ML20094F457
| ML20094F457 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 02/17/1992 |
| From: | WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | |
| Shared Package | |
| ML20094F455 | List: |
| References | |
| NUDOCS 9202240326 | |
| Download: ML20094F457 (31) | |
Text
' Att$chment 1 to WM 92-0022 REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST y
~
\'
FOR WOLF CREEK GENERATING STATION ES0"#$0S$k 7)S85ldem P PDR
< At.techment ifto WM 92'-0022-TAllLE OF CONTENTS PAGE INTRODUCTION 1
SUMMARY
1 Cl!RONOLOGY 1 INTRUMENTATION 2
.METilODOLOGY 2- .
TYPE "A" TEST RESULTS, ANALYSIS AND INTERPRETATION 3 TYPE "B" AND "C" TEST RESULTS 4
. REFERENCES 4 FIGURES 1 Integrated Leakago Rate 5 !
l 2 Verification Leakage Rate 6 I 3 Containment Air Mass ,
4 Containment. Pressures- 8 S- Containment Temperatures 9 APPENDICES 1 Plant Information and Technical Data 10 2- Instrumentation Specifications- 11 3'- Sensor Locations and Volume Fractions 12 4- Instrumentation Schematic 13 5' Type "A" Test Results 14 6 ILRT Additions 15 7 Instrument Selection Guide, ISG 16 8 Type "B" and "C" Test Results 17
- l. , . - . . _ - . _ _. ., ...,___ _
A'ttachment i to WM_92-0022 INTRODUCTION The second~ periodic Integrated Leakage Rate Test (ILRT) (Type "A" Test) was successfully completed for Wolf Creek's reactor containment building during the fifth refue31ng outage. This test was performed to demonstrate that leakage from the reactor containment building does not exceed the limits stated in the Technical Specifications for Wolf Creek Generating Station. The plant procedure for integrated leakage rate testing was used, and the requirements of 10CFR50 Appendix J were followed. Appendix 1 contains general plant information and technical data.
SUMMARY
A 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> duration integrated leakage rate test was performed using the Total Time Analysis in accordance with ANSI N45.4-1972.
Total Time Calculated Leakage Rate .0559 wt%/ day Leakage Rate of 95% Upper Confidence Limit .0667 wt%/ day
. Acceptance Criteria, 0.75 La .15 wt%/ day The leakage rate at the 95% Upper Confidence Limit plus the total of leakage rate additions met the acceptance critoria also.
95% UCL + Leakage Rate Additions .0704 wtt/ day The capability of the instrumentation for measuring the integrated leakage rate was verified by imposing a known leakage rate on the l
containment and confirming that the measured composite leakaga rate
! fell within the calculated limits.
Imposed Leakage Rate .2 wt%/ day Measured Composite Leakage Rate .1686 wt%/ day Upper Acceptance Limit .2745 wt%/ day Lower Acceptance Limit .1745 wtt/ day The Instrument Selection Guide (ISG) was calculated and it met its acceptance criteria. Pressure transmitter PT-31 failed during the test, this was accounted for in the ISG calculation.
Instrument Selection Guide .0072 wt%/ day
= Acceptance Criteria, 0.25 La .05 wt%/ day CHRONOLOGY Wolf Creek's second periodic ILRT occurred at the beginning of the fif th refueling outage. System lineups, test instrumentation setup and other preparations were performed from September 23 to September 27,- 1991. The_ containment was inspected prior to the ILRT, and no structural deterioration was discovered that could Page 1 of 27
Atthchment1toWM92-0022
-affect either the containment structural integrity or leak- l tightness. Leak inspections of the containment penetrations were performed during pressurization and no significant leaks were discovered.
15:30 09/27/91 Commenced final containment inspection 16:02 09/27/91 Commenced containment pressurization 04:16 09/28/91 Stopped containment pressurization at a test ,
pressure of 50.2 psig.
Commenced stabilization phase 09:00 09/28/91 Started Type "A" test leakage measurement 09:00 09/29/91 Ended Type "A" test 3 09:04 09/29/91 Imposed a leakage rate on the containment of 13.22 scfm 09:15 09/29/91 Started verification test leakage measurement 13:15 09/29/91 Ended verification test 13:17 09/29/91 Began depressurization of containment 11/20/91 Completed last Local Leak Rate Test-(LLRT) '
needed to finish calculating leakage savings and penalties INSTRUMENTATION Wolf Creek's ILRT instrumentation system consists of 24 platinum Resistance Temperature Detectors (RTD's), six chilled mirror hydrometers, two Mensor precision pressure gauges and two mass flowmeters. These instrument provide data input to the Volumetrica Data Acquisition system. See Appendix 4 for a schematic of the instrumentation system.
METHODOLOGY Wolf Creek's ILRT - procedure provides the option of completing either a full duration test of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or a short duration test of 6 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Both test methods are described by Wolf Creek's safety analysis report. The data reduction program calculates the containment leakage rate by the total time method for both ANSI N45.4-1972 and Bechtel Topical Report, BN-TOP-1. ANSI N45.4 describes a single-sided confidence limit. - The short duration test is performed according to the Bechtel Report BN-TOP-1. For information only, the mass point containment _ leakage rate is calculated as described by ANSI /ANS 56.8-1981 The leakage rate from the containment is determined by measuring .
