ML20151V071
| ML20151V071 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 02/03/1986 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20151V060 | List: |
| References | |
| 35, NUDOCS 8602110190 | |
| Download: ML20151V071 (19) | |
Text
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' ATTACHMENT Consumers Power Company Big Rock Point Plant-Docket 50-155
'SPECIAL REPORT NO. 35 REACTOR CONTAINMENT. BUILDING INTEGRATED LEAK RATE TEST February 3, 1986' 2-9602110190 860203 PDR ADOCK 0500 5
P 18 Pages IC0186-0016-NLO4 L
a s-e BIG ROCK POINT NUCLEAR PLANT REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST Report Contents Page.
1.0
SUMMARY
1-4
1.1 INTRODUCTION
I 1.2 RESULTS 1-4 2.0 DISCUSSION-4-7 2.1 ANALYSIS TECHNIQUES 4-5 2.2 DATA ACQUISITION.....
5-6 2.3 CONTAINMENT CONDITIONS..
7
3.0 CONCLUSION
S......
7-8
4.0 REFERENCES
8 LIST OF FIGURES Figure 1 - Hold Test Graphs of Containment Average Temperature, Vapor Pressure and Pressure.
9 Figure 2 - Hold Test Graph of Containment Mass.
10 Figure 3 - Verification Test Graphs of Containment Average Temperature, Pressure and Mass 11 LIST OF TABLES Table A - Summary of Big Rock Point Plant Containment Integrated Leak Rate Tests...............
12 Table B - Summary of Local Leak Rate Tests............
13-17 PR1185-0364A-TM32
1 1.0
SUMMARY
1.1 INTRODUCTION
Consumers Power Company's Big Rock Point Nuclear Plant completed its tenth (in a series from 1962) reduced pressurt Containment Integrated Leak Rate Test (Type A). A summary of past Type A tests is given in Table A.
The results of all Local Leak Rate Tests (Types B and C),
conducted since the previous Type A test, are listed in Table B.
The containment enclosure has a net free volume of 912,891 cu ft designed for 27 psig with a calculated accident peak pressure of 23 psig. The vessel.is made of carbon steel plate ranging from 1/2" to 3/4" thick with 1" to 1-1/2" of polyurethane insulation; therefore, it is susceptible to changes in atmospheric conditions.
Partly cloudy conditions prevailed through a majority of the 24-hour hold j
test. Skies cleared during the verification period. Temperatures 5
ranged from 49' to 68*F.
Diurnal effects were experienced requiring the verification test to be extended 6.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />. However, hold test stability was not adversely affected.
1.2 RESULTS In order to fulfill the requirements of Reference 4.3, a Type A test began with pressurization on October 25, 1985 and concluded with depressurization on October 28, 1985. A reduced test pressure of 13.75 psig was recorded at the end of the 24-hour hold test.
From the 24-hour hold test data, the measu ed containment integrated leak rate (L,) was 0.0915 wt %/ day with an upper confidence limit g
of 0.0959 wt %/ day. The total containment leak rate was 0.1268 wt
%/ day, following additive corrections for Type C tests in accordance with Reference 4.6 for repaired and unvented valves.
l PR1185-0364A-TM32 I
L-
9 2
Following the 24-hour hold test, a measured leakage verification test was performed employing the method suggested by Reference 4.7, Appendix 3, and adopted by Reference 4.3.
A controlled leak (L,) of 0.277 wt %/ day was imposed on L,. Reference 4.4 states the measured g
composite leak rate (L ) shall be bound by L, + L, i 0.25 L, ie, c
g 0.279 5 L, 5 0.457 (wt %/ day), where L is the maximum allowable t
leak rate at test pressure. The measured composite leak rate over the verification test period was 0.292 wt %/ day which met the requirements of Reference 4.4 and Reference 4.3,Section III.A.3.b, and thus confirmed the Type A test measured leak rate.
For a reduced test pressure of 13.75 psig, the maximum acceeptable leak rate for a Type A test is 0.2676 wt %/ day (0.75 L ) per g
Reference 4.3,Section III.A.5.b.1, including Type C additions made compulsory by performing repairs prior to conducting a Type A test or by not venting a pressure boundary. Having met this acceptance criterion, the Big Rock Point Plant was able to resume power opera-tion without further repairing any containment penetrations and reperforming the Type A test.
The following plant modifications affecting containment integrity were completed since the 1982 Type A tert:
1.
Feedwater Check Valve VFW-305 was installed. The applicable Type C test specification is TR-39I.
2.
Penetration H-92 was dedicated for RDS nitrogen supply. The applicable Type C test specification is TR-39R.
i i
l PR1185-0364A-TM32 t
3 3.
Two (2): Appendix R penetrations were installed in the equipment hatch. Local leak rate testing is an integral part of the equipment hatch Type B test, Specification T180-01B.
Preceding the Type A test, no post shutdown repairs or changes were made to any of the containment's Type B penetrations, permitting all Type B penetrations to be tested in their true "as found" condition.
