 1500 63.622 0.815 62.806 91.083 85,035.44 0.599 0.428 a.287 0.569 1530 63.613 0.820 62.792 91.045 85,072.41 0.603 0.465 0.328 0.602 1600 63.592 0.822 62.770 90.927 85,060.36 0.606 0.496 0 364 0.628 1630 63.571 0.815 62.756 90.710 85,074.48 0.563 0.516 0.390 0.642 1700 63.556 0.812 62.744 90.475 85,095.37 0.512 0.525 0.406 g0.643 23 c i i

~. _._. - -TAbtE SIX UNIT ONE 48 PSIG TYPE A TEST case 1(a,b)scr lm L 95% LOWER 95% UPPER s TIME CONTAINMENT CONTAINHENT CONTAINHENT CONTAINitENT CCMTAIN!!ENT TOTAL TIME STATISTICALLY CONFIDENCE C0:lFIDENCE PRESSURE AVG. VAPOR DRY AIR AVERAGE CRY AIR MEASURED AVERAGED' LEVEL LEAK LEVEL LEAP (PSIA) PRESSURE PRESSURE TEMPERATURE PASS (LBm) LEAK RATE LEAK RATE RATE RATE (PSI) (PSIA) (OF) (2/ DAY) (%/ DAY) (t/0AY) (?/ DAY) 1730 63.552 0.813 62.739 so.636 85,063.34 0.549 -0.537 0.425 0.650 1800 63.559 0.816 62.743 90.832 85,038.17 0.573 0.552 0.445 0.660 l 1830 63.565 0.822 62.743 91.094 34.998.37 0.618 0.571 0.468 0.675 L-1900 63.563 0.824 62.739 91.320 84,957.86 0.661 0.595 0.494 0.635 1930 63.571 0.830 62.741 91.580 84,920.98 0.690 0.620 0.521 0.718 2000 63.579 0.834 62.745 91.782 84,894.92 0.717 0.644 0.547 0.741 2030 63.588 0.839 62.750 91.522 84,940.88 0.636 0.655 0.562 0.474 L 2l00 63.570 0.837 62.733 91.235 84,954.98 0.602 0.659 0.571 1 0.748 2130 63.556' .0.826 62.729 90.970 84,993.58 0.531 0.654 0.569 0.738 2200 63.552 0.823 62.728 90.819 85,020.44 0.491 0.644 0.562 0.725 2230 63.550 0.824 62.726 90 945-83.,997.61 0.509 0.636 0.558 c.714 2300 63 550 0.825 62.725 : 91.082 84,975.02 0.526 0.632 0.557 O.707 2330 63 551 0.828 62.723 i .91.323 84,935.24 0.562 0.632 0.360 0.703 l 2400 63.551 0.830 62.720 91.481 84,907.50 0.583 0.634 0.565 0.703 2430 63.548 0.833 62.715 91.659 84,873.07 0.610 0.639 0.573 0.705 2500 63.552 0.836 62 715 91.828 S4,847.45 o.627 0.645

  • 0.582 0.709 l

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2 TABLE SEVEN i UNIT ONE 48 PSIG TYPE A TEST Case 1(a,t.) 7 l InducedLeakRatekhase Lm L 951 LOWER 95I UPFER s TIME CONTAINMENT CONTAINMENT CONTAINMENT CONTAINMENT CONTAINMENT TOTAL TIME STAT!STICALLY CONFIDENCE CONFIDENCE PRESSURE AVG. VAPOR DRY AIR AVERAGE DRY /slR MEASURED AVERAGED LEVEL LEAK LEVEL LEAi (PSIA) PRESSURE PRESSURE TEMPERATURE V. ASS (LBm) LEAK RAiE LEAR RATE RATE RATE (PSI) (PSIA) (OF) (2/ DAY) (%/ DAY) (%/ DAY) (t/ DAY) r l 1730 63.538 0.882 62.656 93.460 84,516.76 t 1800 63.535 0.889 62.646 93.593 84,482.74 1 932 1830 63 534 0.892 62.643 93.690 84,463 85 1 503 1.503 10.086 2.119 [~ 1900 63 537 0.898 62.639 93.888 84,428.77 1.666 1.636 1.224 1.989 [ 1930 63 541 0.901 62.640 94.083 84,400.65 1.649 1.625 1.447 -1.804 2000 63 549 0.905 62.643 94.261 84,377.65 1.580 1.585 1.469 1.702 I '2030 63 558 0.911 62.647 94.431 84,356.80 1 514 1.528 1.425 1.631 4 2100 63 569 0 912 62.657 94.637 84,339 00 1.442 1.461 1.355 'I.567 2130 63 5C? 0.920 62.662 94.830 84,316.16 1.424 1.419 1 326 1.511 ~ 2200 63 597 0.926 62.67I 95.012 84,300.13 1.367 1.369 1.280 1.459 K r I I \\ j r l 2:

TACLE EIGitT UNIT ONE 48 PSIG TYPE A TEST a Case 1(a b)mr Final Six Hours From Ref,erence Time Zero Lm L 95'; LOWER 95;; UPPER 3 TIME CONTAINMENT CONTAINMENT CONTAINMENT CONTAINMENT CDhTAINMENT TOTAL TIME STATISTICALLY C0tlFl 0E!1CE - CONFIDENCE PRESSURE AVG. VAPOR DRY AIR AVERAGE CRY AIR MEASURED AVERAGED LEVEL LEAK LEVEL LEA

  • i (PSIA)

PRESSURE PRESSURE TEMPERATURE P. ASS (L3m) LEAK RATE LEAK RATE RATE RATE l (PSI) (PSIA) (OF) (t/ DAY) (%/ DAY) (t/ DAY) (%/ DAY) 0000 63.995 0.786 63.209 92.539 85.405.13 1900 63 563 0.824 62 739 91.320 84,957.86 0.662

  • [

l 1930 63.571 0.830 62.471 91.580 84,920.98 0.698 0.681 0.502 0.859 2000 63 579 0.834 62.745 91.782 84,894.92 0.717 0.694 0.597 0 792 J 2030 63.588 0.839 62.750 91.522 84,9'io.88 0.636 0.677 0.577 0 776 2100 63 570 0.837 62.733 91.285 84,934.98 0.602 0.657 0.545 0.768 2130 63 556 0.826 62.729 90.970 84,938.58 '0.531 0.624 0.472 0.776 j 2200 63.552 0.823 62.728 90.819 85,c20.44 0.491 0.590 0.413 '0 766 j 2230 63 550 0.824 62 726 90.945 84,997.61 0.509 0'.566 0.393 0 739 I 2300 63 550 0.825 62.723 91.082 84.975.02 0.525 0 550-0.388 0 7 1'3 2330 63 551 0.828 62.723 91.323 84,935.24 0.562 0.545 0 397 0.693 t 2400 63 551 0.830 62.720 91.481 84.907.50 0.583 0 546 0.410 0.681 I 2430 63.548 0.833 62.715 91.659 84,873.07 0.610 0.553 0.426 0.679 i 2500 63.552 0.836 62.715 91.828 64,847.45 0.627 O.563 0.443 0.682 r< ~ j l i 1 I; l L

E.2.b Statistical Technique in order to comply with the calculation techniques of ANSI Nh5.4 and' 10CFR50 - Appendix J, it was necessary to perform a least squares fit .of the ILRT data. The method of "Least Squares" is a statistical pro-cedure 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 devittions 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 data points in the ILRT. The value of the leak rate based on the regression is called the statistically averaged leak rate. Since it is assumed that the leak rate is constant during the testing period, a plot of the measured contained dry air mass versus time would ideally yield a straight line with a negative slope (assu.r.ing a non-zero leak rate). Since sampling techniques and test conditions are not perfect, the data points deviate from the ideal straight 1;ne situation. Based on this statistical process, the calculated leak rate is obtained from the equation: W = AT+ D where W = contained dry air ress at time t (lbs) B = calculated contained dry air masa at time t=0 (Ibs) A = calculated leak rate (lbs/hr) t = test duration (hours) B Contained Dry Air Hass (Ibs) One* t Test Duration (hrs) I ( The values of the constants A and B such that the regression line is best fitting to the IPCLRT data are: A= [NE(ti)(WI)]-[(Eti)(EWI)] l [NE(ti)* - (Eti)l] i - AEtt B= N 27

By definition, leakage out of the primary containment is considered positive leakage; therefore, the statistically averagsf leak rate in weight percent per day is given by Ls = (-A)(2400)/(WBASE) (weight %/ day) in order to calculate the 95% confidence Ilmits of the statistically averaged leak rate, the standard deviation of the least squares slope and the T-Distribution function are used as follows: I(N-2)- ((NI(Wi)2 (ty;)2} -A ))1 I 2 0" NE(ti)4 - (Eti)4 LCL = Ls-WBASE (TE)(2400 ' UCL = ls+ WBASE whereTE=1.645+I'[9 +25 g N = number of data sets ti = test duration at the ith, data set Wh = contained dry air mass at the ith data tot o = standard deviation of least squares slope TE = value of the single-sided T-distribution function with 2 degrees of freedom L = calculated leak rate in %/ day LCL = 95% lower confidence limit UCL = 95% upper confidence ilmit W ASE = contained dry air mass at time t=0 B w Other formulas used to actually calculate the average subvolume and volume weighted temperatures and vapor pressures are as follows: 3 = I(al RTD's -in j$ subvolume) T Number of RTD's in jth subvolume E(all dewcell in Jt_h_ subvolume D.P.J = Number of dewcells in J Q subvolume Pv,J = see vapor pressure table and convert D.P.J (CF) to Pv,J (PSI) where TJ = average temperature of the jg subvolume D.P.J = average dewpoint of the J Q subvolume Pv,j = average vapor pressure of the jg subvolumc 28 l u

p. ,4 / ,, i M* A 7 T= E (VFj) (Tave.J) J=1 where VFJ = the volume weighting factors Tave,j = the average absolute temperature'in the j e subvolume "3 Tl'l Tave,j = i=1 NJ I where TI,j = the absolute temperature of the i g RTD in the jth subvolume NJ = number of RTD's in the jtj), subvolume PT = Absolute primary containment pressure NVOL Pv = E (VFj) (Pv,j) J-1 P=PT - Py ~"

primary containment dry air pressurc NVOL T

E (VFj)(Tj) j=1 where NVOL = number of primary containment subvolumes VFj = volume weighting f actor of the jg subvolume T = volume weighted average primary containment temperature l Heasured Contal_ned Dry Air Mass (Ibs) l (28.97) (144) (P) (TOTVOL) g, 71545.33)(T+459.69) l = 2.6995 ((P)(TOTVOL) 1 T+459 69). where P = primary containment dry air pressure j i TOTVOL = total primary containment free air volume = 276,402 ft3 ( T = average primary containment volume weighted temperature j Measured Leak Rate (%/ day) Lm = (W ASE - VI)(W2400 ) B tl BASE = 2400 (1 y; } ti WBASE 29 t .___._m

SECTION F - TYPE A TEST RESULTS AND INTERPRETATION F.1 Saturated vs. Unsaturated Environment i Based upon data obtained during the 48 psig 24 hour test, the following results were determined: Acceptance Case 1(a,b) Case 1(a,b) SAT CI terion l i Statistically Averaged Leak (wt%/ day) 0.495 1 0.061 0.645 1 0.064 $[0.750 Measured Leak Rate (wt%/ day) 0.475 0.627 $50.750 Statistically Averaged Leak Rate during final six test hours based on reference time zero (wtt/ day) 0.415 + 0.102 0.563 1.0.120 550.750 j By assuming complete saturation in the primary containment', the leek rate in all cases was found to be approximately 0.150 wt%/ day higher than in case 1(a,b). However, even the 95% upper confidence limits were found to lie wall within the 0.750 %/ day operational acceptance criterion in all cases. Figures Five through Thirteen are included to graphically illustrate the various leak rates, temperatures and pressures monitored during the test. leak of 6.0 scfm (0.713 wt%/ day) was imposed on the primary containment for the induced leak rate portion of the ILRT. The calculated leak rates during this portion of the test were as follows: Acceptance Case 1(a,b) Case 1(a,b) RAT Criterion Statistically Averaged 0.958 s Ls $ 1.458unsat 1.108 ; Ls $; l.608 sat Leak Rate (wt%/ day) 1.073 1 0.104 1.369 + 0.089 5 Measured Leak Rate 0 938 ;Lm 25 I'033 3 unsct (wtt/ day) 1.055 1.367 1.090 3; Lm5 1.590 sat Figures Five and Six illustrate that both the upper and lower 95% confidence limits fall within the 10.250 wt%/ day acceptance criterion boundaries for the 4 induced test phase. From Appendix B, it is seen that the total instrument uncertainty is found to be eq"el to 0.133 wt%/ day (2(7]). For each case involving the final six hours of the 48 psig test from reference time zero, this uncertainty added to the 48 psig - test statistical leak rate is again demonstrated to satisfy the operational acceptance leak rate criterion. ~ 30 y w --riw~ v v--9-- -r-- iy .-t- .,,w- --w--.-- -e-w-

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F.2 Addition of Su'ovolumes 2A and 28 investigation of the originally calculated data was found to dcrconstrate a direct cycling relationship with operation of the. shutdown cooling system. Unmonitored temperature Increases in the immediate vicinity of the reactor vessel resulting from reactor core decay heat 3roduction gave evidence of an inleakage phenomenon as Ind!cated by the pressure sentors. After identirication of the cause of this situation, it became necassary to develop a mathematical model to cccount for this unmonitored leakage. F.2.a Subvolume 2A This subvolume was defined to be the volume of the airspace within the reactor vessel minus the volumes occupied by the moisture separator and dryer. This subvolume was continuously exposed to the drywell environment during the iLRT by having two manual valves to the drywell equipment drain sump opened throughout the test. The average tenperature of this subvolume was considered to follow the vessel shell temperature (T21)- F.2.b Subvolume 2B This subvolume was defined to be the airspace between the reactor vessel and the biological shield. In order to determine the heat transfer coefficient across subvolume 2B and the biological shield, heat transfer coefficients of the materials were applied to the respective material thicknesses. The following equation was derived using heat transfer thecry to obtain the average temperature for this subvolume: 21-I )

  • T T2b = 0.394(T 2

2 where T21 = vessel shell temperature as trend monitored by the thermocouple listed in Table One T2 = subvolume 2 average temperature Prior to the addition of these subvolumes, the free air volumes of the ar.nular airspace between the vessel and the biological shield and the airspace present in the reactor vessel had been accounted for, but only with respect to the total drywall free air volume. Therefore, these volumes nad been taken to follow the average temperature and pressure of the entire primary containment withcut affecting the containment leak rate. Although these two subvolumes occupy only 4.4% of the entire primary containment free air volume, significant temperature variations experienced during each phase of the ILRT were found to have a pro-found affect upon the measured leak rates. The affect which led to this discovery is Illustrated on Figure Eleven. Definite peaks and valleys are noticed in the continuously increasing curve of Subvolume 2. As was noted on Figure One, Subvolume 2 is defined to be the free air volume external to the biological shield at an elevation consistent with that of the reactor core. Although subvolume 2 is separated from the vessel by the vessel insulation, an air space, and the biological shleid, thermal gradients are still apparent. 40

Because the reactor vessel shell temperature had been computer trended during both phases of the ILRT, it was possible to develop Figure Fourteen. The resul-tant calculated values of T2b are then seen to satisfy the expected relationship between Subvolume 2 and the reactor vessel. The addition of these two subvolume temperatures (T and T2b) thus accounted for the effects of the shutdown cooling 2a system operation during the test. F.3 Arabient Effects on Leak Rate Due to the confined aspects of the drywell within the reactor building and the magnitude of the pressure involved, outside ambient temperature and pressure variations had no noticeable effect on the leak rate. F.4 TIP Leakage Effects A routine inspection for leaks during the 24 hour phase of the ILRT revcaled leakage through the Traversf rig incore Probe (TIP) system at 6:00 PM on March 5, 18 hours into the 24 hour test. This leakage was estimated to ba approximately 1.0 scfm (~0.1 wt%/ day). The effect of the TIP leakage on the ILRT fcr the two cases of saturation are as follows: With TIP leakage Without TIP leakace Case 1(a,b) - wt%/ day 0.495 0.415 Casu 1(a,b) SAT - wt%/ day 0.6h5 0.563 in each case, the leak rate decreases by approximately 0.08 wt%/dey followir.g isoletion of the TIP leakage, in comparison to the 0.1 wt%/ day estimated leakcge above. In spite of this TIP leakage, the indicated leak rate was well below the 0.750 wt%/ day acceptance criterion. Because the ball valves in the TIP system have shown a tendency to stick open during power operation, a modification had been initiated to include inste11ation of a manual isolation valve upstream of the ball valve to provide isolation per-mitting maintenance of the ball valve during operation. However, since the valves had not arrived in time for installation, the TIP tubes had been altered to provide a space for the manual valve. Temporary tubing connected by suage lock fittings had been Installed to complete the path untti replaced by the new manual valve. The TIP leakage occurred at the swage lock fittings because the fittings had not been sufficiently tightened. F.5 Pre-Operational Results vs. Test Results t An investigation was conducted to determine why the Icak rates calculated during this test were different than the pre-operational test results. Tha variation betweer. the pre-operational and current ILR7 measured leak rates is approximately 0.3J wt%/ day (~ 2.5 scfm). Basically, the nuestion reduces to which of the tollowing items is responsible for this variation: a. Structural deterioration of the primary containment isolation barriers since the pre-operational ILRT, or b. Testing inadequacies 41

