ML20205S554
| ML20205S554 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/31/1986 |
| From: | Notigan D GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20205S489 | List: |
| References | |
| NUDOCS 8704070056 | |
| Download: ML20205S554 (39) | |
Text
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i l
I REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST OYSTER CREEK, 1986 i
i Prepared By:
D. V. Notigan 0704070056 070327 PDR ADOCK 05000219 PDH p
TABLE OF CONTENTS Introduction Section Page Number General Data 1
Primary Containment Technical Data 1
Type A Test Data 2
Supplemental Test Data 2
Definition of Terms 3
Type A Test Methods and Test Results 4
Type A Test Acceptance Criteria 8
IV.
Supplemental Test Results 9
l V.
Supplemental Test Acceptance Criterla 10 l
VI.
Type A Test Summary and Conclusion 12 VII.
Type A Test Chronology and Highlights 13 VI!!.
Type B and Type C Local Leak Rate Tests 16 IX.
Secondary Containment Leak Rate Tests 23 Attachment !
- Calcu14tional Methods 24 i
Attachment !! - Leak Rate Detection System 29 Attachment !!! - Supporting Test Data 34
INTRODUCTION The Oyster Creek, Primary Containment Integrated Leak Rate Test (PCILRT) t was conducted on the dates of October 25 -29, 1986.
The twenty-four (24) hour l
Type A Test was performed in accordance with 10CFR50, Appendix "J"; the applicable Oyster Creek Technical Specifications; and, the approved Station Procedure number 666.5.007, " Primary Containment Integrated Leak Rate Test".
Guidance in conducting the test was provided by ANS/ ANSI 56.8 - 1981.
Included herein, in accordance with 10CFR50, Appendix "J", and Oyster Creek Technical Specifications, is a summary of pertinent data as follows; Type B and Type C local leak rate test results; Secondary Containment Leak Rate Test results; an analysts and interpretation of test results; and, a Type A Test chronology. A description of the leak detection system, calculational methods, and supporting test data are provided as attachments. Additional test supporting data is available for review at the station site in accordance r
with ANS/ANS! 56.8 - 1981.
l l
i
I.
GENERAL DATA OWNER:
Jersey Central Power & Light / General Public L'tilities OPERATOR General Pubile Utilities Nuclear 00CKEiNO:
50 - 219 LOCATION:
U.S. Highway Route 9, Forked River, New Jersey l
CONTAINMENT DESIGN:
Mark I, General Electric Co.
TEST COMPLETION DATE:
October 29, 1986 PRIMARY CONTAINMENT TECHNICAL DATA l
CONTAINMENT NET FREE AIR VOLUME (Cubic Foet) 311,392 DESIGN PRESSURE (psig) 62 (Drywell) 35 (Torus) 1 DESIGN TEMPERATURE ("F) 281 (Orywell) l 175 (Torus)
DESIGN ACCIDENT PEAK PRESSURE, P., (psIg) 35 CALCULATED ACCIDENT PEAK TEMPERATURE ('F) 275 (Drywell) 145 (Torus).
TYPE A TEST DATA TEST METH00:
Absolute 1
l DATA ANALYSIS:
Mass Plot TYPE A TEST PRESSURE 36.055 PSIA MAXIMUM ALLONABLE LEAKAGE RATE: L.:
0.567 %wt./ day MINIMUM TYPE A TEST DURATION:
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> MEASURED TYPE A TEST LEAKAGE RATE, L..:
0.331 %wt./ day UCL-95 CALCULATED LEAKAGE RATE:
(Level Corrected. Type 8 and Type C 0.338 %wt./ day LLRT adjusted)
SUPPLEMENTAL TEST DATA CALIBRATED LEAK SUPERIMPOSED:
0.610 %=t./ day MIN! MUM SUPPLEMENTAL TEST DURATION:
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> SUPPLEMENTAL TEST PRESSURE 33.985 PSIA MEASURED SUPPLEMENTAL TEST COMPOS!fE LEAKAGE RATE. L.:
0.807 %wt./ day 2-
DEFINITION OF TERMS PARAMETER DEFINITION I
P...............
Calculated peak containment internal pressure related to the design basis accident in PSIG.
P..............
Containment vessel reduced test pressure selected to measure the integrated leakage rate during the Type A Test in PSIG.
L...............
Maximum allowable leakage rate at Pressure P.,
as specified in the station technical specifications in
%wt./ day.
L...............
Maximum allowable leakage rate at pressure P. In %wt./ day.
L...
Total measured containment leakage rate at pressure P. and P. respectively, obtained frcm testing the containment with its related components and systems as close as practical to those conditions which would exist under the design basis accident in %wt./ day.
L...............
the known leakage rate superimposed on i
the containment during the supplemental test in %wt./ day.
l L'...
The measured containment leakage rate at the test pressure in %wt./ day.
L...............
The composite leakage rate measured during the supplemental test in %wt./ day.
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II.
