ML20091M404

Reactor Containment Bldg Integrated Leak Rate Test, 831223-25

ML20091M404
Person / Time
Site:	Millstone
Issue date:	12/25/1983
From:	NORTHEAST NUCLEAR ENERGY CO.
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ML20091M403	List: ML20091M401 ML20091M404
References
NUDOCS 8406110285
Download: ML20091M404 (31)

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.m NORTHEAST NUCLEAR ENERGY COMPANY MILLSTONE UNIT 2 DOCKET NUMBER 50-336 REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST DECEMBER 23-25, 1983

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'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. Local-Leak Rate Measurement System C. List of Penetration D. Test Results 1 APPENDICES'

- A. Sensor Volume Fractions and Locations B. Trend Report Data C. ILRT Computer and Trend _ Data D. Local Leak Rate Test Panel E. Local Leak Rate Test Data.

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- I. -INTRODUCTION

'The Type A reactor containment building integrated Leak Ra.te Test is

_ performed to demonstrate that leakage through the primary reactor containment and systems, and components penetrating the prinary 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 i Specification, Section 4.6.1.2.a and 10 CFR 50, Appendix J. The test methbd as-required by the Technical Specifications is the absolute method L 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)." The durations of the Type A and verification tests were in accordance with the requirements of BN-TOP-1.

1 The test was performed using the methods employed for the last integrated Leak Rate Test performed in April of 1979. For the 1979 test two separate i computer systems were utilized to calculate the leakage rate. One system was used by the Bechtel Power Corporation and the other by Northeast Nuclear Energy. Both computer systems yielded identical results when the j precision of the systems'were taken-into consideration. Since the NNECo i -program'was proven against the Bechtel program for the 1979 test, Bechtel was not_ employed for the current test. These test results are being reported in accordance with 10CFR50, Appendix J,-Section V.B.3.

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The 40' month i 10 month time period between type A tests as required by

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Technical Specification 4.6.1.2.a was exceeded for this test. The actual time between Type."A"' tests was 55 months. This deviation from Technical

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Specification surveillance requirements was documented in a letter to the-NRC dated October 26,.1982.

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Page 4 II. CONTAINMENT INTEGRATED LEAK RATE TEST A. Plant Information i

1. General E. Owner Northeast Nuclear Energy Company

b. Plant Millstone Unit 2

c. Location Waterford, Connecticut

d. Containment Type Prestressed, post tensioned concrete

e. Nuclear Steam Supply Combustion Engineering PWR System I

f. Date Test Completed December 24, 1983

2. Technical Information

a. Containment Net Free Air Volume 1,920,000 FT3 ,

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

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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

3. Instruments (2)

- Texas Instrument Model 145-01 Precision Pressure Instrument No.-2714 with Bourdon Capsule, serial number 5974.

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- Texas Instrument Model 145-01 Precision Pressure Instrument No. 2715 with Bourdon Capsule, serial number 5975.

2. Drybulb Temperature (18 sensors)

a. Range: 0-350 F

b. Accuracy: 1 0.6*F at 100 F

c. Repeatability: 10.1% Full Scale l

d. Instruments (18):

- Resistance Temperature Detectors - Rosemont Model 104 AHC

'3. Dewpoint Temperature (4 sensors)

a. Range:* 20-120 F

b. Accuracy: 10.1 F

c. Repeatability: 10.1% Full Scale

d. Instruments:

- Three Foxboro Model 2701RG Dewcells

- One Foxboro Model 2717G Dewcell

4. Verification Flow (1 channel)

a. Range: 4.5-45 SCFM

b. Accuracy: 1% Full Scale

c. Repeatability 10.3% Full Scale

d. Instrument:

- Wallace-Tiernan Flowmeter Model Number 522H22008 NOTE: 1) One.drybulb temperature sensor declared 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the figure of merit should be checked to ensure that it is less than 0.25 La or 0.125%/ day. For this test the Figure of Merit based on a test duration of 8.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> and 17 of 18 dewcells functional was 0.0683%/ day, well below the allowed 0.125%/ day.

• Normal range is 50*-150*F, prior to the test the range was lowered due to low dewpoint _ temperature.

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3) Sensor locations and volume fractions are listed in Appendix A.

C.

SUMMARY

OF EVENTS December 22, 1983 2300 Hours - A tour of containment was conducted. A survey of the containment air temperature and dewpoint at various locations was taken with portable instrumentation to ensure that installed instrumentation was functioning properly. The average of these values was compared to the values of the data acquisition system with the below listed results.