-the mass of containment air and calculating its change over time.
The ideal gas law is used to calculate the air mass. The containment volume is assumed constant, as is the gas constant for dry air. Pressure and temperature are the only variables.
l Temperature data is input from the 24 RTD's and six hygrometers l
l Page 2 of 27 l
i__ _ _ , - - _ _ _ ___________ _ ___ _ _ _
-- . . - ~ . _ . . . - ~ - - - . . . ~ ~ - ~ - . - ~ . ~ - - - - - . . _ - - -
Attachment i to WM 92-0022 overy 15 minutes to the ILRT computer. The program calculates
' volume weighted average' containment dry bulb and dowpoint temperatures by using the volume f ractions assigned to each sensor.-
The volume fraction assignments are the same as were used for the preoperational ILRT. Volume fractions are-listed in Appendix 3.
The containment pressure is an average of the output of the two pressure gauges. The dry air pressure is calculated by subtracting the water vapor pressure f rom the total containment pressure. The water vapor pressure is the saturation pressure that corresponds to the saturation temperature (dowpoint Temperature) of the containment. From the dry air pressure and the average containment temperature the mass of the dry air in containment is calculated.
The Instrument Selection Guide (ISG) is calculated using the method described in ANSI /ANS 56.8-1981. The ISG is used to evaluate the ability of the ILRT measurement system to measure the integrated leak rate. The formula is a function of sensor errors, number of sensors, pressure, temperature, and time.
Following the integrated leakage rate measurement, a leak is imposed on containment equal to La i 25%. A verification test is then perf ormed to verify the adequacy of the instrumentation to measure the containment leakage rate. The leak is imposed by throttl. ng the air flow from containment through one of the two mass flowmeters.
TYPE "A" TEST RESULTS, ANALYSIS AND INTERPRETATION Test results are shown in Appendix 5. A 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> duration test was performed in accordance with ANS1 N45.4-1972. The leakage rate at the two-sided 95% upper confidence limit (UCL) was decreasing constantly through the test, and_it met the acceptance criteria in less than three hours of test time. See figure 1.
The leakage rate at the 95% UCL was .0667 wt%/ day. This value is far enough below the acceptance criteria of 0.150 wt%/ day to allow for leakage rate additions. Leakage rate additions are made for systems that are left in - service during the ILRT and for water ,
levels in containment that show a net increase. From Appendix 6, the total leakage rate addition is .0037 wt%/ day. The leakage savings for components that were isolated during the test was calculated to be .1465 wt%/ day.
At the end of the 24' hour test, the ISG was calculated'to be .0072 wt%/ day as shown in Appendix 7. It met the acceptance criteria of less than 0.25% La or 0.050 wtt/ day. Pressure Transmitter PT-31 failed during the test. This was accounted for in the final ISG calculation.
A verification test was performed where a leakage rate of 13.22 L
l Page- 3 of 27
-Attachme'nt 1:to WM 92-0022-4 scfm or 0.1686 wt%/ day was imposed on containment. The verification test lasted 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> as required. The measured composite leakage rate stabilized within the limits calculated, and the last leakage rate recorded was .2121 wt%/ day. See figure 2.
Figures 3,4, and 5 plot the containment air mass, pressure, and temperature, respectively, from the beginning of the stabilization period to the end of the verification test. Other information retained at the plant and available for review includes the ILRT procedure, the Local Leakage Rate testing procedure, system descriptions, instrument calibration documentation, and Quality-Assurance audit results. The ILRT procedure includes a chronological. log of events, system lineups and all test data.
TYPE *B" AND "C" TEST RESULTS The results of all Type "B" and "C" tests performed since the first ILRT are listed in Appendix 8.
REFERENCES
- 1. . Wolf Creek Generating Station -
Updated Safety Analysis Report.
- 2. Wolf Creek Generating Station Test Procedure: Containment Integrated Leakage Rate Test, STS PE-018 Rev. 1
- 3. 10CFR50, Appendix J, " Primary Reactor Containment Leakage
- Testing for Water Cooled Power Reactors."
- 4. ANSI N45.4-1972, " Leakage Rate Testing of Containment Structures for Nuclear Reactors."
- 5. ANSI /ANS 56.8-1981, " Containment System -Leakage Testing Requirements."
- 6. Bechtel Topical Report BN-TOP-1, Rev.1, " Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants," November 1, 1972.
I i
l Page 4 of 27
~
Integrated Leakage Rate .
3 Data-from 0900 on 09/28/91 }
to 0900 on 09/29/91 i:
s s
0.5 y i s n.
0.4
.f .
'T1 i 2
6' s 0.3 i ;
C 9.
- , g i g - i .
es 30.2 -
2 t:q '\ :
0.1
\,___ - -- -_
0.0 0 2 4 6 8 10 12 14 16 18 20 22 24
]
Duration (Hours)
- - CLR ~~MLR ANSIUCL Acceptance Criteria
- _ _- _ _ L-- - --
a Verification Leakage Rate 1
E Data from 0915 on 09/29/91 _
to 1315 on 09/29/91 g x
0.30 $
Upper Acceptance 0.25 I 0.20 cn (.O C
$ Lower Acceptance '
m s 3
o' 0.15 .
