ML20125A949

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Reactor Containment Bldg Integrated Leak Rate Test, 790425-0501
ML20125A949
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Site: Millstone 
Issue date: 08/10/1979
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NORTHEAST UTILITIES
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NUDOCS 7908200373
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{{#Wiki_filter:..... -. r DOCKET NO. 50-336 t MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 i REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST i. APRIL 28 - MAY 1, 1979 i l Oc:ket#3byJ.it6 C:drcl# MdFZWJs9 Cre.F/0779 of Dacumint: Eit' LfJ dY 3:0:iiT FILE r i I i l l h l T AUGUST, 1979 6 908200574 )

p ~ ~3 y,- . r. _+e I. INTRODUCTION II. CONTAINMENT INTEGRATED LEAK RATE TEST-A. Plant'Information B. Integrated Leakage Rate Measurement System C. Summary of Events-D.. _ Test Results - Type A-Tests III. LOCAL LEAK RATE TESTING 'A. Description-of Program B. LocalileakRateMeasurementSystem C. List of Pesetration -D. Test Results i APPENDICES. . A. Sensor Volume Fractions and Locations B. Trend Report Data f[ C. -ILRT Computer and Trend Data t. D. ! Local Leak Rate Test Panel: E. Local Leak-Rate' Test Data i ! Mr p b..;. t

m is : / PAGE 1 I. INTRODUCTION \\ _The Type A reactor containment building Integrated Leak Rate.. Test is performed to demonstrate that leakage through the primary reactor containment and systems, and components penetrating the primary containment, do not ' exceed the allowable leakage rate specified in the Plant Technical Specifications. The recent successful periodic Type A and supplemental verification tests were performed according to the requirements of the Millstone Technical Specification, Section 4.6.1.2.a and 10 CFR 50, Appendix J. The test method as required by the Technical Specifications is the ' absolute method as described in ANSI N45.4-1972, " Leakage Rate Testing of Containment Structures for Nuclear Reactors." The leakage rate was calculated using formulas from ANSI N45.4-1972 and BN-TOP-1, Rev.1, " Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants (Total Time)." In addition the leakage rate was calculated by the mass point method using formulas from ANS N274, " Containment System Leakage Testing Requirements," Draft No. 1, Rev. 3 - June 25, 1976 and Draft No. 2, Rev. 3 - November 15, 1978. Two separate computer systems were utilized to calculate the leakage rate. One system was employed by

PAGE 2 Bechtel Power Corp. and the other by Northeast Nuclear IAf - Energy Company. The NNECo mass point calculations were done in accordance with Draft No. 1 of ANS N274 and the Bechtel calculations were done in accordance with Draft-No. 2. The two computer systems yielded identical results when the precision of the computer systems was considered for both the Total-Time and Mass Point methods of calculation. -The durations of the Type A and verification tests were in accordance with the requirements of BN-TOP-1. These test results are being reported in accordance with 10:CFR 50, Appendix J ' Section V.B.3. II. -COUTAINMENT INTEGRATED LEAK RATE TEST A. Plant Information 1. General a. Owner - Northeast Nuclear Energy Company b. Plant Millstone Unit 2-c. Location Waterford, Connecticut d. Containment Type Prestressed, post tensioned concrete e. Nuclear Steam 4 Supply System Combustion Engineering, PWR f. Date Test Completed April 30, 1979 .m i. a 9 m y- .~1-g ,g,, y e-~g--,,.. -, - -., ,-,--,w-- -*y -ee ev,.,-, -,= e-v,--m,-w.m, r, -n.,r ,onrv,-,-. - -w-- ,-e

m PAGE 3 . d.. - xI g- - 2. Technical Information. k, 'a. Containment Net Free s Air Volume 1,920,000 C0. FT. .b.: Design Pressure 54 PSIG c.. Design Temperature 120 F d. Calculated Peak Accident Pressure, Pa-54 PSIG e. Containment ILRT Average Temperature Limits 50-120'F f. Calculated Peak Accident Temperature 289 F B. Integrated Leakage Rate Measurement System 1. Absolute Pressure (1 Channel) .a. Readout: 0-100,000 counts b. Accuracy: 0.015% of reading c. Resolution: 0.001% Full Scale d. Range: 0-100 PSI-e. Instruments (2) - Texas Instrument' Model 145-01 Precision Pressure Instrument No. 2714 with Bourdon Capsule, serial number 5974. 9

5 PAGE 4 {'~'s -Texas Instrument Model 145-01/ Precision Pressure' Instrument No. 2715 with-Bourdon Capsule, serial number 5976. 2. Drybulb~ Temperature (18 sensors) i a. Range: 0-350 F b. Accuracy: + 0.6 F at 100*F c. Repeatability: +0.1% Full Scale d. Instruments (18): - Resistance Temperature Detectors - Rosemont Model 104 AHC 3. Dewpoint Temperature (a sensors) a. Range: 50-150 F f b. Accuracy: 1.0.1 F c. Repeatability: +0.1% Full Scale 9 'd. Instruments: - Three Foxboro Model.270lRG Dewcells - One Foxboro Model 2717G Dewcell t 4. Verification Flow (1 channel) a. Range: 4.5-45 SCFM b. Accuracy: 1% Full Scale c. Repeatability: 1.0.3% Full Scale h

PAGE 5 _. ~ t d. Instrument: d - Wallace-Tiernan Flowmeter Model Number 5222M22008 NOTE: 1) One dewcell was inoperative during the test. 2)- The Overall Instrument Figure of Merit is used as an acceptance criteria for instrument selection.