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~ i-A review of the pre-operational local leak rate test results for isolation valves and testable penetrations indicated that the current AS LEFT leak rate prior to this ILRT was approximately 1.35 scfm (0.16 wt%/ day) higher than for the pre-operational test accounting.for approximately 50% of the leakage variation. Normal component and seal wear of a relatively small quantity could readily account for this leakage. Wear of this nature is to be expected to some c..ter.t and does not, in most cases, affect the isolation ~ function. However, periodic repairs are made of these valves in an attempt to maintain their isolation integrity. The successful pre-operational ILRT, performed April 20 to April 21, 1971, demonstrated an average measured leak rate of 0.111 wt%/ day. Although the Instrument uncertainty for the pre-operational ILRT was calculated to be 0.096 wt%/ day, a nuv.ber of assumptions concerning accuracies and repeatabilities using present methods yields a revised uncertainty of 0.314 wt%/ day. When this value is applied to the measured leak rate for the pre-opcrationci ILRT, the result is found to Sc very close to the current test result. Therefore, although the pre-operational ILRT uncertainty as calculated by present analysis was larger than previously reported, the pre-operational result is still well within acceptable limits, and in addition helps explain the leak rate variation from the present test. Thus, it is felt that both items identified contributed to the variatien between the pre-operational ILRT results and the results of this inserv*ce leak test. F.6 Future Test Procedural improvements in order to prevent repetition of difficulties experienced during this ILRT, plans are being made to incorporate the following items into succeeding ILRT procedures: a. Reactor shutdown cooling system operation will be initiated prior to the start of future ILRT's, and operated throughout the test to main-tain a nearly constant reactor vessel water temperature. This should eliminate the gross leak rate variations experienced as a result of internittent shutdown cooling system operation. b. During future ILRT's, better administrative controls will be used to provide for a more organized data reduction and analysis system. The result of these objectives will be to provide future ILRT's with greater accuracy and improved organization based on experience gained from this test. 44 e--,.%a+e.m--

APPENDIX A TYPE S AND TYPE C TESTS Presented herein are the results of local leak rate tests conducted on all testable penetrations, gasketed seals, doors and isolation valves since immediately preceding the pre-operational ILRT in 1971. All isolation valves with leakage in excess of the individual valve leakage limit were restored to an acceptable leak tightness prior to the resumption of pcuer operation. Total leakage for double-gasketed seals and total leakage for all other pene-trations and isolation valves following repairs satisfied the Technical Specification limits. These results are listed in Table A-1. 45

U-TABLE A-1 TYPE B AND TYPE C TEST RESULTS VALVE (S) OR TEST . V.EASURED LEAP BATE (SfFHj_ p PENETRATION VOLUME l AS FOUND - DATE AS LEFT - DATE A0 203-1A Main Steam Line 8.3 12/31/70 8.3 12/31/70 2.75 4/1/74 2.75 4/1/74 isolation 0.283 1/3/76 0.283 1/3/76 i A0 203-2A Valves 0.0 12/31/70 0.0 12/31/70l 2.75 4/1/74 2.75 4/1/74 0.288 1/3/76 0.288 1/3/76 A0 203-!B 3.74 12/31/70 3.74 12/3!/70, 52.4 4/27/73 3.25 5/1/73 5.15 5/13/74 5.15 5/13/74 21.0 1/3/76 6.f! I/17/16 A0 203-2B 1.0 12/31/70 1.0 12/31/70 10 95 5/13/74 10.95 5/13/74 10.10 1/3/76 3.86 1/3/76 l A0 203-IC 1.94 12/31/70 1.94 12/31/70 0.0 5/13/74 0.0 5/13/74 70.88 1/3/76 1.74 1/3/76 v A0 203-2C 0.468 12/31/70 0.468 12/31/70 l 216 5/13/74 8.64 7/14/74 1.72 1/3/76 1 72 1/3/76 i i A0 203-ID 1.92 12/31/70 1.92 12/31/70l l 17 35 6/3/74 5.76 6/3/74 1.94 1/3/76 1 94 1/3/76 A0 203-2D 0.0 12/31/70 0.0 12/31/70 17.35 6/3/74 0.0 7/8/74 9 59 1/3/76 9 59 1/3/76 l l { 46 .m. e

TABLE A-1 (CONT) VALVE (S) OR TEST MEASURED LEAK RATE (SCFH l PENETRATIOrl VOLUME AS FOU:'D - DATE AS LEFT - DATE j MO 220-1 Main Steam Linc 0.24 12/31/70 0.24 12/31/70l Mc 220-2 Drains 4.02 5/28/74 4.02 5/28/74 4.28 2/10/75 4.28 2/10/75 47.70 1/3/76 5.75 3/3/76 A0 220-44 Primary Sample 0.0 12/3!/70 0.0 12/31/70 A0 220-45 0.70 6/6/74 0.70 6/6/74 0.0 1/26/76 0.0 1/26/76 I I i CV 220-58A Feeducter Ir.let 6.14 12/31/70 4.14 12/31/70 l Loop "A" Inboard 646.5 4/25/74 1.49 7/13/74 i 0.896 1/17/76 0.896 1/17/76 CV 220-62A Feedwater inlet 1.48 12/31/70 1.48 12/31/70, Loop "A" Outboard 0.0 7/14/74 0.0 7/14/74 j 378.0 1/17/76 0.834 2/6/76 CV 220-583 Feedwater Inlet 2.49 12/31/7C 2.49 12/31/76 Loop "B" Inboard 888.2 4/25/74 2.99 6/25/74 3026.0 1/8/76 5.38 1/12/76 i 13.44 3/,8/76 13.44 '/8/76 j CV 220-62B reedneter inlet 5.63 12/31/70 5.63 12/31/70 i Loop "8" outboard 1332.0 4/25/74 11.10 6/25/74 ! 3040.0 1/10/76 14.46 2/4/16 is MO 1001-20 RHRS to Radwaste 0.0 6/1/74 0.0 6/1/74 M0 1001-21 0.0 1/30/76 0.0 1/30/76 MO 1001-23A RHRS Containment 0.079 12/31/70 0.079 12/31/70

  • l MO 1001-26A Spray - Loop "A" 2.50 4/9/74 2.50 4/9/74 l

l.12 1/14/76 1.12 1/I4/76 MO 1001-23B RHRS Containment 0.0 12/31/70 0.0 12/31/70! HD 1001-26B Spray - Loop "B" 0.0 4/22/74 0.0 4/22/74 l 1.55 1/13/76 1.55 1/13/76 M0 1001-29A RHRS Return - Loop 0.0 4/11/74 0.0 4/11/74 l "A" 23 1/14/76 2.3 1/14/76 MO 1001-29B RHRS Return - Loop 1.54 4/25/74 1.54 4/25/74 l "B" c.0 1/14/76 0.0 1/14/76 l t 47 L

6 TABLE A-1 (CONT) VALVE (S) 0R TEST MEASURED LEAK RATE (SCFH) PENETRATION VOLUME AS FOUND '0 ATE l AS LEFT - DAlt MO 1001-34A RHRS Suppression 0.824 12/31/70 0.824 12/31/70 MO 1001-36A Chamber Spray - 11.34 4/9/74 11.34 4/9/74 MO 1001-37A Loop "A" 249 0 1/14/74 6.05 1/27/74 MO 1001-34B RilR Suppression 0 935 12/31/70 0.935 12/31/70 MO 1001-36B Chamber Spray - 3 51 4/22/74 3.51 4/22/74 MO 1001-37B Loop "B" 3 34 1/14/76 3 34 1/14/76 MO 1001-47 RHRS Shutdown 7.80 7/11/74 7.80 7/11/74 MO 1001-50 Cooling Suction 4.68 1/14/76 4.68 1/14/76 MO 1001-60 RHRS Head Spray 0.0 7/11/74 0.0 7/11/74 MO 1001-63 0.0 1/13/76 0.0 1/13/76 _i MO 1201-2 Clean-up System 0.033 12/31/70 0.033 12/31/70 MO 1201-5 Suction 9.10 7/14/74 9.10 7/14/74 2.48 1/26/76 2.48 1/26/76 MO 1201-80 Clean-up System 0.0 7/16/74 0.0 7/16/74 Return 0.0 1/26/76 0.0 1/26/76 l MG 1301-16 RCIC Steam Supply 0.0 12/31/70 0.0 12/31/70 NO 1301-17 0.0 5/22/74 0.0 5/22/74 0.0 1/16/76 0.0 i/16/76 CY 1301-41 RCIC Turbine 6.4 5/9/74 6.4 5/9/74 Exhaust 0.0 1/4/76 0.0 1/4/76 CV 1301-40 RCIC Condensate 1.55 12/31/70 1 55 12/31/70 Drain 2.45 4/15/74 2.45 4/15/74 1.25 1/4/76 1.25 1/4/76 i l A0 1601-21 Drywell and 0.069 12/31/70 0.069 12/31/70 A0 1601-22 Suppression 99.0 4/16/73 6.5 4/16/73 A0 1601-55 Chamber Purge 15.0 5/5/73 15.0 5/5/73 A0 1601-56 12.86 6/26/74 12.86 6/26/74 197.1 1/4/76 10.32 1/9/76 A0 1601-20A Suppression Chamber 1.08 12/31/70 1.08 12/31/70 CV 1601-31A Vent Lines #1 0.00 4/30/73 0.00 4/30/73 3.10 5/20/74 3 10 5/20/74 0.00 1/5/76 0.00 1/5/76 A0 1601-208 Suppression Chamber 0.035 12/31/70-0.035 12/31/70 ; CY 1601-318 Vent Lines #2 0.00 4/30/73 0.00 4/30/73 ; 3.34 5/21/74 3.34 5/21/74 l 1.33 1/5/76 1.33 1/5/76 48

TABLE A-l (CONT) VALVE (S) OR TEST MEASURED LEAK RATE (SCFH) PENETRATION VOLUME AS FOUND - DATE i AS LEFT - DATE A0 1601-57 Drywell and 0.38 12/31/70 0.38 12/31/70 A0 1601-58 Suppression Chamber 0.90 5/4/73 0.90 5/4/73 A0 1601-59 Supply Air Purge 0.37 1/4/76 0 37 1/4/76 A0 1601-23 Drywell and 0.38 12/31/70 0.38 12/31/70 A0 1601-24 Suppression Chamber 5.50 4/20/73 5.50 4/20/73 A0 1601-60 Exhaust 5.50 4/22/74 5.50 4/22/74 A0 1601-61 5.40 1/5/76 5.40 1/5/76 A0 1601-62 A0 1601-63 A0 2001-3 Drywell Floor 0.497 12/31/70 0.497 12/31/70 A0 2001-4 Drain Sump 4.00 4/12/74 4.00 4/12/74 Discharge 8.85 1/5/76 8.85 1/5/76 A0 2001-15 Drywell Equipment 0.522/0.572 12/31/70 3.522/0.572 12/31/70 A0 2001-16 Drain Sump 1.34 5/3/74 1.34 5/3/74 Discharge 10.37 1/5/76 10.37 1/5/76 no 2301-4 HPCl Steam Supply 0.15 12/31/79 0.15 12/31/70 no 2301-5 1.43 5/24/74 1.43 5/24/74 4.03 1/15/76 4.03 1/15/76 CV 2301-45 HPCI Steam Exhaust 0.83 12/31/70 0.63 12/31/70 A03 4/16/74 4.03 4/16/74 ({4.47 1/4/76 12.86 1/4/76 ~ CY 2301-34 HPCI Condensate 0.191 12/31/70 0.191 12/31/70 Drain 0.41 4/15/74 0.41 4/15/74 0.26 1/4/76 0.26 1/4/76 l A0 4720 Drywell Pneumatic 0.40 1/10/76 0.40 1/10/76 A0 4721 0 90 1/10/76 c.90 1/10/76 A0 8801A 02 0.28 5/25/74 0.28 5/25/74 0.18 1/4/76 0.18 1/4/76 Analyzer A0 8802A 2.05 5/25/74 2.05 5/25/74 Suction 1.99 1/4/76 1.99 1/4/76 A0 8801B 0.09 5/z5/74 0.09 5/25/74 j 0.17 1/4/76 0.17 1/4/76 A0 88028 6.58 4/16/74 6.58 4/16/74 25.92 1/4/76 0.02 2/20/76 A0 8801C 0.38 5/25/74 0.38 5/25/74 0.47 1/4/76 0.47 1/4/76 l 6 49 L

TABLE A-1 (CONT) VALVE (S) OR TEST HEASURED LEAK RATE _(SCFH) PEHETRATION VOLUME AS FOUND - DATE l AS LEri - DALE A0 8802C 02 Analyzer 0.40 5/25/74 0.40 5/25/74 Suction (cont'd) 1.92 1/4/76 1 92 1/4/76 A0 880l? 0.095 6/27/74 0.095 6/27/74 1.77 1/4/76 1.77 1/4/76 A0 8802D 0.662 6/27/74 0.662 6/27/74 2.06 1/4/76 2.06 1/4/76 A0 8803 02 1.175 6/28/74 1.175 6/28/74 0.65 1/5/76 0.65 1/5/76 Analyzer A0 8804 0.98 6/28/74 0 98 6/2S/74 Return 1.50 1/5/76 1.50 1/5/76 X-1 Equipment Hatch 0.183 7/8/70 0.183 7/8/70 600' 1800 0.150 5/5/73 0.03 5/7/73 1.20 6/15/73 1.20 6/18/73 1 0.00 9/28/73 0.00 9/28/73 0.70 7/17/74 0.70 7/17/74 0.00 10/6/74 0.00 10/6/74 i 1.40 10/17/74 1.48 10/17/74 0.85 4/2/75 0.85 4/2/75 0.45 4/23/75 0.45 4/23/75 0.93 1/3/76 0.93 1/3/76 l X-2 Drywell Personnel 0.0703 12/2/70 0.0703 12/2/70 Airlock 0.00 5/18/74 0.00 5/18/74 0.00 1/9/76 0.00 1/9/76 X-4 Drywell llcad 1.0 5/4/74 1.0 5/4/74 Access Hatch 0.0 1/25/75 0.0 1/25/75 39.2 2/2/76 17.66 2/5/76 X-6 CRD Removal Hatch 0.021 7/8/70 0.021 7/8/70 591' 196 0.00 4/30/74 0.00 4/30/74 0.15 10/6/74 0.15 10/6/74 0.00 10/17/74 0.00 10/17/74 0.05 4/21/75 0.05 4/21/75 0.00 1/3/76 0.00 1/3/76 50

TABLE A-1 (CONT) VALVE (S) OR TEST ttEASURED LEAK RATE (SCFH) ~ l PENETRATION VOLUME AS FOUND - DATE j AS LEFT - DATE X-35A TIP 0.0 4/20/74 0.0 4/20/74 0.0 1/7/76 0.0 1/7/76 FLUX X-358 0.0 .4/20/74 0.0 4/20/74 NON. 0.0 1/7/76 0.0 1/7/76 X-35c FLANGE 0.0 4/20/74 0.0 4/20/74 0.0 1/7/76 0.0 1/7/76 592' 25-45 X-35D 0.6 4/20/74 0.6 4/20/74 0.0 1/7/76 0.0 1/7/76 X-35E 0.0 4/20/74 0.0 4/20/74 0.0 1/7/76 0.0 1/7/76 X-35F 0.0 4/20/74 0.0 4/20/74 0.0 1/7/76 0.0 1/7/76 X-35G 0.0 4/20/74 0.0 4/20/74 0.0 1/7/76 0.0 1/7/76 X-200A Torus Access Hatch 0.026 11/16/70 0.026 11/16/70 582' 1200 (!!crth) 0.008 9/28/72 0.008 9/28/72 0.00 12/30/72 0.00 12/30/72 0.00 5/5/73 0.00 5/5/73 0.00 5/7/73 0.00 5/7/73 0.85 9/30/73 0.05 9/30/73 0.00 7/18/74 0.00 7/18/74 0.00 4/1/75 0.00 4/1/75 0.00 ' 1/3/76 0.00 1/3/76 X-2008 Torus Access Hatch 0.00398 11/30/70 0.00338 11/30/70 582' 240o (south) 0.00 9/28/72 0.00 9/28/72 0.00 12/30/72 0.00 12/30/72 l 0.00 12/31/72 0.00 12/31/72 l 0.00 2/9/73 0.00 2/9/73 0.00 5/5/73 0.00 5/5/73 0.00 8/5/73 0.00 8/5/73 0.00 9/30/73 0.00 9/30/73 0.00 7/18/74 0.00 7/16/74 0.23 4/1/75 0.23 4/1/75 0.57 4/24/75 0.57 4/24/75 0.80 4/29/75 0.80 4/29/75 0.00 1/3/76 0.00 1/3/76 Drywell Drywell Head 0.0 12/31/70 0.00 12/31/70 Head Flange 4.73 7/15/74 4.73 7/15/74 0.00 4/18/75 0.00 4/18/75 0.00 1/3/76 0.00 1/3/76 51

