ML20126F747
| ML20126F747 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 12/31/1980 |
| From: | Goodman L DAIRYLAND POWER COOPERATIVE |
| To: | |
| Shared Package | |
| ML20126F745 | List: |
| References | |
| LAC-TR-093, LAC-TR-93, NUDOCS 8103190648 | |
| Download: ML20126F747 (57) | |
Text
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' LAC-TR-093 O
REACTOR CONTAINMENT BUILDING INTEGRATED TEAK RATE TEST (ILRT)
FOR THE LA CROSSE B0ILING WATER REACTOR (LACBWR)
DECEMBER 1980 BY: L. S. GOODMAN DAIRYLAND POWER COOPERATIVE 2615 EAST AVENUE SOUTH LA CROSSE, WISCONSIN 54601 8103190(a$
i LAC-TR-093, :
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TABLE OF CONTENTS ,
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I PAGE I
I. INTRODUCTION------------------------------------------------------- 1 II.
SUMMARY
AND CONCLUSIONS-------------------------------------------- 2 III. TEST EQUIPMENT----------------------------------------------------- 3 IV. CALCULATIONAL METHOD----------------------------------------------- 5 V. RESULTS ANALYSIS--------------------------------------------------- 9 VI.
SUMMARY
REPORT OF TYPE B AND C LOCAL LEAKAGE RATE TESTS------------ 11 A. I n t r od u c t i o n - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 11 B. Summary of Tests Not Meeting Acceptance Criteria--------------- 11 C. I n s t ru me n t E r ro r An al ys i s-------------------------------------- 18 APPENDICES:
Appendix 1 - Integrated Containment Leak Rate Test Data ;
( C al cul a t ed 24- Hou r Te st )----------------------------------- 20 ;
Ap pe ndix 2 - R aw Da t a (24- Hou r Te st )------------------------------------- 24 Appendix 3 - Supplemental Verification Test Data (Calculated)------------ 40 Appe ndix 4 - Raw Dat a (Suppl ement al Test )-------------------------------- 41 Appendix 5 - Summary of Type B and C Test Results 6/79-12/8U------------- 44 I
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LAC-TR-093 ;
T LIST OF FIGURES FIGURE TITLE PAGE ,
NO. , - _ _
LACBWR Containment Integrated Leak Rate Test Equipment Layout- 53 1
2 Containment Dry Air Mass (L b m) vs. Time,1980 Integrated 54 Leak Rate Test--------____________ ....-----------------------
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' LAC-TR-093 I. INTRODUCTION The ninth Type A Reactor Containment Building Integrated Leak Rate Test ,
(ILRT) for the La Crosse Boiling Water Reactor (LACBWR) was successfully performed December 14-18, 1980. The test was performed in accordance with Section 5.2.1.1 of the LACBWR Technical Specifications and the applicable requirements of Title 10 of the Code of Federal Regulations, Part 50, Appendix J. This test was the second to be perforced on an accelerated test schedule basis due to the failure of the two consecutive tests performed in July 1975 and October 1978. The first test performed on the accelerated basis was conducted May 12-17, 1979, with successful results. The requirement is such that a Type A test shall be performed at each plant shutdown for refueling until two consecutive Type A tests meet the acceptance criteria, at which time the original retest schedule may be resumed. The test was performed at a test pressure (Pa) of 52-53 psig and the absolute method of leakage r :e determination, specifically the mass plot analysis technique, was utilized. Leakage rates were determined in accordance with ANS-N274,
" Containment System Leakage Testing Requirements," Revision 2, May 15, 1978.
Dairyland Power Cooperative (DPC) was responsible for conducting the test.
DPC personnel performed the test in accordance with LACBWR Operating Manual Procedure, " Containment Vessel Leak Rate Test," as contained in Volume XI, Section 2.
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' LAC-TR-093 l
-II.
SUMMARY
AND CONCLUSIONS Results of the December 1980 Type A Test indicated anL integrated leakage rate
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Il (Lam) of 0.09192 weight percent per day at the 95 percent upper confidence l evel . The Technical Specification maximum allowable test leakage rate is 0.1 u weight percent per day and thus a-successful test result was 7chieved. The l calculated leakage rate, without the 95 percent upper conficence level factor, .
was determined to be 0.08920 weight percent per day. !
A supplemental verification leak test was performed after the 24-hour Type A i test to verify the accuracy of the Type A test results. Results of the l supplemental test were acceptable based on the requirements of Pargraph ;
III.3.(b) of 10CFR50, Appendix J.
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- LAC-TR-093 l III. TEST EQUIPMENT The LACBWR Type A. Test leakage rate detection system consists of twelve (12)-
i 3-wire platinum resistance temperature detectors (RTD's), six (6) 11thium chloride dew cells and a fused quartz bourdon tube manometer. The RTD's and- a dewcells are positioned in the containment strucure as illustrated in Figure !!
- 1. .The analog signals from these sensors are input to a data acquisition !
system located external to the containment structure. The data acquisition f system interrogatges the RTD and dewcell sensors on demand for dry bulb temperature and humidity information. The containment absolute pressure !
information'is input to the fused quartz manometer, externally connected to the containment structure. The analog signals from the.various sensors are processed through an analog to digital converter and transmitted at preset intervals to a Nuclear Data ND6600 computer.
The computer operates in a real time mode to collect and store the transmitted ..
information and calculates on demand the containment air leakage rate. The l block of stored information for leakage rate calculation is selected from any portion of the stored data base.
Figure 1 also illustrates the equipment utilized for conduct o'f the '
supplemental verification test in which a calibrated leak is introduced'to the '
containment structure to check the sensitivity of the leakage rate measurement.
system. .
The instrumentation used was calibratedw ~ ith traceability to the National Bureau of Standards within six months prior to the conduct of the test. 3 Individual sensor / component perfc ;mance specifications are provided below. t Drybulb Temperature Measurement (RTO)
Configuration: 3-wire [
Operating Range: 0 to 1500F j Accuracy: + 0.10F 't 60-1200F, T 0.10F Repeatability:
, Sensitivity: 0.010F Element: Platinum Quantity: 12 ,
I Dewpoint Temperature Measurement (Oew Cell) !