Average Containment Temperature by Survey: 70.40 F Average Containment Temperature by the Data Acquisition System: 70.35 F Average Containment Dewpoint Temperature by Survey: 39*F Average Containment Dewpoint Temperature by the Data Acquisition System: 36.2*F December 23, 1983 0200 Hours - The air compressors were started for containment pressurization.

0530 Hours - One air compressor was not running properly. It was valved out of service for repairs.

0600 Hours - All air compressors were stopped for a 10 PSIG survey of all external areas of containment. No leakage was found.

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Pagn 7 0630 Hours - Six air compressors were started for pressurization.

0700 Hours - The seventh air compressor was returned to service.

1300 Hours - One nitrogen overpressure piping header on the electrical penetrations was indicating containment pressure. Both piping systems were disconnected to allow free leakage thru the electrical penetrations.

1415 Hours - The refrigerator air dryer tripped out.

1630 Hours - Water was detected from penetration 14, containment sump discharge header vent valve 2-SSP-75.

1719 Hours - The refrigerator air dryer was returned to service.

Loose wires were found in the control panel.

2000 Hours - No water or apparent air leakage was detected from valve 2-SSP-75.

2010 Hours - The tendon end anchor inspection commenced.

2237 Hours - Test pressure (54.3 PSIG) was attained. All air compressors were secured. At this time l penetration 14 was isolated for the test and local leak rate tested after the test.

December 24, 1983 0033 Hours - The "B" containment air recirculation fan was taken out of service due to high amperage.

0130 Hours - Containment air pressure decreased to 54.1 PSIG, possibly due to falling outside air temperature. The 1

tendon end anchor inspection was complete.

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, Page 8 0200 Hours - The air compressors were re-started to pressurize the containment to 54.7 PSIG.

0300 Hours - Pressure stabilized.

0330 Hours - Pressure in the containment was released through the blowdown muffler and reduced to 54.3 PSIG.

0400 Hours - Containment pressure stabilized at 54.3 PSIG. The stabilization period was started. Started taking data every 15 minutes.

0500 Hours - Containment air drybulb temperature instrument TE to 8110 was reading low, 58 F versus 73 average. It was j 0730 Hours taken out of service and the weighting factor of its counterpart instrument TE 9767 was changed to reflect this condition.

0800 Hours - The containment air temperature stabilization criteria was met. Started the peak pressure test.

l 1830 Hours - The peak pressure test was terminated.

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l 1835 Hours - Health Physics obtained an air sample prior to initiating a controlled leak for the verification test. No pressure readings were taken at this time due to the sampling.

1900 Hours - Containment air sample was clean.

I 1915 Hours - Established a controlled leak of 31.5 SCFM, started l verification test.

December 25, 1983

.0015 Hours - Verification test was ended.

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0035 Hours - A continuous air monitor was set up and containment depressurization was initiated through the blowdown muffler.

2035 Hours - Cont &inment was depressurized.

2130 Hours - Initial containment entry.

D. Test Results

1. Test Method Absolute

2. Data Analysis Techniques Total Time per ANSI N45.4-1972 and BN-TOP-1, Rev. 1.

3. Test Pressure a) Pressure at Start of Test = 54.442 PSIG b) Pressure at End of Test = 54.380 PSIG c) Pressure at Start of Verification Test = 54.365 PSIG d) Pressure at End of Verification Test = 54.285 PSIG

4. Maximum Allowable Leakage Rate, La = .500%/ Day 75% of L, = .375%/ DAY

5. Integrated Leakage Rate Test Results %/ DAY using total time method.

Calculated Leak Rate = 0.184 = L,,

Upper 95% Confidence Level * = 0.319

6. Verification Test, Imposed Leakage Rate = 0.519 = L o

7. Verification Test Result = 0.646 = L,,o

8. Verification Test Limits l L,, - (L,,, - Lg) l 1 25 L, Where: L,, = 0.184 l 0.18A - (0.646 - 0.519) l 1 0.125 L,,o = 0.646 1 0.057 l 1 0.125 L o

= 0.519

.25 L, = 0.125

• The Upper 95% Confidence Level is defined as the calculated leakage determined from the regression line analysis plus the.95% percent confidence interval.

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9. .In order to conduct an ILRT with a duration less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> an additional acceptance criteria must be met per Bechtel Topical Report 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 stabilize at a value less than the maximum allowable leak rate L,. The magnitude of the calculated leak rate may be increasing slightly as it tends to stabilize. In this case the 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 be linearly extrapolated to the 24th hour data point. If this extrapolated value of the calculated leak rate exceeds 75% of the maximum allowable leak rate (La),

then the test must be continued.

The linearly extrapolated value of the Leak Rate using the last twenty data points from 1315 to 1815 on 12/24/84 is .200%/ Day.