TABLE A-1 (CONT) VALVE (S) OR TEST MEASURED LEAK RATE (SCnt) PENETRATION VOLUME AS FOUMn - DATE T AS LEFT - DATE SL-1 Shear Lug 0.0 10/22/70 0.0 10/22/70 0.0 5/21/74 0.0 5/21/74 Inspection 0.0 1/20/76 0.0 1/20/76 SL-2 Hatches 0.0 10/22/70 0.0 10/22/70 0.0 5/21/74 0.0 5/21/74 0.0 1/20/76 0.0 1/20/76 SL-3 0.0 10/22/70 0.0 10/22/70 0.0 5/21/74 0.0 5/21/74 0.0 1/20/76 0.0 1/20/76 SL-4 0.0 10/22/70 0.0 10/22/70 0.0 5/21/74 0.0 5/21/74 0.0 1/20/76 0.0 1/20/76 SL-5 0.0 10/23/70 0.0 10/23/70 0.0 5/21/74 0.0 5/21/74 0.0 1/20/76 0.0 1/20/76 SL-6 0.0 10/23/70 0.0 10/23/70, 0.0 5/21/74 0.0 $/21/74 i 0.0 1/20/76 0.0 1/20/76 SL-7 0.0 10/22/70 0.0 10/22/70 O.0 5/21/74 0.0 5/21/74 0.0 1/20/76 0.0 1/20/76-SL-8 0.0 10/23/70 0.0 10/23/70 0.0 5/21/74 0.0 5/21/74 0.0 1/20/76 0.0 1/20/76 X-7A Primary Steart. 0.1 5/2/73 0.1 5/2/73 595' 60 0.0 1/4/76 0.0 1/4/76 X-7B Primary Steam 0.15 5/2/73 0.15 5/2/73 595' 15 0.00 1/4/76 0.00 1/4/76 X-7C Primary Steam 0.0 5/1/73 0.0 5/1/73 595' 345 0.0 1/3/76 0.0 1/3/76 X-7D Primary Steam 0.0 5/1/73 0.0 5/1/73 595' 3550 0.0 1/3/76 0.0 1/3/76 X-8 Primary Steam Drain 0.0 5/1/73 0.0 5/1/73 Line 592' 00 0.0 1/3/76 0.0 1/3/76 52

TABLE A-1 (CONT) VALVE (S) OR 'IEST MEASUREO LEAK RATE (SCFil) PENETRATION VOLUME AS FOU;iD - DATE AS LETT - DATE X-SA Reactor Feedwater 0.0 5/2/73 0.0 5/2/73 598' 90 0.0 1/4/76 0.0 1/4/76 x-9B Reactor Feedwater 0.0 5/1/73 0.0 5/1/73 598' 3500 0.0 1/3/76 0.0 1/3/76 x-10 Steam to Rcic 0.0 5/2/73 0.0 5/2/73 605' 60 0.0 1/4/76 0.0 1/4/76 x-11 IIPCI Stc&m Supply 0.1 5/2/73 0.1 5/2/73 0.0 1/4/76 0.0 1/4/76 x-12 RHRS Supply 0.0 5/1/73 0.0 5/1/73 605' 343 0.0 1/3/76 0.0 1/3/76 X-13A RHRS Return 0.2 5/2/73 0.2 5/2/73 i 591' 85 0.0 1/4/76 0.0 1/4/76 l x-138 RHRS Return 0.4 5/4/73 0.4 5/4/73 591' 265 0.0 1/3/76 0.0 1/3/76 x-14 clean-up Supply 0.0 6/1/73 0.0 6/1/73 625' 270 0.0 1/3/76 0.0 1/3/76 X-23 cooling water Supply 0.1 5/2/73 0.1 5/2/73 591' Soo 0.0 1/4/76 0.0 1/4/76 X-24 cooling water acturrt 0.1 5/2/73 0.1 5/2/73 588' 50 0.0 1/4/76 0.0 1/4/76 } x-25 Vent From Drywell 0 30 5/2/73 0.30 5/2/73 649' 213 0.00 1/3/76 0.00 1/3/76 X-26 Vent to Drywell 0.45 5/4/73 0.45 5/4/73 591' 232 0.00 1/3/76 0.00 1/3/76 x-36B CRD Hyd Sys Return 0.0 5/2/73 0.0 5/2/73 618' 1950 0.0 1/3/76 0.0 1/3/76 X-47 Standby Liquid Con-1.6 5/1/73 1.6 5/1/73 l trol 641' 298o 0.0 1/3/76 0.0 1/3/76 i 53 l

TABLE A-1 (CONT) VALVE (S) Oh TEST tIEASURED LEAK RATE (SCFH) - l PENETRATION VOLUME AS FOUND - DATE AS LEFT - DATE X-17 Reactor '!essel Head 0.05 5/2/73 0.05 5/2/73 Spray 605'0" 0.00 1/7/76 0.00 1/7/76 X-16A Core Spray inlet 0.0 5/2/73 0.0 5/2/73 642' 200 0.0 1/4/76 0.0 1/4/76 X-16B Core Spray inlet 0.3 9/30/70 0.0 9/30/70 642' 155 0.2 5/2/73 0.2 5/2/73 0.0 1/4/76 0.0 1/4/76 i X-100A CRD Position in-0.0 10/15/70 0.0 10/15/70 dication 611' 400 0.0 4/20/74 0.0 4/20/74 0.0 1/7/76 0.0 1/7/76 i X-1008 Power 0.0 10/15/70 0.0 10/15/70 611' 45 0.0 4/20/74 0.0 4/20/74 0.0 1/7/76 0.0 1/7/76 i X-1000 Neutron t;onitor 0.0 10/13/70 0.0 10/13/70 609' 1600 0.0 5/2/73 0.0 5/2/73 0.0 1/6/76 0.0 1/6/76 l 'X-100D Neutron Monitor 0.0 10/16/70 0.0 10/16/70 611' 1700 0.0 5/2/73 0.0 5/2/73 0.0 1/6/76 0.0 1/6/76 X-100E Neutron Monitor 0.0 10/16/70 0.0 10/16/70 611' 2200 0.0 5/2/73 0.0 5/2/13 0.0 1/6/76 0.0 1/6/76 X-100F CRD Position in-0.0 10/13/70 0.0 10/13/70 dication 610' 3220 0.0 5/2/73 0.0 5/2/73 0.0 1/4/76 0.0 1/4/76 X-100G Power 0.0 10/13/70 0.0 10/13/79 610' 33o 0.0 5/2/73 0.0 5/2/73 0.0. 1/4/76 0.0 1/4/76 X-101A CRD Position in-0.0 10/16/70 0.0 1/16/70 dication 609' 142o 0.0 5/4/73 0.0 5/4/73 0.0 1/7/76 0.0 1/7/76 54 ~

TABLE A-1 (CONT) VALVE (S) OR TEST HEASURED LEAK RATE (SCFH) PENETRATION VOLUME AS FOUND - DATE AS.LEFT - DATE X-1018 CRD Position in-0.0 10/14/70 0.0 10/14/70 dication 609' 1470 0.0 5/2/73 0.0 5/2/73 0.0 1/7/76 0.0 1/7/76 X-101D Recirc Pump Power 0.0 10/13/70 0.0 10/13/70 609' 1270 0.0 5/2/73 0.0 5/2/73 0.0 1/6/76 0.0 1/6/76 X-102A Recirc Pump Power 0.0 11/6/70 0.0 11/6/70-609' 1270 0.0 5/4/73 0.0 5/4/73 0.0 1/7/76 0.0 1/7/76 X-103 lhermocouple 0.0 10/19/70 0.0 10/19/70 609' 130o 0.0 5/4/73 0.0 5/4/73 0.0 1/7/76 0.0 1/7/76 X-1043 CRD Position in-0.0 10/15/70 0.0 10/15/70 dication 6118 300 0.0 4/20/74 0.0 4/20/74 0.0 1/6/76 0.0 1/6/76 X-104C Recirc Pemp Power 0.0 10/13/70 0.0 10/13/70 609' 1250 0.0 5/4/73 0.0 5/4/73 f 0.0 1/7/76 0.0 1/7/76 X-104F Power 0.0 10/13/70 0.0 10/13/70 610' 337 0.0 5/2/73 0.0 5/2/73 0.0 1/4/76 0.0 1/4/76 i X-105A Power 0.0 10/15/70 0.0 10/15/70 611' 52 0.0 1/7/76 0.0 1/7/76 0 X-1058 Power Drive Modules 0.0 10/16/70 0.0 10/16/70 611' 20o 0.0 5/2/73 0.0 5/2/73 0.0 4/20/74 0.0 4/20/74 0.0 1/6/76 0.0 1/6/76 X-105C CRD Pec! icn !n-0.0 10/16/70 0.0 10/16/70 l dication 611' 205 0.0 5/2/73 0.0 5/2/73 l 0.0 1/6/76 0.0 1/6/76 I i 55 ( l l

TABLE A-1 (C0flT) l 11EASURED LEAK RATE (SCFH) TEST VALVE (S) OR AS FOUND - DATE f AS LEFT - DATE VOLUME PEr1ETRATION l 0.0 10/13/70 0.0 10/13/70 Recirc Pump Power 0.0 5/2/73 0.0 5/2/73 X-105D 611' 3000 1/6/76 0.0 1/6/76 0.0 0.0 10/16/70 0.0 10/16/70 X-107A 0.0 5/2/73 0.0 5/2/73 Neutron tionitor 611' 215 1/6/76 0.0 1/6/76 0.0 - _.) e 6 56 ^

APPENDIX B AS FOUND LEhK RATES The AS FOUND leakage for primary containment Isclation valves, excluding the Main Steam Isolation Valves, was 3388.85 scfh, wl:Ich is in excess of the allowable Technical Specification limit of 110.18 scfh. Tlie leakages prior to and after the outage are summarized as follows: AS FOUND AS LEFT TECHNICAL SPECIFICATION LEAKAGE LEAKAGE LIMIT ITEM (SCFH) (SCFH) (SCFH) Isolation Valves (except MSIV's) 3388.85 59 27 and Total 110.13 Testable Penetrations 0.00 0.00 Double-Gasketed Seals 40.13 17.66 36.72 Main Steam isolation Valves (tested at 25 psig) A0 203-1A 0.283 0.288 11.5 A0 203-2A 0.288 0.288 11.5 A0 203-1B 21.00 6.51 11.5 A0 203-20 10.10 3.86 11.5 A0 203-1C 70.88 1,74 11.5 A0 203-2C 1.72 1.72 11.5 A0 203-ID 1.94 1 94 11.5 Ad 203-2D 9.59 9.59 11.5 Total 115.81 ' 25.94 Complete details of these local leak rate test failures are contained in Reportable Occurrence 50-254/76-7. a 57

APPENDIX C TYPE A TEST INSTRUMENTATION ERP.OR ANALYSIS The analysis contained herein is based on the Instrun.entation used in the test in order to show the acceptability of this instrumentation with respect to the leak rate in question. In accordance with ANSI N45.4-1972, the computation of the primary containment leak rate is given by the equation: L(%) = (b)(100)(

2), 2400(g,

TIP9 T P)) H WI H 2 where L = primary containment leak rate (%/ day) H = time interval between data sets #1 & #2 (hours) W1 = weight of the contained dry air mass at test data set #1 (Ibs) W2 = weight of the contained dry air mass at test data set #2 (Ibs) T1 = volume weighted primary containment temperature at test data set #1 (O ) R T2 = volume weighted primary containment temperature at test data set #2 (O ) R Pg = dry air absolute pressure at test data set #1 (PSIA) P2 = dry air absolute pressure at test data set.f2 (PSIA) The standard variation on L due to the uncertainties in the measured variables is given by: $(L) = [(, 8(Pj)) +( 3(P )) +( $(T)) +(T 5(T )) 2 I 2 substituting H = 24 hours 3P). L _P.2. ~1 3' T2 PP ~~ Py 3L T 1 i ~5 "" T P1 ~ SP2 2 3L P9 1 'dT) "" T2 Py * % 3L Tj Pp

  • 1

" T ' P; G 3T2 2 1 x P m F and T1sT2=T assuming P 2 where P = average absolute dry air pressure (PSIA) T = average volume weighted primary containment absolute temperature (OR) Therefore, $(L)=100(2(6(P)2)+2([y-}}I (T)2 y 58

APPENDIX <* (CONT'D) The instrument specifications are as follows: RTD PPG Dewcell Flowmeter Thermocouple 0 Range 32-250 F 0-100 PSIA 0-10 SCFM 0-g00F Accuracy +0.150F +0.015 PSI +1.00F +0.1 SCFM +2 F kepeatability 70.05 F 70.001 PSI 70 5 F 70.02 SCFM 70.25 F instrument Error Analysis Calculationof6(Y) a. 7 T= E (VFj)(Tave, j) j=1 where VFJ = the volume weighting factors Tave.J = the average absolute temperature in the M subvolume N TI,1 Tave.j = !=1 N,J where TI,j = the absolute temperature of the le RTD ir. the j e subvolwce NJ = number of RTD's in the jg subvolums Now, 6(i) is calc ' lated from 7 6(T) = I 6(Tave.j) j.) BTave.J 0 where = VFJ Blaverj ~: 6(Tave.j) = N There fo re. 7 6(5) = E (VFj)(RTD accuracy) J-j (NJ)i b. Calculation of 6(P) 6(P) = [6(P )2 + 6(Py)2j{ T where PT = total absolute primary containment pressure Py = partial pressure of water vapor in the primary con-ta ir. ment 59

1 APPENDIX c (CONT'D) substituting 6(P ) "

  • h T

7 6(Py) = E (VFj)(dewcell accuracy) J-] (NJ)i where PPG = precision pressure gauge NJ = number of dewcells in the j g subvolume Therefore, 7 6(P) = [(PPG accuracy)2 +(E (VFj)(deweell accuracy))2}i (t of PPG's)2 j=1 (Nj)* Following are the designated volume fractions and sensor allocations: Subvolume Volume Fraction No. of RTD's No. of Dewcells 1 0.03045 1 0 2 0.07887 2 1 2a 0.02965 1 0 2b 0.01467 1 0 3 0.09142 3 0 4 0.12162 3 1 5 0.10410 3 1 6 0.13347 3 1 7 0 39575 5 2 The analyses are performed using the following test values: F = 63.776 PSIA T=92.1840F=Sgl.9R I Dewpoint = 87 56 F With an average dewpoint of 87.560F, an accuracy of + 1.00F corresponds to + 0.020 PSl; a repeatability of + 0.5 F corresponds to + 0.010 PSI. 1. Calculation of 6(L), Accuracy Analysis (T)= (0.03045 X (.15) + (0.07887 x (2)*) + (0.02965 x (1)i) + 0 0.15 2.0 0.15 1)1 0.15 0.15 0.15 2 + (0.012162 X (3)1), (o,jo4jo x (3)*) + (0.13347 X (3)*)+(0.01467 x (.0 ) 1)i + (0 39575 X 0.15) = 0.1671 R (5)i i 1 60

APPENDlX C (cont.) ~ 6(P ) " 0.015 = 0.01061 PSI T

  • U)k 0

6(Py) = (0.15364 X (.020)+(0.21304 X 0.020)+(0.10410 X 0.020) 3)i (1)l (1)i + (0.13347 X 0.020)+(0 39575 x 0.020) (1)i (2)I - 0.01768 PSI NOTE Humidity volume fractions 1,2,2a & 2b and 3 & 4 are combined. Therefore, 6(P) = [(0.01061)2 + (0.01768)2) = 0.02062 PSI The accuracy uncertainty is then found to be c(L) = 100 (2(0.02062)2 + 2(0.1671)"); 63.776 551 3 = 0.06264 t/ day 2. Calculation of 6(L), Repeatability Analysis Using the formulas developed previously, the repeatability error analysis is performed by substituting the instrument repeatability erres for the instrument accuracy errors. 6(T) = (0.03045 X )+(0.07887 X )+(0.02965 x 0 2 )+(0.01467 x -f-) 0 +(0.09142 X 0.05)+(0.12162 X 0.05)+(0.10' 10 X 0.05)+(0.13347 X (3)* (3) l (3)i (3)* l +(0 39575 X 0.05) 0.03725 A = (5)* 6(P ) " 0'001 T (2)t l = 0.000707 PSI i l 61 -r

e. n,. _, _ _ -.

