ML20236X869
| ML20236X869 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 12/07/1987 |
| From: | Azar M, Hunsader S COMMONWEALTH EDISON CO. |
| To: | Murley T NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation |
| References | |
| 3935K, NUDOCS 8712100324 | |
| Download: ML20236X869 (58) | |
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"JACTOR CONTAINMENT BUILDING INTEGRATED LEAKAGE RATE TEST BRAIDWOOD NUCLEAR STATION UNIT TWO PRE-OPERATIONAL TEST September 6 - September 11, 1987 Prepared by M. Azar i
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l i 1 - I ig TABLE OF CONTENTS Page 1.0 Abstract 3 2.0 Summary of Type A, B & C Test Results 4 i 3.0 Test Preparations 8 4.0 Test Methodology 12 5.0 SLamary of Events 15 6.0 Type A Test Data 21 6.1 Reduce Pressure Test 22 6.2 Full Pressure Test 24 6.3 Full Pressure Supplemental Test 27 7.0 Type A Test Plots 28 7.1 Reduced Pressure Test 29 7.2 Full Prer,sure Test 32 7.3 Full Pressure Supplemental Test 35 8.0 Interpretation of Test Results 38 8.1 Reduced Pressure Test 38 8.2 Full Pressure Test 38 8.3 Full Pressure Supplemental Test 39 9.0 Type B & C Test Results 40 10.0 Attachments 45 11.0 Containment Modification , 54 1 2 _____ _ _ _ __ 3 $7315])
l t 8 A 1.0 ABSTRACT This report provides the details of the Braidwood Unit Two Preoperational Conta.inment Integrated Leakage Rate Test (ILRT) performed September 6 through September 11 1987. The test' was performed in accordance with Appendix J to 10CFR50, ANSI N45.4-1972, and the Byron /Braidwood Final Safety Analysis 1 R6 post. This report contains information on the following items associated with the Braidwood Unit Two Containment Leakage Rate Program:
- 1. Type B & C Local Leakage Rate Testing
- 2. ILRT/ SIT Plant Equipment Lineup
- 3. Reduced Pressure ILRT
- 4. Full Pressure ILRT 5 Supplemental Verification Test Item 1 took place _from rebruary to August 1987 in addition some retesting was done in October of 1987. A brief discussion of the Local Leakage Rate Test Methodology and a summary of the leakage rates can be found in Section 9. Item 2 was performed from August 24 to September 2, 1987. Item 3 started on September 6 and Item 5 concluded on September 11, 1987.
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3 1 (3721u)
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2.0
SUMMARY
OF TYPE A, B, & C TEST RESULTS 2.1 Test Acceptance Criteria for the Type A Test. 2.1.1 Acceptance Criterion #1 stated: "For the Full Pressure ILRT, verify the overall Integrated Leak Rate, which is equal to the 95% Upper Confidence Limit of L,,added to.the required local leakage rate additions, is less than 0.75 L,". The 95% Upper Confidence limit was determined to be
.0490%/ Day or 3.78 SCFM. The local leakage rate additions are as follows:
Penetration No. Reason Valve No. Liakage (SCCM) 82 & 83 No way to vent 2SD002A & 2B 1512 80 & 81 No way to vent 2SD002C & 2D 512 88 & 89 No way to vent 2SD002E & 2F 5112 90 & 91 No way to vent 2SD002G & 2H 52120 P98 Fuel Transfer Tube 3512 a4 Pressurization Line CPP Line 124.112
*I3 Pressure Sensing Line 2VQOl6 25.612
*I3 Induced Leak Line 2VQ017 2.512
*P36 H M nitor Return 65612 2
)
TOTAL 966.2129** SCCM
- Tested subseq~oent to the test
** ERROK TOTAL CALCULATED by the square root of the sum of the squares of the individual errors.
{ l 4 (3721u) l
f $ s 996 1 29 SCCM x 1 CF = .035 i .001 SCFM 28317 CC The total local leakage rate addition is .035 SCFM (.00046%/ Day). The overall Integrated Leak Rate is .0435%/ Day (3.36 SCFM) which is'less than the acceptance criterion of .75 L[(.075%/ Day)or5.79SCFM. 2.1.2 Acceptance Criterion #2 stated, "For the Full Pressure ILRT Supplemental Test, verify the measured composite leakage L c *" "
- a of the sum of the superimposed leakage LO ""
- previously measured leakage L ,. i.e.