TYPE A TEST METH005 AND TEST RESULTS The containment leakage rate was deterr ened by utt11 zing the Absolute Analysis Method and the Mass Plot Calcuational Technique. Changes in the water level of the reactor vessel were computed and included in each data set collection. At the conclusion of the test, the results of the Absolute and Mass Plot Methods were corrected to account for changes in the containment net-free air space due to water accumulation in the drywell sump. These results were further adjusted to incorporate the results of Type B and Type C Local Leak Rate Testing (LLRT).
The level corrected leakage rates and the LLRT adjusted leakage rates are given below.
LEVEL CORRECTION CALCULATION The UCL-95 calculated leakage rate was corrected to account for water accumulation into the containment sump as determined by the following equation:
L'
- L + (24)(0.1338)(Fi F.
) (100)
(311,392)ai where.
L - UCL -95 calculated leakage rate in %wt./ day 24 - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> / day 0.1338 - conversion factor for converting gallons to cubic feet Fi - final sump Integrator reading in gallons F. - Initial sump integrator reading in gallons 100 - 100%
311,392 - containment not free-air space in cubic feet AT.
time interval between initial and final suinp Integrator reading in hours 4-
Substituting Type A Test values, L' = 0.338 %wt/ day + (2400) (0.1338)(1686)
(311.392)(38)
L' = 0.338 %wt./ day + 0.046 %wt./ day L' = 0.384 %wt./ day LOCAL LEAK RATE TEST ADJUSTMENT The level corrected leakage rate is adjusted to include Type B & C test results of isolation valves which were isolated from the Type A test pressure. The total leakage for this adjustment is the sum of all the isolated penetrations minimum leak rates. A summary of these test results is
'I as follows:
LEAKAGE RATE (SCFH)
PENETRATION 920 PSIG Cleanup System Relief to Torus 0.059 Cleanup System from Reactor 0.652 1
)
Cleanup System to Reactor 0.689 CRD Hydraulic Return Line 0.027 Drywell Sump Discharge 0.124 Feedwater Check Valves (Northside) 0.291 Feedwater Check Valves (Southside) 0.004 l
Liquid Poison Check Valves 1.510 i
PASS Liquid Poison & Rx Sample Valve 0.010 RBCCW from Drywell 0.285 RBCCW to Drywell 2.676
+
Reactor Sample Line 0.004 TOTAL 6.331 SCFH 920 psig The post Type A Test local leakage rate test adjustment is 6.331 SCFH corrected to a test pressure of 20 PSIG.
This value must be equated to a I
leakage rate in %wt./ day in order to be added in to the Type A Test results.
6.331 SCFH - 0.021 %wt./ day j
Therefore, the total post Type A Test Local Leak Rate Tests adjustment factor is an additional 0.021 %wt./ day.
- l I
4
The Type A Test results at the measured and at the 95% confidence level for the Absolute Mass Plot Method are given in Table I.
Both the level correction factor and the LLRT adjustment factor for the Absolute Mass Plot method are also provided.
TABLE I TYPE A TEST RESULTS
SUMMARY
8 HOUR MEASURED LEAKAGE CALCULATED UCL-95 LEAKAGE MEASURED LEAKAGE DESCRIPTION RATE (%wt./ day)
RATE (%wt./ day)
RATE (%wt./ day) uncorrected / unadjusted 0.331 0.338 0.387 l
level corrected / unadjusted 0.377 0.384 0.433 level corrected /LLRT adjusted 0.398 0.405 0.454 Figure I is a graphical description of the Type A Test performance as determined by the Absolute Method and Mass Plot Analysis Technique.
The large increase in the leakage rate between the elapsed time of 2 - 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> is attributable to an increase in reactor water level over this period. As previously described in Section II, each data point is corrected for reactor t:ater level by calculating the corresponding change in air mass inside the reactor vessel.
The increased water level resulted in a reduction in net-free air space, thus decreasing the calculated containment air mass.
The decrease in calculated air mass for each data point produced an increasing leakage rate. Following this period reactor water level was lowered to normal level and the leakage rate decreased, as expected.
The UCL-95 leakage rate then began to converge with the measured leakage rate toward the latter part of the test. Also included in Figure I is the curve for the measured (window) leak rate for the final 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of the test. l
-- i
l l
Figure 1 OYSTER CREEK ILRT TEST h
4 k
i p o.2 l
E e
MEASURED LEAKRATE l
- UCL-96 LEAKRATE 4
8 HOUR WINDOW LEAKRATE 5
~
0.0 a I
U i
i i
i i
9 5
19 15 29 25 ELAPSED TIME (HOURS)
III.
ACCEPTANCE CRITERIA - TYPE A TEST 10CFR50, Appendix "J" requires that the leakage rate, L.., (at the 95% upper confidence level) shall be less than 0.75L..
Calculation of L.
in %wt./ day:
L. (P./P.)"
L.
1.0 %wt./ day (20psig/35psig)2 L.
L.