A plot of leak rate versus time showing the extrapolated leak rate to the 24th hour is shown in Appendix "B".

10. A number of systems were required to remain operational in ordar 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 each of these penetrations. A list of these penetrations and the. leak rate determined by the Type C tests are presented below. Also as previously indicated in the summary of events, penetration 14 was isolated just prior to the test. The leak rate determined by-

, type "C" tests was made prior to repairs and is also presented below.

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Page 11 PENETRATION VALVES VALVE DESCRIPTION LEAKAGE RATE (%/ day)

NUMBER- TESTED 2 2CH-089 Letdown Isolation .00001368

.10 .2SI-651/709 Shutdown Cooling .000080051 24 2RB-30.1A Reactor Building Com- .000060378 ponent Cooling Water to Containment 25 2RB-28.10 Reactor Building Com- .000013568 2RB-28.20 ponent Cooling Supply /

2RB-28.3D Return to "D" Contain-ment Air Recirc Cooler 26 2RB-28.1B Reactor Building Com- .00007327 2RB-28.2B ponent Cooling Supply /

2RB-28.3B Return to "B" Contain-ment Air Recirc Cooler 27 2RB-28.1A . Reactor Building Con.- .00006716 2RB-28.2A ponent Cooling Supply /

2RB-28.3A Return to "A" Contain-ment Air Recirc Cooler 28 2RB-28.1C Reactor Building Com-' .000013568 2RB-28.2C .ponent Cooling Supply /

2RB-28.3C- Return to "C" Contain-ment Air Recirc Cooler 29 2RB-37.2A Reactor Building Com- .00006716 ponent Cooling Water Return from the Contain-ment.

53 2RB-30.18 -Reactor Building Com- .00002035-ponent Cooling Water Supply to the Contain-ment 49~ 2-FIRti-108 . Fire Main Supply .00006648

Page 12 PENETRATION VALVES VALVE DESCRIPTION LEAKAGE RATE (%/ day)

NUMBER TESTED 54 2RB-37.2B Reactor Building Com- .00006716 ponent Cooling Water Return from the Contain-ment 85 Spectacle Pressurization Line .000013568 Flange For the ILRT 63 2-AC-114 ILRT Sample Connections .00001696 2-AC-117 64 2-AC-112 ILRT Sample Connections .000013568 2-AC-116 14 2-SSP-16.1 Containment Sump Discharge .058156 Total Leakage .058729%/ Day When the total leakage from the above listed penetrations is included in the leakage rate values for step 5 the leak rate becomes:

Calculated Leak Rate = 0.184%/ Day Plus Penetration Leakage + 0.058729%/ Day Total 0.242729%/ Day Upper 95% Confidence Level = 0.319%/ Day Plus Penetration Leakage + 0.058729%/ Day Total 0.377729%/ Day 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 l lock is tested in accordance with Section 4.6.1.3 of the Technical

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Specifications. A description of the local leak rate test equipment is described in section III.B and a listing of individual penetrations is contained in Section III.C.

B. Appendix D shows a diagram of the local leak rate test panel. It should be noted that flow indicators F-1 and F-2 have range scales of 20-250 cc/ min, and 200-2000 cc/ min. or 0-250 cc/ min. and 250-2500 cc/ min. depending on the Local Leak Rate Test Equipment used. This resulted in a minimum recorded leak rate value of 20 cc/ min or 25 cc/ min. The actual leak rate is less than the minimum value shown in Appendix E.

C. A listing of the containment penetrations which are subject to Local Leak Rate Testing is given below.

PENETRATION NUMBER FUNCTION 1 Primary Makeup Water 2 Letdown 3 Cheinical and Volur.e Control 4 Containment Spray 5 Containment Spray 10 Shutdown Cooling 11 Safety Injection 14- Containment Jump Discharge 21 Primary Coolant Sample 22 #1 Steam Generator Blowdown 23 #2 Steam Ganerator Blowdown 24 Reactor building Component Cooling Water 25 Reactor Building Component Cooling Water 26 Reactor Building Component Cooling Water 27 Reactor Building fot onent Cooling Water 28 Reactor ouilri',9". ~;om .nent Cooling Water

-29 Reactor BuiLM .y C,,-. Sent Cooling Water 30 Reactor Builoin Component J Cooling Water 31 Reactor Building. Component Cooling Water 32 Reactor Building component Cooling Water 33 Reactor Building Component Cooling Water

l Paga 14 i PENETRATION NUMBER FUNCTION 35 Liquid Radwaste 37 Instrument Air 38 Station Air 39 Containment Purge 40 Containment Purge 43 Chemical and Volume Control System 49 Containment Fire Protection Water 51 Gaseous Radwaste 53 Reactor Building Component Cooling Water 54 Reactor Building Component Cooling Water 61 Radiation Monitoring 62 Hydrogen Monitoring 63 ILRT Sample Connections 64 ILRT Sample Connections 65 #1 Steam Generator Blowdown 67 Refueling Water Purification 68 Refueling-Water 72 #2 Steam Generator Blowdown 82 Hydrogen Purge System

