ML20002C880

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Special Rept 27, Reactor Containment Bldg Integrated Leak Rate Test,Sept 3-26,1977
ML20002C880
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 02/03/1978
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20002C878 List:
References
NUDOCS 8101120270
Download: ML20002C880 (39)


Text

{{#Wiki_filter:, t O SPECIAL REPORT NO. 27 .'d (. REACTOR CONTAINMENT BUILDIEG INTEGRATED LEAK RATE TEST September 3 through 26, 1977 INTP.0 DUCTION In fulfillment of the requirements of the Big Rock Point Plant Technical Speci-fications, Section 3.7, the Containment Integrated Leak Rate Test (ILRT) was conducted on September 3-26, 1977. This test was the 8th reduced pressure test of the series dating from June 1962. A summary of the past ILRT results is pro-vided in Table 1 and Local Leak Rate Test results in Teble 2. Weather conditions during the 1977 Integrated Leakage Rate Test ranged from overcast and rain to clear and sunny. The temperature throughout the total test-ing time was as low as 450F and as high as 890F. The wind speed varied from calm to 30 MPH. This great variation in temperature and sky conditions did cause some variations to be experienced in containment temperature and, hence, containment pressure. This is because the containment vessel is made of carbon steel plate ranging from 1/2" thick to 3/4" thick with 1/2" of cork mastic for insulation and, thus is readily influenced by atmospheric conditions. The following items are included in this report: .h] I. Test Procedure A. Test Data Aquisition B. Description of Physical Setup II. Test Results A. Calculational Methods and Analysis of Allowable Leakage Rate B. Integrated Leak Rate Test Results C. Instru=ent Error Analysis III.Appendicies, Tables and Graphs A. Appendicies 1. Local Leakage Rate Test Summary 2. Instrument Error Analysis 3. Technical Justification For Next Scheduled ILRT Being in 1980-1981 4. Analysis of Allowable Leakage B. Tables Table 1 - Past ILRT Test Results Table 2 - Local Leak Rate Test Results From April 1974 to September 1977 Table 3 - Major Events C. Figures and Graphs i k 1. Raw Data Graphs l A. Figure 1 - Containment and Atmospheric Temperatures and Dewcell l Temperature Plot 2 o f M O R '? b

3 s Special Report No. 27 Reactor Containment Building integrated Leak Rate Test i I. TEST PROCEDURE Pressurization The containment vessel was pressurized with two 750-cfm air compressors, each equipped with an aftercooler. Two high-volume filters were incor-parated for oil vapor separation. Pressurization to 2.3 psig was com-pleted in approximately 4 hours. Then, due to compressor malfunction, only one compressor was used af ter this and a pressure of 13.3 psig was attained 30 hours later. Temperatures recorded downstream of the compressors during pressurization were as follows: Cooling Water into Aftercoolers 650F Cooling Water Out of Aftercoolers 87'F Air Into Coolers 140*F Air Out of Coolers 85'F Vessel Ventilation The heating and cooling unit fans in the vessel were'*op[ rating through-out the test to provide mixing of the air. The steam drum cavity access door l was open to allow mixing of the drum cavity air with vessel air. l Moisture Control t l l The only surfaces of water to provide a significant source of moisture to the air is the spent fuel pool and the reactor vessel. Aluminum covers were installed on the spent fuel pool and the reactor vessel head was in place, protecting against evaporation. The other surfaces (sumps and reactor cooling water tank) have relatively small areas; however, l l the reactor. cooling water tank was covered.throughout the test, and l the su=ps were pumpeddown as an initial condition prior to pressurization. Temperature Control l l The heating and cooling units were lef t out of service in this test for two reasons. First, previous containment leak rate tests conducted with the addition of heat to vessel air to avoid temperature drops during night-time hours were not wholly successful. Second, the cooling of the pressuriz-l ing air to near ambient conditions before its entry into the containment vessel j facilitated rapid stabilization of temperature. A. Test Data Aquisition l Data were taken at one-half intervals of the following: s. Containment pressure-(. b. Barometric pressure c. Differential pressure between sphere and reference vessels d. Containment temperature (4) e. Reference temperature (3) -f. Outside temperature (1) g. Containment Deweell temperature (4) ~

/ 2* ~ Specici Report No._jy__ Re ct:r Containment Building' Intagratid L ck Rata T:st Introduction (Contd) III.. Appendices, Tables and Graphs (Contd) C. Figures and Graphs (Contd) 1. Raw Data Graphs (Contd) B. Figure 2 - Containment Pressure (prior to vapor pressure correction) and Barometric.' Pressure 2. Containment Leakage Rate' A. Figure 3 - Containment Mass Vs. Time (Absolute Method) 3. Figure 4 - Containment Test Manometers 4. Figure 5 - Reference Chamber - Temperature and Vapor Pressure Instrumentation Locations + 9 e _,e',' * -* , es i e b 1 e 4 ewe e mse s em. e a oemo se. = * * -w ---e e r-y