Ib0*bam - 0.25L,) i L i (L +L + 0.25 L,); where the superimposed leakage rate Lgshall be between 75% and 125% of L,." The superimposed leakage L was 7.72, SCFM which was 100% of L,. .The previously measured leakage L was 3.36 StTM. 0.25 L, is equal to 1.93 SCFM, yielding an acceptance criteria range of 9.15 SCFM to 13.01 SCFM. The measured composite leakage L was 12.16 SCFM which was within the acceptance criteria range. 2.2 Test' Acceptance Criteria for the Type B & C Tests 2.2.1 Acceptance Criterion #1 stated: "The combined leakage rate, including the measurement error, for all penetrations and valves subject to Type B and C tests shall be less than 0.60 La at a minimum pressure of Pa (44.4 psig)". The tests were 5 (3721u)
i 1 l, performed by locr1 pressurization.using air or nitrogen and measuring the. amount of air or nitrogen it takes to keep the system at l. approximately.46 psig. 0.60 La = 277.77 scfh and. the measured leakage was 43.65 scfh + 2 scfh. , 1 l 2.2.2 ~ Acceptance Criterion #2 stated: "The Equipment Door Air Lock shall each have a leakage rate of L L less than or equal to 0.05 La at a minimum pressure 1 of Pa (44.4 psig)". This was met by pressurizing the airlocks with air and measuring the amount of p -air required to keep the Airlock at approximately 46 psig. The integral Personnel. Airlock pressurization test had a measured leakage rate of
.1317 scfh. The Cmergency Airlock pressurization test had a measured leakage rate of .0364 scfh.
This is less than the allowable of 23.15 scfh (.05 La )' . 2.2.3 Acceptance Criterion #3 stated: " Normal Containment Purge-(VA) Penetrations P-95 and P-97, consisting of containment isolation valves-(2VQ002ALB, 2VQ007) and (2VA001A&B, 2VQ006) respectively, shall have a measured leakage rate less than 0.05 La at a minimum pressure of Pa (44.4 psig)". This was met by~ pressurizing the area between the valves (2VQ001A & B or 2VQ002A & B) and measuring the amount of air required to keep the l 4 area at approximately 46 psig. The measured j l i I 6 (3721u)
leakage rate for 2VQ001A & B.was .0509'scfh. The measured leakage rate for 2VQ002A & B was .1162
- sefh. The allowable leakage rate for each is 23.15 1
scfh. 2.2.4 Acceptance Criterion #4 stated: "Miniflow Containment Purge (VQ) Penetrations P-94 and P-96, Econsisting of containment isolation valves (2VQ005A, B & C, 2VQ003,'2VQ009) and (2VQOO4A & B,
'2VQOO8):respectively, shall each have a measured leakage rate less than 0.01 La at a minimum
- pressure of Pa (44.4 psig)". This was met by pressurizing the area between the isolation valves and measuring the leakage. The measured leakage for 2VQ005A, B & C and 2VQ003 wa's .0345 scfh. The measured leakage for 2VQ004 A & B was .0159 scfh.
The allowable leakage rate for each penetration is 4.63 scfh. 2.2.5 Acceptance -Criterion #5 stated, "Each Personnel Lock Door Gasket Interspace shall have a measured leakage rate less than 1.94 scfh at a minimum pressure of 10 psig". This was met by pressurizing the interspace to approximately 10 psig and measuring the leakage. The measured leakage Equipment Hatch door gasket interspaces were 0.8-sgfh and 2.8 scfh. The measured leakage Emergency Hatch door gasket interspaces were .6 scfh each. ( 7
.(3721u)
l l 3.0 TEST PREPARATIONS i 3.1 Type A Test Procedure l The Unit 2 Preoperational Containment ILRT was performed in accordance with test procedure BwPT PC-51, revision 0 t and revision 20 of the Braidwood Startup Manual. BwPT-PC-51 was written to comply with Appendix J of 10CFR50 and ANSI N45.4-1972, although much of the methodology used was taken from ANSI 56.8-1981. During execution of the test procedure 15 test change requests were issued. 3.2 Type A Test Instrumentation Setup Containment Air mass data was taken utilizing a ! Volumetrics Data Acquisition System (DAS). Twenty five RTDs for temperature measurement and ten lithium chloride deweells for determining vapor pressure were located in containment as shown in Attachment 10.1. A multiplexer scanner (MUX) located inside containment scanned the j sensor outputs and transmitted the reading through a permanent electrical penetration to the DAS console located in the Auxiliary Building. Containment absolute pressure gauges located in the DAS and connected to containment by a short run of poly-flo tubing. Additional in:trumentation used included an ambient pressure transducer, ambient temperature RTD and a mass flow meter used to measure the superimposed leakage of the supplemental verification test. ( 8 (3721u) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ . _ _i