0.756 %wt./ day L.. < 0.75 L. - 0.75(0.756 %wt./ day) therefore, L.. < 0.567 %wt./ day
. ),
\\A b
IV.
SUPPLEMENTAL TEST In accordance with 10CFR50, Appendix "J", a supplemental test was performed at the conclusion of the Type A Test to provide a definitive method for verifying the measurement capability and integrity of the leak detection instrumentation.
The supplemental test utilized the superimposed leak verification method in which a calibrated leak was superimposed on the existing leaks in the primary containment. A leakage rate of 3.00 SCFM was introduced into the leak detection system and the corresponding composite leakage rate was determined by utilizing the Absolute Analysis Method and the Mass Plot Calculational Technique. The results of the supplemental test are given in Table II.
TABLE II SUPPLEMENTAL TEST RESULTS PARAMETER LEAKAGE RATE IN 7.wt/ day L.
0.610 L..
0.331 L.
0.756 L.
0.807 ANALYSIS AND INTERPRETATION Figure II is a graphical description of the supplemental test performance as determined by the Absolute Method and Mass Plot Analysis Technique.
As can be seen from the plot, near the latter part of the four (4) hour test, the
\\
UCL-95 leak rate begins to converge upon the measured leak rate.
V.
Acceptance Criteria'- Supplemental Test In order for a successful supplemental test, the results must satisfy the following order relationship, in accordance with ANS/ ANSI 56.8 - 1981.
(L. + L.,. - 0.25L.)1 L. 1(L. + L.. + 0.25 L.)
Substituting appropriate values from Table II, the acceptance criteria order relationship provides the following result:
(0.610 + 0.331 - 0.189)1 0.807 1 (0.610 + 0.331
+ 0.189) 0.752 1 0.807 1 1.130 As can be seen, the results from the four (4) hour supplemental test satisfy the order relationship for acceptance criteria.
It is therefore concluded that a successful supplemental test was performed.,
Figure II OYSTER CREEK VERIFICATION TEST 1.2 -
l i
i 1-m Q
0.0 -
a 0.6 -
w m
e MEASURED LEAKRATE g
E a UCL-95 LEAKRATE 0.4 -
M 4m a
0.2 -
0: :
i i
i i
0 1
2 3
4 ELAPSED TIME (HOURS) -
VI.
TYPE A TEST
SUMMARY
AND CONCLUSION A.
"As-Found" Results The results of the "As-Found" containment leakage rate exceeded the acceptance criteria required by 10CFR50, Appendix "J", due to excessive containment valve / penetration leakage as determined by the " pre-repair" Local Leak Rate Testing Program. Valve repairs and corrective maintenance were completed and the applicable valve " post-repair" leakage rate results were obtained in accordance with 10CFR50, Appendix "J".
Both " pre-repair" and
" post-repair" results are included in Table III.
Instrument tolerance factors were included in each LLRT test result.
B.
"As-Left" Results The results of the twenty-four hour Type A Test determined a primary containment leakage rate well below that required in 10CFR50, Appendix "J".
The accuracy of the test data has been verified by the satisfactory performance of a four hour supplemental test.
It is therefore concluded that the validity of the test data has been confirmed and that all Type A Testing requkrementsof10CFR50, Appendix"J",havebeenfulfilled. _
i VII TYPE A TEST CHRONOLOGY AND HIGHLIGHTS The Chronology of significant events prior to and during the performance of the Type A Test is as follows:
DATE TIME EVENT 10/23/86 1600 Completed QC inspection of containment structure.
10/24/86 2300 Completed valve and system line-ups for test.
10/25/86 0400 Installed torus north / south manways and performed LLRT test on gaskets.
10/25/86 0800 Closed and locked up drywell airlock.
Installed tie-downs on inner door.
10/25/86 1400 Completed leak rate tests on drywell airlock doors and seals.
10/25/86 1730 Commenced pressurization of containment.
10/25/86 1752 Dewcell No. 3 reading low.
Monitoring for possible deletion.
10/25/86 1756 Entered new volume fraction for RTD's due to the inoperability of RTD No. 2.
10/26/86 0130 Declared Dewcell No. 3 inoperable and reweighted remaining Dewcells in the zone.
10/26/86 0500 Entered Stabilization mode.
10/26/86 0530 Isolated pressurization source at a containment pressure of 37.001 PSIA.
10/26/86 1002 Entered 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> type A test mode.
10/26/86 1045 Type A test failing.
Began looking for leaks.
The following leaks were discovered and repaired.
1.
Containment spray System; V-21-17, V-21-15, V-21-5, all packing leaks.
Isolated DP transmitter on containment spray HX northside..
k
TESTCHRONOLOGYANDHIdHLIGHTS(CON'T)
DATE TIME EVENT 2.
Purge system; V-23-14 flange.
3.
V-38-1047 instrument valve fitting by rack RK03.
4.
Volumetrics cabinet air fitting.
10/26/86 1753 Official restart of type A test.
10/26/86 2040 Leak rate is failing PCILRT.