4 i. Sp:cial Report No. 27 Re:ctor Containment Building Integrated Leak Rate Test I. Test Procedures (contd) 5. Description of Physical Setup Temperature . h: Resistance-bulbsatfourlocationswithinthec$ntainmentwere usedito determine the average temperature. These bulbs were located near the four major reference volumes and their tempera-tures were averaged in proportion to the volumes they represented. Vapor Pressure The average vapor pressure was determined through use of four electronic-type Dewcel elements. Location of these elements and the method of averaging was the same as with the' resistance bulbs ~ discussed above. As can be seen in Figure 1, the vapor pressure cycles diurnally. Inspection of containment walls showed that condensation of mois-i ture occurred during the time when the vapor pressure was decreasing. Pressure Measurements r./ "* .1.'g The barometric pressure was measured using a standard mercury baro-meter. The containment pressure was measured by a mercury manometer and the differential pressure ber. ween the containment and reference system was measured with an inclined water manometer. Equipment and' Instrumentation -Dese,ription Ba rome ter-Measures atmospheric pressure Meriam Instrument Company - Type W Model 31 EG10 Measurement Accuracy .005" Hg Mercury Column Measures containment building pressure Meriam Instrument Company Type W- - Model 30 E325 . Measurement Accuracy .05" Hg 4 S l .[

g Sp:ciS1 Rep;rt No. 27 R30ct:r Contcinment Building Intsgrated Lstk Rate Tast I. Test Procedures (contd) ( 4 B. Description of Physical Setup _ (contd) pifferential Manometer Incline water manometer Meriam Instrument Company Type WM Model 40 HE35 Measurement accuracy .00073" Hg Inclined Mercury Manometer Measures reference system prcssure Meriam Instrument Company Type W Model 30 EB25 Measurement accuracy .04" Hg Tcaperature Measurements Foxboro Dynatherm Resistance Bulb read by a General Electric 312 Computer Measurement accuracy smallest scale division: .12

  • f, t

( ~ Vapor Pressure Measurements The Foxboro Company Electronic type Dewcel element Model 270lRG with NR226 RTD Measurement accuracy.001" Hg Gas Meter - For Controlled Leakoff Test American Gas Meter Company Type AL-175 Company number 3742-00401 3 Capacity - 175 f t /hr Accuracy - + 1% Gas meter calibrated by Consumers Power Company SP&LS Department Cas Meter - For Feedwater Check Valve Leakage Measurement American Gas Meter Company Type 175 AM-TC S/N 1694923 Accuracy - + 2% Calibrated by Consumers Power Company SP&LS Department s m'

( '6 Special Report No. 27 Reactor Containment Building Integrated Leak Rate Test I. Te st Procedures (contd) B. Description of Physical Setup (contd) Equipment Air compressors (2) - 750 cfm Aftercoolers (2) ,High volume filters (2) II. TEST RESULTS A. Calculational Methods and Analysis of' Allowable Leakage ~ Test Methods Two test methods are available for use for the containment leak rate test at Big Rock Point. These are the reference vessel method and the absolute method descirbed in ANSI N45.2 - 1972. Measurements were recorded each half hour and the cumulative leakage determined at the end of each one-half hour period. A linear least squares fit to the cumulative leakage data was made and the standard deviation determined using the above data. 1.65 times the standard deviation was used to demonstrate the 95 percent confidence interval.* )*f. [ Reference Vessel Method The reference system.aed to measure the leak rate is the same as has been used on previous tests on the Big Rock Point Containment Vessel. This system consists of 8 interconnected chambers. The volume of each chamber is theoretically proportional to the volume of the air space in which it is located. A schematic diagram of the reference system and test instruments is shown in Figures 4 and 5. The reference system was-extensively checked and leakage rates performed before and after the test. These measurements showed that the leakage rate, if any, was insignificant. In addition, the reference pressure was less than containment pressure to insure conservative interpretation of a reference volume leak. The percent leakage is calculated by the following expression: ~ P ) + (P -P y)~ - (P - P ) + (P -P )- - (P y ~ 8' " T P-P P -P LOO 2 1 V, 1 V1 A I Where: (P - P) = the differential pressure between the reference system and the containment, inches of Hg pressure of the containment, inches of Hga P = l Vapor pressure of the containment air, inches of Hga P = y P = Vapor pressure of the reference system air, inches of Hga y T = Temperature, 'R 1 = Start of test period l 2 = End of test period

~ ( 7 Special R:p;rt No. 27 .Rencter Contcinment Building Intigrated Lask Rate Tast II. Test Results (contd) { A. Calculational Methods and Analysis of Allowable Leakage (contd) Reference Vessel Method (contd) Early in testing period, it was determined that the reference vessel system was weighted to the warmer portions of containment. It was felt that the absolute method would then yield a more accurate deter-mination of containment leakage. Absolute Method The absolute method depends on absolute measurements of the temperature and pressure of the containment structure atmosphere. This method has been used successfully in the past at Big Rock Point.. The percent leakage is calculated by the following' expression: p. 4 , % Leakage 1 - 1 (f_2 2) 100 ~ 2(1 V) y Where the units are the same as described previously. ./ This percent leakage is then converted to cont'aihme'nt mass by calculating the containment initial mass and multiplying by(1-%' leakage). Calculation of a linear least squares fit to the cumulative leakage is then performed. Measurements Both the Reference Vessel and Absolute Methods require measurements of temperature, barometric pressure, containment pressure, containment vapor pressure and in the case of the reference vessel method, the differential pressure between the reference system and the contained atmosphere. The various measurements were described above and are plotted in Figures 1 thru 3. Allowable Leakage Rates Technical Specifications .174%/ day 10CFR50 Appendix J .347%/ day The calculations supporting the above leakage rate limits are contained in Appendix 4. 4 ( 9