.t (D % l N 0.10 l! ,
Calculated Leak Rate ,
i 0.05 i
0.00 0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 Duration .(Hours) i
~
Containment Air Mass .;
Data from 0430 on 09/28/91 [.
to 1315 on 09/29/91 3' s
s1 807000 ?
g' '
M 806750 -V e
4
'S r. :
806500 t,
?
a\ ILRT Test i f-
- 3. 806250 b b'N
~ (Q -E i N i ;
5 E806000 I q c.
O CD 2 i z-
~+w Mt ^~ x a
t CO 805750 a 'I 805500 t ON i n 805250 o t n
805000 0 2 4 6 8 101214161820222426283032 Duration (Hours)
~
Containment Pressure .
Data from 0430 on 09/28/91 [
to 1315 on 09/29/91 ;
E
- 8 64.6 h Total Air Pressure N S
64.4 t y
/ e i 64.2 j j
! $ i Dry Air Pressure !
u) 64.0 1
/ z[
0 8 Q-r a
c
- 63.8
' i ILRT Test U
63.6 /
o
! n n 63.4 0 2 4 6 8 101214161820222426283032 Duration (Hours) t
Containment Temperatures s Data from 0430 on 09/28/91 l to 1315 on 09/29/91 ;;
E :
n 79 g
- N Dn/ Bulb Terrperature -
S - V-i 77
.t y e .
, 75 9 [i a
3, 1 /
/'bi ILRT Test f
e O g 73 / i j C '
i - T CD { 71 '
e z a-G t
\ Net Bulb Temoeraturo 69 !
I
/
[- o O n 67
[n 65{
0 2 4 6 8 10 12 14 16 18 20 22 24 26 28 30 32 Duration (Hours) .
Nttachment1toWM92-0022 I
APPENDIX 1 PLANT INFORMATION AND TECilNICAL DATA A. Plant Ittformation
- 1. Owners:
- a. Kansas Gas and Electric Company
- b. Kansas City Power and Light Company
- c. Kansas Electric Power Cooperative
- 2. NRC Docket No 50-482
- 3. Plants Wolf Creek Generating Station
- 4. Location: 5 miles S. East of !!wy 7 5, New Strawn, Kansas
- 5. Containment Type Reinforced, Post Tensioned Concrete
- 6. Date Test Completed: September 30, 1991 B. Technical Data
- 1. Containment Net Free 2,500,000 cu. ft.
Air Volume
- 2. Design Pressure 60 psig
- 3. Design Temperature 320 F
- 4. Calculated Peak 48.1 psig Accident Pressure, Pa -
- 5. Peak Accident 384.9 F Temperature Page 10 of 27
, Attachment 1 to WM.92-0022 APPENDIX 2 INSTRUMENTATION SPECIPICATIONS A. Monsor Precisj s,Prosauro Gaugo
- 1. Range 0-100 pain
- 2. Accuracy: 10.0024-F.S. ,
- 3. Sansitivity: 0.001 psia
- 4. Repeatab111ty: 0.001 psia
'B. 100 Ohm Platinum RTD's
- 1. Range: 60-120 F
- 2. Accuracy: 10.1*F
- 3. Sensitivity: 0.01 F
- 4. Repeatability: 0.01 F C. Chilled Mirror livoromotors
- 1. Range: 49-100 F
- 2. Accuracy: 10.54*F
- 3. Sensitivity: 0.1 F
- 4. Repeatability: 0.1 F C. F_ ass Flowmetor
- 1. . Range 0-15 seem
- 2. Accuracy: 12% F.S
- 3. Sensitivity:- 11% F.S 4.. Repeatability - 0.05% F.S Page 11 of 27
._ . .. _ _ _ . . .__.__-___.m.-. - - - . . _ . . _ . _ _ _ _ . _ . _ _ _
Attachment 1 to WM 92-0022 4
APPENDIX 3 SENSOlt LOCATIONS AND VOLUME FilACTIONS Distance Prom Volume Sonsor Elevation Azimuth Conter Fraction /
No. (ft) (dogrees) (ft) Sensor GP-TE-1 2180 0 28' 0" 0.0327 !