Type C test leak rate improvements for components which were repaired during the refueling outage prior to performing the Type A test, and required to be added to the results thereof, are:
Repaired Leakage Improvement
- Valve 'amponent Train (wt %/ Day)**
Reactor and Fuel Pit Drain 0.0066
/CV-4027 and CV-4117)
C1.an Sump Discharge 0.0002 (CV-4102 and CV-4031)
Exhaust Vent Valve 0.0215 (CV-4094/5)
Resin Sluice Line 0.0005 (CV-4091/2)
Total Repair Improvements 0.0288
- Leakage improvement taken as the difference in minimum pathway leakage before and after repairs, as discussed in Reference 4.6, adjusted to actual test pressure at 95% upper confidence limit
- Containment mass taken as 130,683.9 pounds PR1185-0364A-TM32
4 Containment pressure boundary lines which could not be readily vented necessitating the Type C test results be added to the Type A test results are:
Type C Leak Rate
- Valve Component Train (wt %/ Day)**
Demin Water Isolation 0.0015 (CV-4105 and VMU-300)
Treated Waste Return 0.0003 (CV-4049 and VRW-313)
RDS Nitrogen Supply-1.18E-8 (PCV-4520, VC Inc-20 and VC Ine-301)
ILRT Test Penetrations 0.0003 (H-80, H-88 and H-91)
Total Unvented Leak Rate 0.0021
- Type C leak rate adjusted to actual test pressure at 95% upper confidence limit
- Containment mass taken as 130,683.9 pounds Successful results of the Big Rock Point Type A test have verified the integrity of the containment building and confirmed the effective-t ness of the Type B/C testing program. Therefore, the next Type A test has been tentatively scheduled for the 1989 refueling outage.
A compilation of all Type A test measured data and calculations of required Type C corrections thereto have been filed with the working copy of the CILRT procedure (Reference 4.5).
I 2.0 DISCUSSION 2.1 ANALYSIS TECHNIQUES The weighting factors used to calculate the average containment dry bulb and dew point temperatures have been calculated based on the number of sensors within a subvolume. The containment vapor pressure is computed by converting the Foxboro dew point temperature
. sensor (deweell) readings to vapor pressure readings through the use 1
PR1185-0364A-TM32 n
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of the ASME steam tables for water and applying the appropriate weighting factors. The containment vapor pressure is subtracted from the absolute pressure to give the ccatainment dry air partial pressure. The partial pressure of dry air and the weighted average containment temperature are then used to calculate the leak rate in 4
wt 1/ day.
j The absolute method of determining the leak rate was used for this
-test and measurements were recorded every 15 minutes. The leak rate was computed using the mass point method of analysis which is endorsed by Reference 4.2.
In the mass point method of analysis, data from an absolute system i
is reduced to a contained mass of dry air by application of the ideal gas law. The test data consists of a time series of inde-pendent values of contained air mass.
If the assumption is made that the leak rate is constant with time, the data lends itself to analysis by the method of linear least squares. The slope of this j
line represents the rate of change of air mass with respect to time, l
which is the leak rate. Because of its independent nature, a measurement error will result in only one bad data point and not I
materially affect the test results. Although no data was rejected in this test, the data rejection criteria found in Appendix D of Reference 4.2 was used by the computer program to check for anomalous data.
2.2 DATA ACQUISITION i
The test procedure employed was the absolute method as endorsed by Reference 4.2, Section 5.
The instrumentation system consisted of twenty (20) Resistance Temperature Detectors (RTDs), ten (10) dewcells and two (2) pressure sensors used to measure the average dry bulb and dew point temperatures and containment pressure, respectively. The weighting factors used to calculate the average containment air temperature were determined on the basis of the i
PR1185-0364A-TM32 t
6 number of sensors within a subvolume. The maximum weighting factors were 5.836% for an RTD and 11.645% for a dewcell. An in situ calibration check of all sensors was performed.'
The sensitivities of the RTDs, dewcells and pressure gauges are within the requirements established by Reference 4.2, Section 4.3.1.
The calculated Instrument Selection Guide (ISG) for the instrumen-tation system is 10.005% per day which meets the requirements of Reference 4.2, Section 4.1.2.
Adjustments to this calculation were not required as no sensors were lost during the test.
Sensor data was collected by the ILRT panel purchased from Volumetrics (Model 14629) and transferred to the PDP 11/03 digital minicomputer after receiving the data. The minicomputer program performs the functions listed below:
1.
Reduces raw data into weighted average temperatures, vapor pressures and containment pressure necessary for use in the leak rate calculations.
2.
Calculates the leak rate in wt %/ day using the mass point analysis method.
3.
betermines the 95% upper confidence limit of the leak rate using the methods described in Reference 4.2, Appendix B.
4.
Calculates the data outlier and the appropriate rejection level according to the criteria of Reference 4.2, Appendix D.
5.
Provides plots of individual test parameters as well as contain-ment average temperature, pressure, vapor pressure and mass as a function of time.