Dewpoint Range: 32 to 140cp [
i Dewpoint Accuracy: + 1.00F over 600F Range I Dewpoint Repeatability: T 0.50F Dewpoint Sensitivity: 0.10F Type of Sensor: [ithium L Chloride Quantity: 6 (See Note 1)
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- LAC-TR-093 Note 1:' During the test, two dew cell units, Nos..17 and 18 (Refer to ,
Figure 1) appeared to malfunction, one reading significantly high I and the other low. A new Instrument Selection Guide Criteria (ISG) factor was calculated to determine whether a valid test could be conducted without using'the readings from these.two dew cells. -The calculated .T.SG was 10.00910 %/ day. . The ISG criteria is .25 (La)>
which is 0.025 %/ day. Since the calculated ISG was within the limit, a valid test could be performed with the data from the two malfunctioning dew cells eliminated from the calculations.
The manufacturer has been contacted, and an ivestigation is underway to determine the cause of the failures, in order to prevent reoccurrence during future tests.
Pressure Measurement (Manometer) ,
i Operating Range: 0 to 100 psia Accuracy: 1 02% of reading ;
Repeatability: .001% of full scale Stability: Less than .001% F.S. per degree Fahrenheit Ambient Temperature Range Type of Sensor: Quartz Bourdon Tube j
Quantity: I Flow Measurement (Wet Test Gas Meter)
Capacity: 5-60 ft 3/ hour Pressure Range: 0.5 to 8.0 Inches H 2O Accuracy: 1 5%
i Data Acquisition System A/D Conversion: Dual Slope Integration V+F, Constant Scan Rate Di splay: 5 + Digit, Polarity, Decimal and Legend Sampling Rate: 2.5 Channels / Seconds Common Mode Rejection: DC-180db, 10,000 Ohm Unbalance AC-180db at 50-60 Hz Input Impedance: 1,000 Meg Ohms / Volt Ambient Temp. Range: 0-500C Zero Offset: Recalibrate before Each Reading Automatically Voltage Temperature: + .002% of Reading (.25 pV/DC) l l Accuracy: I .005% F.S.,1 005% of Reading at 250C l
with 110% A.C. Power Variation I
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T'O'-MT**m'Mq W@t +' W W W*re og 3,p,e wgge y imp yp-
LAC-TR-093' IV. CALCULATIONAL METHOD The calculation of the containment: leakage rate was performed utilizing the mass point analytical technique in accordance with the industry recognized standard ANS-274, " Containment System Leakage Testing Requirements," f Revision 2 - May 15,1978. This method of leakage rate determination depends !
i on the measurement of the temperature and pressure of the containment -
atmosphere with correction for changes in water vapor pressure. These parameters are utilized to determine a contained mass of air by application of the perfect gas law. The test data thus consists of a time series of independent values of contained air mass. It is assumed that leakage rate is constant with time, thus the data can be analyzed by the method of linear least' squares. .The slope of the air mass versus time represents the rate of change of air mass with respect to time, which is the leakage rate. An upper confidence limit (UCL) was set such that:there was only a 5 percent chance that the actual containment leakage rate exceeded the calculated value. .The derivations and details for this method of calculation are presented in the above stated ANS document.
Symbols and Subscripts Symbol s:
j P - Total absolute pressure in the containment'(psia)
T - Mean absolute temperature of the containment air (OR )
V - Internal free volume of the contajnment (assumed to remain constant for the duration of the test - ft ) -
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R - Gas constant for air (53.35 ft-lbf/lbm OR) t Py - Partial pressure for water vapor. (PSIA) i N - Number of pairs of measurement W - Measured mass of contained air (lbm)
T - Time interval of measurement after initial measurement (hr)
II - At & B - Least squares line relating measured masses to corresponding times of measurement A - Slope of least squares line B - Intercept of least squares line S a - Estimate of standard deviation of slope of least squares line S b - Estimate of standard deviation of intercept of least squares line Sab - Estimate of covariance between slope and intercept of least squares line i
LAC-TR-093 L - 2400A/B - Estimate of leakage rate, derived from least squares slope :
and intercept, expressed as a positive tumber (%/ day)
T95 - 95th percentile of student's t-distribution UCL - Exact upper one-sided limit of a 95% confidence level fer the leakage rate r Subscripts:
t 1 - Indicates the ith data point The calculational methods used in the computer code for mass point technique makes use of a least squares analysis as follows:
The least squares line is given by:
II = At + B where the slope (A) and intercept (B) are given, respectively by:
N(ItiWj) - (IWj) (Eti)
A =
N(It $2 ) - (Itj)2 AND B =
(IWj)(Itj2 ) - (Iti Wj)(Iti)
N (Itj2) - (Itj)2 Each tj is the elapsed time between a clock time for the initial ~
reading and the clock time at which the ith reading is taken. The formulas for A and B 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 time t1 = 0. The values of tj 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:
f L = (-2400)(A/B)
The uncertainty in the estimated value of leakage rate is assessed in terms of the standard deviations of A and B and their convariance followed by the computation of an upper limit of the 95th confidence i level for the leakage rate.
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. LAC-TR-093 n
The estimate of the common standard deviation of the masses with respect to the line is given by: i S = [.IIW ~ U)2] #
N-2 where:
Wj is the measured mass at time tj and Vj is the estimated mass at time ti from Vj = Atj + B In order to determine the standard deviation of the slope (Sa) let:
" (N(Itid) - (Itj )2 ] 4 )
then:
S = K[N]If To determine the standard deviation of the intercept (Sb )
Sb = K[Itj2]35 I
and the covariance of the slope and intercept (SAB) is Sab = K2 [-Itj]
In order to calculate the exact upper one-sided limit of a 95%
confidence level for the leakage rate, let:
a=B2-t95 (S b2)
I b = AB - t 2 95 (Sab) and c=A2-t gg 9 i
LAC-TR-093 ;
then the exact upper one-sided limit of a 95% conficence level for-the leakage rate is determined as follows:
r VCL (+95) = -2400 [b - (b2 -ac)h]/a All raw data for temperature and dewpoint input to the calculational methods described above was corrected for instrument error using calibration data provided by the equipment sunplier. In addition, the pressure sensor readings were corrected us aj a similar technique. Containment Subvolume Weighting factors were assigned to the temperature and dew point sensors thus prov10ng a single ambient and dew point temperature reading indicative of containment condi tions. Weighting facurs were modified during the conduct of the test to conpensate for the two malfunctioning dew cells discussed in Section III.
With regard to comuter code qualification, an internal audit was performed on the computer code prior to first utilizing it in performing a leak rate test on the LACBWR containment. The audit consisted of an in-depth check of the equations used to confirm agreement with those recommended by the governing standards. In addition, independent leakage rate calculations were performed during the initial phases of the Type A Test and compared with comuter code results. The results of this check agreed favorably with the values obtained using the computer code.