-83 Hydrogen Purge System 85 ILRT 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 SEXB6- Electrical Penetration SEXB7 Electrical Penetration SEXB8~ Electrical Penetration l

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Pag) 15 PENETRATION NUMBER FUNCTION SEXB9 Electrical Penetration SEXC1 Electrical Penetration

.SEXC3 Electrical Penetration SEXD1 Electrical Penetration SEXD3 Electrical Penetration 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 SWXBS Electrical Penetration SWXB6 Electrical Penetration SWXB7 Electrical Penetration SWXB8 Electrical Penetration SWXB9 Electrical Penetration SWXC3 Electrical Penetration SWXCS 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 SEXA4-2 Electrical Penetration

.SEXA4-3 Electrical Penetration

'SEXA8-1 Electrical Penetration SEXA8-2 -

Electrical Penetration

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/ Page 16 l PENETRATION NUMBER FUNCTION SEXA8-3 Electrical Penetration SWXA2-1 Electrical Penetration SWXA2-2 Electrical Penetration i SWXA2-3 Electrical Penetration SWXA8-1 Electrical Penetration SWXA8-2 Electr ical Penetration SWXA8-3 Electrical Penetration Equipment Hatch Transfer Tube Personnel Hatch D. 1. A complete listing of individual penetrations and leakages from 1979 through 1983 is shown in Appendix E. The total combined leakage rate of all Type B and Type C penetrations shall not exceed 0.60 La, where La is a leakage rate equal to 0.50 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, at a pressure of 54 PSIG. Thus, the total leakage rate must be less than 0.30 weight percent per day. The total accumulated leakages since the previous Type A test are given below:

YEAR TOTAL LEAKAGE (weight %/ Day) 1979 As Left 0.0410 1980 As Found 0.294 1980 As Left 0.019 1981 As Found 2.312*

1982 As Left 0.01524 1983 As Found 1.315*

1983 As Left 0.018

• The total leakage rate for penetrations subject to type B & C testing exceed the allowable limit primarily due to the excessive leakage on the-RBCCW penetrations. These events were the subject of Licensee Event Reports 50-336/84-05/3L-0 and 50-336/82-06/3L-0 forwarded on 2/24/84 and 4/8/82.

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2. In accordance with Section 4.6.1.3.b of the Technical Specification an overall personnel air lock leakage test at 54 PSIG (Pa) is required at least once per 6 month period. The leak rate must be_less than or equal to .05 La (.025%/ day).

The results of the leak tests since the previous type A test are presented below:

Date Tested Personnel Air Lock Leakage 5/18/79 2.362 x 10 -2%/ Day 11/3/79

-2 3.22 x 10 %/ Day

• 11/3/79 2.38 x 10 ~3

%/ Day

-4 2.65 x 10 %/ Day 4/15/80 9/28/80 2.26 x 10 -2

%/ Day 9/28/80

-3 5.30 x 10 %/ Day

.3/10/81 -3 2.10 x 10 %/ Day _

9/14/81 6.0 x 10 ~4

%/ Day

~1 3/4/82 2.66 x 10 %/ Day *

~4 3/4/82 1.1 x 10 %/ Day 9/]5/82 0.0%/ Day 11/27/83 2.45 x 10 -3

%/ Day 3/18/83 0.0%/ Day

• The personnel access door leakage rate exceeded _the allowable

. limit twice since the previous integrated leek rate test. In both cases the cause of the leakage was due to the door operating rod packing gland seal. . These events were reported on licensee Event Reports 50-336/79-34/3L-0 and 50-336/82-006/3L-0 forwarded on 11/20/79 and 4/8/82 respectively.

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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) 5/19/80 0.001073%/ Day 10/15/80 0.00121%/ Day 3/8/82 0.0002%/ Day 3/15/83 0.0002%/ Day SS:ejz i

/ Page Al APPENDIX A SENSOR VOLUME FRACTIONS (and Locations)

- TEMPERATURE RTO ELEV AZ DIST. FROM VOLUME TE- (Ft.) (Deg.) CL (Ft.) FRACTION

- 9769 150 90 12 0.096 8110 105 220 40 .0000*

9767 105 40 45 .1730 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 9766 3 125 65 0.032

'8091 -15 330 35 0.069 9768 -18 135 50 0.069 TOTAL 1.000 DEWPOINT ME#

9772 55 320 60 0.2950 8064 55 105 60 0.2770 9773 ~ -20 10 35 0.192 9774 -20 330 35 0.192 TOTAL 1.000

- " Instrument Failed

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APPENDIX B Page B1 . , .