However, when instruments fail and/or the test duration is less than 24 hours, the figure of merit should be checked to ensure that it is less than 0.25 La or 0.125'W/ day.

For this test the Figure of Merit based on a test duration of 15.25 hours and 3 of 4 dewcells functional was 0.03481;/ day, well below the allowed 0.125%/ day. 3) Sensor locations and volume fractions are listed in Appendix A. C. Summary of Events April 28,1979, 1000 Hours - A tour of the containment was conducted. A survey of the containment air temperature and dewpoint at ,q G(v) various locations was

PAGE 6 e ' T* taken with portable instrumentation Q to ensure that the-installed instrumentation was functioning s i-properly. The average of these values was compared to the values of the data acquisition 4 i. system with the below listed r [ results. i-AVERAGE CONTAINMENT TEMPERATURE BY SURVEY: 78 F AVERAGE CONTAINMENT TEMPERATURE BY THE DATA ACQUISITION SYSTEM: 77 F AVERAGE CONTAINMENT DEWPOINT TEMPERATURE BY SURVEY:

61. 5 F l

AVERAGE CONTAINMENT-DEWPOINT TEMPERATURE BY.THE DATA ACQUISITION SYSTEM:

61. 7 F 1

NOTE: During the survey of the dewpoint temperatures, dewcell ME9772, one of four, was found inoperable. The . weighting factors for the three l remaining dewcells were accordingly revised within the Data Requisition i System. u

PAGE 7 s-1145 Hours - The air compressors dd were started for containment pressurization. [ Pressurization continued (except for one 15 minute period at 1515 hours to add oil to the air dryer) until ~ the test pressure of 54.3 PSIG -was reached.] 1900 Hours - With the containment pressure at approximately 14.7 PSIG an inspection of all external ,y areas of the containment was conducted to determine if any serious leaks existed which would necessitate securing the - 4 containment pressurization i' (- None were found. l NOTE: At 0200 hours on April 29, 1979 clocks were moved ahead one hour I to accomodate a shift-1- l: to Daylight Savings l-L. Time. 's-I-

r-- PAGE 8 ~., ~ April ' 29,1979, 1300 Hours - One containment air. recirculation fan was declared -p inoperable due to high current as a result of the high containment pressure. 1402 Hours - All compressors were secured with containment pressure at 54.3 PSIG. Data acquisition was started. 1800 Hours - An inspection of all penetration areas external to the containment was conducted [- g to locate any possible leaks or 4 any containment structural -deterioration. As a result of l this inspection it was decided to place the outside flange back i on the ILRT pressurization line. It appeared that the pressurization line isolation valve, 2AC64 ~ (which is not the normal pressure I boundary) was leaking by the seat. The usual pressure boundary i7 for this line is a spectacle

j., - [,.. ' PAGE 9 flange which cannot'be installed 'during the ILRT. Consequently, ~ a penalty is taken for this penetration, and its leakage as determined by a Local Leak Rate Test is added to the total leakage as measured by the ILP.T. Also at this time Surveillance Procedure 2734C, Tendon End Anchorages and Adjacent Concrete Surfaces,-was completed. Section 4.6.1.6.2 of the Technical Specification requires that.this inspection be accomplished during the ILRT with the containment at peak pressure. 1835 Hours - The containment ' stabilization criteria were met and the test commenced. April 30, 1979, 0300 Hours - A survey of all external areas of the containment was completed with no problems k found.

PAGE 10 g,,. O. 0950 Hours - The Type A ILRT was terminated with a measured leak. rate of 0.061% per day with an upper 95% confidence limit of 0.120% per day as determined by the-Total Time Method. 1005 Hours - A 30.2 SCFM leak rate was established on the containment to verify:the accuracy of the data acquisition system. This leak rate equates to approx-imately 0.5 weight %/ day or La. 1050 Hours - The 30.2 SCFM leak on the containment was stabilized and the verification test was commenced. .1750 Hours - The 30.2 SCFM leak on the containment was secured and the verification test was successfully completed.

PAGE 11 1900 Hours - Venting of the containment was initiated. ~ 'May 1, 1979, 1300 Hours - A contaiment entry was made at a containment pressure of 1 PSIG. D. -Test-Results 1. Test Method Absolute 2. Data Analysis Techniques Total Time per ANSI N45.4-1972 and BN-TOP-1, Rev. 1. NOTE: Mass point analysis results are also provided for information only. 3. . Test Pressure 54 PSIG 4. Maximum Allowable Leakage Rate La-0.500%/ day. h 5. 75% of La 0.375%/ day l' 6. Integrated Leakage Rate Test Results in Weight [ % per day (Lam) i' TOTAL TIME MASS POINT i a) Lam (From regression L lineanalysis) 0.061 0.062 1 L l l-l L

r PAGE 12 , z' f t q b) Upper 95% Confidence .IV)- Limit on Lam 0.120 0.073 7. Verification Test Imposed Leakage Rate, 0.481 Lo, % day ~8. Verification Test Results Total Time - 0.514 in Weight Percent per day. Mass Point - 0.482 l 9. Verification Test Limits in Weight Percent per day, a) Total Time Analysis Upper Limit (Lo+ Lam +.25 La) 0.672 4 -LowerLimit(Lo+ Lam.25La) 0.422 j _ b) Mass Point Analysis Upper Limit (Lo+ Lam +.25 La) 0.673 Lower Limit (Lo+ Lam.25 La) 0.423 10. In order to conduct an IRT with a duration of less than 24 hours an additional acceptance criteria must be met as directed by BN-TOP-1, Rev. 1. The Trend Report based on Total Time calculations shall indicate that the magnitude of the calculated leak rate is tending to Il stabilize at a value less than the maximum l-allowable leak rate L(a). The magnitude of the calculated leak rate may be increasing slightly as it tends to stabilize. In this case the u i