The calibrated leakage rate (La) which is used for detennination of acceptance of the supplemental verification test was computed using h the following equation for a point calculation: s t
2 a brated = (14.7 lbf/in2)(144 in2 /ft )(SCFH From Flow DeviceJ(2400) f Leakage Rate) 0 (53.35 ft-Lbf/Lbm R)(527.690R)(Containment Air Mass, Lbm)
A running sum of leakage rate (%/d)versus Time Data sets were introduced to a least square fit analysis for average calibrated h
leakage rate determination. The calibrated leakage rate was calculated by use of a programmable calculator. A minimum number of 20 data sets approximately equally spaced within a minimum time period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> was required for an acceptable data base.
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. LAC-TR-093
'V. RESULTS ANALYSIS Referring to' the namenclature as.used in 10CFR50, Appendix J, the total measured as-found containment leakage rate (Lam) was determined to be as foll ows: '
. Calculated Leakage Rate, Wt.%/ day: 0.08920
- Calcul'ated leakage Rate at 95% Upper Confidence Level, Wt.%/ day: 0.09192 The maximum allowable test leakage rate (Lam) shall not exceed 0.1 Wt.%/ day at a test pressure of 52-psig-(Pa) according to LACBWR Technical Specifications.
Therefore, this test is considered successful. To provide.a margin for possible deterioration of the containment leakage integrity during the interval between Type A tests, LACBWR Technical Specifications require that the leakage rate acceptance criteria be reduced to .75 Lam or 0.075 Wt.%/ day prior to plant startup. This criteria was not met, so valve modifications were made prior to plant startup to reduce leakage to within the 0.075-Wt.%/ day startup criteria.
The Reactor Vent Header Valve and Reactor Cavity Purge Check Valve had not passed Type C Tests conducted during the Type A Test. (RefertoSection VI.B). Replacement of these valves resulted in reduced leakage of 5.77 SCFH.
The Feedwater Check Valve (65-26-001) was sent to the factory for reapplication of its Teflon sealing surface. The leakage through the Feedwater Check Valve was reduced from 10.256 SCFH, measured during the Type A Test, to 0.02 SCFH after repair. Therefore, a total of 16.01 SCFH of leakage was reduced from paths measured during the Type A Test. This corresponds to an as-left leakage rate of 0.06 %/ day, which was within the plant startup criteria of 0.075 %/ day.
i Appendix 1 contains leakage rate test calculated data and results including the zero time intercept and slope of the containment air mass vs. time relationship depicted in Figure 2.
Raw data was collected at 10-minute intervals over a 24-hour period on December 16 and 17,1979, resulting in 145 total data sets for integration into the leakage rate calculation. Appendix 2 contains the test raw data used.
No leakage paths were isolated during test conduct. l The accuracy of the Type A Test results was verified by a supplemental test by bleeding air out of containment at a known rate and then comparing the composite leakage rate for the containment during this time (L ) to the previously determined containment integrated leakage rate (Lam). In accordance with 10CFR50, Appendix J, the following criteria must be satisfied for the supplemental verification test to be acceptable:
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- LAC-TR-093 (Lo + Lam - 0.25 La) I LC 1 (Lo + Lam + 0.25 La) i where: Lo = Calibrated Leakage Rate (superimposed) Wt.%/ day Lam
= Calculated Integrated Leakage Rate, Wt.%/ day LC
= Composite Leakage Rate, Wt.%/ day La
= Maximum Allowable Leakage Rate at Test Pressure Pa = 0.1 Wt.%/ day The superimposed leakage rate (Lo) was determined to be 0.06181 Wt.%/ day using the calculational method described in Section IV. The calculated cmposite leakage rate (L C) was determined to be 0.13328 Wt.%/ day using the c a puterized calculation methods previously described in Section IV. The integrated leakage rate (Lam) was previously calculated to be 0.08920 Wt.%/ day. Using the criteria discussed above, the following demonstrates criteria acceptance l and therefore that the 24-hour integrated test results are valid.
0.06181 + 0.08920 - 0.25 (.1) < 0.13328 < 0.06181 + 0.08920 + 0.25(.1) 0.12601 < 0.13328 < 0.17601 Twenty-eight (28) sets of data were acquired between the hours of 1805 and 2235 on December 17, 1980, for supplemental verification test computation.
The data was collected at 10-minute intervals. Appendix 3 contains calculated supplemental verification test data for determination of the c mposite leakage rate (LC ). Appendix 4 contains the raw data utilized in cmputation of the composite leakage rate (LC ) and the calibrated j (superimposed) leakage rate (Lo). o e
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VI.
SUMMARY
REPORT OF TYPE B AND C LOCAL LEAKAGE RATE TESTS A. I ntroduction_ ,
Results of the reactor containment penetration leakage tests (Type B) and !
isolation valve leakage tests (Type C) are found in Appendix 5, Summary of Type B and C Leakage Test Results, 6/79 - 12/80.
The acceptance criteria set forth in Sections 5.2.1.2 and 5.2.1.3 of LACBWR Technical Specifications were considered the limiting criteria; the total >
leakage limits established in 10CFR50, Appendix J (Sections III.B.3 and :
III.C.3) are not contained in existing LACBWR Technical Specifications.
The LACBWR staff was responsible for conducting the tests which were performed in accordance with approved procedures.
B. Summary of Tests Not Meeting Acceptance Criteria
- 1. Penetration: Emergency Airlock Penetration No.: M-38 Acceptance Criteria: 0.749 SCFH*
Test Date: 12/23/79 Test Leakage Rate: 1.0372
- 0.02 Lpo where Lpo = 37.5 SCFH.
A Type B penetration leakage rate test to determine the leakage rate of the Containment Building emerency airlock was performed on December 23, 1979. The reruits of the test did not meet the acceptance criteria as specified in the LACBWR Technical Specifications, Section 5.2.1.2.6.
Since the inner door of the emergency airlock provided a leak-tight closure, containment integrity was not jeopardized by the observed deficiency. The reactor was in Operating Condition No.1 - Power Operation - at the time of the test. j An investigation was conducted promptly to determine the source of leakage.