Attachment 10.2 contains specifications for the aforementioned equipment including values for accuracy, repeatability, sensitivity and resolution for the RTDs, dewcells, and pressure sensors. The quality and quantity of the sensors chosen were such that the Instrument Selection Guid (ISG), as defined by ANSI 56.8-1981, would still be less than 0.25 La for a test duration less than 24 hours assuming failure of several RTDs or dewcells and one pressure sensor. Attachment 10.3 depicts the general arrangement of the Integrated Leakage Rate Monitoring System relative to the containment wall. 3.3 Type A Test Data Processing Leakage rate data was acquired by the DAS every 15 minutes. This included Time, Julian Date, RTD temperatures, Dew Cell temperatures and absolute pressure sensor readings. The data was sent electronically to the Prime Computer through two telephone modems in a RS232 format as shown in Attachment 10.4. The Prime Computer placed the incoming data into a permanent file from which it drew one data set at a time to compute the leakage rate. From the Prime Computer User Terminal the data was reviewed for completeness and accuracy and then entered into the leakage rate program. Leakage rates, raw data and calculation summaries could be printed as desired for review snd later permanent storage. The multicolor plotting of leaktge rates and other date on both hard copy i 9 1
s (HP Plotter) and the Ramtek 6211 CRT was available to facilitate trending parameters such as containment leakage rate, dry air pressure, vapor pressure and containment average temperature. The Unit 1 ILRT data sets were used to prove the validity of the prime computer ILRT code. The results of the data set entered in the computer were compared with the Unit I results and found acceptable. 3.4 Type A Test Subvolume Determination The containment was divided into 5 discrete subvolumes. Subvolume demarcation and size are indicated on Attachment . 10.1. Subvolume 4 is defin>ed as the annulus between the outermost containment wall and the Missile sa.rrier below the 426' level. Subvolume 5 is the volume inside the Missile Barrier below the 426' level, not including the reactor cavity. Two dew cell sensors were distributed to each subvolume so that loss of any one sensor would not leave a subvolume uncovered. RTD sensors were placed so that each sensor had a weighting factor of 3-5*/. and loss of any one sensor would not result in an RTD weighting factor of greater than 10'4 for any single sensor. Containment temperature surveys were performed prior to the test to justify the location of the sensors. The surveys showed a maximum temperature variation of 3.8 P over one subvolume thus validating the sensor locations. 10 (3721u)
3.5 ILRT/ SIT Plant Equipment Lineup The valve and equipment lineups are detailed and specific, i.e. component by component with individual signoffs. This ensured containment integrity conditions as close as l possible to those which exist after a design basis Loss of Coolant Accident (LOCA). It also assured penetrations were properly drained and vented. Out of Service cards were hund to preclude misalignment during the test. 3.6 Structural Integrity Test The Structural Integrity Test (SIT) of Unit 2 containment preceded the Integrated Leakage Rate Tests. It utilized the valve and equipment lineup of the ILRT procedure to isolate the containment and protect equipment within exposed to pressure. During the SIT the containment was pressurized to greater than 57.5 psig or 115% of its design pressure of 50 psig. A post-SIT / pre-ILRT inspection of accessible interior and exterior containment surfaces indicated no significant deterioration of the containment structure. 3.7 Type A Test Pressurization Eight 1500 SCFM Diesel Driven " oil free" air compressors with air coolers and dryers were used to pressurize containment. The compressors were situated on the east side of the Fuel Handling Building. Pressurization was accomplished through a six inch header pipe which penetrates containment at penetration P-4. (See attachment 10.5 for a general arrangement). l l 11 (3721u)
4.0 TEST METHODOLOGY 4.1 Reduced Pressure ILRT During this 24 hour test, pressure, temperature, and l humidity data were taken to determine the statistically averaged containment leakage rate Lg (weight percent /24 , hours).- The test was conducted at a noniinal pressure of l Pt (24 psig) above the required minimum of 22.2 psig (0.5 P,). Reactor Containment Fan Coolers were operated 6 during the test. 4.2 Full Pressure ILRT During this 24 hour test, pressure, temperature, and humidity data were taken to determins the statistically averaged containment' leakage rate L (weight peretnt/24 hours). The test war conducted at a nominal pressure of 46 psig above the required minimum of P (44.4 psig) the Design Basis Accident containment pressure. Reactor Containment Fan coolers were not run during ti.is test. The purpose of this test was to determine a 95% Upper Confidence Limit value of L g for a 24 hour period. 4.3 Temperature Stabilization Periods Prior to start of each ILRT a Temperature Stabilizatioit Period of a minimum duration of 4 hours was emplored. The criterion for temperature stabilization was as follovis: The latest rate of change of the weighted average containment air temperature averaged over the last hour does not deviate by more than 0.5'F/hr from the average l rate of change of tne weighted average contairaent air temperature average over the last 4 hoitrs. 12 (3721u) l
, a 4.4 Supplemental Verification Test Following the Full Pressure ILRT, a deliberate leak of known magnitude was superimposed on the existing containment leakage through a calibrated flowmeter. The superimposed leak was maintained between 0.75 L, and 1.25 L,(5.79 and 9.64 SCFM).