MILLSTONE UNIT 2 CONTAINMENT INTEGRATED LEAK RATE DATA N 88.1983 c.55*

7 j TREND REPCRT-CALCULATED LEAK RATE R 0.525- eo E

N 0.500-0 e 0.475- e e C i A 0.450- e a C 0.425-  ! e 0.404 l l A e e T 0.375 , ,

E 0 0.350- i L 0.325-  !

E A 0.300- i K  :

0.275- e a R

A 0.250- i T e  :

E 0.225- e Z 0.200- l P 0.175- l e E  : i R 0.150- i 0 0.125- , ,  !

A e T 0.100 ,. .. _ _,_ .,_ _,. .,. .,. .,__ ,. .,y _,. _,. .,. _,_ _,. .,. .,_ _,. .,. _,. _,. .,. .,_ _,. _,_ _

1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 3 3 3 3 3 9 0 1 2 3 4 5 6 7 8 9 0 1 2 3 4 5 6 7 8 9 0 1 2 3 4 b b b b b b b b b b b b b b b b b b b b b b b b b b 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TIME

l P g2-B2 MILLSTONE UNIT 2 , ,, ,

CONTAINMENT INTEGRATED LEAK RATE DATA nzervara u. teas 0.550H r i O.525 i-PEAK PRESSURE TEST '

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'O.500i* -

t i

t 0.475-j ,

0.450-4 - .

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0.425-i , .

i 0.400-i '

1 i -

L 0.375 ; 1

, + * + i

~E 1 i i A 0.350 - i l

K R

0.325 4

+++++*++++++++++++*++++4 #

e A

T 0.300-j ,

i s i E 0.275 '

q . = c ,

% 0.2501 i

1 e a ~ ~

c P 0.225 -

a 3 a A E l i a -

a 0 -" Y R 0.200-j  :

c N i 1

0 3 a c -~ m D 0.175 . i A i 2 e Y 0. i SO -i O .125i1  !  ;  : e O .100 -j

++++*++++ +,,,++++ r i

i 0.075i, - ,

0.050 4 ,

++++++,,+++*+'+t i  !

0. 025 -j* e .

f 0.000f  ; , , ,

9:00 10:00 t1:00 12:00 13:00 14:00 15:00 16:00 17:00 18:00 19:00 TIME LEGEND: Calculated Leak Rate O Measured Leak Rate i + Upper and Lower 95% Confidence Limits

Paga B3 MILLSTONE UNIT 2 ' '

CONTAINMENT INTEGRATED LEAK RATE DATA DICEMBEF. M,1983 3 . e _:a , VERIFICATION TEST- ,

' t 8 1.44-LEGEND: Calculated Leak Rate '

3 0 Measured Leak Rate i.3d - ,

Y Upper and Lower 95% Confidence Limits

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19:00 20:00 21:00 22:00 23:00 24:00 TIME

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APPENDIX C PEAK PRESSURE TEST DATA--MP2ILRT DEC 24, 1983 LEAK RATE BASED ON TOTAL TIME CALCULATIONS TIME TEMP PRESSURE MEASURED CALCULATED 95% CONFIDENCE LIMITS

-(R) (PSIA) LEAK RATE LEAK RATE LOWER UPPER

'1000 533.648 68.761 1015 533.651- 68.758 0.5210+00 0.2470+00 0.112E+00 0.382D+00 C 1030 533.645 68.759 0.119D+00 0.245D+00 0.110E+00 0.3800+00 i 1045 533.657 68.758 0.235D+00 0.243D+00 0.108E+00 0.378D+00

[ 1100 533.649 68.756 0.202D+00 0.241D+00 0.106E+00 0.376D+00 1115 533.660 68.754 0.264D+00 0.2390+00 0.104E+00 0.374D+00 1130 533.629 68.750 0.209D+00 0.237D+00 0.102E+00 0.372D+00 1145 533.652 68.750 0.231D+00 0.2350+00 0.100E+00 0.3700+00

[ 1200_ 533.647 68.748 0.230D+00 0.233D+00 0.985E+00 0.368D+00 1215 533.652 68.745 0.265D+00 0.231D+00 0.965E+00 0.3660+00 4 1230 533.652 68.748 0.196D+00 0.2290+00 0.945E+00 0.364D+00 1245 533.584 68.744 0.1190+00 0.227D+00 0.926E+00 0.3620+00 1300 533.653 68.743 0.217D+00 0.226D+00 0.906E+00 0.3600+00 1315 =533.660 68.741 0.2370+00 0.224D+00 0.886E+00 0.3580+00 1330- 533.667 68.736 0.2790+00 0.222D+00 0.867E+00 0.3560+00 <