m PAGE 13 [ average rate of increase of the calculated leak rate shall be determined from the accumulated data over the last five hours or last twenty data points, whichever provides the most points. Using this average rate the calculated leak rate can then be linearly extrapolated to the 24th hour data points. If this extrapolated value of the calculated leak rate exceeds 75% of the maximum allowable leak rate (La), then the test must be continued. a) Linearly extrapolated value of the Leak Rate using 20 data points from 0450-0950 hours t i on 4/30/79: 0.135%/ Day NOTE: A plot of leak rate versus time showing the linearly extrapolated values is contained in Appendix B.

11. A number of systems were required to remain operational in order to maintain the plant in a safe condition during the ILRT.

As a result the containment isolation valves for these-systems were not tested by the ILRT. In accordance with Section III A.1.d of Appendix J to 10CFR50 a Type C test was conducted for p each of these penetrations. A list of these ) penetrations and the leak rate detennined by the Type C tests are preser.ted below.

F.., PAGE 14 PENETRATION VALVES VALVE DESCRIPTION LEAKAGE RATE (%/ day) NUMBER TESTED - 2CH-516 - Letdown Isolation .0000 -10 .251-651/709 Shutdown Cooling .0004 24 2RB-30.1A Reactor Building Com-- .0011 ponent Cooling Water to Containment 25 2RB-28.lD Reactor Building Com- .0001 2RB-28.2D ponent Cooling Supply / 2RB-28.3D Return to "D" Contain-ment Air Recirc Cooler 26' 2RB-28.lB Reactor. Building Com- .0010 2RB-28.2B ponent Cooling Supply / 2RB-28.3B Return to "B" Contain-I ment Air Recirc Cooler 27 2RB-28.1A Reactor Building Com- .0004 2RB-23.2A ponent Cooling Supply /- 2RB-28.3A Return to "A" Contain-l: ment Air Recirc Cooler 28 2RB-28.lC Reactor Building Com- .0003 [. 2RB-28.2C ponent Cooling Supply / f, 2RB-28.3C Return to "C" Contain-i ment Air Recirc Cooler l i ). (.- E [..

PAGE 15'

.V f' PENETRATION ~

VALVES VALVE DESCRIPTION LEAKAGE RATE (%/ day) NUMBER.- TESTED ^ ~29' 2RB-37.2A-Reactor Building Com- .0011 ponent Cooling Water Return.From The Contain-ment 53 .2RB-30.lB Reactor Building Com- .0001 ponent Co. ling Water Supply to the Contain-ment 54 .2RB-37.2B Reactor Building Com- .0004 -ponent Cooling. Water Return from the Contain-ment 85 Spectacle Pressurization Line .0001 Flange. For The ILRT TOTAL LEAVAGE .0050 When the total leakage from the above listed penetration is included in:the ILRT results listed in 6 above the leak rate becomes: TOTAL. TIME MASS POINT 1 i Leak Rate (%/ day) .066 .067 Upper-95% Confidence l Limit (%/ day) .125 .078 l' I

1 A

y 7 l

r .[ PAGE 16 ~, .h NOTE: 1. The' test data for both the Total \\ l 'M Line and the Mass Points Methods is shown in Appendix C. Also included is a plot of temperature versus time and a plot of total mass versus time. III. LOCAL LEAK RATE TESTING A. Description of Program Type B and C Local Leak Rate Testing of containment penetrations as outlined in Appendix J to 10CFR50 is performed in accordance with Section 4.6.1.2.(d, e and f) of the Technical Specifications except for tests involving the containment air lock. The -containment air lock is tested in accordance with Section 4.6.1.3 of the Technical Specifications. A description of the local leak rate test equipment is described in section III.B and a listing of individual penetrations is containad in Section III.C. B. Appendix D shows a diagram of the local leak rate test panel. It should be noted that the range scales for the flow indicators F-1 and F-2 had range scales of 20-250 cc/ min and 200-2000 cc/ min respectively for the testing conducted in 1976 and 1978. This resulted in minimum flow indications of 20 cc/ min ]o) ~

'PAGE 17 fr for the low range scale and 200 cc/ min for the high 9% range' scale. Consequently, the minimum leak rate' shown on the. data for these years is 20 cc/ min. In 1979, however, the meters had range scales of 0-250 .cc/ min and 250-2500 cc/ min as shown in Appendix D. This resulted in a minimum leak rate of 25 cc/ min for 1979 test data. C. A listing of the containment penetrations which are subject.to Local Leak Rate Testing is given below. PENETRATION fiUMBER FUNCTION 1-Primary Makeup Water 2 Letdown 3 Chemical and Volume Control 4 Containment Spray 5. Containment Spray 10 Shutdown Cooling 11 Safety Injection 14 Containment Sump Discharge 21 Primary Coolant Sample 22

  1. 1 Steam Generator Blowdown 23
  2. 2 Steam Generator Blowdown 24 Reactor Building Component Cooling Water On) o

n. .;1, PAGE 18

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PENETRATION NUMBER ' FUNCTION y~g