s \\ 8 Specici Reptrt No. 27 Reactor Containment Building Integrated Leak Rate Test II. Test Results (contd) B. Integrated Leak Rate Test Results During the integrated leak rate testing period, there were two hold tests and two controlled leakoff periods. TheJadditionalholdtest and leakoff periods.were due primarily to a malfur.ctioning air compres-sor and a leaking feedwater check valve'. An explanation for performing two hold tests and two controlled leak tests follows as well as the final integrated leak rate test results. During initial pressurization of containment an air compressor was found to be injecting oil into its air handling unit. As a result, oil was blown past the air filters into the sphere. The bad compres-sor was removed from service and pressurization was continued with the one air compressor. The first hold test was completed with apparent acceptable leakage and the first controlled leakoff test was initiated. During this period, a leakage rate significantly larger than the superimposed controlled leak was noted and subsaquent investigation resulted in discovery of leakage through the feedwater check valves. It was apparent from the test data that,the feedOatef leakage was excessive, and therefore, the feedwater line was isolated and a second controlled leakoff test begun (with intentions of performing a subsequent second hold test as well). During the initial hours of the second hold test, inconsistencies in absolute containment pressure readings lead to the discovery of oil in the lines connecting the manometer to conta.inment. Apparently, some of the oil blown into containment by the air compressor malfunction had precipitated in the instrin,ent lines to containment. As a result of this discovery, the sensing lines were purged and the controlled leak test restarted and a' redundant "U" tube mercury manometer was installed to ensure the sphere mano-meter was accurately following containment pressure changes. The original and redundant manometer readings followed each other closely and thus proved the validity of the original manometer readings through-out the remainder of the leak rate test. The controlled leakoff testing was continued and resulted in an observed leakage of.306%/ day. The second hold test was initiated and the resultant observed leakage rate was.002 +.043%/ day, which was more than acceptable, when compared to Technical Specification (.174%/ day) and Appendix J limits (.347%/ day). The hold test was terminated and the containment depressurized Lased upon the above acceptable leakage rate.

i 9 Sp cial Report No. 27 R::ctor Contcinment Building Int;grrt:5 Lrak Rata Tact II. Test Results (contd) B. Integrated Leak Rate Test Results (contd) Comparing the integrated leakage rate results for the imposed leakage with the observed hold test leakage: .347%/ day +.002%/ day =.349%/ day-Error Band -25% =.262%/ day +25% =.426%/ day This proves the instrument accuracy to the satisfaction of ANSI N45.4/1972 by falling within a i 25% error band. The feedwater check valve was determined to be leaking excessively through use of a calibrated gas flow meter. Maintenance was performed on the valve seat and subsequent local leakage rate ' testing resulted in an acceptable leakage rate. Local leakage rate testing resulted in an acceptable leakage rate. The valve leakage rate af ter maintenance was 91.0 + 1.01924 hrs. ( 95% confidence interval) or in terms of % containment mass / day, .070 1 001"/ day. To correct the second hold test results of.002'f.d43, for unaccounted-for leakage rates, the following calculations were perfo.rmed. Unaccounted Loca1 Leakage Rates Equivalent Component (+ 95% confidence interval) Containment Leak Rate Feedwater check valve 91.0 i lb/24 hrs. .070 i.001%/ day ILRT instrument .0026 Essentially zero penetrations Treated waste return .001 Essentially-zero Demineralized water supply 2.52 Essentially zero .070 1 001%/ day Measured ILRT Results +.002 +.043 Cerrected ILRT Results .072 1 043 =.ll5"/ day at 45% con-fidence level Noting from Appendix 4, the Technical Specification leakage rate limit was.174%/ day. Thus, the final 1977 containment integrated leakage rate was more than acceptable.