1345 533.653 68.737 0.234D+00 0.2200+00 0.847E+00 0.355D+00

-1400 533.638~ 68.739 0.1880+00 0.2180+00 0.827E+00 0.353D+00 L 1415 533.639 68.737 0.1870+00 0.2160+00 0.808E+00 0.3510+00 1 1430 533.658 68.739 0.184D+00 0.2140+00 0.788E+00 0.3490+00 1445 533.663 68.738 0.185D+00 0.212D+00 0.768E-01 0.3470+00

-1500 533.655 68.736 0.1820+00 0.2100+00 0.749E-01 0.345D+00 l 1515 533.670 68.735 0.1970+00 0.2080+00 0.729E-01 0.3430+00 l 1530 533.622 68.733 -0.157D+00 0.206D+00 0.709E-01 0.341D+00 i

1545 533.679 68.729 0.223D+00 0.204D+00 0.690E-01 0.3390+00 f 1600 533.682 68.730 0.2070+00 0.202D+00 0.670E-01 0.337D+00

1615 533.683 68.730 0.2000+00 0.2000+00 0.650E-01 0.3350400 l 1630 533.695' 68.727 0.2190+00- 0.1980+00 0.631E-01 0.3330+00 6 i'i 1645 533.686 68.728 0.1990+00 0.1960+00 0.611E-01 0.331D+00

'1700 533.686 68.727 0.1950+00 0.1940+00 0.591E-01 0.3290+00 1715 533.691 68.724 0.2060+00 0.1920+00 0.572E-01 0.3270+00 l_ 1730' 533.698' 68.724 0.205D+00- 0.1900+00 0.552E-01 0.325D+00

1745 533.717 68.724 0.2090+00 0.1880+00 0.532E-01 0.323D+00

.! 1800 533.691- 68.720 0.204D+00 0.1860+00 0.513E-01 0.321D+00 1815- 533.732 68.722 0.2140+00 0.~184D+00 0.493E-01 0.3190+00 i

The Calculated Leak Rate using the Total Time Method = 0.184.

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. Page C2 VERFICATION TEST DATA--MP2ILRT DEC 24, 1983 LEAK RATE BASED ON TOTAL TIME CALCULATIONS TIME TEMP PRESSURE MEASURED CALCULATED 95% CONFIDENCE LIMITS (R) (PSIA) LEAK RATE LEAK RATE LOWER UPPER 2015 533.753 68.699 2030 533.752 68.692 0.103D+01 0.7790+00 0.329E+00 0.123D+01 2045 533.725 68.691 0.342D+00 0.767D+00 0.317E+00 0.122D+01 2100 533.781 68.683 0.941D+00 0.755D+00 0.305E+00 0.120D+01 2115 533.769 68.678 0.821D+00 0.743D+00 0.293E+00 0.119D+01 2130 533.768 68.673 0.7870+00 0.730D+00 0.281E+00 0.1180+01 2145 533.733 68.671 0.594D+00 0.7180+00 0.269E+00 0.1170+01 2200 533.735 68.666 0.6180+00 0.706D+00 0.257E+00 0.1160+01 2215 533.757 68.661 0.681D+00 0.694D+00 0.245E+00 0.1140+01 2230 533.742 68.655 0.665D+00 0.6820+00 0.233E+00 0.113D+01 2245 533.773 68.653 0.682D+00 0.6700+00 0.220E+00 0.112D+01 2300 533.768 68.646 0.7070+00 0.658D+00 0.208E+00 0.111D+01 2315 533.759 68.642 0.678D+00 0.6460+00 0.196E+00 0.109D+00 THE CALCULATED LEAK RATE USING THE TOTAL TIME METHOD = 0.646

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. Page D1 APPENDIX D 9

PCV PI PCV -

1 1 2 V1 V2 V4 PLY V11 VENT M V9 V6 FI-1 V5 pg 2

TEST VOLUME FI-2 V8B V7B CONNECTION p

LOCAL LEAK TEST PANEL INSTR DESCRIPTION PCV-1, Pressure Regulator, Range 0-100 psig PCV-2 PI-1 Pressure Gauge, 0-100 psig, 2 psig increments PI-2

• Pressure Gauge, Wallace & Tiernan Absolute Pressure Gauge Model 61A-1A-0100, Range 0-100 psia, accuracy 0.1% full scale, sensitivity .01% full scale.