GP-TE-2 2180 90 2P' 0" 0.0327 GP-TE-3 2180 180 28' 0" 0.0327 GP-TE-4 2180 270 28' 0" 0.0327 GP-TE-5 2140 45 35' 0" 0.0553 GP-TE-6 2140 135 35' 0" 0.0553 GP-TE-7 2140 225 35' 0" 0.0553 GP-TE-8 2140 315 35' 0" 0.0553 GP-TE-9 2100 0 35' 0" 0.0530 GP-TE-10 2100 90 35' 0" 0.0530
-GP-TE-11 2100 180 35' 0" 0.0530 GP-TE-12 2100 270 35' 0" 0.0530 GP-TE-13 2060 60 56' 0" 0.0405 GP-TE-14 2060 180 56' 0" 0.0406 GP-TE-15 2060 300 56' 0" 0.0405
-GP-TE-16 2070 180 15' 0" 0.0406 GP-TE-17 2069 0 22' 0" 0.0406 GP-TE-18 2030 0 61' 0" 0.0380 GP-TE-19 2030 120 59' 0" 0.0380 GP-TE-20 2030 240 61' 0" 0.0380 GP-TE-21 2030 0 27' 0" 0.0380 GP-TE-22 2010 90 33' 0" 0.0380 GP-TE-23 2010 270- -22' 0" 0.0300 GP-TE-24 1988 0 22' 0" 0.0052 Total: 1.0000 GP-ME-19 2180 Center O' 0" 0.1309 GP-ME-20 2140 Center O' 0" 0.2213
-GP-ME-21 2100 Center O' 0" - -0.2119
'GP-ME-22 2060- Center O' 0" 0.2025 GP-ME-23 2030 120 59' 0" 0.1141 GP-ME-24 2010 0 27' 0" 0.1193 Total: 1.0000 Page 12 of 27
M r+
e o
- s c+
24 Signal g RTD's Conditioning 7 s
e AUTO N
. o o'
AND N 6 Signal N Hygrometers Conditioning MANUAL u
SCANNERS $
4
- =
m
'y 4-20 c1A 'Z k e
Converters $. 3 4 f w
C U
~
w
- N-
, DATA Volf Creek ea S 2 Mensor 0-10 rA ACQUISITION Personal b y Pressure Gauges Drivers SYSTD1 Computer E N .:r d
w O
2 Mass 4-20 mA DISPLAY Flovneters Converter VOLLMETPsICS INTEGRATED LEAEAGE RATE MEASURDiENT SYSTDi
Attachment 1 to WM 92-0022 APPENDIX 5 TYPE 'A" TEST RESULTS A. Accepted Results
- 1. Test Method, Absolute
- 2. Data Analysis Technique, Total Time per ANSI N45.4-1972
- 3. Minimum Test Pressure, 48.1 psig
- 4. Integrated Test Acceptance Limits
- a. La, 0.2 wt%/ day
- b. 0.75 La, 0.15 wt%/ day
- 5. Total Time Integrated Leakage Rates
- a. 95% UCL, 0.109 wt%/ day
- b. Calculated (Regression Line), 0.043 wt%/ day
- 6. Verification Test Leakage Rates
- a. Imposed Leakage Rate, 0.175 wt%/ day
- b. Measured Composite Leakage Rato, 0.236 wt%/ day
- 7. Verification Test Acceptance Limits
- a. Calculated Leakage Rate + 0.043 Imposed Leakage Rate + 0.175 25% La + 0.050 Upper Limit = 0.268 wt%/ day
- b. Calculated Leakage Rate + 0.043 Imposed Leakage Rate + 0.175 25% La - 0.050 Lower Limit = 0.168 wt%/ day D. Information Only Results
- 1. Wolf Creek, Mass Point per ANSI 56.8-1981
- a. 95% UCL Leakage Rate, wt%/ day
- b. Measured Leakage Rate, wt%/ day
- c. Verification Test Composite Leakage Rato, 0.230 wt%/ day Page 14 of 27
Attachment 1 to WM 92-0022 APPENDIX 6 ILRT ADDITIONS A. Leakane Penalties for Systems in Service Durino ILRT P-17 Fuel Transfer Tube 400 scem P-22 Reactor Coolant Pump Seal Injection .120 accm P-28 Essential Service Water 2500 seem P-29 Essential Service Water 120 scem P-34 ILRT Pressurization Line 300 accm P-39 Reactor Coolant Pump Seal Injection 30 seem P-40 Reactor Coolant-Pump Seal Injection 30 seem P-41 Reactor Coolant Pump Seal Injection 130 seem P-51 ILRT Instrumentation Lines 75 seem P-80 Reactor Coolant System Charging 200 accm Total Leakage Rate 3905 sccm or 0.0019 wt%/ day B. Leakane Rate Due to a Net Increase in Water Level Net Increase in Water Level 328 gallons / day Equivalent Leakage Rate 0.0018 wt%/ day C. Leakane Savinos of Work Performed on Isolation Components P-28 Essential Service Water 307311 scem P-160 Containment Shutdown Purge Exhaust 400 scem Total-Leakage Rate 307711 scem or 0.1465 wt%/ day 1
Page 15 of 27
Attachment 1 to WM 92-0022 4
APPENDIX 7 INSTRUMENT SELECTION GUIDE, ISG The ISG is Calculated as Described in ANSI /ANS 56.8-1981,