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25 Reactor Building Component Cooling Water ,26 Reactor Building ~ Component Cooling Water 27 Reactor Building Component' Cooling Water 28 Reactor Building Component Cooling Water 29' Reactor Building Component Cooling Water 30 Reactor Building Component Cooling Water 31 Reactor Building Component Cooling Water 32 Reactor Building Component Cooling Water 33 Reactor Building Component Cooling Water 34 Nitrogen Supply For Safety Injection 35 Liquid Radwaste 37 Instrument Air 38 Station Air 39 Containment Purge 40 Containment Purge 43-Chemical and Volume Control System 51 Gaseous Radwaste 53 Reactor Building Component Cooling Water 54 Reactor Building Component Cooling Water 61 ' Radiation ilonitoring 62 ' Hydrogen Monitoring 63 ILRT Sample Connections 64 ILRT Sample Connections !w

r= PAGE 19 - 4. I'.' PENETRATION NUMBER FUNCTION f k 65'

  1. 1 Steam Generator Blowdown 67 Refueling Water Purification 618 Refueling Water 72
  2. 2 Steam Generator Blowdown 82 Hydrogen Purge System 83 Hydrogen Purge System 85 Integrated Leak Rate Test Pressurization Path 86 Radiation Monitoring 87 Hydrogen-Monitoring 88 Hydrogen Monitoring 89 Hydrogen Monitoring SEXA5 Electrical Penetration SEXA6 Electrical Penetration SEXB2 Electrical Penetration SEXB4 Electrical Penetration SEXB5 Electrical Penetration SEX 86 Electrical Penetration SEXB7 Electrical Penetration SEXB8 Electrical Penetration SEXB9 Electrical Penetration SEXC1 Electrical Penetration SEXC3 Electrical Penetration SEXD1 Electrical Penetration SEXD3 Electrical Penetration a

y PAGE 20 PENETRATION NUMBER FUNCTI0ft ]Q SEXD6 Electrical Penetration SEXD8 Electrical Penetration SEXD9 Electrical Penetration SEXE6 Electrical Penetration SEXE9 Electrical Penetration SWXB1 Electrical Penetration SWXB2 Electrical Penetration SWXB3 Electrical Penetration SWXB4 Electrical Penetration SWXB5 Electrical Penetration SWXB6 Electrical Penetration SWXB7 Electrical Penetration SWXB8 Electrical Penetration SWXB9 Electrical Penetration SWXC3 Electrical Penetration SWXC5 Electrical Penetration SWXD1 Electrical Penetration SWXD3 Electrical Penetration SWXD5 Electrical Penetration SWXD8 Electrical Penetration SWXD9 Electrical Penetration SWXE5 Electrical Penetration SWXE9 Electrical Penetration SEXA4-1 Electrical Penetration

E x \\ m. -[' c. PAGE 21 w s PENETRATION NUMBER FUNCTION SEXA4-2 Electrical Penetration ( ^- SEXA4-3 . Electrical Ptnetration SEXA8-l' Electrical Penetration SEXA8-2 Electrical Penetration i 4 ( ~ SEXA8-3 Electrical Penetration _ l-Electrical Penetration [ \\ SWXA2-1 ~ e 3 SWXA2-2 Electrical Penetratien .-\\ i SWXA2-3 s Electrical Penetration 6 .\\ t 5 4 SWXA8-1 Electrical Penetration v<- 1 i SWXA8-2 Electrical Penetration SWXA8-3 Electrical Penetration' s Equipment Hatch 4 (;-.. Transfer Tube . (qn C/ g 4 Personnel Hatch s ,v: i I. 1. A complete listing of individual penetrations 5 D andleakagesfrom1976through1978isshowkin' UD Appendix E. The total combined leakage rate o'fy.s ( all Type B and Type C penetrations shall not i exceed 0.60 La, where la is a leakage rate equal to 0.50 percent by weight of the containment air per 24 hours, at a pressure of 54 PSIG. Thus, the total leakage rate must be less than 0.30 weight percent per day. The total accumulated .s, leakages since the previous Type A test are s .[ given below: r s

r ..-e PAGE 22 ..,r] YEAR TOTAL LEAKAGE (weight'%/ Day) ,1976 0.2443 -(1)1977 0.'1690 1978 .0655 (2)1979 .0410 NOTE (1): Due to an extended outage in the Spring of 1977 to support retubing of the main condensers, additional testing and repair of selected containment penetrations was performed. NOTE (2): In 1979 several penetrations based on Local. Leak Rate Testing required b repair. The before repair. leakages 3 of these penetrations were not recorded in all cases. As a result the possibility exists that the total accumulated leakage may have exceeded 0.6 La. l This situation and the corrective g actions which were taken was the subject of Licensee Event Report 79-ll/3L-0, Docket Number 050-00336, forwarded on May 18, 1979. l .s I L

f PAGE 23 2. In accordance with Section 4.6.1.3.b of the j. Technical Specification an overall personnel I ~ ~ air lock leakage test at 54 PSIG (Pa) is required at least once per 6 month period. The leak l rate must be less than or equal to.05 La I (.025%/ day). The results of the leak tests since the previous 4 [ type A test are presented below: DATE-LEAKAGE 6/7/76 1.3 X 10-5 %/ day 5 1/11/76 1.3 X 10 %/ day 12/4/76 5.44 X 10-4 %/ day 6/19/77-1.35 X 10-5 %/ day . O 12/19/77 (3) 4/10/78 9.758 X 10-3 %/ day 10/10/78 (4) 12/21/78 2.034 X 10-2 %/ day 4/1/79 1.129 X 10-2 %/ day 5/18/79 2.362 X 10-2 %/ day NOTE (3): The surveillance was not performed at this time because' the plant.was in mode 6, shutdown for refueling,'and the test is not required in this condition. --.--y,,r,- -,.-,,..-,w.., _....,..-.v. r, ---.-.----er. -.-.. - - -,- -.~..-.4 ,m.