._.,r., +.,,. -_-_7 _._-,.-.,.,.,,,,-r,,--._

APPENDIX C (cont.) 6(Py) = (0.15364 x 0.010)+(0.21304 x 0 030)+(0.10410 x 0. 0l 0). j (1)i (1)i (1)r (0.13347 X 0)+(0.39575 x ) - 0.00384 PSI Therefore 6(P) = ((0.000707)* + (0.00884)2ji = 0.00867 PSI The repeatability uncertainty is then fou.id to be 6(L) = 100 [2(0.00887): + 2(0.03725 )2) 63 7/6 551 9 l = 0.02186 t/ Day 3 Total Instrument uncertainty The total Instrument uncertainty is found from o(L)tntal = [(c(L)eccuracy)8 + (c(L) repeatabili ty) * } = [(0.06264): + (0.02186)2]i i = 0.0663 %/ Day 2c(L) total = 0.133 t/ Day i l 62 ~ -

.e.o s APPENDIX D DEWCELL PROBLEM All dewcells placed in the primary containment were essentially rendered inoperative due to the near-saturation characteristics of the ambient environ-ment. In effect, water condensation within ihe dewcell sample lines resulted in dewpoint temperatures exceeding the ambient dry-bulb' temperatures. According to the dewcell manufacturer, this phenomenon is an Indication of complete saturation of the air by water vapor and the correct dewpoint value is by definition the dry-bulb temperature. Following are excerpts of a letter from the dewcell manufacturer: "The type of sensors used in the VEEKAY hygrometer system are capacitance transducers whose AC impedance is a function of the equilibrium water vapor pressure in their immediate vicinity. The impedance measured is a complex function of resistance and capacitive reactance. In the event that the sensor is exposed to gases whose Relative Humidity is at or near 100%, a film of liquid water will appear across the sensor. This will cause the resistive component of the measured impedance to be much higher than that asscciated with water vapor only. This condition is termed sensor saturation and impedance value.s obtained under this condition are not Indicative of the gaseous water vapor pressure. In as much as this condition indicates the formation of IIquid water, then one knows that the gaseous vacor pressure associated with this system is nothing more than the equilibrium vapor pressure of liquid water at the temperature of the system. This temperature is defined as the dewpoint temperature. Thus, under conditions of saturation, the system dewpoint is equivalent to the system temperature." " Measurements in systems which are known to approach 100% R.H. (such as during this test) are made with the sensor in a heated cell. The function of this device is to insure that the sensor does not come into contact with gas which is near saturation. In these cases, the readout will continue to be the vapor pressure reading, but may still l l give a value greater than the ambient gas temperature. This is caused l by vaporizing droplets of liquid water taken into the heated sample cell l and producing a higher vapor pressure than that associated with the gas l at its ambient temperature saturated. condition. Again, this conditloa Indicates 100t R.H., or by definition a dewpoint equal to the ambient i gas temperature. By applying pressure to a gas which is below saturation, a saturation condition can readily be produced." j i "In summary, I would like to emphasize that in cases of systems which are pressurizing ambient air, it is very likely that water saturation will be achieved. When this occurs, dewpoint measurements are at best difficult and provide little useful information because the dewpoint temperature of a saturated gas is nothing more than its ambient tempera-ture." In addition to this phenomenon, a post-test calibration of the six dewcells l Indicated that the manufacturer's supplied calibration curves for the dewcells t I 63

~ .L-4 *.. ; t

y i

did not correspond to the calibration results, and were in fact quite ir. accurate in the BOOF to 1000F dewpoint range, which was the temperature range experienced during the tect. Consultation with the dewcell manufacturer verified that the erroneously Indicated dewpoints had been caused by improper aging of clu:ninum oxide probes within the dewcells. The manufacturer has stated that this is a one time occurrence upon initial exposure to an environment such as that experi-enced during the test. In spite of this assurance, future pre-test deecell calibrations will still be conducted in order to verify sensor stabilizattor.. g l l 64

!I?' C:mm:nwralth Edistn (('[l ~. O ~ .' ' "'h Quac-Oties Nue: ear Pow:r Station .i

i. Post O!f co Box 216 3/ Cerec sa. I'hne:s 61242

' ', ',./ Te ephone 8*' 309/651-2241 g NJr.-76-216 .une 14, 1976 Benard C. Rusche Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 S;bject: Reactor Containment Building Integrated Leak Rate Test quad-Cities Nuclear Power Station Docket No. 50-254, DPR-29, Unit One Enclosed please find the report " Reactor, Containment Building Integrated Leak Rate Test, Quad-Cities Nuclear Power Sta*. ion, Unit One, March 4-6, 1976" and related appendices descri'ing this Type A test. a The performance of this test was witnee. sed and inspected by a representative of tne NRC's Reglon ii1 0ffice. Questions and comments from his insoectloa report are addressed throtignout the body of this report. This report is submitted to you in accordance with the requirements of 10 CFR 50, Appendix J, Section V.B.I. The *nfr.rmation contained in the Appendices to this report is Intended to comply with t'ie requircrrents of 10 CFR 50, Appendix J, Section V.B.3. According to 10 CFR 50, Appendix J, Section Ill.A.6. the test schedule applicable to the next Ty.e A test is to be reviewed and approved by the Commission. The nec; Type A test for Quad-Cities Unit One is scneduled for March,1979; the Commission's review and approval of this schedule is hereby requested. Very truly yours, COMMONWEALTH E9f SON CCMe'ANY QUAD-CITIES NUC,.EAP P0'iER S,T).Tl0N !,f)fl./ /.- / .y. e$Vh0' /

11. J. Xalivianck!s Station Superinteidant

- NJK/MPF/tav cc: MIPC (2) attn: W. Mcdonald .l. G. Keppler i;. B. Weinstein G. A. Abrell !*. A. Palmer S. B. Stepher.sor.

QT" l 1 ."1 b Rev: *, 3 i Sep*.a %.- 19 7 f. l I P CL T.T S t.:'.? LE E e.'." ~ /J:i'.LY S I 3 Un ce rta i r t" in the I.canurew.r.t of fea t-Qi t it - _Prit.; C..n t a i n r.-- t Lea!: P. - t... /,. ItlsT!<UrciT ACCui:ACY Er,ROR ARA 8.YSiS Por AIsl 1445.4-1972, the cc:^;utation c,i the lesh rate is giv: n by the equaticn: - k'o 2100 TI L(2)e(2h )()05)(U1

  • - )= gj- (1 gP >)

g 7f; l,)- wh:.rc L = pr!r. cry con er i nv.nt leo'; rate (%/ day) I H = t i ne i n te rv a l b e twee n d:: t c !.e t s !!! C f 2 (hou rt.) U) = u.:ight of tim contained drj ai r re.:.cs at tes t Jcta set !) (Ibs) I tf2 = t.*c i r.h t o f the con t a i ned d ry a i r m:s:. at tcst date i.et s'2 (1bs) = ve l e... i:ai g:it:.d pr ir.nry c n ta ' r.:nt ,T ) c temperature at test dela s:t til (OR) T2 = Vul rU3 '..ai ;St d priitary c:e i.ci nm::r.t t tcreareture at test dat; att (2 (OR) l P) = d r y a i r c h c;1 e t <. p re t t, e r. a *. t r.s t dew sct il (PS I /.) P2 = dry c i r c .c h::r n ec c:r ec :t t:st dctc ct 42 (PS : *.) T!r: st:.e.:'crd variatien on L du.: to the enccrtcintier, iri the cowred t l variab!<o is given by: (Bl.-?- 6 (P )) 2 + (Bil-- U (T ) )) ' + (-h.:- 6 ( 6(i.) r. - [($l,-l 5(P ))2 2 2 c: 12 i 4 c substituting H = 24 hours l 3L _l. ..T1 P 7-- ~- BP) T2 P12 Pj 2 _,l_ BL,_ T1 I BP2 T2 P1 Pj B L _. _ P2 ~. _I__ I BT) T2 P1 T2 DL, T1 P2 l_ ~ I BT2 T2 P T2 2 assuming P) =P2 = P and T1 uT2=T where P = average absolute dry air pressure (PSIA) k T = average volume wei lhted prir.iary t containment absolute ternperature (OR) I. 4PPROVED c '- n-~ s -.D > ", w/b. O. C. o, 3, n,

qTf IDI-Tl Rev!: :< n 3 The re !c r::, 6(L) = 100 [2( $.'.D_ ) + 2( ME)1 5 F V I 1. Cciculation of 6(T) I 11 (VF )(Tave,j) I Y=I j J-l where VFJ = the volume weighting factors Tavo,j = the average ab.olute temperature in the je sub-I Vol uric NJ Tave..J = E I!.;d B i=1 l') where T;,j = t!.c cL:,olete ter.:n rature of thu ig RTD in the jg I. sub v:,l ui.n lij = nur'r.:r ei I;TD's in the jth I subvol c.: liva, 6 (T) i s cal cul ctEd fi v... 11 DT 6(D = E U fave, j 6(Taye,j) 3"1 where,fave,jBT _, d J 6(Ta%.J) = RTD cccurnet (Hj) $~ Therefore, 11 I 6(T)= E (VFj)(RTD accuracy) J=1 (Nj)7 2. Calculation of 6(P) 6(P)= {6(PT) + 6(PV).*TI I whcre P7 - tot:1 ebselete primary containm.cnt orcssure Py = partial pressure of water vapor in the p"ir.ory containment g W P.P R O V E D - l SEP 3 ' 107G O. C. O. G. n.

'ffS 150 Tl I:csision 3 I* I sul c t l i u t ii.9 6 (P ) " - E.. '1T Qi)',. (F c1. f. ti/ r.): 6 (P ) "' (VFj) (de:uce l l ccuracy) V J-l (lij)i there PPh a precisio.. pressure gauge Nj = nu.mber of h wcells in the j Q subvoluma Therefore, 2 6 (E) = [ 9{'e ct, +( (y7j) (gg,a ,c m_g.) ) ] p, 3 Instruccrit Spect ficctions niD FPG Dewcell Flo..mter nan;;c 32-250r-0-100 PSIA 0-10 SCr!; /securacy + 0. 5'.M 4 0.015 PSI + 1.0 F + 0.1 SCFil l 0 I-itepestability [ 0, iO t' T,0.C21 PSI [0.5F [ 0.02 scrit l 0 4. C il... :.. r !.. ..T G (;.),.'.;.c: ;.c / :.1 ;: b I. followin ; crc the dc e.ign. ted volua., iractione. and sent.or allocations: I Subvolic.e Vo l u;..c t!o. of 11 0. of Fracticn RTD's Dewcells 1 0.03477 2 0 I 2 0.03166 2 0 3 0.03625 2 1 4 0.01248 2 0 'I 5 0.07958 3 0 6' O.10Gh2 4 1 7 0.09110 4 0 l 8 0.08601 4 1 9 0.03075 1 1 10 0.46565 5 2 11 0.02533 2 T.C.'s Sat. Assume the following values: I 7 = 63.u i SI A 0 T = 92 F = 551.7 R 0 (, Dewpoint = 80 F APPROVED l SEP 391976 O. c. O. S. R.

QTS 150 T1 Revisien 3 f Therefore, TIT.)+(0.03G25 x 9(2;rfS) i 0.59 6(T) - (0.03477' x 9 ~5&)4 (0.03166 x i I C2)r J 0.50 0 _52- +(0.01243 x 0.50)+(o o795c x T3B)+(0.10642 x T4)i) l T2)7 0.5 0.50 0 } T4')$)+(o,og.:o; x TU:)+(0.03075 X ( 50) +(0.09110 x i)* I 6505xP[O)+(0.02533XhS,0) +(0.1 r )- = 0.26300R 0d5 u 0.01061 PSIA 6(P ) ".Tzu T l Vith an everage detpoint of 800F, an accuracy of + 1 F corresponds to + 0.017 PSI. T[f)+(0.12831 x ~0.0,17)+(o,ig75; x (.017_) 0 0.017 6(Py) = (0.066','3 x fl)I l)2 I~ 0.01,1)+(0.02533 x _.p l) 0 +(0.11676 x li)]>l),(o,4g553 x Tif2 c;0 (2TI ( = 0.01455 PSI Therefore, 6(P) = [(0.01061)2+(0.01456)2]l l = 0.01802 The accuracy uncertainty is then found to be 6(L) = 100 [2 (0.01802) 2+2 (0. 2630) 2 3t 63 0 551.7 = 0.0786 weight t/ day l S. calculation of 6(L), Repeatability Analysis Using the forrnulas developed previously, the repeatability error analysis is performed by substituting the instrument repeatability errors for the instrument accuracy errors. gc WPPROVE 4 'SEP 3. wig l O. C n a

\\ QTS 150-T1 I* Revision 3 I 6(T) = (0.03477 X 0 IOl+(0.03166 x 0.10)< (0.03625 X 0 IO) (2)i (2)i (2)s- +(0.01248 X E IS)+(0.07950 X 0.10)+(0.10642 X 0.10) (2)s (3)I (4)1 +(0.09110 X 0.10)+(0.08601 X U IO)+(0.03075 X 0.10) (4)i (4)I (1)1 +(0.46565 x 0 I0)+(0.02533 X 0 10) (5)f (2)i = 0.052^0R 0 Vith an average dewpoint of 80 F, an accurccy of + 1 F corresponds to + 0.008 PSI. 6(Pv) = (0.06643 X -)+(0.12031 X -f-)+(0.19752 X ) 0 000)+(0.46565 X 9 008)+(0.02533 X EJP3) +(0.11676 x (1)i (2)$ (2)i I = 0.00605 PSI A(PT) ".0.001, o.co.0yfrs1A len I~ Therefore, 6(7) = [(0.00071)2+(0.006S5)23} = 0.00689 The reper.tability uncertainty is than four.d to be 6(L) = 100 [2(0.00609)2+ 2 (E:.9526)231 63 0 551.7 =.0.0205 weight %/ day I 6. Total Instrument Uncertainty c(L) Total = [(o(L) Accuracy)2 + (o(L)Repeatabil!ty)2 3 3 l = [(0.0786)2 + (0.0205)231 = 0.0812 weight %/ day I 2a(L) Total = 0.1674 welght %/ day i I I {PPROVET (final) 'ggp 39 ;g7g O. C. O. S. p.

b QT S i f,0-T2 Revision 3 Sep t c..:,be r 19T. D/,TA SHEETS USFD A!!D CALrutATIO:IS l'./.0E TO ODIAN ULUnLY LCI.i; EATES ( Calculations of Free Volumes and 1lalghtinn Fjctors Torus The calculated free volume of the torus is'116,937 ft3 This free volume was calculated assuming a water height in the torus of +2.0 inches. For I the IPCLRT, the water height should be 0.0 inches, which will cdd free air This additional free voluma can be calculated frcm: volume to the torus. 2 l V = vb (n2-r ) whcre V = the added f ree volume of ti,e torus h = the height char.pn of the vtater in feet I R = the rejor radius of the tores in feet r = the minor radius of the torus in feet 3 Therefore, V = +1437 ft. For the purposes of this test, the torus inti.rnal vent pipe and vent'hcader volums h.vc been subtracted fro.a the torus frce air volume since the air vole >e ereloced by the heeder is essantially indepcodent of the reuninder of the torus free air voluc.c. Tl.i s volum.c i s fou.h' to be cqual to 14,710 ft3 The cetm.'l tn-us e.ubvolume is found to be equu! to: 116,937 + 1437 = 110,374 ft. { 3 Drvwell Since the dryuell end torus were divided into twelve separate subvolu.es I for the calculations, the FSAR nu nbers will serve as a comparison to tha volumes calculated (see Figure 3). The total volums of the drywell was calculated to be: V = 197,913 ft3 this compared with the FSAR volume of the drywell of V = 198,440 ft3 Calculation of the shaded arcas in Figure 4 gives the calculated oc.upied volume of tha drywell. This occupied volume is OV = 45,370 ft3 this again, was compared to the FSAR volume. The FSAR volume for the os.:vpied volume of the drywell is OV = 40,204 ft3 APPROVED i SEP 3-1976 I O. C. o. s. n.

QTS 150-1? I Revislui 3 I it is r.ecessary to matene that internr.1 drp;cil equip.i.nt [ In this an:,1y-is, in the dry-such as pump:, piping, valves, etc. c:cupy an ew.n distribution vell such t!.et the ratio are equal to the ratio;, of the free volu:res cal-from the occupicd dryacil culatcd. This assumptico cli:ninatet, this cc.mponent volume calculat'on. The free volum of each of the twelve regions in Figure 4 was then cciculated according to tlie folicwing volume forrnuli: 1. Volume of a sphere V=4i3rr3 Volume of a right circular cylinder 2. 2 V=tr h 3 Volur : ci a spherical scoment V=I/21:h (3r-h) 2 The free volum:s calculated arc: 3 Free Volur.: il = 10,056 ft Fra V:.!u.r.: t2 = 9,165 ftf I. Frac Volui..c f3 = 10,49'. fi;) .( Free Volua:: Jh = 3,612 fL3 3 l I'cce Volu:c.c,45 = 23,039 f t l 3 Free Vc.lume f6 = 30,6t>C it I E 3 Free Volu:.:e #7 = 26,373 f t M,6 Free voiun2 ca = 24,90c ft3 7 1 l E Free Volume f9 = 8,901 ft33-P 3 Fi ec V.21un.e fl0= l 34,863 f t 3 Free Volu:ac ill= 7,340 ft Th. volur,c weighting factors are then found to be I VF(l) = 0.03677 VF(2) = 0.03166 VF(3) = 0.03675 VF(4) = 0.01248 I VF(5) = 0.07958 VF(6) = 0.10642 VF(7) = 0.09110 I VF(8) = 0.08601 VF(5) - 0.03075 VF(10) = 0.46565 l VF(11) = 0.02533 (- APPROVEI I SEP 301"76

O QTS 155-T2 I Revisiv, 3 Frnr, rigure 4, the subvoluac fl free volume is defined to he the air trace above the vessel-drywell flange. The subvolume #2 free vnlume is the airsp:ce between elevction:, 652'C" ond 666'9". The subvolume #3 free volums is the airspecc external to the biological shleid betwcen elevations 628'8" and 652'6". The subvolume f4 frco volume is defined to be the annular cirspace between I the reactor vessel and the biological shield. The subvolume //5 free volum: Is the airsp::ce external to the biological shield between elevations 614'6" and 628'8". The subvolume f6 f ree voluine is the airspace external to the biological shield between clovations 602'10" cnd 614'6". The subvolume !8 I 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 shic1d betwcen elevations 579810" und 593'0" in the drywell I The subvolume !9 free air vnlume. is tiic airspace in the CRD pit basement. below the reactor vessel. The subvolume #10 fice air volume is the volone ene.losed by the drywell-tores vent pipes, vent spheres, downcomars, torus internsi vent header, and the torus airspcce chove 0". The subvnlume fil I free air volume is the reactor vessel airspace above 35" minus the steam dryer volunc and one-half of the noisture separator volume. I I-I .I I I I APPROVED (final) SEP 3p 1976 I Q.C.O.S.R.

s. Itev'sion 3 I.. Sept e'.'i>er 15 ; s Idealized View of Dr/.ull and hies Used to Calculat. Frec Volvi.::, - 3 7 ' 0" -- - = - -d l I' - 3 4 '_8" __ _-- _-N 681'9" g 677'6" /- ,, w /,- I _11. / 666's" 662'0" .;._.,,22 s on b :l. u E ) l/,/,/// ./ /,/ _ 655'2"

l., / _ _.....