- 1. Pressure Instrumentation Error, ep g , [(0.001)2 + (0.001)2 4
ep = 0.0014 psi
- 2. Temperature Instrumentation Error, or g,, g(0.10)2 + (0.10)2 g -
e7= 0. 0289 *F
- 3. Vapor Pressure Instrumentation Error, ev Dew point Temperature = *F Saturation Pressure Change = psi / F g , f(0.10 x 0. 0129 5) 2 + (0.10 x 0. 0129 5F 5
ey= 0.00075 psi
- 4. ISG 400 0.02 %
ISG =
6.25 x4xh (0 . 001 %_ ) 2 ,(537.677)2-. ( 0 .64.592 64.592 0 0 07 Ei ) 2 ISG = 0. 007 2 wt%/ day
Attachment 1lto WM 92-0022-Al'PENDIX 8 TYl'E "11" AND "C" TEST llHSUl/PS Penetration Number Cceronent Descriptitin Component Descriptien Component Description Date L..Kage Rate ( ces) Le kage P.te teces) Leak g. Rate (seem)
P-14 EJ HV-24 EJ llV-26 10/26/88 01 4 43 1 4 03/26/90 01 4 01 4 P-15 _EJ IIV-Q EJ 11V-2 5 11/07/88 01 4 01 4 03/26/90 250 1 20 300 1 20 P-17 0-RINGS 12/14/88 014-03/11/90 220 1 20 04/27/90 20 1 4 P-22 BB HV-8351B BB-V148 10/21/88 01 4 600 1 20 11/14/88 01 4 03/27/90 20 1 4 280 t 20 P-23 BG f(V-8152 BG HV-8160 10/16/88 01 4 01 4 11/17/88- 8000 1 232 7800 1 232 03/26/90 0-1 4 01 4 P-24 BG 11V-8100 BG HV-8112 BG-V135 10/18/88 0- 1 4 0-1 4 750 1 20 11/17/88 014 01 4 800 1 20 03/20/90 2800-t 232 01 4 190 1 4 04/06/90 35 i 4 P-25 BL-8046 BL HV-8047 03/15/90 8200
- 232 8000 1 230 P-26 !!B HV-7136 HB HB 7176 l
10/17/88 01 4 014 03/20/90 014 02 4 l
l l
l l
Page 17 of 27
.. _ . - - . - - =, .
......- - - - - . . - . - . ~ .. - . - - . .- ...- .- - - . .. ....- ._ - . - .-
Attachment 1^ to t!M 92-0022 I
r
-Penetration Number Component Description Component Description Component Description Date Leakage Rate (sect) Leakage Rate (acca) Leakage Rate (oces)
P-28 .EF HV-32/34' 11/06/88 0i4 11/12/88 0*4 12/13/88 01 4 04/08/90' 95 1 4 04/13/90 0*4
- P-29 EF HV-46/48/50 EF HV-46 11/06/88 0t4 11/12/88 500 1 20 04/08/90 0 i-4 ;
04/13/90 3000 1 232 P-30 KA'FV-29 KA-V204 03/25/90 2050 1 230 130 4 09/27/91' 1700 1 230 180 1 20 P-32 LP FV-95 LF FV-96
- 10/28/88 01 4
.03/22/90- -014 0i4 09/21/91 100 1 4 0*4 P-34 FLANGE -;
11/18/88 014
-03/07/90 014 04/05/90 440 1 20 09/16/91 30014 P FLANGE 09/26/91 540 1 20 P-39 BB HV-8351C BB-V178'
~
10/21/88-: 014 0t4 11/14/88 01 4 03/27/90- 0*4 360 1.4 04/12/90 115 1 4 P-40 BB HV-8351D BB-V208
'10/21/88 0*4- 014 11/14/88. Oi4 103/27/90 0i4 01 4 v.
P-41 BB HV-8351A' 'BB-V118
-10/21/88- O'i 4 014 11/14/88- 01.4 03/27/90 0i4 0i4 -
04/12/90 55
- 4-Page 18'of 27
~ Attachment-1 to WM 92-0022-Penetration Nuaber- Component Description Component Description Compw ant D*scription Date- Lankage Rate (sect) bakage Rate (occa) Leakage Rate facea)
P-43 HD-V016 HD-V017 t
10/18/88 01 4 01 4 03/21/90' O14 5000 1 232 P-44 HB HV-7126 HB HV-7150 10/17/88- 014 01 4 03/20/90 01 4 01 4 P 65_
EP HV-8880 EP-V046 10/20/88 43 i 4 014 03/22/90 01 4 01 4 04/27/90 01 4 P-51 003-HEB-1 005-HBB-1
'10/19/88 01 4 18 1 4 03/07/90 01 4 01 4 ,
09/16/91 75 1 4 01 4 ;
P-53 EC-V083 EC-V084 10/20/88_ 420 1 20 03/14/90 01 4 160 1 4 P EC-V087 EC-V0jul 10/20/88 01 4 0t 4 03/14/90 01 4 0 1-4 P-55 EC-V095 EC-V096 10/20/88 01 4 4014 03/14/90 01 4 0t4 P-56 GS HV-8 CS HV-9
-10/31/88 0 1 4' 01 4 03/13/90 25 1 4- O t-4 ,
P-56' GS HV-38 GS HV-39 10/31/88 320 1 20 0i4 103/13/90. 500 1 20 014 P-57 SJ HV-131/132 SJ-V111
- 10/19/88 0i4 01 4 03/16/90 0i4 0i4 P-58 EM HV-8888 EM-V006 10/26/88 014_ 01 4 03/22/90 90 ~ 1- 4 0t 4 Page_ 19 of 27