10/26/86 2138 Leak rate is 0.7418%/ day, still failing but beginning to trend down after tightening gland stem nuts on V-21-il valve.
10/26/86 2230 I&C technician discovered excessive leakage on V-23-256.
This is the supply line positioner valve for V-23-13 (N purge line).
Test director instructed technicians to close this sensing valve and replace copper tubing going into the positioner.
10/26/86 2245 V-21-13, V-21-17 packing leaks, tightened packing.
Retightened flange on V-23-14.
Seated relief valves 21-21 and 21-22 for northside containment spray HX.
10/27/86 0100 Assembled crews for leak chasing. All crews were dispatched and instructed to check pressure fittings, valve packings, stems, sensing lines, etc. with leak-tek or streamers to detect possible leakage.
Operations began flooding the drywell head seal cavity to check for leakage around the head.
10/27/86 0300 Results from leak rate crews:
V-28-18 packing leak (on top of torus)
Containment spray and core spray rooms - No leaks Trunnion room - No leaks Containment spray HX - No leaks Drywell head - No leaks TIP room - No leaks.
TEST CHRONOLOGY AND HIGHLIGHTS (CON'T)
)
l DATE TIME EVENT 10/27/86 0330 Sent mechanics down on top of torus to tighten packing on V-28-18.
10/27/86 0430 Found some leaks on compression copper tubing fitting for V-23-25 and V-23-259 on 23' El near scram discharge volume.
Requested OPS maintenance to repair them.
analyzer valves Found packing leaks on 0 2 on 23' El near drywell side entrance. All the valves with yellow handles are leaking.
Requested OPS maintenance to tighten packing on these valves.
10/27/86 0730 I&C technician found small packing leak on NSO4A MSIV.
10/27/86 0750 Have crews out leak chasing.
Presently not in official Type A test status.
10/27/86 1435 Tightened packing on purge valve V-28-18.
10/27/86 1915 Declared re-start of Type A test to have officially started at 1732.
10/28/86 1732 Type A test completed, results satisfactory.
10/28/86 2032 Induced superimposed leak (~ 3.0 SCFM).
Begin 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> verification test.
10/29/86 0032 Verification test completed, results are i
satisfactory.
10/29/86 0130 Begin depressurizing containment.
Prepare for torus to drywell vacuum breaker test.
v f98 I
y
,VIII.
TYPE B AND C LOCAL LEAK RATE TESTS Type 8 and C Local Leak Rate Tests were performed on all testable containment isolation valves, gaskets, and penetrations in accordance with 10CFR50, Appendix "J", and the Oyster Creek Technical Specifications.
The following is a summary of all valves / gaskets which had an unacceptable leakage for their pre-repair tests.
DESCRIPTION VALVE REPAIR a
Feedwater Check Valve V-2-71, 72 Replaced pressure seals and gaskets.
Instrument Air / Nitrogen System V-6-393 Lapped plug to seat.
Reactor Sample V-24-30 Replaced valve.
Torus Vent V-28-17, 18, 47 Adjusted valve linkage and i
added new
]
packing.
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f ;
DESCRIPTION VALVE REPAIR
'Tip Ball Valve #1 Replaced Valve.
RBCCW To Drywell V-5-147 Valve disc seating surfaces were machined.
Seats were lapped.
RBCCW From Drywell V-5-166 Lapped seats and I
added new packing.
RBCCW To Drywell V-5-165 Lapped seats and installed new flange gaskets.
RBCCW From Drywell V-5-167 The valve was 4
blue checked.
Torque switch was adjusted and contacts cleaned.
The valve operated normally. )
i
, _ _. _.,. _. _, ~.
DESCRIPTION VALVE REPAIR Hydrogen Sensing V-38-37, 38 Seats were lapped and new shafts and poppets were Installed.
V-38-39 Solenoid assembly was replaced. Limit switches were adjusted and cover gaskets were replaced.
1 V-38-40, 41, 44 Seats were lapped and new shafts and
)
poppets were i
installed.
Cleanup System From Reactor V-16-1, Replaced packing i
and reset torque switch.
V-16-2 Reset torque switch.
Main Steam Isolation NS04A Replaced packing and adjusted stem nut.
All penetrations passed their subsequent post-repair local leak rate tests.
l The " Pre-repair and " Post-Repair" results from the local leakage rate I
testing are shown on Table III and include the pre-and post-repair results of l
l all tests conducted since the previous Type A Test.
I.-.
..__m.