The duration of the test was defined as a minimum of 4 hours e.nd 10 sets of data. The acceptante criterion for the test was follows: The statistically averaged i Composite Leakage Rate (L ) is within 0.25 L, (1.90 SCFM) of the sum of the statistically averaged Full Pressure ILRT 2eakage rate (L ) and the average flowmeter induced leakage rate (L ). 4.5 Method of Leakage Rate Determination The leakage rate is assumed to be constant during the testing period, ideally yielding a straight-line plot with a negative slope. However, sampling techniques and test conditions are not perfect; consequently, the measured values will deviate from the ideal straignt-line situation. A Least Squares Fit Statistical Analysis was performed to determine a regression line for mass versus time after each set of data was acquired. The slope bf this regression line was designated to be the statistically averaged leakage cate (L,,) for the Full Pressure ILRT. l l l 13 (3721u)
r
- l. -
I. I Asso".:iated with the statistically averaged leak rate was the 95% upper confidence limit leakage tate Ib ucla). The calculation of this upper limit was based upo l n the standard deviations from the regression line and the o ne-sided T Distribution function. An expanded discussion of the Least Squares Fit Stat.istical techniques used can be fo und in Attachment 10.6. I
\
14 (3721u)
5.0
SUMMARY
OF EVENTS 8/24/87 0830 Began lineups on SD, CV, PC, RE and WM systems 1120 Comple'ed t SD Lineup 1130 Completed WM Lineup 1314 Began Lineup on AF & FW systems 1322 Began Lineup on MS system 1421 Completed FW and AF Lineups 1742 Completed CV Lineup 1750 Completed MS Lineup 2130 Completed FC Lineup < 8/25/87 0030 Began Lineup on VQ 0200 Began Lineup on CS 0900 Began Lineup on SI 1330 Began Lineup on OG 2015 Completed CS Lineup and began FP Lineup 2115 Completed FP Lineup 8/26/87 0235 Completed OG Lineup 1420 Completed SI Lineup except for 2SI880SA, B. C and D 3 valves. I 8/29/87 1830 Began Lineup on PR i 15 i L (3721u) ! I _ _ _ _ - _ _ . _ _ _ _ _ _ . ._. - _ _ - _ _ _ _ _ . _ _ _ ._.__ _._ -____ ________ _ -____ _N
L l l l l 8/30/87 l l 0245 Completed Lineup for 2SI8808A, B, C and D 0400 Completed Lineup on PR 1000 Completed VQ Lineup 2330 Began Lineup on CC 08/31/87 i 0545 Completed RE Lineup 1540 Completed CC Lineup 1830 Began Lineup on PS 9/1/87 0300 PS Lineup completed with the exception of 2PS227B 1400 Completed SA Lineup 1802 ' Began SX Lineup and Completed RY Lineup 9/2/87 0400 Placed SX and CC in operation for the 2B RHR Hx at 3300 9Pm 0445 Completed SX Lineup 0715 Completed RH Lineup 1024 Capped 2PS229B P-36 ' 1830 Began Lineup on WO & IA l, 9/3/87
. ?
0100 Completed IA Lineup 0310 Completed WO Lineup l 0600 SIT pressurization concerned 16 (3721u). 4
9/5/87 1500 SIT depressurization completed 1530 Containment access authorized and POST SIT. PRE ILRT inspection initiated
'9/6/87 0625 SIT equipment relixation complete 0910 Briefed testing personnel, verified prerequisites and initial conditions 0915 Entered ILRT procedure at Step 9.1.1 support system CC and SX verified operating 1034 Started pressurization 1129 CNMT pressure high alrrm annunciated 1220 Exited ILRT procedure at 5 1/2 psig Step 9.1,7 at the request the operating engineer because of six simultaneous fire alarms in containment 1355 Started pressurization and reentered ILRT producer at Step 9.1.8 after ensuring the shift foreman was satisfied !