PAGE 24 NOTE (4): The surveillance was not performed as .t required at this time. This was identified by the NRC Office of-Inspection and Enforcement in Inspection Report 50-336/78-37 in December 1978, and the surve'illance successfully completed on 12/21/78. Plant Incident -Report 78-157 which discusses the incident was also prepared. 3. Section 4.6.1.2.e of the Technical Specifications requires that the combined bypass leakage rate shall be less than or equal to.017 La (.0085 %/ day). The total accumulated bypass leakage rates since the previous ILRT are listed below: YEAR TOTAL LEAKAGE (%/ day) 1976 .00043 %/ day 1978 .0010 %/ day 1979 .0011 %/ day 4 RAS:ame

m-PAGE A1 APPENDIX A SENSOR VOLUME FRACTIONS (and Locations) RID ELEV AZ DIST. FROM VOLUME TE (Ft.) (Deg.) ((Ft.) FRACTION 9769 150 90 12 0.096 8110 105 220 40 0.086 9767 105 40 45 0.087 8111 90 320 60 0.086 8112 90 105 60 0.087 8084 44 5 45 0.058 8108 44 145 60 0.058 8109 44 263 58 0.058 8097 30 125 20 0.016 8098 30 235 20 0.014 8094 20 350 45 0.040 9770 18 220 55 0.040 9771 18 90 50 0.040 8087 3 5 32 0.032 9765 3 240 65 0.032 O 8091 9766 3 125 65 0.032 -15 330 35 0.069 9768 -18 135 50 0.069 TOTAL 1.000 ME i 9772 55 320 60

  • 0.000 8064 55 105 60 0.616 t

9773 -20 10 35 0.192 9774 -20 330 35 0.192 i ( TOTAL 1.000 \\

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PAGE C1 .d s APPENDIX C 5 MILLSTONE UNIT 2 54 PSIG ILRT LEAKAGE RATE (WEIGHT PEPCENTeDAY) TDTAL-TIME ANALYSIS TIME AND DATE AT STACT DC TEST: 19?5 0429 ELAPSED TIME: 15.25 HOURS TIME TEMD. PRESOUD.E MEASuoED (R) (PSIA) LEAKAGE RATE 1935 533.765 69.3921 1950 533.755 69.3903 0.073 1905 533.730 68.3993 -0.119 1920 533.697 68.3937 -0.075 1935 533.692 69.3919 -0.012 1950 533.643 69.3790 -0.071 2005 533.636 69.3753 0.006 2020 533.619 69.3744 -0.023 2035 533.599 69.3693 0.*020 2050 533.575 68.3669 0.013 s 2105 533.531 69.3650 -0.040 2120 533.514 68.3607 -0.010 2135. 533.519 69.3592 0.015 2150 533.465 69.3552 -0.017 2205 533.452 69.3509 0.012 2220 533.405 69.3496 -0.025 2235 533.399 69.3417 0.020 2250 533.371 69.3406 0.009 2305 533.353 68.3395 - 0. 001 2320 533.327 69.3343 0.012 2335 533.296 68.3324 -0.003 2350 533.299 69.3324 -0.009 5, 533.262 69.3259 0.012 20 533.263 68.3240 0.023 35 533.267 69.3240 0.025 50 533.229 68.3199 0.019 105 533.237 68.3186 0.032 120 533.229 69.3219 0.009 135 533.230 69.3183 0.026 150 533.204 68.3155 0.023 205 533.253 68.3159 0.050 220 533.204 69.3119 0.038 235 533.193 68.3105 0.036 250 533.172 69.3116 0.019 305 533.135 68.3076 0.016 320 533.119 68.3069 0.010 335 533.140 68.3091 0.015 350 533.105 68.3053 0.008 405 533.031 69.3062 -0.030 420 5335031 68.3063 -0.030

PAGE C2 _e APTENDIX C l' % (' MILLSTONE UNIT 2 54 PSIG ILRT LEAKAGE RATE (WEIGHT PERCENT' DAY) TOTAL-TIME ANALYSIS TIME AND DATE AT STADT DC TEST: 1935 0429 ELAPSED TIME: 15.25 HOUPS TIME TEMD. DPESSUDE MEAiURED (R) (pilAN LEAKAGE RATE (CONTINUED FROM PAGE 1 OF TOTAL-TIME ANALYSIS) 435 532.995 69.3036 - 0. 040 450 533.168 69.3024 0.045 505 533.147 69.3030 0.033 520 533.139 69.3009 0.036 535 533.119 69.2990 0.033 550 533.135 69.2999 0.036 \\'- 605 533.100 69.2993 0.026 620 533.069 69.2947 0.024 635 533.157 68.2951 0.056 650 533.117 69.2937 0.044 705 533.132 69.2906 0.057 720 533.131 69.2910 0.055 735 533.109 68.2890 0.051 750 533.143 69.2861 0.070 905 533.135 69.2876 0.062 820 533.116 68.2844 0.063 935 533.096 69.2815 0.062 850 '533.099 69.2910 0.063 905 533.070 68.2781 0.060 920 533.081 68.2741 0.072 935 533.056 68.2739 0.064 950 532.990 68.2695 0.054 0.018 MEA 4 DF MEASURED LEAKAGE RATES = = 0.500 MAXIMUM ALLOWABLE LEAKAGE RATE 0.375 75 % Oc MAXIMUM ALLOWABLE LERKAGE RATE = h THE UDPER 95% CONFIDENCE LIMIT 0.120 = ps_j/ THE CALCULATED LEAKAGE RATE 0.061 =