The problem was traced to a leak in the mechanical seal of the interior door operating shaft which extends through the airlock shell to the outside. Two o-rings and the shaf t packing were found to be flat. A new seal was installed and the Type B leak rate test was reperformed with zero leakage observed. No prior incidents related to degradation of the emergency airlock shaft seals l
have been recorded. (Ref.: R0-79-19, LAC-6711) l j
- LAC-TR-093 3
- 2. Penetration: Electrical Penetration Unit Nos. 3, 4, and 5 i Acceptance Criteria: 0.375 SCfH Each*
Test Date: 4/9/80 l
- 0.01 Lpo where Lpo = 37.5 SCFH.
As a result of conducting Type B leak tests on April 9,1980, the indicated leakage flow rates from electrical penetration unit Nos. 3, 4, and 5 were found to exceed the permissible value prescribed in LACBWR Technical Specifications, Section 5.2.1.2.(b). The leakage rates found were 0.589 SCFH on penetration Unit No. 3, 12.377 SCFH on Unit No. 4, and 0.589 on Unit No.
5.
The subject units employ the MI cable-type penetration. This type has solid conductors, compacted magnesium oxide insulation and a round copper sheath.
The MI cable rurs through an inner chamber formed by the containment shell and an inner chamtar wall; the chamber for each unit is 8 feet 8 inches high with a cross section 3 inches deep and 8 inches wide. The penetration is made ray passing the MI cable through brass glands which are screwed into 3/8-inch tapped holes in the containment shell and in the inner chamber wall. The copper sheath is sealed at the gland. The inner chamber is pressurized to leak-test the penetrations. Each unit contains sixty-six (66) individual cable penetrations.
The individual cable penetrations listed below were observed to be leaking by the soap bubble detection method at the penetration side indicated.
Inspection revealed the noted penetration condition.
PENETRATION UNIT NO. 3 Individual Penetration No. Penetration Side
- Discovered Condition 258 R Cracked Gland Body 26B T Cracked Gland Body i 30B R Cracked Gland Body PENETRATION UNIT NO. 4 Individual Penetration No. Penetration Side
- Discovered Condition l Cracked Gland Body 25B T 26A T Cracked Gland Body i
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PENETRATION UNIT NO. 5 Individual !!
Penetration No. Penetration Side
- Discovered Condition ;1
.I' 5B R Slight Seepage from Under Gland Nut 12A T Cracked Gland Body 13A T Cracked Gland Body
- R denotes reactor side; T denotes turbine side.
Three of the above individual penetrations had leaked in January 1979 and had been sealed with Scotch Cast Resin #5 epoxy sealant compound and one had been sealed with the epoxy after leaking in 1975 and in 1978. Four of the individual penetrations had no previous leakage history.
None of the individual penetrations on which Velodur Metal, a high strength, high heat resistant sealing product, had been used leaked. This sealing product was first used at LACBWR in April 1979, and it is believed it will provide a significant improvement over the previously used sealing material.
The results of these tests support this belief.
Repairs were effected which consisted of replacement of the entire individual F MI cable penetration at penetration locations 25B, 26B, and 30B on Unit No. 3 [
and 258 and 26A on Unit No. 4. The cracks in the glands in individual Unit t No. 5 penetrations 12A and 13A were soldered and tested satisfactorily. This !
repair method has also demonstrated success in the past. The gland threads l were cleaned and wrapped with Teflon tape on individual Unit No. 5 penetration ;
58, which had shown only a slight seepage from under the gland nut.
Post-maintenance leakage rate testing was performed on April 11, 1980, for
- Unit Nos. 3 and 4 and on April 18, 1980 for Unit No. 5. Resulting leakage i rates were acceptable at 0.029 SCFH for Unit No. 3, 0.019 SCFH for Unit No.
l 4, and 0.029 SCFH for Unit No. 5.
With the accomplishment of effected repairs and attainment of successful Type B testing, no further corrective action for this discovery is necessary.
It is believed that random cracking of the fittings occurred as a result of mechanical tightening accomplished during post-construction leak rate tests.
l The inability of some electrical penetration seals to remain leak tight during test conditions has been attributed to hardening and embrittlement of the formerly used epoxy sealant compounds. In the event further degradation l
j of electrical penetration gland seals is observed on subsequent leak tests which reveal cracked fittings, appropriate replacements will be made. Also, (;
l only the Velodur Metal sealant is planned to be used in the future, when use l
of a sealing compound is deemed necessary. In addition, we have initiated an I engineering evaluation to detennine an acceptable method of improving 3 penetration integrity which may include supplementary test methods and f
i corrective repairs. (
Reference:
R0-80-01, LAC-6873) l A
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LAC-TR-093
- 3. Penetration: Electrical Penetration Unit No. 6 Acceptance Criteria: 0.375 SCFH*
Test Date: 11/27/80 Test-Leakage Rate: 2.95 SCFH
- 0.01 L po where L po is 37.5 SCFH.
As a result of conducting Type B leek tests on November 27, 1980, the indicated leakage flow rate from electrical penetration unit No. 6 was found to exceed the permissible value prescribed in LACBWR Technical Specifications, , Section5.2.1.2.(b).
The leakage was determined to be through Individual Penetration No. 29B on the Electrical Penetration Room side of the penetration chamber. No leakage was detected through the Containment Building boundary side of the penetration chamber.
The' gland on Individual Penetration No. 29B was found to be cracked. It was cleaned and soldered and a retest was performed on December 1,1980. The result was acceptable, with zero leakage. This repair method has demonstratec success in the past.
With the accomplishement of effected repair and attainment of successful Type B testing, no further corrective action for this discovery is necessary at this time. It is believed that random cracking of the fittings occurred as a result of mechanical tightening accomplished during post-construction leak ,
rate tests. The inability of some electrical penetration seals to remain leak ;
tight during test conditions has been attributed to hardening and j embrittlement of the formerly used epoxy sealant compounds. In the event further degradation of electrical penetration gland seals is observed on subsequent leak tests which reveal cracked fittings, appropriate repairs will 4 be made. In addition, we have initiated an engineering evaluation to determine an acceptable method of improving and monitoring penetration i ntegrity. (
Reference:
R0-80-13, LAC-7278) e
- 4. Penetration: Containment Ventilation Discharge Dampers Valve No.: 73-25-005 Penetration No.: M-21 Acceptance Criteria: 0.375 SCFH*
Test Date: 4/15/80 Test Leakage Rate: 40.79 SCFH f f
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- 0.01 Lpo, where Lpo is 37.5 SCFH. ;
i As a result of conducting periodic Type C leak tests on Containment Building ventilation dampers on April 15, 1980, the leakage flow rate determined from l '
the exhaust dampers exceeded the permissible leakage flow rates as defined in '
LACBWR Technical Specifications, Section 5.2.1.2.(b). Supplemental tests I verified zero leakage across the containment boundary. >
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LAC-TR-093 ,
F The method of leakage rate determination used for this test requires prer.,surizing the ventilation piping space between the two dampers with air to ;
52 psig. After isolating the air supply, pressure decay versus elapsed time o is observed. As a means to assist in the determination of the point (s) of leakage, a blank flange was installed downstream of the downstream damper (73-25-006) and flow measurements made. No leakage could be detected past the lower dampers, showing that containment integrity had been maintained.