and all prerequisites initial conditions were reverified 1700 Started the RCFC at 15.1 psig 1701 NSO tripped the A RCFC because the pump meter came up to 325 amps and held there. Deficiency J written 1710 The A RCPC was restarted per the direction of ILRT STE after discussing the problem shift foreman, and VP-52 STE. l i 1835 CNMT press Hi Hi Hi alarm annunciated l 1940 Shut down RCFC Fans 1 l 17 l l (3721u)
1950 Exited Section 9.1 entered 9.2 all prerequisites and initial conditions verified 1951 Began shutting down compressors a 2000 Began temperature stabilization 9/7/87 0100 Temperature stabilization reached, reduced pressure test started 1100 Major leak on the pressurization line identified but could not be fully isolated. NRC inspector was informed of the leak and the plan to terminate the reduced pressure test at the end of the 24th hour period and during the full pressure test the containment pressurization line would be blanked off by valve 2VQO11 (M105-3). 9/8/87 0100 Terminated reduced pressure test with an upper confidence Leak rate of .0844%/ day exited section 9.2, entered section 9.3. All prerequisites and initial conditions verified. Started pressurization 0750 Exited section 9.3 and entered section 9.4 all prerequisites and initial condition verified 0812 Peak pressure reached. 0846 Pressurization line blanked off 0900 Temperature stabilization started NRC inspector informed (R. Menden) 18 (3721u)
1300 Temperature stabilization completed Loca pressure test j started. NRC inspector informed 1315 Loca pressure test started. NRC inspector informed (R. Mendez) 9/9/87 0145 Dewcell #32 deleted from the calculations because of erratic readings 1704 Completed Loca test with an upper confidence leak rate of
.0490*4/ day. NRC inspector informed 1714 Exited section 9.4 entered section 9.5 all prerequisites and initial condition verified 1728 Began induced leakage with flow set at 7.72 SCFM through the mass flow meter 2315 Induced leakage test successfully completed with NRC concurrence 2330 Exited section 9.5 and entered section 9.6 after verifying prerequisites and initial conditions 9/10/87 0115 Began depressurization .
l 0715 Reached VP-52 test pressure of 27 psig and stopped depressurization 1820 VP-52 test completed 2130 Began depressurization again ; 19 (3721u)
9/11/87 1300 Containment depressurization complete. Entered containment for final inspection 1335 Exited section 9.6-20 ILRT completed. WO containment damage was noted 1345 Began ILRT Restoration procedure 9/28/87 1300 Completed restoration portion of the ILRT procedure l l i i f 20 l (3721u)
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8.0 INTERPRETATION OF TEST RESULTS 8.1 Reduced Pressure Test The statistically average containment leakage rate L rm (weight percent per 24 hours) was .0644%/ day after 24 hours and 154 datasets. The 95% upper confidence limit c1r was 0.0844%/ day. of the containment leakage rate L The plot of leakage versus time show a steep slope downward for the first four hours with a sharp increase in the upward direction for the next three hours then finally a constant steady decreasing slope over the last seven hours once the leak in pressurization was isolated about 80%. Plots of containment dry air mass and corrected pressures versus time display a steadily decreasing trend throughout the test due to the constant leak in the pressurization header. 8.2 Full Pressure Test The statistically averaged containment leakage rate L,, (weight percent per 24 hours) was 0.0435%/ day after 24 hours and 112 datasets. The 95% upper confidence limit 1 of the containment leakage rate, L 3, was .0490%/ day with the leak in pressurization header to containment J isolated and no Reactor Containment fan coolers producing heat, the containment building cooled during the test resulting in a downward trend of the containment average pressure and temperature plots. The plot of containment q l i leakage was well below the allowable limit and at the termination of the test, still decreasing. i i l 38 (3721u)
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8.3 Supplemental Verification Test The statistically average composite leakage rate Lc "*'
.1576%/ day after 4.75 hours and 25 datasets.- This was lwithin .25.of L, of the sum of the statistically average Full Pressure leakage rate and the average mass flowmeter induced leakage rate as discussed:in Section
'2.1.2.
I< l 39
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- 9.0 TYPE B & C TEST RESULTS 9.1 Local Leak Rate Methodology Type B & C tests were conducted in accordance with Appendix J to 10CFR50 and ANSI N45.4-1972. The test volumes were pressurized and regulated with air or nitrogen to nominally 46 psig. The test volume leak rats was determined by measuring the flowrate necessary to maintain the test volume at 46 psig after a suitable stabilization period.