PAGE C3 APPENDIX C h MILLSTDNE UNIT 2 ILRT VERIFICRTION TEST LERKRGE RATE (WEIGHT PERCENT / DAY) TOTRL-TIME ANALYSIS TIME AND DATE RT STRDT OF TEST: 1050 0430 ELRPSED TIME: 7.00 HOURS TIME TEMo. PRESSURE MERSURED (R) (PSIR) LERkRGE RATE 1050 533.012 69.2527 1105 532.995 69.2499 0.102 1120 533.003 69.2431 0.594 1135 533.010 63.2450 0.349 1150 533.027 69.2399 0.519 1205 533.099 69.2390 0.699 1220 533.073 69.2363 0.567 1235 533.094 69.2326 0.599 1250 533.053 69.2299 0.493 1305 533.020 69.2229 0.492 1320 533.060 69.2211 0.531 1335 533.044 69.2164 0.517 1350 533.096 69.2136 0.569 1405 533.029 69.2107 0.479 \\ 1420 533.040 69.2070 0.495 / 1435 533.106 69.2064 0.547 Ns-1450 533.061 69.2031 0.491 1505 533.139 69.2032 0.543 1520 533.116 69.1993 0.529 1535 533.121 69.1991 0.507 1550 533.155 69.1942 0.540 1605 533.161 69.1979 0.495 1620 533.167 69.1892 0.533 1635 533.192 69.1974 0.532 1650 533.097 69.1923 0.476 1705 533.100 69.1921 0.461 1720 4533.121 69.1762 0.499 1735 533.092 69.1741 0.456 1750 533.099 69.1696 0.472 0.502 MERN OF MERSURED LERKRGE RATES = YERIFICATION TEST LERKRGE RATE UPPER LIMIT = 0.667 YERIFICATION TEST LERKRGE RATE LOWER LIMIT = 0.417 0.514 THE CALCULATED LERKRGE RATE = f

PAGE C4 AP ENDIX C P MILLSTONE UNIT 2 54 PSIG ILRT [ ) LERKAGE RATE (WEIGHT PERCENT / DAY) (m,/ MASS-POINT ANALYSIS TIME AND DATE AT START DF TEST: 1835 0429 ELAPSED TIME: 15.25 HOURS TIME TEMP PRESSURE CTMT. AIR MASS LD!S TOT.Rv5. MASS (R) (PSIA) MASS (LBM) (LBM) LDSS (LBM Ho) 1835 533.765 68.3921 664163 1850 533.755 68.3903 664159 5.0 20.2 1905 533.730 69.3893 664179 -21.4 -33.7 1920 533.687 68.3837 664179 0.9 -20.6 1935 533.682 68.3818 664166 12.2 -3.2 1950 533.643 68.3790 664199 -21.3 -19.7 2005 533.636 68.3753 664160 27.2 1.8 2020 533.619 68.3744 664174 -13.7 -6.3 2035 533.599 68.3693 664152 21.9 5.4 2050 533.575 68.3669 664155 -2.6 ~ 3.7 2105 533.531 68.3650 664191 -36.3 -11.2 2120 533.514 68.3607 664170 20.6 -2.7 2135 533.518 68.3592 664151 19.5 4.1 2150 533.465 68.3552 664178 -27.1 -4.6 2205 533.452 68.3509 664151 26.6 3.3 2P'^N 533.405 68.3496 664199 -37.1 -6.9 68.3417 664141 47.1 5.4 2i-)533.399 L 533.371 68.3406 664153 -11.7 2.3 2305 533.353 68.3395 664165 -11.7 -0.4 2320 533.327 68.3343 664147 19.2 3.4 l 2335 533.296 68.3324 664167 -20.1 - 0. 9 2350 533.288 68.3324 664177 -10.0 -2.6 5 533.262 68.3259 664145 31.9 3.3 20 533.263 68.3240 664126 19.7 6.4 35 533.267 68.3240 664121 5.0 7.0 50 533.228 68.3199 664130 -9.7 5.3 105 533.237 68.3186 664106 23.9 9.7 120 533.229 68.3219 664149 -42.1 2.2 135 533.230 68.3183 664112 36.2 7.3 150 533.204 68.3155 664117 -5.2 6.3 205 533.253 68.3158 664059 59.1 13.9 220 533.204 68.3119 664082 -23.1 10.4 235 533.193 68.3105 664092 -0.1 10.1 250 533.172 68.3116 664119 -36.9 5.3 305 533.135 68.3076 664126 -7.2 4.3 320 533.119 68.3069 664139 -13.1 2.7 335 533.140 68.3081 664125 14.5 4.2 350 533.105 68.3053 664141 -16.4 2.3 5 533.031 68.3062 664242 -101.0 -8.3 533.031 68.3063 664243 -1.0 -0.2 532.985 68.3036 664274 -31.1 -11.1 0 533.168 68.3024 664035 239.7 12.5 505 533.147 68.3030 664067 -32.0 9.2 520 533.139 68.3008 664055 11.4 10.0 535 533.118 68.2990 664064 -8.7 9.0 550 533.135 68.2998 664050 13.4 10.0