FI-1, Flow Indicator, Brooks full view rotameter, model 1370-00F2AAS FI-2 Dual Scale Measuring Air at 42 psig, 70*F, Scale Range:

Various, as indicated on Flow Mster Face.

• Alternate gauge, Heise - range 0-100 psig

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e Page E1 APPENDIX E LOCAL LEAKAGE RATES The attached pages show "As Found" and "As Left" local leakage rates for containment penetrations, electrical, piping, equipment hatch, and fuel transfer tube.

The electrical penetrations are designated as SEX or SWX. Since 1980 the leakage from these penetrations has been consistently low. A change from General Electric to Conax Co. electrical penetrations during the 1980 refuel outage has shown improved leakage rates. Penetration SEXA4 tube A4 shows leakage above 9000 SCCM

.however, when this penetration is tested warm (80-100*F) the leakage is minimal.

The leakage rate increases to the value shown as the seal cools. This leakage is not significant when all other penetrations are considered.

NOTE: The local leak rate test equipment contain flowmeters with either 20, 25, or 100 SCCM as the lowest reading. When the leakage rate thru a penetration is not detectable, 20, 25, or 100 is recorded as the leakage value for that penetration.

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r Page E2 APPENDIX E LOCAL LEAKAGE RATES A review of the leakage rates for the piping penetrations show several that have been large contributors to the overall Type "B" and "C" leakage rate. These penetrations (25/30, 26/31, 27/32, 28/33) contain 6" and 10" diameter Fisher Type 9222 Butterfly valves with T-ring seats. These valves are currently being investigated / evaluated in an effort to reduce their leakage rate.

In addition penetration 14 (inside and outside) valve indicates a higher "As left" than "As Found" leakage rate for 1983. This penetration was isolated during the type "A" test. Immediately following the test a type "C" test was performed. The type "C" leakage rate was above administrative limits, therefore the valves were repaired and another type "C" test performed. This final type "C" test result appears in the table.

Due to concerns identified in Section 3.1 of NRC Inspection No. 50-336/83-03*,

Northeast Nuclear Energy Company (NNECo) is presently reviewing the classification and application of the General Design Criteria provided in Appendix A to 10CFR50 to certain penetrations at Millstone Unit No. 2. NNECo intends to docket the results of this review in the near future.

NOTE: The type "C" leakate rate obtained immediately after the type "A" test was added as penalty leakage to the type "A" test leakage rate.

"T. T. Martin letter to W. G. Counsil, dated February 25, 1983.

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APPENDIX E LOCAL LEAKAGE RATE (STANDARD CUBIC CENTIMETERS PER MINUTE-SCCM)

PENETRATION 1979 1980 1980 1981 1982 1983 1983 1983 NUMBER AS LEFT AS FOUND AS LEFT AS FOUND AS LEFT AS FOUND AS LEFT SEXA5 2458 2973 100 20 20 20 20 SEXA6 25 25 20 20 20 20 20 SEXB2 1580 1658 88 100 20 20 20 SEXB4 25 25 20 100 20 20 20 SEXB5 25 2423 20 20 20 20 20 SEXB6 2412 4455 20 20 20 20 20 SEXB7 25 25 20 100 20 20 20 SEXB8 25 25 100 100 20 20 20 SEXB9 50 35 100 20 20 20 20

-SEXC1 25 25 25 20 20 20 20 SEXC3 25 25 25 20 20 20 20 SEXD1 25 25 20 100 20 20 20

SEXD3 25 25 64 100 20 25 25 t SEXD6 25 25 20 20 20 20 20 SEXD8 25 2430 20 20 20 20 20 SEXD9 50 118 100 20 20 20 20 SEXE6 60 25 20 100 20 20 20 l SEXE9 25 25 100 100 20 20 20 l SWXB1 25 25 20 20 20 20 20 SWXB2 25 25 20 20 20 20 20 SWXB3 119 182 20 20 20 20 20 SWXB4 25 25 100 20 20 20 20 SWXB5 25 1997 20 20 20 20 20 SWXB6 25 25 20 100 20 25 25 SWXB7 207 197 20 20 20 20 20 SWXB8 295 246 20 100 20 20 20 SWXB9 25 89 20 20 20 20 20 SWXC3 25 25 25 100 20 20 20 SWXC5 25 25 25 100 20 20 20 SWXD1 25 25 562 163.4 200 176 168 SWXD3 25 1948 20 100 20 20 20 SWXD5 25 1087 100 100 20 20 20 SWXD8 25 25 100 100 85 85 44 SWXD9 25 25 20 100 20 20 20