4 E - q.,/;..' / ['. / 6r,7 ' 3" _j*/. M.. In d -jj ~g - - [ ' f/ ~ ' 0ccupied 'V/ // 7 ,jVofume e, l/ ,/,.. ' j,,l i } / l Pl../:./-.2 4 ' 1 ""../.. C ' - E fFrcc ' Volume ),N / /.3/,/.. /,) 'l (05'i0" /,/ .{ j i.~./ j'/./, / ^; l -- c,2 D ' 0. ". ~~ ,.. l ;. i / 4./.. ' < i. (c.rsting; E uj j..,' /.- g,, i' " /.- j q' / .. f,,. ',. 7 \\ ,/ i, / // 5 \\. l /__,'/ \\ / ' /,/ t. 614'6" / 7 /f (C re t i r,0) I / / / 6 I (,03 ' 2" r-g--[7 i - - 605 4 " .l /j! f,'/ \\ 60?'10" 7 ) \\ / 7 \\ C 20 ' 0"- E / l 9 f/ 593'0" / / / 8 \\ ragg,gj, l /\\ / .m fC / ]II A 569'lon Floor) l 30'0" _ 54'6" _ A P P R'O V E D -" N -.V Figure TWO I SEP Sc IS76 (final) O r r< e: o

QTS 150-T7 l I'cVision 3 l FIGURE 0'?C Sco t cr.t c r l's.16 Ii/* PRESSURIZATl0': SYSTCH SClltinTlC ARM;I.El:F!iT (TYPICAL) I 4" Flexible Hose Nh 6" Carbon Steel Pipe 6 El g "W p, I E ' FlexMe

  • t!al l tTj Penetrat. ion

~ d3]-)](TG;s.y Hose} g 4"X4" Flango 3 ric". To Fire -b H s g Hender ~ g j '4" Flexible Fire h,, Comp ."b} pl ,,A,, Da wejj Ccn i Hosc Hose

  1. 2 Spray !!eader 1-4199-43 Station

fD 4"

  • zg y l.,

j[1j O"X4', Fitter-FM ~)/ il'~~ Flexibt Com;>rnssor 3 / 4 ~ M. f_I. fac j. { (Cor.ipres ors ---s ii / (1:0unted c.n S Pad) S N / 'N r I ,4 p; r....... n,.[oss;j n M0 1-1001-25/'

/

Access llatch I I ),/J4 m \\ / f <- !) ~8 I i I 595' Elevation i i I unit one I Drywell s I Unit One ncsetor callaing A'P P R O V Ei- / I SEP 3 : *?76

  • C. O. S. R.

g L4, South I Doors

~ I Guob-.Y..E La

l. ow/o /ofly

' 5tF56e\\ MLn d5W/e/pM _96 48PS6 9$t'eELOCC Ja et orn( = 28% {04 F"i2 omeka 6 .soa aaay aar ise, u.1 w C.lNSEECno.tLREkPa-lk24 f M_6S c Ev0 i i i . owlbnv 2BecLER w w n # &S55schl Q 8_ssG=Gd ILM ..=.. h 9e s men - - t 5 l l L t ee M .m m N* e 4 ene p m Q m k r.=fy.:'a d __.n h. f r_ ph L L A 4 L u w k W i e _co w.w h g wd >;6. 23 h h.v-t, S e/~ t ' h b 4-e s L ' i ; n k.c.- %.ti-J. ~; 4 a & > J L~n-

i-i 116.

t"i e.- tLP i c e

e QTS 150-T6 Revision 4 IPCLRT DEFlfilTICNS March 1977 ( (48 PSIG TEST PRESSURE) l Maximum Allowable Leakage Rate (L ) p Lp = 1.0% of containment volume per day 3 = (0.01)(275,481 f t )/24 hrs. (FSAR) -275%.81ft/24 hrs. 3 3 = 114.784 ft /hr. I, = (114.784 f t'/hr)(48 + 14.7) = 489.59 scfh 14.7 Maximum Allowable Operational Leakage Rate (L ) g Lt = 75% of Maximum Allowable Leakage Rat,e 3 3 = 0 75 (114.784 f t /hr) = 86.088 f t /hr - 0 75 (489 59 scfh) = 367.2 sefh Maximum Allowable Leakace Rate for Double Gasketed Seals (0.10)(367 2 scfh) = 36.72 scfh l Maximum Allowable Leakage Rate for Testable Penetrations & Isolation 'lalve (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 Vaive 11.5 sefh e 25 PSIG test pressure I Ir A P P R C V 2.I., --:c7 ~- Q. C. O. C. T?.

s. 9 0.TS 1 D -T?, P.evi s i en ~. 'I C/.L C '.': 7,T:: -

7c-o;.7 Fr, :. -
  • e?.

.', n - f !;75 r. t.. e.c 112:tc.; f rna pre :ro re t.w.c r=, ?:ci cells c 4 T.TD's to cted in the c er ta i:m'.t a r2 p acessed usin,, tS2.ollo.rieg calculaticas. i,. t.veroga Subvolu.:n Tu..:p_ratu a ced 0;wpoin t. T) = T(all RTD's i the it5 5 6volu c) oc E t.um:.ar of fd; 's in J tn susvoluna _ -5 c u bvo l u-M D. P.; = : (a l l d eu ce l l s i t,i t ilumber of dcvs celis in j th suuvolume where Ty = average temperature of the Jth subvolume D.P.; = average dowpoint of the Jth subvolume B. Average Primary Containnent Temperature and Dewpoint. fjV0'" (Vi ) * (7 ) o T= g "VOL (VF ) '- (0.P. ) o D.P.

  • g J=1 J

J where T = overage containnent t an'po ra tu rc .D.D. = averegn centair ent d point VF) = volum fractio.. cf tha J th subvolume f1VOL = nu.Ther of subvolumes If T is undefined then y J = T' for 1 < J < (flVOL - 2) T J+1 I l for j = tlVOL - 1 Ty = TJ-1 t 1 T. = estimate for J = ttVOL J i If D.P.y is undefined D. P.J.= D.P.J+1 for 1 < J < (14VOL - 2) l l D.P.J = D.P., for j = flVOL - 1 l

-1 D.P., = cstimate for j = f1VOL J

e r - y..

  • 4 lI t' f t e v,u ~ n e

f* T 6 w."! *1 (G t s i

r. Ps l'

..'M~-

f l *. QTS 1r.0-73 g r.u i s ic i 3 L. C.alculation of Dry Air Pressucc. D.P. (oK) = 273 16 + D. P. (CF) - 32 j 1.8 l X = 647.27 - D.P. ( K) 3 EXP0tl = X * (Y + Z

  • X
  • C
  • X )

(0.P. (ug)):t(1 + 0 X) Py = (218.167) * (1!. 695) (p3,) e(EX M A 1.1 ( W) ) I P = E(all nbsolu;$ orcr gre caceld ,p g,) tiumber of a:>sciu:e pressura gaucas v l l l uhcro Y = 3.2437314 i = 5.86026 x 10-3 -3 I-C = 1.1702379 x 10 l l D = 2.1873'62 x 10-3 8 P = volume weigStad ccotainm r.t vapor pres >ure y P = containment dry air absolute pressure C, D, X, Y, 2, and CXPCM are dea. point tu vspor pressure conversica constants and coef ficients. I D. Containr.icnt Dry Ai r fiass. l W = (28.97) * (144) * (P) * (28c506 - 25 * (LEVFL - 30))_ l 1545 33 k (T + 459.63) where W = contcinment dry air mass LEVEL = reactor water level 289506 4 primary containment volume E. lieasured Leak Rate. L (TOTAL) = (W - V )

  • 2400 m

BASE i t/ DAY ' I t I DASE .-I l'I Y ='# C I r-a' r s, I I

I . o QTS t.%-T3 P.svitim 5 t (Polt;T) a 01 - W,)

  • 2400 0/ CAY 1-1)
  • U (t

t i g.1 where W = c ntainment y I r ma n a t t = 0 BASE tg = time from start of test at Ith data set t;_) = time from start of test ct (I-1)th data set Wj = dry air r. ass at Ith data set V.j = dry air mass at (I-1)th data set g L,(TOTAL)= measured Icakage f rom the start of test to Ith data set. L,(P0lllT)= ceasured Icakage between the last two data sets I". Statistical Leak Rate and Confidence Limit. Lit: EAR LEAST SQUARES FITTil:0 THE IPCli.T DATA The m2thod of "Least Squar~cs" is a statistical proced.re for finding the I best fitting rag-escion linc for a set of r.:ss ared d:ta. The c ri terion for tha bust fitting line to a ret of cata poir.ts is th-t tha s m of th2 squares of the deviations of the observed peints fre, the lir.c r.ust b a I minirua. il hen this criterion is met, a unic,us tast fit:Ing lir.e is c3 oincd based on cil of the data points in th: I Leo. in.' val u of the leak r.: :. based on the regression is called the statis Ically averese leak rate. Since it is assu..cd that the leak rate is cc.nste.nt during the testing period, a plot of the ~ measured contain:acnt d' y cir cass 'vc.rsus' ticIf oild" r ideally yield a straight line with a negative slope (assuming a ren-zero I leak rate). Obviously, sampling techniques and test conditions are not l l perfect and consequently the measured values will deviate from the ideal straight line situation. l I Basedonthisstatisticalprocess,thecalculatedleakrateisobtained l from the equation: l W = At + B where U = contained dry air mass at time t l B = calculated dry air mass at time t = 0 A = calculated leak rate t = test duration em n "- l'C.*.3.

I-QTS 15.1-T3 Revi e. i >;n 5 8 No I Dry Air P. ass (1bs) 4 \\ \\ Test Dura. ion (hrs) The values for the Least Squarcs fit constcnts A and B are given by: - t) * (U; - E) A = (fl

  • I(t ;) * (V ;) - It ;
  • IV; } = I(tg I

(N

  • I(t;)2 _ (gg )2)

Z(t; - t) I B = IV; - A

  • It; = {I(t )2
  • I(U;) } - (f(t;) * (U;))

II ft

  • I(t )' - (It.)2 i

i whe rs t = the av.arcg: tira for all data sets U = tne averegn air rass for cli data sets The seco-d fonulas are used in the prccess ccTuter progrc:n to reduce round-off-crror. By definition, Icakapc cat of the contcInm:nt is censidered positive leakage; therefore, the statistically overoga leak rate is given by: l L = (-A) * (2400) s (weight t/ DAY) 3 STATISTICAL UilCERTAlflTIES In order to calculate the 95% confir'.:nce liritts of the statistically average leak rate, the standard deviation of the least squares slope and the student's Toistributien function are used as follows. fl

  • I(U;)2 _ (39 )2 1

2, l o={

  • (N
  • I(t;)2 (gg;)2) - A ):

(N-2) When performing these calculations on the process computer, I(W;)2 and I tutE)d for U;. (IV. # become so large that they overflo.i. To avoid this proble.l.U; i s substi-t.W ; is the difference betuc'n V; and W e BASE

  • I p

l t' e".J $ ;} Q. f. ~. '.',. - l

Ir QTS 1."2-T3 ?.evi s

  • m 3 I

The sin.lc sic'ad T3istribu:icn ti th 2 d :_' ra:s ei i n.....; i s rpp re: -- *. : d I by the follcuing f or:.*.:la f ec:: t;35 HcndL;a.4 91: T.E. = 1.646633 + 1.!.5y_,?,J.,+ lj 7E_~71 I (ll-2 ), (l-2)i The upper confidence lirnit (UCL) is given b>/ UCL = Ls + a * (TE)

  • 2hM- (1 e i,,h t

,/0,a.v. ) e c I I I Ie e I I I I 1 l I .,,....,..s I s l' 6. *. .J I ry n I"' "y ' ' ' ' ' (final) (a... ~., - l

O /b f _* / r -. s ? RTS i30-51 h, P.:vis' n 5 I T"! :.7 r.A t :iTE.W CI July 1973 ,...c......,e2 ,:3.,...,._... ...o c <r 1. Grf fil:ersd ci r s::all be 3.op!!ad by air c: seessors to the dry.; ell f and pec3 sure s ;ppression chanher at penetration nc.ber X-33A. Install the air cc. pressors includi.,g piping.. anifolds and connections to existing penetrations. A double valve isolation er.ists in the Uni: One l fire besdar through the reactor building viall to prevent leakcge via a penetration upon reaching test pressure. Verified 2. Open at least three pairs of sucpression chsmber of drywell vacuu.m braaker valves connecting the drywell and pressure suppressica chare.ber. Vacuum breaker valves shall be secured so as to re.cain in the open position. Verified E q* $ > I i l t l v > o.o.0V C P

r...

a 1 4 (final)

o, 1 o,1070

,, wew

c. c.c. s. n..

{

i e QTC 150-S1 'r Re.>isicn 5 )M !?CLRT C?E'AT10h5 July 1375 DI?ACEtiT ChiCKLIST e Prnpare : e pri ary centair.ent systens and valves fcc the IPCLRT. 1. cc"? *tica ? ch*c!'13 5t 475 53-S5 C'PC'RT Volve 'ta=u?) "I 55ti5f7 c 5 / 5 thi3 requirement. (qT5 150-s7 for uni t T.0). Verified Reactor recirculation icoo, System A, vented and water filled. 2. g Verified Reactor recirculation loop, System B, vented and water Plie'd. 3 Verified 4. Reactor recirculation loop cross tie header vented and water filled. . Verified Af ter cc.~pleting QTS 150-S5(57), open a service air drop en the reactor I 5 building second floor to. vent the service air system frca the drywell. Verified The reactor drywe'll equipment drain sump shall be pumped down to its c. Icwest level. All associated drain' piping discharging into this su: p I should.be drained and without flow. Verified E The reactor drywell floor drain sump shall be pu.mped down to its 7 lowest level. All associated drain piping discharging into this sump r should be drained and without flow. Verified 8. Insure that the internal vessel atmosphere is vented unrestricted to the drywell and intercennecting pressure suppression containment by opening X-220-48 and X-220-49 as a path to the drywell equipment drain sump. Ensure I that the refueling bellows and bulk head hatches are open. Vcrifled ~ 9 Isolate Dw-torus LP transmitter. Veri fled 1 APPROVED I' SEP 121979.o..c.c.s.a. l

CTS 150-32 P.evisien 5 I

15. R2:ord C'.. Ficor r ! c.wi;.. ant d.*in su. p levels j ust prior to contain-rent closure.

Verified

11. The following P.HR3 valves are to be in the fully clesed position ex:2pt for the valves required for shutdov.n ecoling.

tic-X-1001 -18 A MO-X-1001-183 MO-X-1001-23A I MO-X-1001-233 tt0-X-1001-263 MO-X-1001-2cA !!O-X-1001-293 MO-X-1001-36A MO-X-1001-363 MO-X-1001-37A MG-X-1001-373 MO-X-1001-34A MO-X-1001-343 Verified _.. TT E The shutdown cooling system will be used to maintain the reactor wate.- temperature less than 140 F and within 5 during the tast.

12. Fill wi th water all RMR3 piping between the RHRS valves of step 9 and the RHRS pumps.

I Verified

13. The following core spray valves will be in the fully closed position:

l f MO-X-1402-4A M0-X-1402-43 i10-X-1402-25A MO-X-1402-253 l tt0-X-1402-33A (005) l tt0-X-1402-383 (005) Verified

14. Fill with water all core spray interconnecting piping between the core spray valves-of steo 11 and the core spray pumps.

VerifieJ

15. C;.ack that the TIP detectors are in their.hields with each TIP drive flitrogen make-up isolated and 00S.

i The TIP solenoid ball valves should be closed, as-well as TIP purge f. valve assumbly 700-743 t Verified AFFROVED I SEP 121979 0.c.o. s. n

QTS 130-52 r.evision 5

15. Drain instre ent air recei /er 1(?)-4707 Also, close the manual supply air stop valves to X-4722 M3.

Verified

17. Icmediately prior to pressurizing the primary containment, nake a general announcement over the plant public address systein stating 'that the IPCLRT I

is about to begin. This announcement will be made at the direction of the cognizant Tech Staff Engineer. Ve ri fied

13. Isolate PS 1622 A&B and PT 1623 Verified I
13. Verify that the Drywell cooler damper control valves at penetrations X-44, X-104D, and X-1063 (X-44, X-1000, and X-104E for U-2) are closed.