r-PAGE C5 APPENDIX C ~ ^\\ /l MILLSTONE UNIT 2 54 PSIG ILRT \\ LERKAGE RATE (WEIGHT PERCENT / DAY) MASS-POINT ANALYSIS TIME AND DATE AT START OF TEST: 1835 0429 ELAosED TIME: 15.25 HOURS CTMT. 91R MAS 5 LOSS TOT. AVG. MAIS TIME TEMo PRESSURE ~ MASS (LBMT (LBM) LDSS (LBM /Ho ) <e> (oSIA) (CONTINUED FROM PAGE 1 OF MASS-POINT ANALYSIS) 605 533.100 69.2993 664079 -29.0 7.3 620 533.069 69.2947 664094 -4.Q 6.7 635 533.157 69.2951 663977 107.0 15.5 /N 533.117 69.2937 664014 -36.2 12.2 ( 533.132 69.2906 663965 49.9 15.9 Yet 533.131 69.2910 663970 -5.1 15.1 735 533.109 69.2990 663979 -9.2 14.2 750 533.143 69.2961 663907 71.9 19.3 905 533.135 69.2876 663932 -24.5 17.1 920 533.116 69.2844 663924 7.4 17.4 935 533.096 69.2815 663921 3.3 17.3 950 533.099 69.2810 663914 7.3 17.5 905 533.070 69.2791 663920 -6.7 16.7 920 533.091 69.2741 663969 52.6 20.0 935 533.056 69.2739 663997 -29.2 17.7 ( 950 532.990 69.2695 663936 -39.4 14.9 1.920 FREE RIR VOLUME USED (MILLIONS OF CU. FT.) = REGRESSION LINE 664226 = INTERCEPT (LEM) -17.3 = SLDPE (LBM/HR) 0.500 = MAXIMUM ALLOURBLE LEAKAGE RATE 0.375 75 % Dr MAXIMUM ALLOWABLE LERKAGE RATE = 0.073 = THE UPPER 95% CONCIDENCE LIMIT L 7-s 0.062 = ) THE CALCULATED LEAKAGE RATE s i I / t s m,/

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PAGE C6 t APPENDIX C ^ [ MILLSTONE UNIT,2-ILRT VERIFICATION TEST L V} LEAKAGE RATE (WEIGHT PERCENT / DAY) MASS-POINT ANALYSIS TIME AND DATE AT STAoT DC TEST: 1050 0430 ELAPSED TIME:

7. 00 HDUo!.

TIME TEMP PRESSURE CTNT. AIo MASS LDSS TDT. AVG. MASS (R) (PSIA) MASS (LBM) (LEM) LDSS (LEM 'HD) 1050 533.012 69.2527 663746 1105 532.995 69.2499 663739 7.0 29.2 1120 533.003 69.2431 663664 75.1 164.3 1135 533.010 68.2450 663673 -9.8 96.5 1150 533.027 69.2399 663603 70.9 143.2 1205 533.099 69.2390 663504 93.4 193.2 1220 533.073 69.2363 663510 -6.1 156.9 1235 533.094 69.2326 663461 49.7 162.9 1250 533.053 69.2299 663473 -12.3 136.4 1305 533.020 69.2229 663446 27.0 133.2 1320 533.060 69.2211 663379 67.3 146.9 1335 533.044 69.E164 663353 25.9 142.9 -1350 533.096 69.2136 663273 79.5 157.4 les 533.029 6S.2107 663316 -42.7 132.2 1/ 533.040 69.2070 663266 49.7 136.9 16 533.106 68.2064 663179 97.9 151.3 1450 533.061 69.2031 663202 -23.9 135.9 1505 533.139 68.2032 663109 94.S 150.1 1520 533.116 68.1993 663097 20.3 146.3 1535 533.121 69.1991 663079 9.2 140.3 1550 533.155 69.1942 662999 90.2 149.4 1605 533.161 68.1978 663026 -27.5 137.0 1620 533.167 69.1992 662935 91.1 147.3 1635 533.182 69.1874 662S99 36.2 147.2 1650 533.097 68.1923 662955 -56.1 131.7 1705 533.100 69.1921 662949 5.9 127.4 1720 533.121 69.1'762 662967 92.7 135.2 1735 533.082 69.1741 662395 -28.6 126.0 1750 533.099 69.1696 662933 62.6 130.4 FREE RIR VOLUME USED (MILLIDMS DC CU. FT.) 1.920 = REGRcSSION LINE INTERCEPT (LBM) 663723 = SLDPE (LBM/HR) -133.4 = /N VERIFICATIDN TEST LERKAGE RATE UPPER LIMIT = 0.669 I VERIFICATION TEST LEAKAGE RATE LOWER LIMIT = 0.419 THE CALCULATED LEAKAGE RATE 0.492 =

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PAGE D1 a APPENDIX D ~.yn Q l I @ @ O VI V2 V4 A/S INLET g x g. 4 } V5 Vll g V6 VBA FI-l V7A -b<l 4 I X .Vol ume V8B FI-2 V7B 3onnection 4 g LOCAL LEAK TEST P NEL INSTR DESCRIPTION PCV-1, Pressure Regulator, Range 0-100 psig PCV-2 PI-l Pressure Gauge, 0-100 psig, 2 psig increments PI-2

  • Pressure Gauge, llallace & Tiernan Absolute Pressure Gauge Model 61A-1 A-0100, Range 0-100 psia, accuracy 7

0.1% full scale, sensitivity.01% full scale. i FI-1, Flow Indicator, Brooks full view rutameter, model 1370-00F2AAS 'FI-2 Dual Scale Measuring Air at 42 psig, 700F, Scale Range: i-FI-l 0-250 cc/ min, FI-2 250-2500 cc/ min.