Further investigation revealed the source of leakage to be the seat ring of the upstream damper. An indentation, approximately 1/8" wide and 1/16" deep, located on the surface of the seat ring caused the leak. The indentation was formed by contact of the rim of the valve disc when the valve disc is in the open position. A similar indentation on the opposite side of the disc did not leak. The ventilation outlet damper (73-25-005) is an Allis-Chalmers Stream Seal No.150-R,10-inch butterfly valve.
Indentations in the seal ring have been observed before. The upstream and downstream exhaust valves are installed with the same damper orientation.
The tests results show that when the test pressure is applied against the seal ring and damper in the direction which would be experienced during an MCA, the valve is leak tight.
The seat ring was replaced in the upstream damper and both dampers were repacked with the square type braided teflon packing the first used in May, 1979. Use of this new type of packing was discussed in the report on Reportable Occurrence No. 79-08 (LAC-6322, dated May 30,1979). Experience to date with this packing has been good, as evidenced by no leakage occurring past the lower damper operator shaft during this test.
I A post-repair leakage test performed April 18, 1980, resulted in an indicated t leakage rate of 0.05439 SCFH, in conformance with the Technical Specification b criteria. (Reference R0-80-02, LAC-6882) l
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- 5. Penetration: Heating Steam Condensate Return !
Valve No.: 73-25-021 Penetration No.: M-26 Acceptance Criteria: 0.375 SCFH*
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- 0.01 L po, where L po is 37.5 SCFH
- a. Test Date: 4/17/80 Test Leakage Rate: 3.6 SCFH As a result of conducting periodic Type C leak tests on the Containment .
Building Condensate Return Isolation Valve on April 17, 1980, the leakage j flow rate determined from the condensate valve exceeded the permissible i leakage flow rates as defined in the LACBWR Technical Specifications, {
Section 5.2.1.3. g i
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-LAC-TR-093-
.The Contain:nent Building Condensate Return Isolation Valve (73-25-021). is a
- Fischer, Model 667ET,1-1/2-inchivalve, with a carbon impregnated teflon seal ring. .This was thelfirst failure of this valve and can be attributed to aging due to normal wear. The valve seals were replaced and the post-repair
. leakage test performed April 25, 1980, resulted in zero-leakage. No further corrective action.is considered necessary. (
Reference:
R0-80-03, LAC-6882)
- b. Test Date:' 11/27/80 Test Leakage Rate: 14.3 SCFH As a result of conducting periodic Type C leak' tests on the Containment ,
Building Condensate Return Isolation Valve on November 27, 1980, the leakage i flow rate determined from the condensate valve exceeded the pennissible :
leakage flow rates.
The internals of this valve were totally replaced. Also, an evaluation of -
methods to improve this valve's performance is'being conducted. The post- l l
repair leakage test performed December 2,1980, resulted in zero . leakage.
(
Reference:
R0-80-14, ' LAC-7268)
- 6. Penetration: Retention Tank Pump Discharge Valve Valve No.: 54-25-006 Penetration No.: M-22 Acceptance Criteria: 0.375 SCFH*
Test Date: 11/29/80 .
Test Leakage: ' Between 0.56 and 4.0 SCFH
- 0.01 L po, where L po is 37.5 SCFH. j l
As a result of conducting periodic Type C leak tests on the Retention Tank l
j l
Pump Discharge Valve on November 29, 1980, the indicated leakage flow rate was l
found to exceed the permissible leakage flow rate as defined in LACBWR Technical Specifications, Section 5.2.1.3.(b)
The Retention Tank Pump Discharge Valve (54-25-006) is a 2-inch diaphragm .,
operated, BS&B Valve, Model 70-14-2. This was the first failure of this valve. The valve was relapped, the gaskets were replaced and new packing was i nstall ed. The post-repair leakage test performed on December 4,1980, resulted in zero leakage. No further corrective action is considered j necessary. (
Reference:
R0-80-15, LAC-7268)
I ,
l 1
LAC-TR-093
- 7. Penetration: Reactor Cavity Purge Air Line Valve No.: 55-26-006 Penetration No.: M-28 Acceptance Criteria: 0.375 SCFH* l Test Date: 12/16/80 Test Leakage Rate: 1.97 SCFH
- 0.01 L po, where L po is 37.5 SCFH.
As a result of conducting periodic Type C leak tests on December 16, 1980, the leak flow rate determined from the Reactor Cavity Purge Air Line exceeded the permissible leak flow rates as defined in LACBWR Technical Specifications, Section5.2.1.3.(b).
The Reactor Cavity Purge Line check valve (55-26-006) was a Crane, Model 200, 1/2-inch check valve. This valve was replaced. The post-repair leakage test performed December 19, 1980, resulted in zero leakage. (
Reference:
R0-80-17, LAC-7295)
- 8. Penetration: Reactor Vent Header Valve No.: 55-25-003 Penetration No.: M-29 Acceptance Criteria: 0.375 SCFH*
Test Date: 12/16/80 Test Leakage Rate: 3.8 SCFH ,
i l
l
- 0.01 Lpo, where Lpo is 37.5 SCFH.
As a result of conducting periodic Type C leak tests on December 16, 1980, the leak flow rate detemined from the Reactor Vent Header Valve exceeded the permissible leak flow rate as defined in LACBWR Technical Specifications, ,
[
Section5.2.1.3.(b). t The Reactor Vent Header Valve (55-25-003) was a BS&B, Model 70-14-2R, 4-inch, 600 psig, single-port, diaphragm-operated valve with an integral seat. Rust and debris were removed from the area of the valve. The valve was located in a low point of the line, so a new valve was relocated in a vertical portion of the line. The post-repair leakage test performed 1/14/81 resulted in zero l eakage. (
Reference:
R0-80-17, LAC-7295)
I
LAC-TR-093 C. Instrument Er ror Analysis The instrumer errors asscciated with the various subjoct unsuccessful Type B and C leakage rate tests were detennined from manufacturer's specifications, as available, or conservatively estimated.