Veri fled Perforrance of this checklist will put the systems affecting primary containment I in the folic, wing configuration: SYSTEtt CONDITICH I Main Steam isolated, Drained, Ventad P.cactor Feedwater Filied, Pumps Off I Pcactor Building Closed Ccoling Uater to Drysell Filled Pressure Suppression isolated, Vented Core Spray isolated I Lou Pressure Coolant injection isolated High Pressure Coolant I inj ection Isolated (Steam and PJ sides) Reactor Clesnup Isolated. Shutdown Cooling Operating to maintain constant reactor vessel water temperature. Clean Denin to Drywell isolated I Drywell Floor & Equipment Drains isolated, Vented Service Ai r to Drywell isolated, Vented instrument Air to Dryuell isolated, Vented I RCIC isolated (Steam and R1 sidas) R> actor Reci rculation Filled I i APPROVED (final) g y ggg7g Q.C.O.S.'

m C.TS 150-53 I P.evisi.n 6 I?CLF.7 iSST?SE:IT July 1973 FM NTD,1,'.CE CHECKLIST 1. in:. tall 3/3" high p. essure tubirs (two lan-ths) through cne of the installed pipe penetratices located in the personnel airloch. Attach one length of tubing to the pressure instrwentation and one length to the flowme:er to be used during the induced leak test phase. Isolate the floweter. Verified 2. Connect all instruments and their associated read-out devices to their I leads, inside and outside the primary containmer.c. The locations for all teccarature sensing and humidity sensing devices will be supplied by the cogni:: ant Tech Staff Engineer. Instrument lines will penetrate primary I co'.tainment through the capped electrical penetrations located above the personnel access hatches. (Pef QTS 150-517). Verified 3 Verify proper operation of all instruments and read-out devices to be used during the IPCLRT. Give a copy of all calibration data sheets to the re-I sponsible Tech Staff Engineer. Instruce.nt calibration must include the entire route, f rem the sensor to the read-out device. Verified A. C:>tain and suppl / to the responsible Tech Staff Engineer instrument error and readabili ty crror for all instrenents ar.d read-out devices to be used in the IPCL?.T. Verified 5 Cicse instre: ent isolation valves, remove vent raps, and have tagged cos for the folic,.ing drywell pressure switches: PS 1001-S3 A, B, C, D Verified PS 1001-S3 A, B, C, D Verified PS 1001-90 A, B, C, D Verified I*. PS '1001-83 A, B, C, D Verified PS 1001-35 Ve ri fied PS 1622 A 5 B Verified I, PT 1623 Verified PT 1624 Veri fled DPT 87'41-51 verified 6. Install a coisture trap upstream of the.flo.ceter. I Veri fied (final) SEP 121979 .o. c.c. s. a

E ~5. 0.T3 130-3'4 ,Fj P.avision 6 g IPCLP.T T:CliM f C.',L STAFF July 1973 CHECKLIST 1. Eithar arrange for the p'ircha se of qualified instru.--n tation (including I thermometric, baremetric and humidity measuring devicas) which meet ali necessary standards for use in the IPCLRT or veri fy that on-si te instrerenta-tion to be used meets all such standards. Obtain documentation to shove this. Only documented instruments may be used. Il0TE instrumentation for the measurement of humidity shall comply with ASTM E337-62. Verified 2. 14ake a survey of the primary containment for the purpose of establishing any tendencies for regional variations in tamperature. This survey will be used in determining where to place the temperature sensing devices. Provide a map for temperature sensor locations. Ve'rified NOTI I Where tasting experience with a given contain. ment structure has previously established appropriate locations for temperature sensors, temperature surveys may be eliminated. 3 At the same time as the temperature survey, conduct a survey for the purpose of determining the placement of the humidity indicators so that a I representative sampling of the primary containment ai r can be made. Verified NOTE I ' As in the case of the temperature survey, this humidity survey may be eliminated for a containment structure which has known and characteristic humidi ty patterns. 4. Determine the piecement of all temperature and humidi ty sensing de'dcas frem the surveys in steps 2 and 3 above. Veri fied 5 Verify that c i:uclear Energy Liability Insurance Association (llEL-P I A) I representative is notified prior to pressurization. Verified I APPROVED 3 SEP 121979 g .Q.c.c.s.a

h QTS 150-3; F. visica 6 I fs. Ensure thn a computer or cciculator is available for the leak rate calcula-tions. Verified ~ 7 Arrcnge for the availability of the air compressors for use in pressuri::- I ing the containment. Verified 8. Ensure that the air compressors, piping, manifolds and connections to the penetrations are installed by the Maintenance Department as required in Checklist QTS 150-51. Verified 9 Af ter installation of the air compressors, etc., verify proper installa-tion and function of the equipment. Verified

10. Verify the availability of an absolute barometer for the recording of I

atmospheric changes in the reactor building. This device need only be of such accuracy that it will indicate gross barometric variations for corrala-tion to test results. Verified

11. Determine the volume of the primary containment associated with each I

temperatura cad humidity sensing device. This information will be used during the test for volu e weighting the data. NOTE The actual water level of the suppression pcol and of the reactor may have to be taken into account in the final calculations to be done I af ter the test completion. However, r'ealistic assumptions can be made J for these values prior to the test if hand calculations are being done, or the individual test volumes can be recalculated every hour if a computer cede is utilized for,the calculations. Verified

12. Arrange uith the Instrument itechanics and 0AD for the calibration of all instruments to ba used in the IPCLRT.

l Verified l APPROVID ; q :.P.,,2 w-,o l l l .Q. C. o. S. R. 1

I. ry5 150-52 Revision 5

13. A-range wi th the instru.#nt %chnaics for piec:nent o.' the calibra ted i ns t rumen tation in the primary cantain-e.t anJ its conaection to r.:ad-out devices cutside the pri ary cc: tain. ent.

Varify the le :a:ica and cp=rability s tatus of :he ins trur:en:stion. (Ref. QTS 130-51/.) Verified

14. Prepare graph papar for plotting the folicwing informtien vs time for the duration of the test:

a. Absolute pressure of the primary containment. b. Average partial pressure of the water vapor in the centainment. c. Absolute dry air pressure in the containment. d. Average temperature for each containment volume fraction. Average vapor pressure for each containment volume fraction. e. f. Avarage volume weighted tecperature in the containment. g. iteasured centained dry ai r mass. h. Total time leak rate. l 1. Least squares fit laak rate and upper confidence limit. I Verified

15. Initiate a dated log of events and pertinent observations. This leg..ust be maintained for the duration of the IPCLRT.

Verified

16. Obtai.n the instrument accuracies for all instruments and read-out devices to be used in the IFELRT. Perform an error analysis to verify that the I

accuracy of the collected data is consistent with the magnitude of the speci fied leakage rate. This analysis must be done prior to the placement of any instrumentation in the oricary containment for the test. (See I QTS 150-Tl for a sample calculation.) INTERPRETATION Specifically, the cc-bined Instrument and read-out accuracy should -- - b e a t least of the order of the raximum allowable hourly leak rate (L ). p Verified. - ERPROVED QCO$nT.alo sw s e u ,Q.C.C.S.7

.I... GTS 150-54 Revisien 6 5

17. Exoine LLF.T results for ell tests and verify that cll Technical Speci-fication lir.its ha se been ret p-ior to the start of the !?CLRT.

reti fled

13. Verify valve line-up, checklist qis 150-55, prior to starting the test.

(QTS 150-57 for Uni t Two). Ve ri fied

19. Conduct a thorough examination of the drywell and pressure suppression containment to remove any pressurized vessels, gas pressure cylinders, sealed or semi-sealed containers, and anything which, in the judgement of the Test Directcr, could be damaged by the pressure test atmosphere or have a direct bearing on the results of the leakage rate measurement.

I Verified

20. Ensure that the following penetrations are closed and secured:

Equipment Hatch X-1 Drive Removal Hatch X-6 Drywell Head Access Hatch X-4 ~I Access Hatch (Torus) X-200A l Access Hatch (Torus) X-2003 Dry.rell Head Ve ri fied

21. Close the ' inner personrel air lock door and open the outer door. Provide l

I a restraint to the outer ha-d.. heels to prevent accidental operating and install an Out-of-Service card in this location. Lock restraint with an R-lock. Verified

22. Direct'the Operations Department in the pressurizing of the primary centain-t cent.

Verified g l APPROYE0 l (final) SE?121979 p;. c.o. s. a g

473 150-57 Er/isic 5 L 'T 2 ..?,7 G L'. i L i IS ? L:. I '.;.' 9 I E NET.'.ATIC 1 LG;AT!0:1 L I 'il V A L'.'i .., H I R ELT! A l:tLTH 51ZE i:U:13I'. ? ]51 T i O.'l PS:0 C E 3 0?. I S 7 ! 0?! x-7A 595' 600 20" d 2-203-1A C 60-1 Primary S team AJ 2-203-2A C 60-2 I 2-220-9A C 60-2 2-220-10A C 60-2 l'0 2-220-90A 0 60-2 x-73 595' 150 20" A0 2-203-13 C 60-1 Primary Steam A0 2-203-23 C 60-2 2-220-93 C 60-2 2-220-103 C 60-2 I i:0 2-220-903 0 60-2 Y.-7C 595' 345 20" A0 2-203-1C C 60-1 Primary Steam A0 2-203-2C C 60-2 h 2-220-90 C 60-2 3 2-220-10C C 60-2 i0 2-220-90C 0 60-2 I , X-70 595' 355 20" A') 2-203-10 C 60-1 Primary S team A3 2-20'-20 C 60-2 2-220-90 C 60-2 2-220-100 C 60-2 I 1:0 2-220-900 0 60-2 0 2"

0 2-220-1 C

60-1 Steam Drain X-3 592'6" 0 MG 2-220-2 C 60-2 I 2-220-5 C 60-2 2-220-6 C 60-2 t:0 2-220-3 0 60-2 I 1:0 2-220-4 0 60-2 X-3A 598'3" 350o 18" no 2-3205A C 62 Primary Feed Water 2-220-57A 0 62 2-220-85A C 62 I 2-220-115A C 62 2-3212A LC 62 H0 2-1201-80 C 88 I 2-1201-82 0 88 2-1201-127 C 88 2-1201-129 C 88 I i;0 2-1301-49 C 89 It0 2-1301-50 C 89 2-1301-51 C 89 2-220-60A LC 62 X-53 598'3" 90 18" M0 2-32053 C 62 Primary Feed Wa te: I 2-220-573 0 62 2-220-603 f.C 62 2-220-853 C 62 APPROVED SEP 12 lW9 Q. C. C. 3. 7 I

g (75 150-57 .E Revi:ilon 5 4 s;oci?:21 with shatdo.a coolir.g locos I

;,ts LCCAT!'

L i ?.i V A'_V I -12 '. _ ~ ' A'," 5fZi ?;U." d i ?. PM!ON '~:3 D 5 C ' ; "r ' 1 s-33 2-220-1133 C 62 ( r :.) 2-3212B LC 62 AG 2-2301-7 C 87 I A0 2-2301-8 C 87 2-2301-39A C 67 2-2301-833 C 87 2-2301-18 C 87

(- 10 605' 60 3"

M0 2-1301-16 C 89 Steam to RCIC Turb MO 2-1301-17 C 89 I 2-1301-18A C 89 X-11 591'3" 95 10" M0 2-2301-4 C 87 s:aam t.3 spct Tuch Mo 2-2301-5 C 87 2-2301-16 C 87 I 2-2301-77 C 87 X-12 605' 343 20" MO 2-1001-47* 0 81 RMas supply M0 2-1001-50* 0 81 I 2-1001-48 C 81 2-1001-156A C 81 2-1001-1560 C 81 I X-13A 591'3" 85 IS" A0 2-1001-68A* C or 0 81 RHRS Retur., M0 2-1001-29A* C or 0 81 I 2-1031-33A LO 81 2-1001-30A C 81 2-1001-164A C 81 2-1001-1643 C 81 i E x-133 591'3" 265o 18" A0 2-1001-633* C or 0 81 F.:-As Return 3 MO 2-1001-293* C or 0 81 i 2-1001-333 LO 81 2-1001-303 C 81 I 2-1001-164C C 81 2-1001-1640 C 81 X-lh 625' 2700 4" MO 2-1201-2 C 83 Rx Vater Cleanup I MO.2-1201-5 C 88 supply 2-1201-121 C 88 X-16A 642'3" 20 10" A0 2-1402-9A C 78 Core Spray 2-1402-6A LO 73 I 2-1402-26A C 78 2-1402-29A C 78 2-1402-33A LC 78 I 2-1402-66A C. 78 MO 2-1402-4A C 78 MO 2-1402-25A C 78. I X-163 642'3" 155 10" A0 2-1402-93 C 78 co.e spray 2-1402-68 LO 78 2-1402-26B C 78 I 2-1402-293 C 78 2-1402-333 LC 78 2-1402-663 C 78 MO 2-1402-43 C 78 I M0 2-1402-259 C 73

? PROVE 0 EP l 2 W9 l C 0 E "-

U C.75 150-37 R,:vi s ion 5 E P i. iTRAfi GN LO;AT!'1 Liisi V AL'! E

- R E P.

ELIV /.I ' 'W T 4 SIII !liM 3 f ?. P03!Tl0N ?&lD DESC?.;? TION X-17 605' CD 14" PO 2-1']01-60 C S1 RH?.S t?V Mud Spay M3 2-1001-63 C Si 2-1001-62 C 81 X-13 589'9" 1850 3" A0 2-2001-3 C 85 Drywell Ficor Drain I A0 2-2001-4 C 85 Sump 2-2001-2A 0 85 2-2001-23 0 85~ I X-19 593'3" 45 3" Aa 2-2001-14 0 85 Drywell Equi;: ment A0 2-2001-15 C 85 Drain Sump A0 2-2001-16 C 85 I X-20 605' 850 3" 2-4399-45 C 58-3 Clean Demin 2-4399-47 C 58-3 2-4399-48 C 58-3 I X-21 605' 80 1" 2-4699-46 0500S 72 Service Air 0 2-4699-48 C 72 2-4699-75 C&005 72 X-22 605' 750 1" 2-4799-157 0 71-2 Instrument Air I 2-4739-160 0 2-4799-163 Cs005 2-4739-131 0 I 2-4799-182 0 2-4739-207 LC X-23 591'3" 315 8" NO 2-3702 0 75 RBCC',1 1.71 e t I X-24 553'3" 3153 8" no 2-3703 0 75 R3CCU Discharge MD 2-3/36 0 75 X-25 649' 213 13" A0 2-1601-23 C 76-1 Wn t f. c., C ry'.,e l l AG 2-1601-24 C 76-1 I A0 2-1601-62 C 76-1 A0 2-1601-63 C 76-1 2-1601-72 C 76-1 I A0 2-2599-4A, 5A C 642-2 ACAO to SBGT A0 2-2599-43, 5B C 642-2 2-2599-15A, 16A C 642-2 2-2599-158, 163 C 642-2 0 18" A0 2-1601-21 C 76-1 Vent to Drywell X-26 591'3" 322 A0 2-1601-22 C 76-1 A0 2-1601-55 C 76-1 I A0 2-1601-56 C 76-1 it0 2-1601-57 C 76-1 A0 2-1601-53 C 76-1 I A0 2-1601-59 C 76-1 A0 2-8303 C 76-1 A0 2-8S04 C 76-1 I 2-1601-74 C 76-1 2-1601-76 LO 76-1 2-1601-77 C 76-1 I APPROVED SEP 12 ES I o c. : E. o

0,75 153-57 I F. w i i n 5 'F E..,i p.A TI C:: LOCATIc i Ll:.i t AU!i .. ' gt: 3 3 3 ELEV AI!!!JTM S::I t:TH ER ? 05 ' T I Cit P r.10 OISC?.! ? Tic t 1..s t ru.. :s tion y-2 ;' 603' 2 'r50 27A 1" 2-263-2-24 0 77-1 (X-27F is a spc 2) 278 1" 2-263-2-26 0 77-1 27c 1" 2-1001-33c 0 76-1 I 2-1001-69C 0 76-i 27D 1" 2-1001-330 0 76-1 1" 2-1001-690 0 76-1 1 27E 1" 2-263-2-32 0 77-1 0 ins trumer.ta cion X-23 640'6" 210 28A i" 2-263-2-ISA 0 77-1 (X-23F is a spare) I 1" 2-263-2-41A 0 77 233 1" 2-263-2-16A 0 77-1 23: 1" 2-263-2-14A 0 77-1 230 1" 2-263-2-12A 0 77-1 I 23E 1" 2-220-53 0 77-1 Ins trumen ta tion X-29 591'3" 275 1" 2-220-11A 0 60-2 (X-23E & F are I 23A 293 .1 " 2-220-12A 0 60-2 spares) 23C 1" 2-220-113 0 60-2 250 1" 2-220-123 0 60-2 I 0 instrumentation X-30 587'6" 90 30A 1" 2-220-15A 0 77-2 303 1" 2-220-16A 0 77-2 30c 1" 2-262-2-4A 0 77-2 303 1" 2-262-2-3A 0 77-2 30E 1" 2-220-13A 0 77-2 3CF 1" 2-220-14A 0 77-2 I 0 Ins trumen ta ti on X-31 587'6" 270 31A 1" 2-220-153 0 77-2 313 1" 2-220-169 0 77-2 I 31C 1" 2-262-2-43 0 77-2 31D 1" 2-262-2-3B 0 77-2 31E 1" 2-220-133 0 77-2 g 1 5 31F 1" 2-220-148 0 77-2 .X-32 593' 65o Instrumentation I 32E 1" 2-1301-14A 0 09 (X-32A, B, & D 32F 1" 2-1301-143 0 89 are scares) I X-32c 1" A0 2-4720 C 71-2 DW Pneumatic Suction 1"- A0 2-4721 C 71-2~ 'X-33 605' 120o I ns t rumen ta ti on I 33A 1" 2-2301-24 0 87 333 I" 2-2301-25 0 87 l 3 33C 1" 2-1402-27A 0 78 l 5 333 1" 2-i402-27a 0 7s l 33E 1" 50 2-2499-1A, 2A c 641-2 cAn 2-2499-7A, 8A c 641-2 33F 1" A0 2-2593-2A, IA C 642-2 ACAD l 2-2559-11A, 12A c 642-2 APPROVED l SEP 12 D79 l l C C. O. S. o

QTS 150-57 Pavist.m a e F :.;IT.'. AT l Cl LS 'i,T I i:;6 L. l cil V/ UJS N'; - 3 E R EL:V AI' WT4 StIE tr;;ein P2stT!ON P3!0 C E 5 C.'. ! P T ! 0.9 X-35; 592'4" 7:? (TI?s withdem n) Tt? crives X-353 X I X-330 X-35E X-33. Purge Valvas C 71-2 Tl? Purge l X 330 4 ' X-36 613'6" 1S.5 4" 2-0301-94 0 83 CR0 aeturn 2-030!-C6 C 83 2-0301-59 0 83 I 0 1" S0-122 C 41 CRD lasert X-37 610'3" 195 A thru D to 50-123 C 41 614' I X-33 610'3" 195 1" S0-120 C 41 C?.0 withdraw A thre D to 50-121 C 41 614' X-33A 604'7" 160o 10" MO 2-1001-23A C Si RH?. spray Supply 2-1001-25A C 81 h3 2-1001-23 C 81 P M). Dischar e to M3 2-1001-21 C 81 P.a64aste i X-333 625' 200o 10" na 2-1001-233 C 81 fha sprey s'epply M0 2-1001-263 C 81 2-1001-233 C 81 X-40 617'6" 1" 2-263-2-21A-D 0 77-2 Jet Pep Flow A th-.: D 2-263-2-22A-D 0 77-2 2-263-2-303-W 0 77-2 X-41 625' 233o 1" 2-0220-43 LC 77-2 Primary sar:ple l A0 2-0220-44 C 77-2 E A0 2-0220-45 C 77-2 5 .<- 43 A-C 625' 1200 1" FCV 2-8301A C 76-1 02 Analy:ar FCV 2-88013 C 76-1 FCV 2-8301C C 75-1 I FCV 2-8302A C 76-1 FCV 2-88023 C-76-1 l FCV 2-8302C C 76-1 21 sampla Lines C 76-1 CW sample Manifolc l l X-43D-Y 625' 1200 X-4L 625' 150 2-4799-176 + 21 C 71-2 spares to cw l othar manual valves X-47 .641'6" 293o 2" 2-1101-30 C 82 53tc i 2-1101-31 LC 82 2-1101-34 LC 82 I APPROVED SE?121979 l .Q.C.C 0 P l

Q"5 150-57 ?wision 5 I!%i: n GC TIGra L i t. i V A L';I I J

  • ,M I ).