9.2 Leakage Rate Summary: TYPE PENETRATION (P) LEAKAGE RATE (SCCM) B Zone 1 Electrical penetration 9712 B Zone 2 Electrical penetration 10812 B Zone 3 Electrical penetration 400120 B Zone 4 Electrical penetration 370120 B Fuel Transfer Tube Flange 012 B Fuel Transfer Tube Sleeve Bellows 3512 B Equipment Door Personnel Lock 37301200 B Blind Flange #1 on Equip. Door 7.212 B Blind Flange #2 on Equip. Door 2.212 B Equip. Door Double Gasket 3.012 B Emergency Personnel Lock 1030120 B Blind Flange #1 on Equip. Door 24012 B Blind Flange #2 on Equip. Door 1212 B P-4 Cnst pressurization line 240f20 Blind Flanges C P-97 Cnmt Normal Purge (1) 1442t20 40 (3721u)
TYPE PENETRATION (P) LEAKAGE RATE (SCCM) C P-95 Cnmt Normal Purge'(1) 32901200 C P-96 Cnmt Miniflow Purge (1) 450120 C P-94 Cnat Miniflow Purge (1) 976120 C P-I3 Inst. Isolation Valve (1) 1512 C P-I3 Inst. Isolation Valve (2) 1212 C P-70 Pressurizer Strn Sample 1.012 C P-70 Pressurizer Liq Sample 14612 C P-70 Reactor Coolant Sample 5512 C P-70 Accumulator Tank Sample 3512 C P-36 Hydrogen Monitoring (SUC) C P-36 Hydrogen Monitoring (Ret) C P-45 Hydrogen Monitoring (SUC) 11.412 C P-45 Hydrogen Monitoring (Ret) 5812 C P-41 Chemical and Volume Control 80120 Letdown Line C P-11 Reactor Coolant Drain Tank 1.012 (RCDT) Pump disch. C P-65 RCDT to Auto Gas Analyzer 29120 C P-65 Waste Gas from RCDT 33120 C P-27 Pressurizer Relief Tanks 2.112 , (PRT) to Auto Gas Analyzer C P-27 PRT Nitrogen Supply 320 20 C P-28 CV Seal Water Ret. 3112 C P-24 CC Seal Water Ret. 400120 P-44 Primary Water to PRT 150120 C I-5 Pressurizer pressure indicator 2012 C P-21 Component Cooling Ret. 896120 41 (3721u)
i TYPE PENETRATION (P) -LEAKAGE RATE (SCCM) C P-25 Reactor Coolant Pump Seal. 460120-Water Supply l C- P-32 Refueling Cavity Return Header 6.512 C P-57 Refueling Cavity to Refueling 1012 Water Pump C P-1 Cnmt Spray Supply 505120' C P-16 Cnmt Spray Supply 4812 C P-39 Instrument Air Supply 26612-C P-56: Service Air Supply. 98120 C F-30 Demin Water Supply 390+20. C P-47 Reactor Bldg Floor Drains 15+2 C P-13 Hydrogen Recomber Ret. 46120 C P-13 Hydrogen Recomber Suc. 812 C P-69 Hydrogen Recomber Ret. 55120 C P-69 Hydrogen Recomber Suc. 152120 C P-52 Process Rad. Air Sample Suc. 501120 C P-52 Process Rad. Air Sample Ret. 16212 C Process Rad - Equip. Door Suc. 3.712 C Process Rad - Equip. Door Ret. 319120 I i C Process Rad - Emerg Door Suc. 12.512 C Process Rad - Emerg Door Ret. 455120 C P-5 Cnmt Chilled Water Ret 45120 C P-8 Cnmt Chilled Water Ret 157t20 C P-55 Nitrogen Supply 140120 C P-55 Accumulator fill line 4612 C P-82 & P-83 Stm Generator 1A Blowdown 1512 42 (3721u)
- j. TYPE PENETRATION (PJ LEAKAGE RATE (SCCM) l j C P-80 & 81 Stem Generator ID Blowdown 512 C P-88 & 89 Stm Generator 1B Blowdown 5112 C P-90 & 91 Stem Generator 1C Blowdown 52120 C P-4 Cnmt pressurization line test Conn.
C P-6 Cnnt Chilled Water Supply 650120 C P-10 Cnmt Chilled Water Supply 530120 TOTAL OF ALL TYPE B & C LEAKAGE PATHS 19931.6 1 305* SCCM TOTAL IN SCFH (SCCM x 0.0021189) 42.23 i .65* SCFH (<277.8 SCFH)
- The summation of the error shall be done using Error total = (E +E + ...)