  • Alternate gauge, Heise - range 0-100 psig

. - - -. - _ - -. - -. - _ ~ -

PAGE El Q,.:. -APPENDIX'E 3 1.- ENETRATION LEAKAGE RATE (STANDARD CUBIC CENTIMETEP,S 3~ 1-. [ NUMBER PER MINUTE - SSCM) .1976 1977 1978 1979 l.. - 1 20 20 60 i l 2 30 25 65 3-20 20 25 i 20 25 4 400-f 5 20 20 25 10L 750 550 25 1 11 2000 500 1386 1 14 600. 1400 1550 i 21 1000 850 600 i 22 .20 1800 45 i. 1000 991 23 20 1000 1690 24 1800 1 I 25 49,706 20 200 - 26~ 800 2000 1500 i i 27 20 20 598 - '28 272,773 124,406 10633 497 l- ~ 1100 -1690 29 850 i 30 TESTED WITH PENETRATION 25 i i 31 TESTED WITH PENETRATION 26 l- - j-32 TESTED WITH PENETRATION 27 i j i. L33 TESTED WITH PENETRATION 28 j. [ 1-r 4 4 --+is.-mv re a<,-ww% %.--,.-,,w.,..,e4,,,---,1,wve.,,-w-,w-wwe,ww -..,,,.. --s,. w,,m-w,--- we--. ---em---,~-

~. - _ 1.* - PAGE E2 APPENDIX E i .e, f *ENETRATION LEAKAGE RATE (STANDARD CUBIC CENTIMETERS NUMBER PER MINUTE - SSCM) 1976 1977 1978 1979 d '34 750 750 400 350 ,35 20 50 30 37 110 40 56 38 20 20 129 i 39 14,418 2657 5442 1200 40 76,890 52,674 1400 43 20 20 200 110 51 200 800 299 53 23 140 200 54 92 240 600 61 20 20 90 62 55 230 110 63 20 20 25 64 20 20 25 65 TESTED WITH PENETRATION 22 j 67 20 75 25 68 20 20 30 72 TESTED WITH PENETRATION 23 82 20 60 26 83 1700 600 25 i 85 20 90 100 4

.h 5 ,,,..a,. PAGE~E3 F .~ APPENDIX E fe, n THETRATION 1.EAKAGE RATE (STANDARD CUBIC CENTIMETERS NUMBER PER MINUTE - SSCM) 1976 1977 1978 1979 l l 86 20 230 40 i 87 20 75 1244 88 20 20 25 89 20 20 25 1 SEXA5 20 1331 2458 i j - SEXA6 -20 20 25 i SEXB2 20 1800 1580 SEXB4 20 -20 25 SEXB5 20 20 25 SEXB6 20 20 2412 SEXB7 20 20 25 j SEXB8 20 20 25 SEXB9 20 68 50 SEXC1 20 20 25 l SEXC3 20 20 25 SEXDl. .20 20 25 i' SEXD3 20 20 25 ' SEXD6 20 20 25 SEXD8. 20 48 25 l r ~SEXD9 20 30 50 t SEXE6 20 95 60 4 4 i ..,.,)

_ _ _ _ _.. _ _ -.. _ _. ~.. o 's - * - m '.* PAGE E4 i t ~* APPENDIX'E-ENETRATION LEAKAGE RATE (STANDARD CUBIC CENTIMETERS NUMBER PER MINUTE - SSCM) 1976 1977 1978 1979 I [ SEXE9 20 20 25 20 25 >SWXB1- -20 SWXB2 20 20 25 t SWXB3 20 20 119 SWXB4 20 20 25 SWXB5 20 2250 25 SWXB6 20 20 25 200 207 SWXB7 20 i-SWXB8 20 20 295 1 F SWXB9 20 20 25 i SWXC3 250 20 25 SWXC5 350 20 25 20 25 I -SWXD1 20. .SWXD3 20 20 25 I: SWXD5 20 20 25 i -SWXD8. 20 20 20 25 SWXD9 20 20 25 SWXE5 20 2431 169 1 SWXE9 20 20 25 l SEXA4-1 20 20 25 i F -SEXA4-2 20 20 25 i f i [ f. 4 ~, ~..,. _,, _ _, _. _ _ _. _.. _ _..

_ _. _.~ i i PAGE E5 lf,s'=s o< APPENDIX E l .l J:, ENETRATION -LEAKAGE RATE (STANDARD CUBIC CENTIMETERS i I NUMBER PER MINUTE - SSCM) zl976 - 1977 1978 1979 ISEXA4-3 20 20 25- { i: SEXA8-1 20 20 25 -} 20 25

SEXA8-2' 20 1

'SEXA8-3 20 20 25 l i SWXA2-1 20 20 25 SWXA2-2 20 20 25 L f SWXA2-3 20 20 25 i } }SWXA8-1 20 20 25 20 25' j SWXA8-2 20 r 1 SWXA8-3 20-20 25 EQUIPMENT HATCH 20 20 -20 25 t 1

TRANSFER. TUBE ~

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