10 Special' Report No. 27 Reactor Containment Building Integrated Leak Rate Test - II.. Test Results (contd) C. Instrumentation Error Analysis The error analysis is to prove the instruments used in the ILRT are of suf ficient accuracy to' be used in the determination of the containment leakage rate. Appendix 2 contains the required instru-ment error analysis.- It is interesting to note that the controlled leakoff portion of the testing did result in an " observed" leakage rate within the i 25% error band imposed by 10CFR50 Appendix J, Section III.A.3.b. The observed leakage rate error band and the 95% confidence level " observed leakage rate" were: Superimposed leak =.347%/ day + 25% =.436%/ day Containment leak =.002%/ day - 25% =:2262%/ day L =.349 / day t Observed leakage rate.307%/ day A listing of equipment and instrumentation used in the performance of the ILRT was presented in part IB " Description of Physical Setup". 4 III. APPENDICIES, TABLES AND GRAPHS ' M. ** A. Appendices 1. i.ppendix 1 - Local Leak Rate Test Summary Semi-annual Local Leak Testing Semi-annual local leak test results are presented in the plots attached to Table 2. In the period between the last two containment integrated leak rate tests (April 1974 - September 1977) one component has failed semi-annaal local leak rate testing. This component was the'24" contain-nent supply ventilation butterfly valve. This valve was installed during the 1974 refueling outage and is equipped with an adjustable 24" Nordel seat. Each of the four times excessive leakage was discovered, the seat was readjusted and the resulting leakage rate determined to be acceptable. Even though the seat was out of adjust-ment, there appeared to be no signs of excessive wear. As a result of the problems encountered with this valve, the original Nordel seat was replaced during the 1977 refueling outage. A preven-tative maintenance program has been set up for valve seat replacement every two years. This program was initiated to eliminate hardening of the rubber seat material through ageing which results in, the ex-cessive local leak rates. l l t i

f ( 11 Specici Report No. 27 - Recct:r Containment Building Integrated Lerk Rats Tsst III. Appendicies, Tables and Graphs (contd) { A. Appendicies _-- (contd) 1. Appendix 1 - Local Leak Rate Test Summarv'(contd) Refueling Local Leak Testing Results of the 1977 refueling local leak tests are presented in Table 2. During the 1977 refueling outage, twenty-one additional valves in ten different systems were local leak rate tested to comply with the requirements of 10CFR50 Appendix J. There were only three tests which resulted in corrective action to repair leak-age. These tests included those for the demineralized water supply check valve, the cleanup system resin sluice valve (CV-4093), and the control rod drive pump integral poppet valves and discharge check valves. The demineralized water supply check valve was local-leak tested in August 1977 and found to leak excessively. The check valve seat was lapped, the valve retested and found, to be acceptable. Additional testing indicated that even though the check valve leaked excessively, the backup control valve'.*outside containment (CV-4105) would have provided containment integrity. During leak testing of the cleanup demineralizer resin sluice t valves, the volume between the isolation valves in the sluice line could not be pressurized Investigation of the problem one of the valves (CV-4093) was revealed that the operator arm bent and was binding on the vat.e body preventing the valve from fully closing. The operator arm was subsequently-repaired and the isolation valves successfully leak tested. The results of this test indicated that another sluice line isolation valve (CV-4091) would have provided adequate containment isolation. Local leak testing of the control rod drive system lead to the discovery of two components having relatively high leak rates. These two components were the control rod drive pump discharge check valves and the pump integral poppet valves. The cause of the high leak racee was attributed to wear of the components over fifteen years of service. The discharge check valves were replaced by a check valve in the 2" suction line common to both control rod urive pumps. After installation, the new check valve was leak tested satis f ac torily. On the failure of the integral poppet valves to pass their leak tests, the valves were lapped and retested. Tests of the #1 control rod drive pump suction poppets and control rod drive pump #2 discharge poppets resulted in acceptable leakage, i e

i 12 Special Report No. 27 Reactor Containment Building Integrated Leak Rate Test III.. Appendicies, Tables and Graphs (contd) 1. Appendix 1 - Local Leak Rate Test Summary (contd) Local Leakage During ILRT .?. Leakage through an additonal valve, the feedwaYer check valve, was observed during the 1977 integrated leak rate t'est. In order to com-plete the test, the feedwater line was isolated and a second hold test and controlled leakoff test initiated. After obtaining acceptable ILRT results, a gas flow meter was attached to a vent in the feedwater line and the leakage through the feedwater check valve measured. Leak-3 age through the valve exceeded 175 f t /hr. which by itself was in ex-cess of T,echnical Specifications allowable containment leakage. Disassembly and repair of the check valve revealed hard scale deposits on the disk a;d valve seat. After grinding and lapp'ing, a subsequent local test was performed resulting in acceptable leak rates for both the integrated leak rate test and local leak rate testing totals. The feedwater check valve has received little preventative maintenance in its fifteen years of service. In previous integrated leak rate tests, it was not considered necessary to drain and vent.this line to the con-tainment atmosphere. All subsequent Appendix J) Type A integrated leak rate tests will be performed with the valve drained'hnd vented as it was during the 1977 ILRT. Appendix J, Type C tes'tidg vill also be per-formed each refueling to monitor the condition of the valve. O t -O*% O 9$ @$ M4 m36 eid' we Me s 6

r -f B)J 3 I Special Report No. Re:cter Contsinment Building Intsgrated Luk Rats Tact -III. Appendicies, Tables and Graph's (contd) ~ A. Appendicies (contd)

2. -Appendix 2 - 1977 Integrated Leak Rate Test s-4 APPENDIX [

Big Rock Point Plant 1977 Integrated Leak Rate Test INSTRUMENT ERROR ANALYSIS A list of instruments used during the 1977 ILRT was presented"in the "Descrip- ~ . tion of Physical Setup" Section I(B). Instrument and system errors associated with instruments used for the absolute method are as follows: Individual Instrument System Total Error Error Sensors Error Tempera ture .12*F .05'F

l. M..