43 (3721u)
ATTACIOtENT 10.1
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l l 10.0 Attachments l-10.2 ILRMS Specifications
- 1. Drybulb Twenty-Five Channel Temperature System The drybulb temperature sensors shall conform to the following:
Number of se sors: 25 Configuration: 3 wire Type of Sensor: Resistanc9 Temperature Detector (RTD) Element: Platinum Resistance: 100 OHMS 0 32*F The drybulb temperature system readouts, including sensors, j shall conform to the following: Accuracy: 60' - 120*F Range 1 0.l'F i 0* - 150*F Range 1 0.25'F Repeatability: 1 0.01*F Sensitivity: 1 0.01*F Resolution: 0.01*F
- 2. Dewpoint Ten Channel Temperature System The dew point temperature sensors shall conform to the following:
Number of sensors: 10 Configuration: 5 wire Type of' sensor: Lithium Chloride Special: Nylon sock cover for element Range: 32' to 120'F l 4 45 l (3721u) I m _ _ . - 1
1 The dew point temperature' system readouts, including sensors, shall conform to the following: Accuracy: 45' - 90*F Range 1 0.5'F Repeatability: 1 0.50'F ., Sensitivity: 1 0.1*F Resolution: 0.01'F
- 3. Pressere Two Channel System The pressure sensors shall conform to the following:
Number of sensors: 2.
-Type of sensors: Quartz Bourdon tube.
Range: 0 to 100 PSIA Manufacturer: Mensor Corp. The pressure system readouts, including sensors, shall conform l to the following: l. I' Accuracy: 1 015% of reading 1 002% of full scale i 5 microns of abs. press. Repeatability: i .001% of full' scale Sensitivity: i .001 PSIA Resolution: .001% of full scale
- 4. Vacuum System for Zero Pressure Reading Verification Check Vacuum pump: Two stage Free air displacement: 50 liters / min L Power required: 110 VAC 60 HZ Vacuum gauges: Two thermocouple type gauges Hardware Two chcanels and connection j for transf , standard 1
i 46 l (3721u) ,
- 5. Verification Flow System Number of sensors: 1 Type'of sensors: Mass Flowmeter Range: 0 to 10 SCFM-Accuracy: + 1%-F.S.
t
- 6. Ambient Pressure Number of sensors: 1 L
Type of. sensors: Strain gauge Range: 12 to 17 PSIA Accuracy: 1 1% F.S. Repeatability: i .1% F.S. Stability: i .15% 6 Months
- 7. Ambient Temperature Number of sensors: 1 The specifications are identical to that of the other 25 RTDs of item 1
- 8. Time The' built-in clock shall maintain real time by Julian date,
. hours minutes and seconds on a 24 hour time basis.
Accutacy: i 1 minute /24 hrs. Resolution: 1.0 second
- 9. Data Acquisition System A/D Conversion Lual slop integration V, F, ,
constant scan rate Display: 5 + Digit, Polarity, Decimal & Legend { 1
'l 47 l (3721u) j i
l Sampling Rate: 10 Channels /Second Corranon Mode Rejection: DC-140db, 1000 OHM Unbalance AC-140db at 50-60 Hz Normal Mode Rejection: 80db Input Impedance: 1,000 MEGOHMS / Volt
.Nnbient Temp. Range: 32-125*F
!. Zero Offset: Recalibrates before each l reading automatically Full Scale Temp. 1 5 PPM /*C or 0.005%/*C , Accuracy: f .005% F.S., 1 005% of l Reading at 25*C with 1 10% A.C. Power variation. 43 (3721u)
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l 10.0' Attachments
.10.6 'Least Squares' Fit Statistical Technique '
In order to comply with the. intent of ANSI N45.4-1972 and.10CFR50, Appendix J, itLwas necessary to' perform a.least squares fit of the
'ILRT. data. The method for "Least' Squares"?is'a statistical !
.j procedure for finding the best fitting regression line feria set of t
measured data. The criterion for the best fitting:lineLto a set of
- j. data points is that the sum of the squares of the deviations of the 'l 1 -
obscrved points from the line must be a minimum. When this i criterion is met,s a unique best fitting line is obtained based on all of'the data points. 'The value of the leak rate based'on the j regression line is called the statistically averaged' leak rata . Based '<xt this statistical process, the calculated statistical leak i l rate is obtained from the equation: ' l L = -(At+B) l Where L = Containment leakrate, (%/ day) ; l B = Calculated leakrate at time = 0 (%/ day)' l A - Calculated rate of change of the leakrate (%/ day /hr.) j t = test duration in hours ! 1
)
- Containment Leakrate ;
i B l 1 L Slope = A I l I i, o time (hrs) 1 1 1 51 l (3721u).