TABLE III I
LOCAL LEAK RATE TESTS PRE - REPAIR TEST RESULTS POST REPAIR TEST RESULTS LEAK RATES (SCFH)
LEAK RATES (SCFH)
DOUBLE GASKETED SEALS TEST DATE 11_g11g 20 osig TEST DATE 31,311g E glig Bislogical Shield Stabilizer Hanways (8) 4/21/86 0.062 0.047 4/21/86 0.062 0.047 Drywell Airlock 4/12/86 0.086 0.065 4/12/86 0.086 0.065 Drywell Airlock Seal 4/12/86 0.012 0.009 4/12/86 0.012 0.009 Drywell Head Seal 4/12/86 0.110 0.083 4/12/86 0.110 0.083 Drywell Head Manhole Cover 4/12/86 0.047 0.035 4/12/86 0.047 0.035 I
Reactor Bldg. to Torus Vac. Breakers (2) -
Gaskets and 0-Rings 4/15/86 0.399 0.301 4/15/86 0.399 0.301 Stsam Dryer Penetration 4/18/86 0.038 0.028 4/18/86 0.038 0.028 StCam Dryer Taps (16) 4/18/86 0.242 0.183 4/18/86 0.242 0.183 TIP Penetrations (4) 4/28/86 10/3/86 3.058 2.312 Tcrus Haahole Cover - North 4/13/86 0.009 0.007 4/13/86 0.009 0.007
- South 4/13/86 0.009 0.007 4/13/86 0.009 0.007 Ttrus To Drywell Vac. Brkrs. (14) 4/16/86 3.605 2.725 4/16/86 3.605 2.725 l
l
, l l
l
I TABLE III (CON'T)
LDCAL LEAK RATE TESTS PRE - REPAIR TEST RESULTS POST REPAIR TEST RESULTS LEAK RATES (SCFH)
LEAK RATES (SCFH)
PENETRATIONS AND ISOLATION VALV[S TEST DAIE 15 Dsia ZE_siis TEST DATE 35 nsin 1A_a11s C1tanup System Relief to Torus V-16-30 5/24/C5 0.077 0.059 5/24/86 0.077 0.059 C1tanup System from Reactor V-16-1, 2 & 14 5/25/86 8/09/86 5.720 4.320 C11anup System to Reactor V-16-61 & 62 5/21/86 3.242 2.451 5/21/86 3.242 2.451 CR0 Hydraulic Return Line V-15-27 & 28 5/23/86 0.089 0.067 5/23/86 0.089 0.067 Demineralized Water System 4/30/86 0.018 0.013 4/30/86 0.018 0.013 DW Airlock Elec. Penetration 4/12/86 0.011 0.008 4/12/86 0.011 0.008 DW Equip. Drain Tank Discharge V-22-1 & 2 4/26/86 0.006 0.004 4/26/86 0.006 0.004 Drywell Sump Discharge V-22-28 & 29 6/25/86 0.329 0.249 6/25/86 0.329 0.249 Electrical Penetrations (32) 4/13/86 1.291 0.984 4/13/86 1.291 0.984 Feedwater Check Valves V-2-71 & 73 5/02/86 10/3/86 1.886 1.422 V-2-72 & 74 5/02/86 10/3/86 9.959 7.475 Hydrogen Sensing Lines V-38-37 & 38 4/23/86 9/28/86 0.651 0.488 V-38-39 & 40 4/23/86 9/09/86 0.357 0.270 V-38-41 & 43 4/24/86 4/24/86 3.770, 2.850 i
V-38-44 & 46 4/23/86 9/09/86 0.077 0.058
- (
i
TA8LE III (CON'T)
LDCAL LEAK RATE TESIS s.
PRE - REPAIR TEST RESULTS POST REPAIR TEST RESULTS LEAK RATES (SCFH)
LEAK RATES (SCFH)
PENETRATIDMS AND ISOLATION VALVES TEST DATE 35 nsis 10 nsin TEST DATE 35 osia ZR_pils Instrument Air and N2 System V-6-393 & 395 5/01/86 34.570 26.130 9/08/86 10.910 8.155 Is11ation Condenser vent Valves V-14-3 & 13 3/35/86 6.354 4.803 8/05/86 6.354 4.803-V-14-5 & 20 8/05/86 11.086 8.380 8/05/86 11.086 8.380 Liquid Poison Check Valves V-19-16120 5/31/86 3.831 2.896 5/31/86 3.831 2.896 Liquid Poison Post Accident Sample Solenoid Valve and Reactor Sample Line V-40-6 & V-24-30 5/31/86 10/7/86 0.289 0.216 MSIV's NS03A and 4A 4/15/86 38.350 15.980 4/20/86 13.032 9.852 NSO38 and 48 4/17/86 5.830 2.246 4/20/86 5.830 2.246 MSIV Drain Valves V-1-106, 107, 110 & 111 4/15/86 27.970 20.700 10/4/86 0.258 0.195 a
R9CCW From Drywell V-5-166 & 167 5/28/86 19.490 14.735 6/30/86 3.508 2.569 ROCCW To Drywell V-5-147 & 165 5/29/86 7/21/85 3.740 2.815 Reactor Nead Cooling V-31-2 & 5 5/03/86 3.906 2.953 5/03/86 3.906 2.953 Reactor Sample Line V-24-29 & 30 4/30/86 10/7/86 0.164 0.123 1
1 TIP Ball Valves (4)
,/28/86 10/3/86 3.058 2.312 Shutdown Cooling Post Accident Sample Solenoid Valve V-40-8 5/06/86 0.051 0.038 5/06/86 0.051 0.038 Drywell N2 Makeup V-23-17 & 18 4/21/86 0.025 0.019 4/21/86 0.025 0.019..