ELIV 7,Z i!TT 4 stII tiUMBER POSIT!ON P ;l ) 025312710N y 'd 64386" 630 l.s t: u. :en ta ti on I 43: 1" 2-263-2-133 0 77 (X-49 is a s are) 1" 2-263-1-413 0 77 493 1" 2-263-2-163 0 77 I 430 1" 2-263-2-143 0 77 430 1" 2-263-2-123 0 77 49I 1" 2-263-2-10 0 77 x-30 591'3" 303 Main & RCIC Steam I 50A 1" 2-220-11C 0 60-2 Flow Measurement 503 1" 2-220-12C 0 60-2 500 1" 2-220-110 0 60-2 I 503 1" 2-220-120 0 60-2 50E 1" 2-1301-14A 0 89 507 1" 2-1301-143 0 89 I x-3! 610'3" 900 Reci rc to RHR 51A 1" 2-220-66H 0 77-2 Inter 1cck 5!3 1" 2-220-66.: 0 77-2 (.(-51E is a spare) Sic 1" 2-220-663 0 77-2 Sic 1" 2-210-663 0 77-2 51-1" 2-2599-25A 0 642-2 AC.20/ CAM inst ).- 5 2 610'3" 270 Recirc to RHR I 52A 1" 2-220-66G 0 77-2 Interlock & DW 523 1" 2-220-66E o 77-2 P ressure 520 1" 2-220-66C 0 77-2 l 5 '.0 1" 2-220-66A 0 77-2 52E 1" 2-1001-33A 0 76-1 2-1001-69A 0 76-1 I

52. '

1" 2-1001-333 0 76-1 2-1001-633 0 76-1 X-1000 611'6" 195 1" 4 Manual valves C 71-2 spares to tu SO 2-2499-13, 23 C 641-2 ACA0/C.in I 2-2499--73, 8B C 641-2 2-2599-253 0 642-2. A0 2-2599-23, 13 C 642-2 I 2-2599-113,.12a C 642-2 x-1C4E 611'6" 195 1" 6 Manual valves C 71-2 spares to cv x-203A 18" A0 2-1601-60 C 76-1 Vent from sup-I 270 20" A0 2-1601-20A C /6-1 A0 2-1601-61 C 76-1 pression Chamber x-205 A0 2-1601-203 C 76-1 2-1601-73A C 76-1' I 2-1601-73B C 76-1 PS 2-1622A C 76-1 I ~ PS 2-16223 C 76-1 PT 2-1623 C 76-1 APPROVED I SEP 121973

o. c.c. s. 7 g

E 5, CT3 15?-;7 I P..e.ii i, 5 ~~' Ti. :7-2A T l G:e LO:: sit 01 L i;;E \\ h' ' : ..-iER F_LE" A2t."d M 5:2E i:T 3E3 PO5!T!C1 ? 10 CESC'i? *C5

,r 5 153 1"

Torus Lctal Inst Vivs C 76-1 Torus La el 0 X-2:CA 235 14" t10 2-lC01-ISA C 78 P.:i A3 Te s t Line 1:0 2-1001-36A C 81 5 Min. Flow MG 2-1001-3LA C 81 I X-2!C3 1240 14" HO 2-1001-163 C 81 RHA, Core Spray. NO 2-1001-363 C S1 H?Cl, P.CIC, Te M0 2-1402-33A C&OOS 73 & Min. F!cw I M0 2-1402-383 C0003 73 No 2-2301-14 C 87 2-2301-93 C 87 I MO 2-1301-60 C 89 NO 2-1001-343 C 61 I-X-21iA 127 6" MG 2-lC01-37A C 81 RHR Torus Spray 0 0 6" M0.2-1001-373 C 81 P.HR Torus Spray X-2113 233 X-2:2 490 8" 2-1301-53A C 89 RCIC Tt.rbine Exhau: 2-1301-64 LO 89 X -- 215 2160 i" 2-4739-160 0 71-2 Torus Ins t. tb , X-217 2133 i" FCV 2-8801D C 76-1 0 Ana ly.:e r ~ 2 FCV 2-83020 C 76-1 -:- 2 r) 380 24" 2-2301-klA C 87 H?CI Turbine I ^ X-221 2-2301-74 LO 87 Exhaust 240 2" 2-2301-71 LO 87 Condensa te f ron h? 2-2301-413 C 87 Drain Pat I 2-2301-33 Lo 87 2-2301-47 LO 37 X-222 690 2" 2-1301-55 LO 59 Cendansata frem a; 2-130.1-533 C 89 Drain Pot I X-223A 1650 24" M0 2-lC01-7A C 79,81 Shutdown & RHR Pu.- MO 2-1001-73 C 79,81 Suction 2-1001-6A LO 73,81 1 2-1001-159A C 79,81 X-2233 195 24" Mo 2-1001-7C C 73,81 Shutdcwn & RHa "uw NO 2-1001-70 C 79,81 Suction 1 2-1001-63 LO 79,81 2-1001-1593 C 79,81 X-224A 180 18" MO 2-1402-3A C 78 Core Spray Pump 2-1402-7 C 78 Suction l 2-1402-21A C 78 2-1402-34A LO 78 X-22L3 341 18" MO 2-1402-33 C 78 ' Core Spray Pump 0 I 2-1402-10 C 78 Suction 2-1602-218 C 78 2-1402-343 LO 78 APPROV~D c c p t *.y q 1q % =.. .Q.C. C. 9 =- I.

3:

0. S 150-57 Fevisica 5 I

-. U % f. C.'s L ;..iii..i L i..E Val'.I m2 E' E'! t Z l.' U TH SiII f:UM3i?, P05I7: M P ;I D CIS C 1! ?7i C'i 0 24" MO 2-2301-35 C 87 H?CI ? cmp Suction >-2;5 13 I rio 2-2301-36 C 87 2-2301-37 C 27 2-2301-56 LO 87 l 2-2301-91 C 87 l x-226 71 8" HD 2-1301-25 C 81,89 RCIC Pump Suctica 0 2-1301-23 C 29 2-1301-56 LO 89 I 2-220-48 0 77-1 D rywel l Equip. U.a Sc.mp Leakage 2-220-49 0 77-1 Path from Reactor I Vessel (Head vents l l X-227A 68 1" A0 2-2599-3A C 642-2 ACAD/CAA 2-2599-13A, 14A C 642-2 l E S 2-2493-3A, 4A C 641-2 E 2-2499-9A, ICA C 641-2 X-2273 2010 1" A0 2-2599-33 C 642-2 ACAD/ CAM 2-2599-133, 143 C 642-2 I SO 2-2499-33, 43 C 641-2 2-2499-93, 103 C 641-2 I 1 l I Verifled Operating Engineer I l l l I I I l i h?YRCVED (final) 973;n,,.97,g i-1 f .^70

.E E. cts 150-53 I f l'/ 3$On

1.,')

7 U;ii T 2 1.' L'.T CC:t?LETI C:s vat.k I LI:.rJ? !u!y I_,1 'AT!::6 '! A'. ; I '":'3 3 P O S I TI 0.'i P3i0 I ____. _- e. X MO 2-220-30A Opan 60-2 X-73 MO 2-220-903 Open 60-2 X-70 M0 2-220-90c Open 60-2 X-70 MO 2-220-900' Open 60-2 X-E MO 2-220-3 Open 60-2 I M0 2-220-4 Open 60-2 X-9; MO 2-1201-80 Open 88 X-14 MO 2-1201-2 Open 83 MO 2-1201-5 Open 83 X-21 2-L699-L6 Open & R/S 72 2-4699-75 Open & R/S 72 l X-22 2-4799-163 Open & R/S 71-2 X-25 MO 2-1601-37 Closed 76-1 I A0 2-1501-5s Closed 76-1 l A0 2-8303 Open 76-1 l A0 2-3304 open 76-1 l X-32 A0 2-4720 Open 71-2 A0 2-4721 Open 71-2 Y-41 A0 2-0220-44 Open' 77-2 A0 2-0220-45 Open 77-2 X-203 PS 2-1622A Open 76-1 PS 2-16223 Open 76-1 PT 2-1623 open 76-1 X-2103

MO 2-1402-3SA Open & R/S 78 l

it0 2-1402-383 Open & R/S 78 g X-k3 FCV-2-3301A-C Open 76-1 FCV-2-8302A-C Open 76-1 APPROVED I _i_ SEP 121979 I c c.0.s o

1 C.73 130-33 .. v i.t cn I, i ? 5:.irai,7 x c.~e y A.v1

xa.a m S E ?.

PosiTIc.I T:10 )-217 PCV 2-63010 Cyan 76-1 FCV 2-83020 Open 75-1 l x-223A Mc 2-1001-7A open 79, 81 I t10 2-1001-73 Cpen 79, 8! X-2233 NO 2-1001-70 Open 73, 81 I ito 2-1001-7D Open 73, 8! X-224A HO 2-1402-3A Open 78 X-2248 M0 2-1402-33 Open 78 I 2-220-48 Closed 77-1 2-220-43 Closed 77-1 I. I Verified Dpe ra t i n g E.~.g i n ee r l i I I l I ~ I I I AP.witOVEO (finn 1) SEP13)O O q.c.0.S.9. I

w ~..... _. (TS 150-53 I.O /I 3 I 7 k 1 9 -. %,-. ., t. u.. c..... e.- - ; p s.1. ?..i.a. aei-J ?./ 1..', art.. POST-TEST C:'IC:n.! 57 I 1. t.r ; ave th e prassuri za ti ca pipi.,: cnd co.,n=cticn3.4i thin ar.d cutside of the P.sacter 9uilding and s ora for fu:ura t.2e. Assure that seccadarf I con ta i n.nn t is raintained through the fire h=ader penetratica. Verified I 2. Close all supprassion chamber to drywell vacuum breaker valves and locally verify the valve potiticas as closed at the test panet. j verified l 3 close all hatches opened after the ILRT. Verifled JB I I I I I I I I I APPP.0'/ED I (final) Q k#. \\. - I

C.75 150-310 I F.evision 4 1?C'./T 0.I?.;Tl.'is DP* UldtiT July iTic i '.17-Ti5T C;H.'"'.'_ ! s? ) I i 1. ?ct tha primar/ can t:irmea t sy ste is and talves b.ick in the p.e-test c:afiguratica by cc:rpieting QTS 150-35 (3). Verified 2. Return to service the nitrogen take-up for the TIP drives. Verified 3 Secure the ccmpressors used for ?rimary Centainment pressurization. Ve ri fied 4. Close the service air drop cpened prior to the test on the reactor 'cuilding I second floor. Verified 5 Close the instrunnt air receiver, 1(2)-4707, drain. Varified 6. Open the manual supply air stop valves to 4722M S. Verified Record CV floor and equip. ent drain sump levels af ter the containment is 7 m l opened folic ing the test. I Verified Exercise DW-torus vacuum breakers f rem local test panel and assure oper-o.

ability, i

Verified I I APPROVED I 7 01 o c.,fg (final) w C6

    • su l
p. e. e,. a..--

I e -.. - ~

0.;. 15'-5:I I P. - e t. i. 2 1."CL.'T I 3 7 YJ: -hi "..'.. fiTI:We:I J.: ', i /3 v3. ..a C... 2.... f a,. - n I cali*ratic; of c?] ini t u.--n ta :!cn uti l ! 2d I, 2 3.-fa rc. T., pc.; t-m ; s p.); ch e:'; a ?ce the cest in :!:e priyary contain - a t. Verfied 2. Remove all test instrumen tation f rora the drywell and torus and store for future use. Verified 3 Install pipe caps on the pressure sensing lines above the inc.er personnel l air lock door u:ilized for a temporary instrument penetration. l Verified f,. Return to service, open the root valves, and replace the vent caps en the following drywell p. essure switch instrument isolation valves: VERIFIED PS 1001-33 A, B, C & D I PS 1,001-89 A, B, C & D PS 1001-90 A, B, C & D PS 1031-83 A, B, C & D l PS 1001-95 I PS 1622 A & B f I l PT 1623 t i l ' PT 1624 DPT 8741-51 { I A? PROVED (final) $EP121979 ,.c... I -w I

'5 I. 0,T : 150-512 I ?:.<T-1:n 2 lPCLST TE'Me:! CAL ST.U~ Jul, 1973 ?OST-TEST C!iEC:'Lis? .u 1. Obtain a ccgy of the post-tas: calibration data perfor,ed c-the I? LRT instre.antacion. Ve ri fied Grify proper and complete recoval of all ec;uip.mant and ins rementation 2. utilized for the test. Veri fled 3 Verify the post-test valve lineup, QTS 150-s6(8). Verified 4. Verify that any hatches opened for the IPCLRT are local leak rate testad I prior to unit startup. . Verified I I I I I I APPROVED -i-(finai) ggpig7973 Q C.O.S ' I

1. 2.J J.V'/ 0 3, a

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\\ // T.,- l-I Q."S 150-1 L Erv.sion 6 INTICRATED PRIM.W CONTAIN'2.NT Au ust 1979 LIAK RAri T25T ID/ID r A. "y2 POSE This test procedure is intended to establish detailed steps to be followed in deterraining the integrated dryvell and suppression chamber leakage I rate. L B. REFERENCES .c 1. Quad-Cities Nuclear Power Station, Units 1 and 2, Final Safety Analysis report, Section 5 including Amendment 11. T l, 2. Sargent and Lundy, Inc. drawings. a. M-13, sh. 1 (M-60, sh. 1) b. M-13, sh. 2 (M-60, sh. 2) { c. M-15 (M-62) L d. M-24, sh. 2 (M-71, sh. 2) r e. M-23 (M-72) f. M-33 (M-75) b g. U-34 (M-76) h. M-35 (M-77)

i. M-36 (M-73)

(

j. M-39 (M-51) i h.

M-40 (M-82) i F i 1. M-41 (M-83) 'F m. M-43 (M-85) n. M-46 (M-87) o. M-47 (M-SS) w p. H-50 (M-S9) l q. M-58, sh. 3 APPROYED [, SEP1219T3 _1 .Q. C. O. S n. ll =

[* QTS 150-1 g* Revision 6 r. 11 - 1 9 (M-400) s. E-20 (.1-401) e L. t. B-22 (!!-403) u. B-23 (11-404) v. B-235 (M-601) [ 3. 10CFR Part 50, Appendix J, Primary Reactor Containment Leakage Testing for Wter-Cooled Power Reactors. [ 4. ANSI N45.4, Leakage Rate Testing of Containment Structures for Nuclear Reactors. g-5. ORNL-NSIC-5 Volume 2, U.S. Reactor Containment Technology (A Compilation { of Current Practice in Analysis, Detiga, Construction, Test and Operation). 6. TID-20583, Leakage Characteristics of Steel Containment Vessels and I the Analysis of Leakage Rate Determinations. L 7. Topical Report BN-TOP-1, Testing Criteria for Integrated Leakage Rate Testing of Priinary Containment Structures for Nuclear Power Plants. C. _PSEREQUISITES 1. A signed and dated events log must be initiated by the responsible Tech Staff Engineer and will be kept up to date by the cognizant engineer on shift. [ 8 2. A familiarization by Tech Staff personnel of all regulations, standards, { and procedures applying to the IPCLRT including, but not limited to, those listed in REFERENCES. 3. All as-found local _ leak rate tests on valves, seals, and penetrations of the primary containment must be completed before the IPCLRT can E begin. ~ NOTE [ Local leak rate tests must be done prior to and after any repair work being done on any [ penetration or associated isolation valve. In the special case of double gasketed seals, local leak rate tests must be done peior to opening the seal and after closing [ the seal. 4. All pre-test check off sheets must be completed and returned to the responsible Tech Staff Engineer prior to the start of the test. APPROVED OEP12 973 ,.Q.C.0.5.!?.

r-QTS 150-1 Rsvision 6 NOT2 u The work to be performed in these check off [ she-ts involves various deoactments within L the station. It also involves items which ray be scheduled months or core in advance or the test. It is the responaibility of ~ the cognizant Tech Staff En.gineer ta schedule the items and coordinate the work so as to facilitate the execution of the IPCLRI. 5. All instruments to be used for the IPCLRT will be calibrated over the full range of expected use prior to their placement in the primary [ contaicment for each test. The calibration must be in accordance with CECO Quality Procedures. r 6. The pressure suppression chamber water level as monitored on LI-X-1602-3 on panel 90X-3 should indicate approximately 0.0 inches. L 7. Tne reactor vessel water level as monitored on the YARWAY level indicators [ LI X-263-100A and LI X-263-100E on panel 90X-5 should indicate approxi-mately +35 inches. 8. Shutdown' cooling should be placed in continuous operation well in advance of the commencement of pressurization. Reactor water tempera-ture must be less than lio'T and vary less tha's + 3 F durict the test. l Water temperature data vill be obtained throughout the test period. [ i D. PTif. CAUTIONS E

1..All personnel not directly involved in the leakage test will be prohibited access beyond established barriers in the reactor and turbine buildings.