.066*F Vapor Pressure .001"hg .00043"hg 4 ', .0006"hg Pressure (Containment) .05"hg 1 .05"hg -Pressure (Atmospheric) .005"hg 1 .005"hg Individual Instrument Errors are those errors associated with a given reading from each instrument. The System Errors for temperature and vapor pressure are a result of on-line computer roundof f of air temperature and dewcell temperature to the nearest.05*. =.... - ~

( 14 Sp cicl' Report ND. 27 Reactor Contrinment Building Integrnttd Luk Rata TAat The % Containment which leaks per day 'is determined by the following relationship: 2400 B1 Bo where k Absolute method, Containment Mass M = T Itm - ItIm/n B1 = gg2 - (It)2/n Least Squares fit ) Slope & Intercept Im EE Bo = +B1 n n j 'rhe inctrument error associated with this method is determiaed as follows: '~ 2 2 2 .'3 L '2 O 0 + at 1 og L 3B B '.. '..,,a ' t y 1 g 3B, o ,L 3L = 2h00 3B B y - 2h00 3L = B BB B2-1 O O O B = o Im + o cB 0 3B L 3Im 1 BB,= 1_ 3Em Bo = It 3B n y = TI(M) =Yna og 2 2 2 2 = 3B 3B oB ( ) ( Itm) ( ) ( Im) 1 arts BIm e.,

i_ 15 Speciau. Rsport No. 27 _ Ratetor' Containment. Building Intsgrsted Leak R;.te Tast I, '3B ar tm Et2- ( I t)d/n 3B -I t/n 1 = Ym~ Etd - (.It )'-/n. L 2 r( atm)2 ( om) "Itm = 3, _ 3tm an ,1,.. 0 + ( p) (# ) + ( ) (#p) (3 ) (o) 4 Y Y P-P 3 M, _k. 3M = - k y 3P T ST Td '.,e-e 4 3M k j-3P T V 1 1 1 s. m e-s r +,yi &,y.- +

C 16 I Special R; port No. 97 Reactor Containment Building Integrated Leak Rate Test Typical values for the terms in the preceeding equations follows: 8 = +.05 in Hga Containment Pressure P

= 55 7 in Hga P

L(measured with sphere manometer) .6 in Hga o ~ = 1 0006 in Ega -Containment Vapor Pressure P = y pv (measured by Deveells) 0 = +.066*R 530*R T Contain=ent Te=perature T = Time t = 0-+2h hrs at 1/2 hr in',ervals 55*I Contain=ent Mass M =k = k (.10k) 530 Absolute-Slope B (1bn/hr) y Intercept B (1bs) (%/ day)[j, Leak. Rate L 24 hr,.:i*hh 1 [.d 2h00 Const D R'(Contain=ent mass gas constant) Const 1.2h6 E6

  1. Data points n

48/ day Substituting these values and errors into the preceeding equations yields a total instrument error of.125/ Day cor tainment mass. O 9 'i F

I.- 17 Special R; port No. 27 . Retetor Containment Building Integratsd Leak Rata Test { APPENDIX 3 i TECICTICAL JUSTIFICITION FOR NEXT SCHEDULED ILRT BEING IN 1980-1981 The purpose of this analysis is to provide technical justification for the next proposed containment integrated leakage rate test. The proposed date is about 3-1/2 years after the Septenber,1977, ILRT, which is late 1980 or .early 1981. The basiy for this analysis is 10CFF50, Appendix J and the last two containment ILRTs results (197h and lVii). 1 In Section A.6.b of Appendix J, it states : "IftwoconsecutiveperiodictypeAtestsfailthmeetthe ~ applicable acceptance criteria in III-A.5 (b), not with-standing the periodic retest schedule of III.D,a Type A ~ test shall be performed at each plant shutdown for refueling or approximately 18 months'.' UOTE: III.A.S.b is: Acceptance criteria - (1) Redue.ed: pressure tests. The leakage rate Ltm shall be less than 0.75 Lt. If_ local leakage measure:ents are taken to effect repairs in order'.to meet the acceptance criteria, these measurements shall be taken at a test pressure Pt. i (2) Peak pressure tests. The leakage rate

  • Lam shall be less than 0.75 La.

If local l I leakage measurements are taken to effect repairs in order to meet the acceptance l criteria, these measurements shall be taken at a te.t pressure Pa. AND III.D is: Periodic rete '. schedule - 1. Type A test. (a) After the greoperational leakage rate tests, a set of three Type A tests shall be performed at approximately equal intervals during each 10-year service period. The third test of each set shall be conducted when the plant is shutdown for the 10-year plant in-i service inspections. (b) Permissible periods for testing. The performance of Type A tests shall be limited to periods when the plant facility is non-operational and secured in the shutdown i condition under the administrative control and in accordance with the safety procedures defined in the license. (' t Y-~ y -- -, - - - + y