TABLE III (CON'T)
LDCAL LEAK RATE TESTS PRE - REPAIR TEST RESULTS POST REPAIR TEST RESULTS LEAK RATES (SCFH)
LEAK RATES (SCFH)
PENETRATIONS AND ISOLATION VALVES TEST DATE 35 ns18 ZQ_ nits IliT DATE 35 nsie 20 osia t
Drywell N2 Purge V-23-13 & 14 4/21/86 0.223 0.169 4/21/86 0.223 0.169 Drywell 02 Analyzer and Particulate Monitor V-38-9 & 10 4/29/86 0.280 0.212 4/29/86 0.280 0.212 j
Drywell Purge V-27-3 & 4 4/13/86 1.564 1.174 4/13/86 1.564 1.174 Drywell Vent V-27-1 & 2 4/12/86 0.063 0.047 4/12/86 0.063 0.047 Drywell Vent Bypass V-23-21 & 22 4/21/86 0.013 0.010 4/21/86 0.013 0.010 t
Reactor Bldg. to Torus Vac Brkrs. V-26-15 & 16 4/15/86 4.970 3.760 4/15/86 4.970 3.760 V-26-17 & 18 4/15/86 0.399 0.301 4/15/86 0.399 0.301 TIP Nitrogen Purge V-23-70 4/28/86 0.015 0.011 4/28/86 0.015 0.011 Torus N2 Makeup V-23-19 & 20 4/19/86 0.060 0.046 4/19/86 0.060 0.046 TIrus N2 Purge V-23-15 & 16 4/19/86 0.019 0.014 4/19/86 0.019 0.014 Ttrus 02 Analyzer V-38-22 & 23 5/03/86 0.011 0.009 5/03/86 0.011 0.'009 Torus Particulate Monitor V-38-16 & 17 4/30/86 0.009 0.007 4/30/86 0.009 0.007 Torus Vent V-28-17, 18 & 47 4/16/86 19.280 14.570 9/09/86 0.105 0.080
- COULD NOT PRESSURIZE TO TEST PRESSURE.
SUPetARY OF TEST RESULTS 20 nsta (SCFN) 35 esta (SCFH)
Tttal (Post-Repair) 79.932 108.935 TItal (Pre-Repair)
FAILED TO MEET ACCEPTANCE CRITERIA.
L IX.
SECONDARY CONTAINMENT LEAK RATE TESTS Secondary Containment Leak Rate Tests were performed in accordance with 10CFR50 and the Oyster Creek Technical Specifications on four different occasions.
The acceptance criteria of the test is satisfied if the reactor building is capable of maintaining 1 0.25 inches H 0 vacuum with a StanJby Gas Treatment System flow rate of 2600 CFM 2 260 CFM.
The test conducted on 4/10/86 was performed prior to the start of refueling operations.
On August 7, 1986, a test was performed which failed to meet the acceptance criteria due to a low reactor building vacuum.
It was discovered a 1
temporary cap had fallen out of the service water discharge line and allowed outside air to enter the reactor building.
The cap was reinstalled and a subsequent test was performed on August 7, 1986 with satisfactory results.
A chronological summary of the test results is as follows:
i i
DATE CORRECTED FLOW (CFM)
VACUUM (IN. H O)
RESULTS 2
4/10/86 2540 0.256 Acceptable i
8/07/86 2651 0.218 Unacceptable f
8/07/86 2635 0.350 Acceptable
{
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ATTACHMENT I 1
i CALCULATIONAL METH005 Reference 1.
ANSI 56.8-1981, Containment System Leakage Testing Requirements.
The containment leakage rate calculation was performed in accordance with i
l the above standard and utilized the Absolute System Analysis Method and Mass Plot Calculational Technique.
The Analysis Method consisted of determining the mass of air in the containment, absolutely, using the ideal gas law, at each time point during I
the test and then using a straight-line least squares analysis to calculate
]
the containment leakage rate.
I An exact upper one-sided limit of 95% confidence level is.then applied to the leakage rate using the relationships identified below.
The derivations and details for this calculational method can be found in reference 1.'
f The calculational methods employed in the computer code for the mass i
point technique performs a least squares analysis as follows:
?
NOTE: Symbols are defined at the end of this section.
j j
The least squares line is given by A
W - At + B j
where the slope (A) and intercept (B) are given, respectively by l
A - N (I ti W ) - (I Wi ) (I ti )
i N (I ti ) - (I ti )*
I and B = (I H ) (I ti
) - (I t, W ) (I ti )
(I ti
)*
N (I ti )
i
_24-4 1
l l
Each time interval (t) is the elapsed time between a clock time fcr the initial reading and the clock time at which the Ith reading is taken. The formulas for A and 8 do not require equal time intervals.