Attachment i to WM 92-0022 Pettet ratien Nun.t er Cane netit Ducriptit n Coetonet.t Descrittien Cone nent Descripticn Date Lenage Rat e ( s c e ni) Leakage Rate (scend Ledage kate ( s e c c. )
P-62 BB HV-8026 BB HV-80?7 10/20/88 01 4 01 4 03/29/90 01 4 01 4 P-63 EA-V039 KA-118 03/09/90 1900 1 232 1100 1 232 2-14 SJ IIV-128 SJ HV-1?9/130 03/17/90 4200 t 232 3400 1 232 09/22/91 7000 1 940 5200 1 230
~
P-65 GS HV-20/?1 10/19/88 Ji4 12/05/88 01 4 03/12/90 01 4 04/05/90 01 4 P-67 KC HV-253 KC-V478 11/28/88 400 A 20 09/07/89 500 1 20 03/09/90 300 1 23 4600 1 232 09/25/91 860 1 20 6000 t 940 P-68 FLANCE 09/26/91 01 4 P-69 SJ HV-12 SJ HV-13 03/28/90 40 1 4 01 4 09/25/91 460 i 20 220 1 20 _
P-71 EF HV-31/33 EF HV-33 10/25/88 01 4-11/02/88 01 4 03/21/90 01 4 03/25/90 01 4 P-73 EF HV 45/47/49 10/25/88 9000 232 11/02/88 10000 i 936 11/02/88 24000 i 936 12/15/88 75200 1 5300 12/19/88 200 1 20 03/21/90 6000 1 232 03/25/90 1400 1 232 04/12/90 120 t 4 Page 20 of 27
[.. Attachment-1 to WM 92 0022 L .c l
~
Penetration N aber - Component Descripticn Component Dsectiption Consponent Description l Date Leakat* P.* t o ( sect.) Lankage Ratu (sec O Lemus e Rate (seen) i a
P-74 EG HV-58/1?7 EG-V204 10/17/88 1000 1 232 900 1 20 l_ 11/10/88 1200 1 232 ,
i 03/15/90 4600 1 936 . 4600 1.936 04/06/90 14000 1 940 l 04/09/90 5600
- 940 5900 1 936 l i i P-71 EG HV-60/130 EG HV-59/131 l
, :10/17/88 2000 1 232 600 1 20 ;
i 11/16/88 1600 1 232 2600 1 232 l l- .03/19/90 2100
- 232 5100 1 232 ,
! 04/06/90 8000 1 232 l l !
j P-76 EG HV-62/132 EG HV-61/133- l 10/17/88 60 1 4 01 4 l L 11/18/88 01 4 0*4 !
-12/04/88 360 1 20 '
i 03/15/90 40 4 . 40 1 4 -j
[ 04/14/90 220 1 20 l
\ t j P-78 EM-V045 .EM-V046 l 10/17/88 0t4 0t 4-l 03/12/90 400 1 20 600 1 20 ;
l' i P-80 BG-8381 BG HV-8105 .
10/26/88 -5100 1 232 200 1 20 l l 11/14/88 02 4 l l 03/28/90 800 1 20 65 1 4 l P-92_ EM HV-8871 EM HV-8964 l
10/20/88 014 0t 4 i 03/14/90 65 1 4 01-4 i
- -P-93 SJ HV.6/127- SJ HV-5 l
l 03/14/90 ~ 2700 1 232 2200 1 232 l .- 05/01/90 1000 1 20 i 05/04/90 1000 1 20 J 09/22/91 440 i 20 580 1.20 F
P-95 SJ HV-18 SJ HV-19
' 10/19/88 014 01 4 03/22/90 014 01 4 i 09/22/91' ' 19 i 4 19 i 4 l
t I
L l Page 21 of 27 l-WTP' M' M 6 =*vWNw -WWWE'D we-St9-99p'er'u'WW *w www w1Wwy4rw wwww Tw rwunw m meneuver- =s e % -m ume wmm* www' ewi-e--*er-%ww '
Attachment 1 to WM 92 0022 )
l
- r. .si.u on wo., ceuia r..crin ta, cer.a p..uin on ce.wr..a i,. .u i n on l' v.s. usur . na. une ua.s. na. une u u e s v.s. i.no P-97 LGS HV-17 GS liv-18 10/19/88 35 1 4 01 4 I 03/13/90 25 1 4 02 4 i i
f-97 08 HV-33 08 LIV-34 l 10/19/88 50 1 4 01 4 03/13/90 100 1 4 01 4 1 2-91 KB-V001 r,B-V00[
f 10/17/88 165 1 4 200
- 20 '
03/09/90 3800
- 232 6000 1 232 09/21/91_ l100 1 230 8900 1 232 P-99 OS IIV-3 GS HV-4 05 HV-(
10/30/88 0t 4 014 0*4 03/14/90- 90 1 4 014 220 1 20 P-90 OS HV-36 EE_)i,V- 3 7 10/30/88 01 4 014 03/14/90 01 4 01 4 E-101 GS HV-J2 OS liv-13 08 HV-14 10/18/88 45 1 4 0t4 0t4 03/13/90 014 0*4 01 4 P-101 GS liv-31 GS HV-32 10/18/88 01 4 01 4 03/13/90 01 4 0t4 P-160- 07 HZ-8 GT 112-9 GT 112-11/12 12/16/88 380 1 20 014 3000 1 232 03/08/89 10000 1 940 06/12/89 1600 1 230 09/13/89 5100 1 232 12/12/89 11500 1 936-03/08/90 6400 1 232 03/09/90- 1500 1 232 25000 1 936 05/01/90 130000 1 5300 05/02/90 550 1 20 20000 1 940 05/03/90 2000
- 230 2500 1 230 08/07/90 1800 1 230 11/14/90 4800 1 232 02/13/91- 3800
- 232 05/15/91 1700
- 230-
-08/21/91 3100 1 230
- 09/17/91 22000 1 940 2400 i 230 09/20/91 1150
- 230~
Page 22_of 27 L
.. Attachment 1 to WM 92-0022 !