However, this will exclude activities which are essential to plant operation and emergencies. 2. All station radiation protection and safety practices and rules will be strictly followed for this test. 3. All requests for equipment out-of-service for repairs during the test must be evaluated with respect to the fact that the primary containment will be under approximately 48 PSIG. 4. At no time during the period of pressurization, at test pressure, or depressuri stion of the drywell and pressure suppression containment [ will travel of the reactor building crane be allowed over the reactor cavity area. Prior to perfoming any pressurization of total drywell and pressure 5. suppression containment, isolation of pressure sensors is mandatory to prevent automatic actuation of ECCS Reactor Protection System trips. The pressure switches will be isolated at their respective instrument racks, and the vent caps removed. [ A?PRoy10 - .Q.c.o.s.a.

QTS 150-1 Revision 6 I 6. !.2'ITATIC?.S GD.iCTONS a 1. The integrat.ed leakage rate test will be conducted at or abne the calculated. ui.aum pen accident pressure of .'+d PSIG. Time duration of the test i,ressure settings will be a minimum of 14 hours of continuous e laakage rate measuremeats. 2. The method selected for conducting this Class A test is the absoulte pressure-temperature c :thod. The intention of a Class A test is to measure the primary reactor containment overall leakage rate af ter the f containment construction has been comoleted and is ready for operation L and at periodic intervals thereaf ter. p 3. Successful completion of this test will obtain all of the data necessary L to demonstrate the integrity of the primary containment consistent with all station, license, and Nuclear Regulatory Commission requirements. The measured leak rate shall be less than 75% Lp. a. b. The measured leak rate at the upper 95*.' confidence limit, which includes appropriate consideration for random measurement errors L shall be less than 0.75 Lp. .r 4. Drywell pressurization will be discontinued if leakage above the maximum allowable rate is obvious or the drywell pressure cannot be increased. Repairs will be made and the test restarted. NOTE Eefore terminating th2 test, a leak rate must be determined for reporting to the ,u NRC if the leak rate is above Lp (1% per day) as defined in the Technical Specifications. 5. If the test is terminated (either by depressurization or by suspensic.. of data aquisition), or if the test goes to normal completion and the calculated leak rate is above Ip, then a Reportable Occurrence Report must be issued. (TS) [ 6. During the period between the completion of one Type A test and the initiation of the containment inspection for the subsequeat Type A test, repairs or adjustments shall be made to components whose leakage r exceeds that specified in the Technical. Specifications as soon as [ practical af ter identification. [ A??ROYED F SEP10i979 L O C.C. S. 7. r b.

r QTS 150-1 L., Revision 6 r k 7. If during a Tn e A tc.it, iaclwli.y the supptee ntal induce.i 1.eakage test, potentially cuenive Ie. ~<aze paths are identifted hich wiil interfere with satiM actory completion of the test, or which result in 4 the Type A test cot neeting the acceptance criteria, the Type A test shall t,e terminated and the leakage through such paths shall be measured using local leakage testing methods. Repairs and/or adjustments to equipment shall be made and a Type A test performed. The corrective action and the change in leakage rate determined from the tests and overall integrated leakage determined frora the local leak and Type A tests shall be included in the report submitted to the Commission. 8. Closure of containment isolation valves for the Type A test shall be accomplished by normal operation and without any preliminary exercising or adjustments. Repairs of maloperating or leaking valves shall be made as necessary. Information on any valve closure malfunction or valve leakage that requires corrective action before the test, shall be included in the report submitted to the Commission. (TS) 9. The containment test conditions shall stabilize for a period of four [ hours, and until the change in the average volume weighted primary containment temperature is less than 0.5 F per hour, prior to the start of the leakage rate test. r 10. All vented systems.shall be drained of water or other fluids to the extent necessary to assure exposure of the system containment isolation valves to containment air test pressure and to assure that they will be subjected to the post-accident differential pressure. Systems that are required to maintain the plant in a safe condition during the test shall be operable in their nor:nal mode, and need not be veuted. t - [ Systems that are normally filled with water and operating under post-accident conditions, such as the containment heat removal system, need not be vented,

11. Results of the supplemental induced leakage test are acceptable provided that the difference between the supplemental test data and the Type A test data is within 0.25 Lp:

[ 1 0.25 Ip 0.25% per day = 122.4 scfh = 2.04 scfm [. a. If results are not within 0.25 Lp,.the reason shall be determined, L corrective action taken, and a successful supplemental test performed. 12. A general inspection of the accessible interior and exterior surfaces [ of tne primary containment structure and components shall be performed ( prior to any Type A test to uncover any evidence of structural deteriora-tion which may affect either the containment structural integrity of leak tightness. If there is evidence of structural deterioration, i Type A tests shall not be performed until corrective action is taken. i Such structursl deterioration and corrective actions taken shall be { reported as part of the test report. l

13. The Integrated Primary Containment Leak Rate Test will consist of six phases. Each phase will have a definite starting and ending point and l

L, is so defined because of the different types of activities that will occur in each. p p,g g g i 3 lgg ~,. _ _.

y QTS 150-1 Revision 6 [. 7 a. The pr::paration phase. I b. The pressurization phase. F [ c. The 24 hour leakage rate at 43 PSIG phase. d. Tce induced leakage phase at 43 PSIG. c. The depressurization phase. f. The cleanup phase. L NOTE The signed and dated events log started by the responsible Tech Staff Engineer will be kept up to date at all times by the cognizant enginear on shift and updated at least once per shif t. .f F 14. Raw temperature, pressure, and dew point data should not be rejected I statistically, but may be rejected and not used in the final calcula-tions provided there is a good physical reason for the rejection. Data rejected, including the cause or probable cause for the bad data, are to be documented. If the validity of certain data is suspect, but no physical reason is found, then a statistical rejection technique uay be applied. (See'.US 274 Appendix D for Data Rejection Cricerion). A data point may be rejected if it is expected to occur statistically l less than 5% of the time. The statistical rejection of more taan 5% of a set of data should not be allowed. i 15. Measured leakage rates must be corrected for volume changes due to I various level increases (sumps), for any isolated leakage paths, and l for penetrations in use during the test, such as shutdown cooling suction. 16. The corrected measured leakage rate at the 95% upper confidence level must be less than 0.75L,. l l F. PROCEDURE r. i 1. Test Preparation. u e a. Prior to sealing the drywell and pressure suppression chamber for pressurization, the pre-test portion of the following checklists l must be completed. l s. APPROVED bb?12l370.Q.c.o.s.R.

r.- QTS 150-1 Revision 6 6 I .C.i.fI. EI5T EEP.uTME.'iT VERIFII0 g QT5 150-5L Maintenance L QTS 150-S2 Operations QTS 150-S3 Instrument Mechanics QTS 150-S4 Technical Staff r QTS 150-SS Operations and Technical Staff F Pre-test preparation complete 2. Pressurization Phase. IP a. Begin p::essurizing the drywell and pressure suppression containment. b. Af ter the system is at 2 PSIG, inspect all appropYiate penetrations and valves for excessive leakage. Special attention should be paid to the drywell-to-torus vacuum breakers position indication, penetratious which cannot be local leak rate tested, drywell vent and purge valves, TIP penetrations, drpell sample rack valves, L dryvell cooler damper controls, and the dr'/well personnel access. r c. If sources of leakage are found or the primary containment instru-mentation indicates excessive leakage, pressurization should be stopped and this leakage should be estimated. If repairs cannot be achieved without deoressu;i.zation, the dryvell and pressure suppression containment should be vented to facilitate repairs. NOTE The results of the local leak rate test or the estimated leakage rate from all repaired p leaks must be totaled and added to the L results of the 24 hour leak rate calculation to determine a leakage rate at the beginning of the test. [ d. Tha pressurization phase is complete when the average volume weighted containment temperature is found to change less than ' F 0.5 F in a one hour period with the primary containment pressure at or above 48 PSIG. Temperature stabili stion may require addi- ,w tional pressurization' until a balance is achieved. A MINIMUM four 7 hour stabilization period is required. NOTE F l A continuous monitoring of the containment , penetrations should be maintained during the pre surization phase. If any leaks are APPROYED found, an estimate of the leakage rate must E' be made before any repairs are attempted. $EO121979,Q. C. O. S. 9

QTS 150-1 b Revision 6 ~. Test pressurization ecralete. Rau ve pressurinatica flange at the drywell spray header and e. in.; tail blind flange. 3. 24 Hour Leak Rate at 48 PSIG. a. Record the following data at least once every hour: (1) Time and date. (2) Ambient temperature, pressure and relative humidity of the reactor building. (3) Absolute pressure of the primary containment. (4) Air temperatures inside the drywell and pressure suppression [, chamber. (5) Dew point temperatures inside the drywell and pressure { suppression chamber. (6) Reactor water temperacure. v. ~ L (7) Reactor water level. (S) Torus water level. (9) Outside barometric pressure. b. Cale : late, using either the hand method (an example of which is in QTS L50-Y5), or with the aid of a computer or calculator, the following information: (1) Average volume weighted partial pressure of water vapor in the containment. (2) Absolute dry air pressure in the containment. l (3) Average containment volume weighted temperature. l (4) Measured per cent leakage (hourly). l (S) Heasured per cent leakage (total time). l (6) Linear least squares fit per cent leakage and 95% confidence limits. (7) Average temperature by volume. l (8) Average vapor pressure by volone. APPROVED W W SEP 121979 Q. O. 0. S ' s e

QTS 15'a-1 r Eevision 6 I Reco d the a5ym c 31 ulated iafor:uti..: on d.it a :.hets o f the t;.. c. L ionn! in the Cni 150-5 secti n of thi, pr cedure, or re sin Lb ceg :ter priataut. d. Plot the information in "c" as a function of ti. e duriag the test. a e. Leahag:. rate measarements will be made at an average contain:nent pressure (over the time period of the test) of at least AS PSIG. Data taking will continue for at least 24 consecutive hours. E f. From the third data set through the 24th hour data set, the percent leakage (total) will be linear least squares fitted. The result is called the stat:stically averaged leak rate. (See QTS 150-T3 4 for hand method of calculation). L NOTE If any data sets are to be eliminated frcm the leak rate calculations, the reason (s) for doing so must be justifiable (ie. pressure [ sensor computer card failure yielding 0.0 psig, RTD bridge network failure yielding erroneous temperature values, etc.) L g. Co'npare the 24 heur leakage rate to L7 (0.75% pet day) aad L, (1.0% per day). If the leakage rate appraaches L ' ""*#I *ff #E T r should be made to find the source of leakage and repairs cade to { stop it'. The 24 hour phase should then be restarted. Phase 3 ends with the calculation of the 2!th hourly set of infor: nation. [- If the leahage rate is below L,,, phase 4 can begin iu: mediately. If not, the responsible leais cast be repaired and the 24 hour phase repeated. [ 43 PSIG test phase successfully completed. W Total Time Indicated Leak Rate %/ Day Verified 4. 48 PSIG Induced Leak Rate Phase l l Phase 4 is the induced leakage portion of the IPCLRT. During this phase, a deliberate leak of known magnitude will be superimposed on f the leakage rate already calculated during the 24 hour phase. This RJ will provide reassurance against any uncertainties associated with the performance of the leak rate test. This leak should be of th2 same size as the 24 hour measured leak rate. The new leakage rate is then calculated and should appro:<imately equal the 24 hour leakage rate plus the induced leakage rate. This phase then acts as a verification of the accuracy of the data c.btained in phase 3 (see Step D.12). l a. Request the Radiation Protection Department to obtain a drywell air sample prior to beginning this phase of the test since airflow f through the flometer will be vented directly to the reactor he building. APPROVEC ,9_ e r p 1. c. n q,. .s l .Q C.O. 9. O

a l QIS 150-1 Revision 6 w. r [ b. !. r.. - 1 c h 1.e d >. 2 a2 in t>> u.'.nra:rl t est f ar at l>ea st four hstr e In reddi;w.t, acord the ilo. r.:t2 as r.: :asured b > the - f i v....e t e.. L c. If the ialuced leakage c.an be successfully detected by an increase in the calculated leak ra 2, this 1:!.a.Se of th:e test may be terninited E af ter four c'casecutive hours of dat= 6= been obtai.ied. L d. If the induced leakage cannot be satisfactorily detected af ter four hours, an evaluation of the possible cause should then be investigated, corrective acticas taken, and the induced leakage phase restarted following repressurization and restabilization at 48 PSIG. If the results of the leakage measurements obtained prior to the introduction of the superimposed agree with step D.12, the accuracy of the contalument leakage measuring system is verified and the leakage rate results validated. In.!cced leakage successfully detected.. [ Induced Leak Rate %/ Day Indicated Leak Rate %/ Day Verified 5. Depressurization Phase. Phase 5, the depressurization phase, can'begin with the end of tha successful completion of the induced leakage phase. a. Isolate the flowmeter from the containment environment. The containment atmosphere vill be vented either through the Reactor Building Ventilation Exhaust, or to the Standby Gas Treatment System. The venting path will depend upon the results of a dryvell I sample. This sample will be taken by the Radiation Protection Department. (1) Reactor Building Vent System. (a) Verify reactor building vent system is on. (b) OPEN butterfly dampers A-5772-54 and A-5772-53 (or B-5772-54 and B-5772-53) by racking out the breaker for the A purge fan (or 3 purge fan). ~ (c) OPEN A0-1601-24. Verify that A0-1601-23, A0-1601-63, and A0-1601-60 are all CLOSED. (d) OPEN A0-1601-61 and A0-1601-62. APPROVED SE?l2FR> o c.c. s ~'

QTS 150-1 Revisica 6 f (e)

  • '.in canw.nuent p : mare hn b.- a reduced to less than L

5 i = L2, 022.i Au-16el-2.; .d.%-; Y:1-60. F (f) ' Gen contair.n:-nt has been depressurized, CLOSE the following v:sives: A0-1601-23 [ A0-1601-62 A0-1601-60 A0-1601-61, A0-1601-24 (g) CLOSE butterfly dampers A-5772-54 and A-5772-53 (or f B-5772-54 and B-5772-53) by racking in the breaker for L the A purge fan (or B purge fan). (2) Standby Gas Treatment System (a) START both A and B S3GTS Trains. [ (b) C?EN A0-1601-63. Verify that A0-1601-23, A0-1601-60, and A0-1601-24 are CLOSED. F (c) OPEN A0-1601-61 and A0-1601-62. 4 -(d) Ren containment pressure has been reduced to less than 5 psig, OPEN A0-1601-23 and A0-1601-60. (e) When containnmnt has been depressurized, CLOSE the I following valves, if desired. { A0-1601-23 A0-1601-62 f A0-16dl-60 W A0-1601-61 A0-1601-63 (f) S; / one of the SBGTS Trains, if desired. b. After depressurization is complete, normal station drywell entry procedures should be followed for the initial drywell entry. c. k'ith the approval of the Rad Protection Department, the first subsequent drywell entry should be by Technical Staff personnel. The purpose of this entry is to note any deviation from-original position of any instrumentation or ventilation fans used for the test. Any deviations found will be octed and accounted for in the log book. d. Only af ter, the Technical Staf f inspection will the Maintenance Department and Instrtunent Mechanics renove all test equipment f rom the primary containment. APPROYED SEP 101979 { c.c.c.s.'

QIS 150-1 '.levision 6 6. Clea: tup Ehu. Toil ning ::.e (m. t.he fully.'i a; chechW a.:.u t he cm.pl ated: 4 C E C:: LIST DEPA.4T.5 hT U.RI?ICATION QTS 150-S9 Maintenance L QTS 130-510 Operations QfS 150-S11 I:.strument Maintenance QTS 150-S12 Technical Staff [ Post test checklists completed Verified: G. C:!ECKLISTS [ 1. QTS 150-Sl; IPCLRT Maintenance Department checklist. F 2. QTS 150-S2; IPCLRT Operations Department checklist. 2. QTS 150-53; IPCLRT Instrument Maintenance Department checklist. 4. QTS 150-S4; IPCLRT Technical Staff Checklist. 5. QTS 150-S5; Unit 1 IPCLRT Valve Line Up. [ 6. QTS 150-S6; Unit 1 IPCLRT Completion Valve Line Up. 7. QIS 15C-S7; Unit 2 IPCLRT Valve Line Up. 8. QTS 130-5S; Unit 2 IPCLRT Ccmpletion Valve Line Up. 9. QTS 150-S9; IPCLRT Maintenance Department Post-Test Checklist 10. QTS 150-510; IPCLRT Operations Department Post-Test Checklist.

11. QiS 150-Sil; IPCLRT Instrument Maintenance Department Post-Test Checklist.

12. QTS 150-S12; IPCLRT Technical Staff Post-Test Checklist. 13. QTS 150-S13; IPCLRT Data Sheets. H. TECalICAL SPECIFICATION REFERENCES l 1. 3.7.A.I. 2. 3.7.A.2. 3. 4.7.A. E ( .A?PROVID Q 01 Adiv

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^ [' (final) ,Q. C. O. S. r: n e:}}

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