- 1. Test Board (Two Identical Gauges)
Manufactured By: U. S. Gauge Company Model: Supergauge Range: 0-60 psig Accuracy: 1 5% FS (0.3 psig)
During tsst conduct, two pressure gauges were read and the highest change in pressure reading, as an indication of pressure decay, was used for leakage rate calculation. As an indication of instrument error in volumetric flow rate units, the 0.3 psig error relates to approximately 0.08 SCFH error associated with the ventilation inlet or discharge dampers, assuming a one-hour time period.
'! . Electrical Penetration Pressure Gauges Manufactured By: Ashcroft Gauge Company Model: 100-3-1/2" Minor Division: 2 psi Range: 0-100 psi A: curacy: 0-50 psi: 2%
50-200 psi: 3%
By procedure, the electrical penetrations are pressurized to 55 psig for Type B test conduct. Thus, the maximum instrument error is 0.03 (55 psig) =
+ 1.65 psig. This pressure error would related to a volumetric flow rate error of 0.16 SCFH assuming leakage from penetration units 3, 4, 5, or 6 and .
a one-hour test duration. Calibration checks have indicatred that the '
inaccuracy of the gauges is typically lower than 1 psig and the proceeding is thus conservative.
l r
- 3. Air Flow Rotameter l
l Manufactured By: Brooks i' Model: 1110-01F1A1A j
Range: 0 .56 SCFH Accuracy: 1 1% FS The rotameter directly reads the leakage rate of the air through the isolation [
valve it is testing. Conservatively assuming the maximum flow rate the meter e is capable of measuring, the maximum instrument error is 1 006 SCFH. ;
i
- LAC-TR-093 U
- 4. High Range Air Flow Rotameter k Manufactured By: Brooks Model: 1110-06H1G1A Range: 4-48 SCFH i
Accuracy: f.1% FS The high range rotameter is only used for failed leak rate tests to measure high leakage flow rates. Conservatively assuming the maximum flow rate the meter is capable of measuring, the maximum instrument error is f. 5 SCFH.
- 5. Wet Tes_t Gas Meter Manufactured By: Precision Scientific Company Model: 63119 Range: 5-60 ft3 /hr Accuracy: + .5%
Conservatively assuming the maximum instrument capacijy in the error determination, the maximum instrument error is 0.3 ft /hr. Actual error factors associated with each measurement are dependent on the total volume sensed by the instrument.
The summarized instrument error factors associated with the initially unsuccessful Type B and C test described in Section VI.B is provided below:
Valve / Penetration Test Instrument Instrument Error Emergency Airlock Test Board Gauges 0.389 SCFH Ventilation Dampers (Exhaust) Test Board Gauges 0.08 SCFH Electrical Penetration Units Individual Pressure 0.16 SCFH !
3, 4, 5, and 6 Gauges Heating Steam Condensate Wet Test Gas Meter and 0.07 SCFH tiax.
Return Rotemeter Retention Tank Pump Discharge Rotameter and High Range 0.006/.5 SCFH Valve Rotameter Reactor Cavity Purge Airline Rotameter and High Range 0.006/.5 SCFH Rotameter Reactor Vent Header Rotameter and High Range 0.006/.5 SCFH Rotameter
y -
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a 7 APPENDIX 1-t .,
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PAGEG1]'pgq O >
, 2. - !#in .M N DRIRYI,A?JDiPOWiiR1 yLACROSSESBOIL'ING~WATERDREACTOR"<LACBWR) COOPERATIVE: . AW q r
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- ABSOLUTE METHOD
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- ABSOLUTE METHOD
- O , **** MASS PLOT-ANALYSIS ++++
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" " , ' -DRIRYLAND POWER # COOPERATIVE.* PAGE "U O >
' LRCROSSE. BOILING" WATER RFRCTORT CL'ACRWR>
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- ABSOLUTE NETHOD*
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$ATkkA E LCOOPERATTVE. PAGE14 O a
- L.ACROSSE BOILING' WATER-REACTOR (L.ACRWi') Q 4
n v
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. INTEGRATFD CDNTAINMFNT IEAK RATE TEST +ABSOf.UTE METHOD
- I O ,' **** NASS PLOT ANALYSI5+***
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.- APPENDIX 3 , LAC-TR-093 -
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4 N 'DAIRYLAND3POWERMCOOPERATIVE7,. PAGE ,1~ t O
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.;LACR055F;BOILINGiWATER' REACTOR ALACRWR>
4 5 !
O INTEGRATED CONTAINMENT LERK RATE TEST *AEdot.UTE METHOD +
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- INPUT LIST *. '
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f APPEWDIX 5 -
SUMMARY
OF TYPE B AND C TEST RESULTS 6/79 - 12/80 ,
(TABULATED LEAKAGE RATES DO NOT INCLUDE INSTRUMENT AND llVMAN ERROR FACTORS)
I TOTAL AS-FOUND ALLOWABLE LEAKAGE PENETRATION TEST TEST LEAKAGE LEAKAGE AS-LEFT (SCFli) (SCFH) (SCFH) l REMiutKS l NO. l DESCRIPTION l TYPE l DATES l l l l
M-37 Personnel Airlock B 7-21-79 3.56 3.75 3.56 None i 11-17-79 1.88 3.75 1.88 None 3-14/15-80 1.5 3.75 1.5 None 7-12-80 1.i3 3.75 1.13 None 11-30-80 0.0 3.75 0.0 None
. M-38 Emer9ency Airlock B 8-18-79 0.1296 0.749 0.1296 None N 12-22-79 1.0372 0.749 0.0 Installed new shaf t seals
' and 0-rin9s at external door. Retested 12-23-79 with as-left leak rate of 0.0 SCFH. (Refer to R0-79-19, LAC-6711).