4 ret.et t a t icm N.at.o r b yt.o r.t Deecrittice Cos poor t beeetittlun Comput.et4 De6t tlttipti I j Date Leakage Rate (acts) Leakage Kate (occa) L+akap Rate (scen)
P-161, GI_HF-4/5 GT HT-6 GT !!2-7 12/16/88 3400 1 232 1000 1 20 180 i 4 !
03/08/89 3400 1 230 8 06/12/89 2900 1 230 09/13/89 3000 1 232 ;
12/12/89 3000 1 232 !
03/08/90 3900 1 232 i 03/09/90 840 1 230 320 1 0 !
05/01/90 800 t 20 480 1 20 j 05/03/90 3500 1 232 !
08/07/90 2800 1 230 .
11/14/90 3200 1 232 ,
02/13/91 3600 1 232 .
05/15/91 3800 1 230 ;
08/21/91 - 3600 2 230 09/17/91 3300 1 230 :
09/18/91 1150 t 230
- 09/20/91 600 1 20 PEN, L-1 fERSONNEL AIR LOCE ;
12/17/88 398700 1 39870 12/19/88 5400
- 232 i 06/15/89 5200 1 230 <
12/13/89 7000 1 232 '
03/08/90 5000 1 232 05/02/90 40000 1 94C e 05/03/90 5400 1 230 10/09/90 3475 1 230 >
04/02/91 5615 2 232 09/18/91 5300
- 230 ,
PEN, L-2 EQUIPMENT.H41CR 12/15/88 0i4 ,
03/09/90 01 4 '
04/30/90 25 1 4 09/26/91 9014 PEN. L-3 EMERGENCY AIR LOCK 12/14/88 925 1 20 06/07/89. 2400 1 230 12/04/89 2000 i 232
-03/07/90 5100 1 232 04/26/90 1000 1 20 10/02/90 ' 900 1 20 03/27/91 1855 1 232
- 09/19/91 2660 1 230 ELECTRICAL PENETRATIONS - NORTH ROOM 06/16/89 520 1 20 06/12/91 580 1-20
.Page 23 of 27 e--- -.v.e..-.w.--,<,.#,-r-.., -
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, - Attachment 1 to WM 92-0022 s .
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Petet atiem NonA tr Coelwntnt beac 13 tion l Det. L..x.g. a.t e 1.cu s Eth:CTRICAL pef 1ETRATIOf1S - 50llTH E001]
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Attachmer.t i to tM 92 0022 ZXO3 PERSONNEL AIRLOCK DOOR SEAL LIRKAGE RATES
.. hte hut IWr ( t r n' ) Ra t t D' n f e M'r ) hj,g, ifnt Dta't ( s t e n ) (hter Dom f ered
.12/19188 16.70 260.00 06/13/89 6.1) >2100 12/22/09 S.20 226.00 06116/89 4.66 184.00
!!/Y3/88 8.72 306.00 06/16/89 3.36 1.90 12/27/88 -9.04 267.00 06/21/89 4.00 0.04 12/28/88 8.50 210.00 06/24/89 2.66 0.70 12/31188 9.1$ 176.;0 06/27/89 2.0$ 1.69 01/03/89 12.80 I?9.40 06/30/69 0.38 0.38 01/06/8V 24.30 131.90 07/03/89 b.65 0.18 01/09189 3.$3 107.00 07/06/89 0.18 U.0) 08/12/89 2.60 250.00 07/09/89 0.92 0.46 01/15189 '2.45 220.00 9/il?/89 0.86 c.5$
01/17/09 6.1$ 160.00 07/l%l89 6.19 0.33 01/19/89 3A) >2100 07/19189 1.14 1.22 01/19/89 186.00 07/19/89 3.00 2.00 01/22/89 9.01 65.50 07/21/89 1.13 1.09 01/25/89 3.27 169.00 07/24/89 0.11 0.11
-01/28189 3.80 87.10 07/27/89 20.$0 0.60 02/01/89 5.00 173.90 07/30/89 40.10 0.17 02/04/89 - 341.00 1$2.00 08/02/89 16.$0 0.35 02/06189 630.00 137.50 08/0$let 22.90 0.6%
02/10/89 380.00 144.00 08/08/89 0.80 13$.70 02/12/89 501.00 85.00 08/10/89 0.$3 1.27 02/15/89 0.05 191.00 09/12/89 J.81 2,07
-02/19/89 14.40 134.40 08/16/89 0.61 126.10 02/21189 6.04 134.*0 > 08/19/89 0.82 122.00 02124/89 - 8.50 2.50 08/22/89 0.92 141.00 02/27/89 1.0$ 2.18 08/25189 1.81 141.00 03/02/89 4.16 34.00 08/28/89 0.50 142,80 03/04189 13.20 16.70 08/31/89 11.02 1.01 03/06/89 4.30 15.62 09/03/89 2.73 0.75 03/08/89 2.40- 10$.30 09/07/89 1.15 0.59 03/11/89 3 41 2.31 09/09/89 9.70 >2100 03/14189 119.00 1.50 09/10189 9.80 137.00 03/17/89 33.70 9.60 09112/89 11.37 156.00 03/20189 1.60 . 1.72 09/13/89 4.91 138.00 03/23/89 6.40 253.00 09/18/89. 9.20 1.33 03/26/09. 1.68 94.00 09/21189 3.64 0.4) 03129/89 6.12 1.04 09/14/89 4.29 0.45 04/01/u9 6.70 1.40 09/27/89 10.13 2 16 04/04/89 9.81 6.38 09/30/89 29.30 111.50 _