-l J
. e The values of the constants A and B define the sample regression -
line of leakrate on time. A = [NI(ti ((W )] - ((hi)( Wi d i TN1(El 4)-([t T ) - i B = hi-AIt i = d,.t _k(hi -( t.il Wiit l
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Wi = 2400 (1 - M i/MST) ti-tST Where all sthanations are from
\ e i =
ST +1 to i = S p r. I o F e 52 (3721u)
. a In order to calculate the 95% confidence limits of the statistically averaged leak. rate, the standard deviation of the least squares slope and the T-distribution function are used as follows:
8= ,1 N!(Wi)2 _(IWi)2 7 i
-A2 ! 1/2 L(N-2)L El(ti) - (Iti)8 ,
UCL = L3 + a (TE)(2400) " D UCL = L + o(TE) 1.6449(N-2) + 3.5283 + 0.85602/(N-2) Where TE = (n-4) + 1.zzuv - 1.31e4/00-ZT N- = number of data sets ti = test duration at the i'" data set, hours Wi = total time leakrate at iTh data set, %/ day o = standard deviation of least squares slope %/ day-hour TE = value of the single-sided T-distribution function with 2 degrees of freedom (dimensionless) L = calculated leak rate in %/ day UCL = 95% upper confidence limit %/ day Sp = ending data set nunber
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ST starting data set number Mi = containment dry air mass at data set i, Ibms Msy = containment dry air mass at starting data-set, Ibms tp = final test duration, hours
)
1 l 1 53 . (3721u) , I l
e a CONTAINMEN' MODIFICATION l l
)
l \ o 1 F I 54 l (3721u) . [ - --- - -- __ _ _ - - - - - - _ _____________________3
- ,, 'd. .
I SUPPLEMENT REPORT The Hydrogen Monitoring System for Penetration 36 was not test'ed during the Type A test conducted September 6 through the 11,
-1987 due to the icng lead time required for' parts from the
. manufacturer (Valcor) to repair valve (2PS230B). 'After the successful completion of the Type A test,. numerous attempts were made to acquire a similar valve-from'various utilities around the-country. Attempts were also made to expedite the delivery date of a
-replacement valve.from the manufacturer. Due to the~ unusual circumstance of the long delivery. time for 2PS230B valve and the economic justification of. extending.the N-Stamp in order to install this.. valve, the decision was made to remove 2PS230A from Penetration
'45:and install the valve at Penetration 36.
i' The Local Leak Rate was performed on Penetration 36 and the 1 l penalty leakage added to the Type A test. A new valve will be installed in Penetration 45 and a Local Leak Rate will be performed. The preoperational test results will be submitted to the
- j. commission, as specified in 50.4, Appendix J, titled " Reactor L
Containment Building Integrated Leak Rate Test". l t 55
- (3721u) -
.O)
- f, e1 Comm One Firstnw:alth National Plaza,Edison Chicago, Illinois U Address Reply to: Post Office Box 767
.\ Chicago, Illinois 60690 0767 December 7, 1987 Mr. Thomas E.-Murley, Director Office of Nuclear Reactor Regulation E U.S. Nuclear Regulatory Commission Washington, DC 20555 Attn: Document Control Desk
Subject:
Braidwood Station Unit 2
- j. Integrated Leakage Rate Test Results l NRC Docket No. 50-457 l References (a): April 29, 1983 F.G. Lentine ' letter I- to H.R. Denton (b): July 7, 1983 F.G. Lentine letter f'
. to H.R. Denton.
(c): December 1, 1987 S.C. Hunsader letter to T.E..Murley
Dear Mr. Murley:
1 Reference-(c) provided the NRC with the value of the maximum allowable test leakage rate (LT ) for Braidwood Unit 2, for inclusion into the Braidwood Technical Specifications. Pursuant to 10 CFR 50, Appendix-J, Section V, enclosed is the summary technical report of the Braidwood Unit 2 - preoperational. test, entitled, "Reector Containment Building Integrated Leakage Rate Test", from which this value was derived. This report describes the initial type A containment leakage rate test conducted per the requirements of Appendix J, between September 6 and 11, 1987, except as noted in references (a) and (b). The results of this
- j. - - test have been reviewed in accordance with Commonwealth Edison Company procedures and have been accepted by our Project Engineering Department.
'l At the time the. test occurred, it was witnessed by Mr. R. Mendez of the NRC Region III office.
This report is being submitted for NRC review. Please direct any questions you may have regarding this matter to this office. Very truly yours, i
===&
S. C. Hunsader Nuclear Licensing Administrator Attachment cc: S. Sands - NRR NRC Region III Office Braidwood Resident Inspector , $l1 . 3935K
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