4-11-80 0.0 0.749 0.0 None 8-17-80 0.648 0.749 0.648 None 11-28-80 0.259 0.749 0.259 None M-6 Main Steam C 4- 9-80 0.048 0.375 0.048 None r-Penetration M 11-29-80 0.024 0.375 0.024 None h E>
APPENDIX 5 -
SUMMARY
OF TYPE B AND C TEST RESULTS 6/79 - 12/80_ -
(TABULATED LEAKAGE RATES 00 NOT INCLUDE INSTRUMENT AND HUMAN ERROR FACTORS) 10TAL AS-FOUND ALLOWABLE LEAKAGE PENETRATION TEST TEST LEAKAGE LEAKAGE AS-LEFT NO. l DESCRIPTION l TYPE l DATES l (SCFH) l (SCFH) l (SCFH) i REMARKS j M-7 Feedwater Penetration B 4- 9-80 0.054 0.375 0.054 None 11-29-80 0.0978 0.375 0.0978 None
! M-26 Heating Steam and B 4-16-80 0.051 0.375 0.0978 None Condensate Return Penetration 11-29-80 0.0064 0.375 0.0064 None
! M-39 Freight Door B 4- 9-80 0.025 0.375 0.025 None S 11-28-80 0.026 0.375 0.026 None M-36 Containment Building C 4-14-80 0.0 0.37S 0.0 None Vacuun Breaker No. I 11-28-80 0.0 0.376 0.0 None M-32 Containment Building C 4-14-80 0.0 0.375 0.0 None Vacuum Breaker No. 2 11-28-80 0.0 0.375 0.0 None ID Electrical B 4- 9-80 0.031 0.375 0.037 None Penetration 11-27-80 0.0 0.375 0.0 None j{
h IE Electrical B 4- 9-80 0.0 0.375 0.0 None 5 Penetration 23 11-27-80 0.0 0.37S 0.0 None w ,- - - - - - --~":~l_"'
' ' _ .. T_T?' M
APPENDIX 5 -
SUMMARY
OF TYPE B AND C TEST RESULTS 6/79 - 12/80 (TABULATED LEAKAGE RATES DO NOT INCLUDE INSTRUMENT AND HUMAN ERROR FAC10RS)
TOTAL AS-FOUND ALLOWABLE LEAKAGE PENEIRATION TEST TEST LEAKAGE LEAKAGE AS-LEFT NO. l DESCRIPTION l TYPE l DATES l (SCFil) l (SCFil) l (SCFil) l RLMARKS 2A Electrical B 4- 9-30 0.0 0.375 0.0 None Penetration 11-27-80 0.0 0.37b 0.0 None 2B Electrical B 4- 9-80 0.046 0.375 0.04b None Penetration 11-27-80 0.0 0.375 0.0 None 2C Electrical B 4- 9-80 0.0 0.375 0.0 None i
Penetration g 11-27-80 0.0 0.375 0.0 None I
2D Electrical B 4- 9-80 0.0 0.375 0.0 Hone Penetration 11-27-80 0.0 0.375 0.0 None 2E Electrical 11 4- 9-80 0.0 0 375 0.0 None Penetration 11-27-80 0.0 0.375- 0.0 None 3 Electrical B 4- 9-80 0.589 0.375 0.029 Rescaled individual cable Penetration penetrations and retested on 4-11-80 with satisfac- r tory leak rate of 0.029 h, SCFil (as-lef t). (Ret.: g R0-80-01, LAC-6873) 4 w
11-27-80 0.0 0.37b 0.0 None
APPENDIX 5 -
SUMMARY
OF TYPE B AND C TEST RESOLTS 6/79 - 12/60 ,
(TABULATED LEAKAGE RATES 00 fiOT INCLUDE INSTRUMENT AND HUMAN ERROR FACTORS)
TOIAL AS-FOUND ALLOWADi.E LEAKAGE PENETRATION TEST TEST LEAKAGE LEAKAGE AS-LEFT NO. l DESCRIPTION l TYPE l DATES l (SCFH) l (SCFH) l (SCFHl l REMARKS 4 Electrical B 4- 9-80 12.377 0.375 0.019 Resealed individual cable Penetration penetrations and retested on 4-24-80 with satisfac-tory leak rate of 0.019 SCFH. (Ref.: R0-80-01, LAC-6873) 11-27-80 0.0 0.375 0.0 None 5 Electrical B 4- 9-80 0.589 0.375 0.029 Resealed individual cable i Penetration penetretions and retested n on 4-18-80 with as-lef t leak rate of 0.029 SCFH.
' R0-80-01, LAC-6673)
(Ref:
11-27-80 0.0 0.375 0.0 None 6 Electrical B 4- 9-80 0.0 0.375 0.0 None Penetration 11-27-80 2.95 0.375 0.0 Rescaled individual pene-tration and retested on 12-19-80 with as-left leak rate of 0.0 SCFH. (Ref:
R0-80-13, LAC-7278) 1B Electrical Penetra- 8 4- 8-80 0.006 0.0936 0.006 None tions Includes 21 Max. Each Max . M Individual Penetra- E tions Tested 11-30-80 0.0043 0.0936 0.0043 None 05 .
Separately Max . Each Max .
APPENDIX 5 -
SUMMARY
OF TYPE B AND C TEST RESULTS 6/79 - 12/80 ,
(TABULATED LEAKAGE RATES DO NOT INCLUDE INSTRUMENT AND HUMAN ERROR FACTORS)
TOTAL AS-FOUND ALLOWABLE LEAKAGE PENETRATION TEST TEST LEAKAGE LEAKAGE AS-LEFT NO. DESCRIPTION l TYPE l DATES l (SCFH) l (SCFH) l (SCFH) l RLMARKS l
1C Electrical Penetra- B 4- 9-80 0.002 0.0936 0.002 None tions Includes 25 Max . Each- Max .
Individual Penetra-tions Tested 11-30-80 0.005 0.0936 0.005 None Individually Max. Each Max .
M-33 Containment Building B 4-10-80 0.000174 0.375 0.000174 None Spray Hand Wheel 11-28-80 0.0007 0.375 0.007 None 0.05439 Replaced seat ring in up-g; M-21 Containment C 4-15-80 40.79 0.375 Ventilation stream damper, repacked and Discharge Dampers retested on 4-18-80 with as-left leak rate of 0.05439 SCFH. (Ref. :
R0-80-02, LAC-6BB2)
B 4-18-80 0.0 soap 0.0 None bubble C 11-30-80 0.0135 0.375 0.0135 None B 11-30-80 0.0 soap 0.0 None bubble M-31 Contai rnr.ent C 4-15-80 0.258 0.375 0.2b8 None hk Ventilation M Inlet Dampers B 4-15-80 0.0 soap U.0 None l' '
bubble {3
_ _ - . - - _ - - - - _ - _ _ . _ _ _ - . .~_;
APPENDIX 5 -
SUMMARY
OF TYPE u AfiD C TEST RESULTS 6/79 - 12/60 (TABULATED LEAKAGE RATES DO NOT INCLUDE INSTRUMENT AND HUMAN ERROR FACTORS)
TOTAL AS-FOUND ALLOWABLE LEAKAGE PENETRATION TEST TEST LEAKAGE LEAKAGE AS-LEFT NO. l DESCRIPTION l TYPE l DATES l (SCFH) l (SCFH) l (SCFH) l REMARKS M-31 Containment C 11-30-80 0.0 0.375 0.0 None (Cont'd) Ventilation Inlet Dampers B 11-30-80 0.0 soap 0.0 None bubble M-29 Reactor Vent C 4-12-80 0.0988 0.375 0.0988 None Hedder Valve 12-16-80 3.8 0.375 0.0 Replaced valve and retested on 1-14-81 with as-lef t leak rate of 0.0 SCFH.