. Pcge E4 APPENDIX E LOCAL LEAKAGE RATE (STANDARD CUBIC CENTIMETERS PER MINUTE-SCCM)

PENETRATION 1979 1980 1980 1981 1982 1983 1983 NUMBER AS LEFT AS FOUND AS LEFT AS FOUND AS LEFT AS FOUND AS LEFT SWXE5 169 148 20 20 20 20 20 SWXE9 25 25

• 20 100 20 20 20 SEXE4 25 25 25 100 20 20 20 TUBE 1 SEXA4 25 25 25 100 20 20 20 TUBE 2 SEXA4 25 1236 1236 7662 9500 9930 9930 TUBE 3 SEXA8 25 25 25 20 20 20 20 TUBE 1 SEXA8 25 25 25 100 20 20 20 TUBE 2 SEXA8 25 23 25 20 20 20 20 TUBE 3 SWXA2 25 25 25 100 20 20 20 TUBE 1 SWXA2 25 25 25 20 20 20 20 TUBE 2 SWXA2 25 25 25 100 20 20 20 TUBE 3 SWXA8 25 25 25 20 20 20 20 TUBE 1 SWXA8 25 25 25 20 20 20 20 TUBE 2 SWXA8 25 25 25 20 20 20 20 TUBE 3 1 60 20 20 20 20 20 20 21 65 198 198 45 45 790 20 20 25 20 20 250 250 20 20 3 25 20 20 20 20 20 20 41 * * * *

• 20 20 4o 25 20 20 40 40 20 20 51 * * * *

• 20 20 So 25 20 20 50 50 128 128 l

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APPENDIX E LOCAL LEAKAGE RATE (STANDARD CUBIC CENTIMETERS PER MINUTE-SCCM)

PENETRATION 1979 1980 1980 1981 1982 1983 1983 NUMBER AS LEFT AS FOUND AS LEFT A5 FOUND AS LEFT AS FOUND AS LEFT 10 25 7856 7856 3000 3000 3260 118 11 1386 445- 445 283105 20 20 20 141 50 1385 25 15969 116 34 4200 140 1550 25 25 230 230 443 1398.6 21A 30 100 100 115 20 69 69 218 25 20 20 20 20 20 20 21C 600 393 393 2000 20 32 20 21D 25 100 100 20 20 30 30 210 229 25 25 100 100 20 20 22 45 6860 416 900 900 2980 69 23 991 1194 20 20 20 20 20 24 1390 400 400 121 121 89 89 25 T;00 100 100 20 20 7539 20 26 1500 9850 197 820 820 103560 108 27 598 231288 990 73015 40 630241 99 28 497 30913 709 1327406 80 1520906 20 29 1690 179 179 20 20 89 89 30 TESTED WITH PENETRATION #25 31 TESTED WITH PENETRATION #26 32 TESTED WITH PENETRATION #27 33 TESTED WITH PENETRATION #28 34 350 20 20 65 65 276 276 35 30 100 20 89 89 20 20 37 56 128 128 595 595 182 182 38 129 20 20 20 20 20 20 39 1200 5132 1184 3400 3400 988 988 40 1400 145908 1037 172493 100 987 987 431 25 100 20 20 20 20 20 430 110 100 100 20 20 20 20 49 SPARE-PENETR\ TION 100 20 20 98 98 51 299 493 493 5106 181 217 217 53 200 100 100 20 20 30 30 54 600 197 197 100 100 2587 99

, 61 90 25 20 20 20 20 20 1

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o APPENDIX E LOCAL LEAKAGE RATE (STANDARD CUBIC CENTIMETERS PER MINUTE-SCCM)

PENETRATION 1979 1980 1980 1981 1982 1983 1983 NUMBER AS LEFT AS FOUND AS LEFT AS FOUND AS LEFT AS FOUND AS LEFT 62i * * * *

• 5215.6 601 62o 110 25 25 110 110 45 45 63 25 20- 20 20 20 20 25 64 25 20 20 20 20 20 20 65 TESTED WITH PENETRATION #22 67 25 197 ~197 20 20 20 20 68 30 197 197 20 20 20 20 72 TESTED WITH PENETRATION #23 82 26 100 100 1700200 20 4000 20 83 25 25 25 333 333 20 20 85 100 25 25 20 20 20 20 86 40 100 100 20 20 20 20 871 * * * *

• 6539 100 87o 1244 93 93 62 62 28 28 88 25 100 100 20 20 20 20 89 25 25 25 20 20 20 20 EQUIPMENT HATCH 25 100 400 400 61 61 20 FUEL TRANSFER 90 89 89 89 230 230 40 TUBE I

• INNER VALVE WAS NOT CONSIDERED A CONTAINMENT ISOLATION VALVE

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