18 i Special R: port No. 27 Reactor Containment Building Integrated Leak Rate Test Appendix 3 (.contd) During the last two containment leak rate tests, the excessive leakage rates encountered were due to a single component (1974 - supply ventilation butter-fly valve; 1977 - feedvater check valve) which was th'en repaired and test results proven r.cceptable. In the 197h ILRT, a leakage rate oi.309%/ day was experienced during the first hold test. This leakage rate is almost double the Technical Specification limit of.175%/ day. Quoting from page 4 and 5 of the 197h ILRT Report: "Upon investigation for the source of the high measured leaktge rate, it was discovered that the 24-inch butterfly valve on the supply ventilation line into the containment building was leak-ing at the containment-side flange. This valve had been installed during the shutdown prior to conducting the leakIrate test. An estimate of the leakage rate was made by collimating the air flow through a one-inch diameter (I.D.) pipe and measuring the velocity profile across the pipe. The leakage rate through the flange was estimated to be 0.292%/ day. Hence, essentially all of the leakage measured during the first hold test was through the supply vent butterfly valve containment side flange. .I.* Bolts were tightened around the flange and the 1,dakage stopped. The containment pressure was increased to appro'x!,=ately 8 inches of H 0 above the reference system and conditions, vere allowed to 9 stabilize for four hours prior to initiation of the second hold test." This portion of the 1974 test report related the fact that the 2h-inch cupply ventilation butterfly valve containment side flange was leaking through at the rate which was observed in the first hold test. Thus, by tightening down on the bolts around the flange, the leakage storped. (Note the resultant containment leakage rate of.075%/ day was still within the .75 L li=it.) The valve had been installed during the same outage the inte-gratek 14,ge rate test was performed. The ILRT essentially acted as an in-stallation acceptance test for the valve, especially the containment side flange. The 1977 contain=ent integrated leak rate test was the first containment test that was in full compliance with 10CFR50, Appendix J. Draining and venting of several systems to attempt a close approximation of system status ofter an accident was perfor=ed in preparation for the test. The feedvater system was one system in which a leakage path was found. The, leaks.ge path was through two,feedvater check valves. The feedvater system was then isolated and after the completion of the test, the leakage rate through the check valve van determined, utilizing the pressurized containment as a source of air. 'Ihe check valve leakage was measured with a gas flow meter attached to the feedvater line to obtain the magnitude of the leakage. The feedvater line leakage path was detected approximately half way through the controlled leakoff portion of the ILRT. Examination of test results at that time indicated a leakage rate greater than expected in the controlled leakoff portion. [-

i 19 Special'R port.No. 27 'Re:ctor Cont:inment Building Integrat:d Leak Rsta Tast-

  • Appendix 3L(contd)

(' L In turn, investigation of the leakage resulted in the conclusion that the feed-water check' valve was leaking through. The feedvater'line was then isolated. Thus, the initial hold test was considered invalid and corrective action was taken to continue with the containment testing. In conclusion, as a result of the excessive leakage rate encountered, due to the feedvater check valves, and the evidence presented above, this ILRT is considered to be the first ILRT failure. Thus, if the ILRT in 1980-81 re-sults in unacceptable results, then III.A.6(b) applies. 9 O*. E i D M4 6 hO' ge w 4 4 e w

( 2a -Special RIport No. 27 Reactor Contairment Building Integrated Leak Rate Test APPENDIX h ANALYSIS OF ALLO'4ABLE LEAKAGE 10CFR50 Appendix J, Section III.A.h Allowable-Leakage =Laghy-Pa La =.5%/ day from Technical Specifications Section 3 7 P = Test Pressure = 13 psig (test conditions). T P,= Accident Pressure = 27 psig (Ref FHSR Section 3.2.1) h -Allovable leakage = (.5%/ day) ( ) =.347%/ day To obtain the desired controlled leak rate, the following ,[,., must be done: CLR =( 0)-(LR5/ day) (containment. volume) ( 4 min =(100) ( )(9.hx10'FT)(lk(min} = 2.265 FI / min The time to leak off 1 FT vill be: 26.h9 seconds J,1 =.h41 min = CLR 2.265 FTa FTS This is the controlled leakoff based upon the Appendix J maximu=. i l

a 21 ~ 27 Specici R: port No. . Reactor Containment Building Integr:.ttd Leak R*ts Test Appendix k (contd) f Technical Specification Leakage Limit From Section 3.T.6: 5 L. P,2 -1 p = t {- Pd ~1 N t a L, = % leakage rate, at extrapolated pressure L = % measured leakage rate at air test pressure t i P, = extru.polated pressure, atmosphere absolute P = test pressure,' atmosphere absolute t p = viscosity of air at test pressure and temperature g i , = viscosity of air steam nixture at, accident pressure and temperatitre p 9 ;: L, =.50 / day (from Technical Specifications Section 3.7) L = W.now g P, = 27 psig = 2.837 atmospheres absolute P = 1.896 atmospheres absolute (from test data) t p = 181.3 i r p ise (fr m test data) t p = 171.6 micropoise (accident parameter) L .5%/ day =.lTh%/ day .5%/ day = e = g,_ (2.837) -1 81.3 2.870 t P'-1 p ('p*g _ 1) (, 1.896)' - T1.6