i (Ref.: R0-80-17, LAC-7295)
S M-26 Containment Heating C 4-17-80 0.0 0.375 0.0 None Steam Valve C 11-27-80 0.0 0.375 0.0 None Heating Steam C 4-17-80 3.6 0.375 0.0 Replaced valve seals and Condensate Return retested on 4-2b-60 with Valve as-left leak rate of 0.0 SCFH. (Ref.: R0-80-03 LAC-6882)
C 11-27-80 14.34 0.375 0.0 Replaced valve internals and retested on 12-2-80 with as-left leak rate of
- bB0 4,LiG-7hB)
M w
~m- - - - - -
APPENDIX 5 -
SUMMARY
OF TYPE B AND C TEST RESULTS 6/79 - 12/80 (TABULATED LEAKAGE RATES DO NOT INCLUDE INSTRUMENT AND HUMAN ERROR FACTORS)
TOTAL AS-FOUND ALLOWABLE LEAKAGE PENETRATION TEST TEST LEAKAGE LEAKAGE AS-LEFT NO. l DESCRIPTION l TYPE l DATES l (SCFH) l (SCFH) l (SCFH) l RLMARKS M-13 Containment C 4-15-80 0.0 0.375 0.0 None Penetration Station Air Valve 11-29-80 0.0 0.375 0.0 None M-6 3 Main Steam Isolation C 4-20-80/ 5.803/ 22.47 5.803/ None M-7 and Bypass Valve / 4-13-80 4.71 Total 4.71 Feedwater Check Valve 12-16-80 4.657/ 22.47 4.657/ Teflon reapplied to feed-9.81 Total 0.02 water check valve seat to reduce overall Containuient
' Building leak rate.
E; Retested 1-14-81 with as-left leak rate of 0.020 SCFH.
M-17 Decay Heat Blowdown C 4-13-80 0.0 0.375 0.0 None and Steam Traps to Hotwell Containment 12-16-80 0.0 0.375 0.0 None Isolation Valves M-19 Shutdown Condenser C 4-13-80 0.0 0.375 0.0 None Vent to Offgas Isolation Valve 12-16-80 0.0 0.375 0.0 None r-M-23 Primary Purifica- C 4-13-80 0.0 0.375 0.0 None (5 tion Resin Sluice Line Valves 12-16-80 0.0 0.375 0.0 None [,
8
APPENDIX 5 -
SUMMARY
OF TYPE B AND C TEST RESULTS 6/79 - 12/80 (TABULATED LEAKAGE RATES DO NOT INCLUDE INSTRUMENT AND lluMAN ERROR FACTORS)
TOTAL AS-FOUND ALLOWABLE LEAKAGE PENETRATION TEST TEST LEAKAGE LEAKAGE AS-LEFT NO. l DESCRIPTION l TYPE l DATES l (SCFH) l (SCFH) l (SLFH) l REMARKS 1-A Alternate Core Spray C 4-13-80 0.0 0.375 0.0 None Check Valves 12-16-80 0.0 0.375 0.0 None 1-A Electrical Penetra- B 4- 8-80 0.002 0.375 0.002 None tions (Includes 3 Total (3) Each Total (3)
Individual Penetra-tions Test 11-29-80 0.0032 0.376 0.0032 None Separately) Total (3) Each Total (3)
IU 1-A Containment Building C 4-10-80 0.04 0.375 0.04 None
' Suction Drain Line Isolation Valves 11-29-80 0.16 0.375 0.16 None M-11 Demineralized Water C 4-14-80 0.096 0.375 0.096 None Containment Isolation Valve 11-29-80 0.205 0.375 0.205 None M-18 Condensate Deminera- C 4-18-80 0.0023 0.375 0.0023 None lizer to Seal Injec-tion Reservoir Makeup 12- 4-80 0.143 0.375 0.143 None Line Containment Isolation Valve _
M, M-12 Containment Control C 4-15-80 0.0 0.375 0.0 None 5$
Air Isolation Valve E.
12-16-80 0.0 0.375 0.0 None E3
4 APPENDIX 5 -
SUMMARY
OF TYPE B AND C TEST RESULTS 6/79 - 12/80 (TABULATED LEAKAGE RATES DO NOT INCLUDE INSTRUMENT AND HUMAN ERROR FACTORS)
IOIAL AS-FOUND ALLOWABLE LEAKAGE PENETRATION TEST TEST LEAKAGE LEAKAGE AS-LEFT NO. l DESCRIPTION l TYPE l DATES l (SCFH) l (SCFH) l (SCFH) l RLMARKS M-3 HPSW Containnent C 4-14-80 0.019 0.375 0.019 None Isolation Valve 11-29-80 0.2109 0.375 0.2109 None M-23 FESW Ion Exchanger C 4-13-80 0.0 0.375 0.0 None Resin Sluice Line Containment 11-30-80 0.0 0.375 0.0 None Isolation Valves
' M-22 Retention Tank C 4-17-80 0.0 0.375 0.0 None y; Pump Discharge Control Valve 11-29-80 > 0.56 0.375 0.0 Valve was relapped, 9askets
< 4.0 and packing replaced and retested on 12-4-80 with as-left leak rate of U.O SCFil. (Ref.: RO-80-lb, LAC-7268)
M-28 Reactor Cavity Purge C 4-16-80 0.042 0.375 0.042 None Air Isolation Check Valve 12-16-80 1.97 0.3/S 0.0 Replaced valve and retested on 12-19-80 with as-left leak rate of 0.0 SCFH.
(Ref.: R0-60-17, LAC-7295) 9
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1A Containment Building C 4-17-80 0.0017 0.375 0.0017 None E; Pressure Switches 6 11-29-80 0.0 0.375 0.0 None $
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