PR1185-0364A-TM32
7 2.3 CONTAINMENT CONDITIONS The average containment temperature fulfilled the stabilization requirements of Reference 4.2, Section 5.3.1.3, and Reference 4.5, Section 5.3.1, four hours after pressurization was completed. The containment was permitted to stabilize an additional two hours before the hold test portion of the leak rate test was declared to start at 299/02 15:00.
Containment parameters have been plotted to illustrate the average conditions throughout the 24-hour hold test as shown in Figure 1.
The sine wave shape of the temperature and pressure profiles is exemplary of the diurnal effect experienced. Containment mass throughout the 24-hour hold test is shown graphically in Figure 2.
The diurnal'effect, so visible in the temperature and pressure profiles, is barely so in the mass profile.
Diurnal effects encountered near the conclusion of the four-hour verification test created some instability in containment average conditions. Consequently, an additional 6.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> were required for leak rate verification under stable containment conditions.
Figure 3 consists of plots tracking containment average temperature and pressure as well as calculated containment mass for the full 10.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> of verification.
3.0 CONCLUSION
S j
3.1 The Big Rock Point containment satisfied the acceptance criteria for l
the Type A test.
i 1
3.2 The controlled leak rate verified the hold test results.
i 3.3 The calculated ISG fulfilled the acceptance criteria of Reference 4.5, Paragraph 6.3.
PR1185-0364A-TM32
r 8
3.4 The results of all Type B and C tests meet the requirements of Reference 4.4, Section 3.7.
4.0 REFERENCES
4.1 Consumers Power Company Special Report 31, "1982 Reactor Containment Building Leak Rate Test" 4.2 ANSI /ANS 56.8 - 1981, "American National Standard Containment System Leak Testing Requirements" 4.3 10 CFR 50, Appendix J 4.4 Big Rock Point Technical Specifications 4.5 Big Rock Point CILRT Procedure TV-02, Revision 16 4.6 NRC IE INF0P.MATION NOTICE 85-71: Containment Integrated Leak Rate Tests 4.7 ANSI N45.4-1972, "American National Standard Leak Rate Testing of Containment Structures for Nuclear Reactors" PR1185-0364A-TM32
FIGURE 1 9
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12 TABLE A SlDMARY OF BIG ROCK POIFr PLANT CONTAINMDrr IFTERGRATED LEAK RATE TES'IS Test Measured Ieak Allowable Leak Date Pressure (Psia)
Date-Ltm (vt %/ Day) Rate-Lt (vt 5/ Day)
Comments 1/61 27 0.036 0.5 Included pneumatic overload test at 33.75 Psig.
6/62 10 0.36 0.121 Allowed leak mte is 75%
of Technical Specification reduced pressure allowed leak rate from 6/62 to the last test of h/74.
4/64 10 0.037 1 0.034 0.121 h/66 10 0.077 1 0.025 0.121 7/68 10 0.061 1 0.017 0.121 3/70 10 0.08h 1 0.030 0.121 4/72 12 0.028 1 0.072 0.1h9 h/74 13 0.075 1 0.0L7 0.131 Measured containment leakage rate after acceptance of ventilation valve.
1 2
9/77 13 0.072 1 0.043 0.174/0.347 195% eonfidence level of containment leak rate corrected for measured local leakage rate of feedwater check valve 2 Technical Specification limit /10CFR50 Appendix J,Section III A.4 limit.
1 h/82 12.6 0.0201/0.0232 0.3416 1 Nominal measured leakage rate /955 approx upper confidence limit. The The difference in leak-age rates from before maint. and after naint.
results is not added to these leakage rates.
1 10/85 13 75 0.0915/0.0959 0.3568 1 Measured leak rate 955 upper confidence limit.
0.1268 2 Total containment lesk rate inclusive of Type C corrections.
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TABLE B (contd) 16 H-80 Commente/
Date SVY EW PL teL Est CPen CSPD DSPD EC Tnat RS R&FPP CRD MS FW 88.91 DM VP WS Footnotes lo/20/s5
.0004 1;/23/s5.o35s.1059 lo/25/es
.142a
- Unable to held pressure..
Itaperted results are for FL and EqL Pouell check valres.
2Esported results are for optional teste.
E, 7M results are stated la other than percent of tech spec limit.
l l
i MIO186-03044-19tL6-Bt33 l
r 17 TABLE B LEDEND SVV
- Supply Vent Valve EVV
- Exhaust Vent Valve PL
- Personnel Iock EqL
- Equipment Lock EsL
- Escape Lock CPen - Conax Penetrations Hl40, H65, H81, H83 CSPD - Clean Susp Pug Discharge DSPD - Dirty Sunp Pump Discharge EC
- Emergency Condenser Sample-Point Check Valve or Sight Glass Vent Valve WR
- Treated Waste Return RS
- Resin Sluice Line R&FPD - Reactor and Fuel Pit Drain CRD
- Control Rod Drive Isolation MS
- kin Steam Isolation and Drain W
- Feedwater Check Valve i
Dm~
- Demin Water Isolation VP
- Ventilation Probe NS
- Nitrogen Supply'- RDS i
i 118 H 19
-