The leakage rate is expressed as the ratio of the rate of change of the mass and the mass in the containment at the time t - 0.
The values of t i
have units of hours and since the leakage rate is desired in %wt./ day the estimated mass point leakage rate, expressed as a positive number, is calculated as follows:
L - (-2400) (A/B)
The uncertainty in the estimated value of the leakage rate is assessed in terms of the standard deviations of A and B and their covariance followed by a
the computation of an upper limit of the 95th confidence level for the j
calculated leakage rate.
]
The best estimate of the common standard deviation of the air masses with a
j respect to the line is given by:
S - (I (W
$)*)
I
8
(
N-2
)
- where, Ni is the measured mass at time ti and A
A Wi is the estimated mass at time ti from Wi
- Ati
+B and, N-2 is the number of degrees of freedom, a
l In order to determine the standard deviation of the slope (S) let K-S
[N(I t* ) - (I ti
)* ] *
then, the standard deviation of the slope is i
S4 - K[N] *,
4 j
the standard deviation of the intercept is S. - K[I t* ]
and the covariance of the slope and intercept is i
8 S4.
-K
[- I ti 1 ;
In order to calculate the exact upper one-sided limit of a 95% confidance level for the leakage rate, let a - B*
- tis (Si) b - AB - tis (54. ), and c - A* - tis S(*)
Then the exact upper one-sided limit of a 95% confidence level for the leakage rate is determined as follows:
UCL (+95) - -2400 [b - (b' -ac)
]/a The leakage rate is later corrected for changes in containment free-air volume due to water leakage into the containment. Changes in reactor vessel water level are automatically accounted for in the computer program in each data set.
Data for drybulb temperature and dewpoint temperature is corrected for any instrument error using three point calibration data provided by the equipment supplier. Weighting factors are assigned to the RTD Sensors and dewpoint sensors thus providing a mean absolute temperature reading indicative of the actual containment conditions.
In addition, the pressure sensor readings are corrected using a similar technique.
The mass flow sensor readings are corrected for any instrument error using a fifth order polynomial j
equation as a best curve fit to the calibration data provided by the equipment
- supplier, i
i 1
4 t
COMPUTER CODE QUALIFICATION:
An independent audit including a validation and verification was performed on the computer code prior to its utilization for the 1986 Primary Containment Integrated Leak Rate Test at Oyster Creek.
The audit consisted of a technical in-depth check of the equations used to confirm agreement with those equations recommended by the governing standards.
In addition, the ILRT computer code was tested using benchmark data obtained from previous ILRT tests conducted at Oyster Creek.
I 1
1 1
l 1
1 l
4 s
- 4 i
i i
SYMBOLS AND SUBSCRIPTS SYMBOLS P
- Total absolute pressure in the containment (PSIA)
T
- Mean absolute temperature of the contained air (*R)
V
- Internal free air volume of the containment (ft')
R
- Gas constant for air (53.35 ft-lbf/lbm *R)
Partial pressure for water vapor (PSIA)
Py N
- Number of pairs of measurements (w,t)
H
- Measured mass of contained air (Ibm) t
- Time interval of measurement after initial measurement (hr)
W
- At & B-least squares line relating measured contained air masses to their corresponding times of measurement A
- Slope of least squares line B
- Intercept of least squares line S-Estimate of standard deviation of slope of least squares line S.-
Estimate of standard deviation of intercept of least squares line S..
- Estimate of covariance between slope and intercept of least squares line L..
- -2400(A/B) - Estimate of containment leakage rate, derived from least squares slope and intercept, expressed as a positive number (%wt./ day) t.:
- 95th percentile of student's distribution UCL - Upper one-sided limit of a confidence level for the calculated containment leakage rate SUBSCRIPTS 1
- Indicates the ith data point, 1 = 1,2,...n 95
- 95% upper confidence level on statistical analysis. _
l ATTACHMENT II l
LEAK RATE DETECTION SYSTEM l
The leakage rate detection system consists of thirty (30) four-wire platinum Resistance Temperature Detectors (RTD's) and ten (10) lithium chloride dew cells positioned in the containment structure as 111ustrated in figure III.
The analog signals from these sensors are input to a multiplexer scanner also positioned inside the containment. A data acquisition storage system located external to the primary containment interrogates the scanner on demand for temperature and humidity information.
Containment absolute pressure information is input to the data acquisition system from a pair of fused quartz bourdon tube manometers which are connected external to the containment.
The analog signals are processed through an analog to digital converter and transmitter at preset intervals to a PRIME 750 computer. A system sensitivity check is performed by superimposing a known leak titough a calibrated mass flow transducer.
The output from the transducer 1$ also processed via the analog to digital i
I converter and data acquisition system to the computer.
In addition, the system reads and records the external ambient temperature and pressure.
The computer operates in a real time mode to collect the transmitted information and calculates on demand the containment leakage rate.
Figure IV is a detailed functional block diagram of the Leak Rate Detection System.