22 s Specic1 R; port No. 27 Reactor Containment Building Integrated Leak Rata Test TABLE 1 SUl& jay OF BIG ROCK POI!!T PLAtlT C0flTAINENT II."fEGRATED LEAK RATE TESTS 5 ~ Test Measured Leak Allowable Leak Date Pressure (Psig) Rate (%/ Day) Rate (%/ Day) Ccements 1/61 27 0.036 0.5 Included pneumatic over-load test at 33.75 Psig 6/62 10 0.021 0.121 Allowed leak rate is 75% of Technical Specification reduced pressure allowed leak rate from 6/62 to the last test of h/74. h/64 10 0.037 f; 0.03h 0.121 h/66 10 0.077 + 0.025 0.121 ,z 7/68 10 0.061 3;0.017 0.121 '. [ 3/70 10 0.08h j; 0.030 0.121 h/72 12 0.028 f; 0.072 0.1h9 h/Th 13 0.075 f; 0.0h7 0.131 Measured containment leak-age, rate after acceptance of ventilation valve b d 9/77 13 0.072 j;0.0h3 0.17h/0.347)!)955 confidence level of containment leak rate corrected for measured local leak-age rate of feedwater check valve C) Technical Specification limit /10CFR50 Appendix J, Section III A.h limit. e-

2b ? t4 Special RIport No. Reactor Conte.inment Building Intsgratsd Leak RI,ta Tant TABLE 2 LEAKAGE RATES IN LES/2h HR (EXCEPT WHERE SPECIF'IED)_

  • (See attached seven graphs for trending of leakage rates)

EQUIPIEiT PERSGIGEL ESCAPE SUPPLY EXHAUST TOTAL TECH SPEC DATE LOCK LOCK LOCK VENT VALVE VENT VALVE LEAKAGE LIMIT >/30/74 13 9 6.7 0.0 S.69 16.0-h5.3 h23.7 4 1v. 00h rViv. 001 3/ /75 31.74 52.07 0.0 1428.5 90.37 1602.75 h60.0 41v.0.05h div.0.02C 3/./75 8.69 17.k2 0.0 63.79 90.37 180.32 460.0 vTriv.0.05h 771v.0.02 SPECIAL 'IESTS 4/27/75 8.7h 17.42 0.0 76.83 77.06 180.05 h23.1 5/26/75 8.7h. 17.k2 0.0 325.30 77.06 928.52 h23 7 5/29/T5 8.7h 17.h2 0.0' 2.68 77.06 ,[., 105.90 h23.1 5/q ~5 8.7h 17.h2 0.0 3.0 77.06 103.22' 423.1 5/26/75 8.74 17.h2 0.0

1. 61 77.06 10h.83 h23.1 7/24/75 8.74 17.h2 0.0

'h.79 77.06 108.01 h23.1 B/23/75 8.74 17.42 0.0 1.957 77.06 105.18 h23.1 9/22/75 20.55 h.9 6.61 0.97 90 90 124.09 h5h.0 /v1v 0.15 /viv 0.01 h/21/76 12.63 1.7 10.15 745h.4 101.23 7580.1h h17.13 d1v 791v 0.02h2 0.00099 k/23/76 Assumed Assumed' Assumed 1.68 Assu=ed Same 127.h2 h17.13 Same Same Same SPE IAL TESTS b/28/76 Assumed Assumed Assu=ed 0.95 Assumed Sa=e 126.69 L16.81 Same Ss=e Same l @/19/76 Assumed Assumed Assumed 8h.997 Assumed Sa=e 210.73 L17.90 Same Same Same ' operated 51 times since h/21/76) $/J.,, c. 6 Assumed Assumed Assumed 279.h8 Assumed Sa=e h05.22 h17.81 Same Same Sa=e operated 89 times since 5/19/76) I

2c Spezial Report No. 27 Reactor Cont:inment Building Int:6rct:d Leak B;to Tnt TABLE 2 f . LEAKAGE RATES IN LBS/2h HR (EXCEPT WHERE SPECIFIED)_ Mee attached seven graphs for trending of leakage rates) l EQUIP:'EST PERSONNEL ESCAPE SUPPLY EXHAUST . TOTAL TECH SP: 3 LOCK LOCK LOCK 7ENT VALVI VENT' VALVE LEA 5'AGP LIMIT 3 19/76 Assumed Assu=ed Assu=ed 381.69 Assu=ed Sa=e 507.h3 417.86 Same Sa=e Same 19/76 Assumed Assumed Assumed 3k.21 Assu=ed Same 159 95 h17.7 Sa=e Same Same @0/76 Assumed Assu=ed Assu=ed 12.11 Assumed Sa=e 137.85 Same Same Sa=e ./23/76 1.3 0.0 12.35 12.11 31.89 57.66 L37.92 velv.0079 relv.0059 ?/29/76 Assumed Assumed Assumed Assumed Assumed Same 57.66 h37 99 Same Sa=e Sa=e Same RDS pene- .Ir'.'-- tration H-33 tested & leakage 3 found n s 3-1x10-which is essentially

.ero

/h/77 Assu=ed Assumed Assumed 10.97 Assumed Same 56.52 431.08 Sa=e So ::e Same /31/77 2.83 .26 7.19 Assumed Assumed Sa=e 53.15 431.05 A lv.01 r viv 0.0 Same /3/77 Assu=ed Assumed Assu ed Assumed 22.58 h3.8h 433.36 Same Same Same Same ?