-04/07/89- 4.$1 -
0.64- 10/03/89 17.80 -197.60-04/10/89 4.60 0.80 10/06/89 5.80 19).30 04/13/89 6.26 2.70 10/09169 26.80 174.00 04/16/89 3.10 0.43 10/12/89 6.91 1.69 04/19/89 4.00 1.10 10/16189 26.10 _ 158.40 04122/89 7.43 0.2S 10/18189 32.00 -225.00 y 04 'M/ 89 6.70 3.60 10/21/W9 6.90 182.00 04/28189 3.40+ 0.27 10124/89 18.20 -202.00 J.' -03/01/89 11.24 2.80 . 10/27/89 5.00 174.20 05/04/89 6.82 3.02 10/31/89 37.40 l$3.60 05/07/89 4.$0 .0.41 11/02/89 4.00 167.00 03/10/89 8.30 -0.63 11/05/89 34.30 203.00 0$/13189 3.92 0.08 -11/08/89 13.94 1.37 05/16/89 6.90 0.0) 11/11/89 3.$$ 1.93 05/19/89 8.$0 1.80' lill5/89 25.80 106.00 03/22189 3.73 0.60 11/18/89 15.30 210.00 05/25/89 8.18 0.?0 11/20189 7.70 200.00-05/28/89_ _3.89 1.2$ 11/23/89- 1.40 185.60 05/31/89 6.46 0.60 11/26/89 1.48 189.$0 06!03/89 3.39 0.13 -11I29189 0.98 201.00 06/06/89 3.23 0.68 12/0!/89 1.09 208.00 06/09/89 5.33 0.$9 !!/05/69 1.$4 161.60 06/12/89 $.60 0.64 12/08/89 4.6$ 187.30 Page 25 of-27 l 1
Attachment 2 to WM 92-0022 LEAKAGE RATE TEST FAILURES OCTOBER 1988 TO NOVEMBER 1991 FOR WOLF CREEK GENERATING STATION
I i Att'a hment 2 to WM 92-0022 I
l TYPE "A","11" AND *C" TEST FAILURES This summary report is being provided in accordanco with 10CFR50, Appendix J, Section V.D.3. This report providos a summary of the Typo A, B, and C leakago tost results that failed to moot the acceptanco critoria of 10CFR50, Appendix J, Section III.A.5(b), ,
III.D.3, and III.C.3, respectively. )
Typo *B" and "C" test failures occur when the Combined Leakago Rate for all typo "B" and "C" tests exceed 0.6La or 252,028 scem.
P-32 LF FV-96 LF FV-96 is a normally closed valvo on the containmont sump dischargo lino. During the Local Loak Rato Test of LF FV-96, the test volume could not bo pressurized to any measurablo extent.
It was not possible to measure or calculato the lankage through this valve with the availablo equipment. Thoroforo, the leakago through LF FV-96 was assumed to be greator than .6La. The valvo sont was repaired por a Work Roquest.
P-28 EF HV-32 AND EF IIV-34 EF !!V-32 and EF liv-34 are outsido and insido containmont Isolation Valvos on the Essential Servico Water to "B" train Containment Coolers. Normally, those two valves are testod simultaneously by pressurizing the volumo betwoon the two valves.
However, when the Local Loak Rato Test was performed this way, it was impossible to pressurfzo the test volume due to excessivo leakage. Testing between the valves does not afford us the luxury of knowing which valvo is loaking. A temporary proceduro was written to allow testing of the valvos individually. The second test of those valves revealed that EF !!V-32 and EF llV-34 were leaking 281,857 seem and 265,310 seem respectively. The valves wore repaired por Work Roquests.
The dual failure of EF IIV-32 and EF HV-34 also caused the Typo "A" test "As Found" leakago rate to exceed La. This Essential Service Water line was not drained and vented for the ILRT. The "As Found" ILRT condition was datormined by adding the Local Laak Rato test leakage of EF HV-34 to the measured Integrated Loakago Rato at the 95% uppor confidence limit. LER 91-020 discusses this event.
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