Also included in this section are individual appropriate component performance specifications. -
FIGURE III (RCD ar.d Ce.. cell Ser.sor Ia:stien) l i
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INSTRUMENTA' TION I
I l
Orybulb Temperature Measurement i
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Configuration:
4 wire Operating Range:
32-250 *F i
Accuracy:
60-120*F, 0.I*F i
l 32-250*F, 1 15'F 0
1 01*F 0
'I Sensitivity:
Element:
Platinum j
Quantity:
30 e
i a
Dewpoint Temperature Measurement i
)
Operating Range:
0-200*F Accuracy:
2 5'F 1
l Sensitivity:
1 1*F 0
1
)
Type of Sensor:
10 t
i t
l I
l f
I l l
i E.. -.
. _ _ _ u ___ _ _._,_.. ___
=_
Pressure Measurement l
Operating Rangi:
0-100 PSIA 1 01% of reading 0
Accuracy:
1 001% of full scale 0
Sensttivity:
Type of Sensor:
Quartz Bourdon Tube Manometer Quantity:
2 Flow Measurement Operating Range:
0-10 SCFM Accuracy:
12% of full scale Sensitivity:
gl% of full scale Quantity:
2 Time Measurement Accuracy:
il sec/24 hours Data Acquisition Storage System Type Volumetrics Model A-100 Operating Range:
65536 counts (full scale)
Resolution 10 Microvolts Scanner Interface Standard parallel interface which accepts analog input signals Scanner Capactty:
100 channels in block of 10 Sctiner Speed 10 channels /second Power Supply 105 VAC, 60 Hz '
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TREND OF ILAT C AL CUL AT E D V ALUE S 1386
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J3A 4R FN L.c Li L9 3 71 S:32 0.??3 0.?99 3.033 3." 1 2: 47 0.2?S 0.301 0.007 3 01 9: 2 0.287 7.303 0.000 3C1 9:17 0.2i9 C.333 0.000 301 9:32 0.291 0.335 0.000 3 21 9: 47 3.293 0.337 1.333 3 01 10: 2 3.294 0.333 0.000 3 01 10:17 0.296 0.309 0.000 3C1 10:32 0.298 0.311 0.000 3C1 1C:47 0.3C0 C.312 0.000 301 11: 2 0.302 0.314 0.000 301,1.1:17 3.303 7.315 3.300 3 01 11:32 3.304 0.316 0.347 3 01 11:47 0.305 0.317 0.292 3 C1.1,2:: 2 0.307 0.318 0.321 3C1 12:17 0.308 C.319 0.326 3 C1 12:32 0.309 0.320 0.312 3 01 12: 47 3.313 0.320 0.305 J 01 13: 2 0.311 0.321 3.302 3 01 13:17 0.311 0.321 0.303 301 13:32 0.312 0.322 0.307 301 13: 47 0.313 0.322 0.307 3 01 14: 2 0.314 0.323 0.315 3 01 14: 17 3.314 0.323 3.339 3 C1 14: 32 3.314 0.323 0.303 301 14:47 0.315
'.324 0.303
~
3 :1 15: 2 0.316 c.324
?.314 3C1 15:17 0.316 C.325
?.316 3 C1 1 ~ : 32 0. 317 0.325 0.325 3*;1 15: 47 3.319 9.327 3.342 3 11 16: 2 0.321 0.327 3.3.62 3C1 15: 17 0.323 0.331 0.381 301 16:32 0.324 C.333 0.386 3C1 16:47 0.325 C.334 0.388 3 C1 17: 2 0.326 0.334 0.386 3 11 17:17 3.327 0.334 3.380 3 ?1 17: 32 3.3?7 0.335 3.377 l
3 :1 17:47 0.328 0.335 0.375 3 :1 14: 2 0.320 C.336 3.37?
3 ~1 18: 17 0.333 C.3? 7 0.381 l
3 ".1 13:32 0.331 2.331 J.38 4
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';'t TREND OF [L RT C ALCUL ATE D V ALUES 1986 MEAS UCL95 J tA HR MN Le LR 3 C1 21:17 0.000 0.030 3 31 21:32 0.3G3
'). 3 3 0 3 01~ 21 : 47 0. 0 03 0.030 3C1-b2: 2 0.000 0.033 301~,2 2 :17 0. 9 71 1.207 3 C.1. 2 2 : 3 2 0. ? 9 7 1.064 301.22: 47 0.884 0.997 301'23: 2 0.809 0.72'6 3 01 23:17 0.757 0.Er79 4
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3 01 2 3:32 0. 7F.6 0.858 l-3 01 23:47 0.755 0.821 3C2 G: 2 0.733 0.795 5'C2
'0:17 0.739 0.'37 7
~ 302 0:32 0.753 C. 7-? 6 3.02
'0:47 0.77.1 0.81 3
[
3 02
',1 : ~ 2 0. 7 8 2 0.82.0
~302 1:17 0.796 C.833
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3C2 1:32 0.807 C. 8 4 1.,,
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