25 Special Report No. 27 Reactor Containment Building Int:gratad Lsak Rata Test (- REFUELING LEAK RATE TEST FINAL RESULTS '(For Period 7-25-77 Through 9,-25-77) Conax Penetrations Leakage Rate (1b/2hhrs) Comments E ko 0.0 E 65 0.0 H-81 0.0 H-83 0.0 Dirty Sump Discharge 0.282 Clean Sump Discharge 0.0 Emergency Condenser Shell Side 0.0 Sample Point Treated Waste Return . 001 Demineralized Water Supply 2 52 e[. -Retest after lapping . /. *% check valve seat Cleanup Demineralizer Resin 1.k2

-Retest after repair of

( ,- valve Sluice Line Reactor and Fuel Pit 11~.77 Drain Line Ventilation Probe 0.0 Integrated Leak Rate Test . 0026 Penetrations (H-80, H-88, H-91) Control Rod Drive Pump Piston 17 Cooling Line Check Valves Feedvater Check Valve 187 0. -Retest after lapping check valve seat Supply Ventilation Valve . 731 -Test after preventative maintenance - rubber Total of other. remaining seat replacement Lenka6e rates as of 7-3-77 32.87 238.30 - NOTE: This leakage rate total is extrapolated to 23 psig per Tech. Spec. Section 3.7 ( '. Technical Specification Limit is hh0.25 lb/2h hr. --=

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(. 'l 26-Special RIport No. 27 'RIactor Containment Building Integratsd Leak Rate Test f ' TABLE 3 - MAJOR EVEIITS ' '9 h 13':h5 started pressurization 94 17:10 2nd air compressor found *,o be passing oil through air handling unit and taken out of service 9-5 08:11 Pressurization continued without air co= pressor 9-6 10:30 completed pressurization 9-6 16:30 Begin first h'old test 9-8 08:00 Terminate first hold test and begin controlled leakoff portion of test 9-9 -12:00 Feedwater check valve found leaking isolated feedvater line and continued controlled leakoff

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.( 9-12 Discovered oil in sphere pressure sensing lines." Purged lines and installed redundant sphere pressure U tube mercury manometer "Due to an air compressor used during containment pressurization which passed oil through the air handling unit and into the containment. 9-12 20:30 Re-established controlled leakoff portion of test 9-13 20:30 Terminated controlled leakoff portion of testing based upon acceptable results using total = ass method for both the original and the redundant sphere pressure manometers. Began second hold test. 9-lh 20:30 Terminated second hold test based upon acceptable results. 4g through the feedwater Deter =ined that leakage ratq/hr. 9-15 J Initiated corrective check valve exceeded 175 ft actions to be performed after containment was depressurized. 9-15 13:h5 Begin depressurization 9 06:00 ~ Depressurization completed (~ '9-26 Acceptable. local leak rate test results of feedvater valve s

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8 A 9 10 o y SPilERE T 6 g 2 a u REFERENCE 6 e c e T T .I U ~ e o a 1 A co.E " m E 2 88 ' @ E Reference Voltimo Locations UU Tw 1. CRD Pump Room as o 2. Accumulator Room Cas 5. RCP Instrument Room Meter .c .o a o c" 6. Fuel Pit Pump Room ^ ^ 7. Steam Drum Enclosure

  • 8.

Decentamination Room

  • 9.

Over Reactor Deck Personnel 1.ock Sol, 502 10. Near New Fuel Storage

  • k New Fuel Storage 503, SO4
  • Large volume units h

Emergency Condenser SOS, S06 Level Recirc Pump Room 507, 508

[ = ' W.: REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) DIS'ihlBUTION FOR INCOMING MATERIAL 50-155 REC: DAVIS D F: OPG: SF:IEIT:f.Y W S DOCDATE: 02 / 03/ 7::: NRC CONSI..lMERS PWR DATE RCVD: 02/07/7: DOCTiPE: LETTER NOTARIZED: NO COPIES RECEIVED LTR 1 ENCL 40

SUBJECT:

FORl4ARDING SPECI AL REPT NO 27, " REACTOR CONTAINMENT EUILDING INTERGRATEli L EAK RATE TEST" FOR THE SUDJECT FACILITY. PLANT NAME: BIG ROCf: PT REVIEt4ER INITIAL XJM DISTRIEUTOR INITIAL-oorc*on*wp*n* DISTRIBUTION OF THIS MATERIAL IS A5 FOLLOWS ***+**+++*******+* CONTAINMENT LEAL'. RATE TESTINO-APPENDIX J. (DISTRIBUTION CODE A017) FOR ACTION: BRANCH CHIEF DAVIS **W/7 ENCL I NT ERN AL.. f6 r T i s- *

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