ML20074A828
| ML20074A828 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 05/11/1983 |
| From: | OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
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| References | |
| NUDOCS 8305160116 | |
| Download: ML20074A828 (44) | |
Text
{{#Wiki_filter:. _ .-. . . = t i I REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST JANUARY, 1983 ' I i' I i f f i OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION UNIT N0. 1 8305160116 830511 PDR ADDCK 05000285 R PDR
. - - - - - - - - - - - - - - - - - - ~ ~ - - - - ~ ~ ~ ~ ' ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
i i TABLE OF CONTENTS Section Item Title Page
1.0 INTRODUCTION
1 2.0 GENERAL AND TECHNICAL DATA 1 i 3.0 ACCEPTANCE CRITERIA 2 4.0
SUMMARY
OF EVENTS 2 5.0 METHODS OF ANALYSIS 3 6.0 DISCUSSION OF RESULTS 5
7.0 REFERENCES
6 Appendices 8 A. SCHEMATIC ARRANGEMENT OF TEST INSTRUMENTATION 9 i B. REDUCED LEAKAGE RATE DATA 11 C. LEAKAGE RATE TEST GRAPHS 15 D. INSTRUMENT ERROR ANALYSIS 19
1.0 INTRODUCTION
The Fort Calhoun Station Unit No.1 reactor containment building was subjected to its third integrated leak rate test durina the period from January 6,1983 to January 10, 1983. The purpose of this test was to demonstrate the acceptability of the containment building leakage rate at a design basis accident internal pressure of 60.0 psig. Testing was performed in conformance with the requirements of 10 CFR Part 50, Appendix J, and Fort Calhoun Station Unit No.1 Technical Specifications. In addition, the recommendations of ANSI 56.8-1981 and ANSI N45.4-1972, were considered where appropriate. Leakage rate testing was accomplished at a pressure of 60.0 psig for a period of 10~ hours. The 10 hour period has followed by a 4 hour supplemental test for a verification of test instrumentation. 2.0 GENERAL AND TECHNICAL DATA 2.1 General Data Owner: Omaha Public Power District Docket No. 50-285 Location: Approximately 19 miles north of Omaha, Nebraska Containment Description Reinforced concrete cylinder with steel liner, post tensioned in three directions Date Test Completed January 10, 1983 2.2 Technical Data Containment Net 1.05 x 106 ft.3 Free Volume: Design Pressure 60.0 psig Design Temperature 305'F Calculated Accident Peak Pressure 60.0 psig Calculated Accident Peak Temperature 288*F
3.0 ACCEPTANCE CRITERIA Acceptance criteria established prior to the test and as specified by the Fort Calhoun Station Unit No.1 Technical Specifications are as follows:
- a. The maximum allowable measured leakage rate under DBA conditions, shall not exceed 75 percent of 0.10 percent by weight of the
, containment air per 24 hours (La) at a pressure of Pa = 60.0 psig.
- b. The test accuracy of the Type A test shall be verified by a supplemental test to demonstrate the validity of the measurements.
Results of this supplemental test shall be acceptable provided the correlation between the supplemental test data and the Type A test data demonstrates an agreement within 25 percent of La; i.e., 0.025% per day. 4.0
SUMMARY
OF EVENTS 4.1 Pressurization and Stabilization Phase Pressurization of the reactor building containment was started on January 6,1983. The pressurization rate wa;; approximately 3.0 psi per hour. Containment building pressure reached' 60.0 psig at approximately 1800 on January 6,1983 and pressurization was stopped. At this time, it was determined that the lithium chloride degell temperature sensors were not functioning properly because they had not been saturated with lithium chloride solution prior to the start of pressurization. The reactor containment building was depressurized to 20 psig and the
, dewcells were saturated. Pressurization w>ts started again at 1600 on
! January 7,1983 and then terminated at 0500 on January 8,1983. After a minor pressure adjustment of the test prerrsure and a 4 hour stabilization period, the test was started at 1444 on January 8,1983.
4.2 Integrated Leak Rate Testing Phase , From 1444 to 1614, the measured leakage bate showed a decrease from an initial value of 0.441%/ day to 0.032t/ day. However, from 1614 until 2029, the leakage rate gradually increased to 0.087%/ day which was above the acceptance criteria. Leak detection had been started but only a small i
, leak on a sample line valve which tied unto the ILRT pressurization system could be identified. This valve l was repaired and the test was restarted at 2229 on January 8, 1983. ;Again, for the first four hours, the data indicated a very small leakagq rate of approximately 0.006%/ day.
However, from 0229 to 1659, the measured leakage rate gradually increased and then stabilized at a value of 0.079%/ day. During this time, leak detecticn continued and it was determined that the water seal on the steam generators had been lost. The Oater seal is required since the steam generator manholes seat with pressure in the gererator and unseat with pressure in the containment. The water seal was reestablished on the steam generators and the ILRT was restarted at 1744 on January 9, 1983.
.~,
4.2 (Continued) Starting at 1744 on January 9,1983, the measured leakage rate decreased and stabilized at an acceptable value. At approximately 2330 on January 9,1983, one RTD indicated erratic behavior (cycling). This sensor was rejected and all previous data sets recalculated with that sensor's input deleted. For the 10 hour period from 1744 on January 9, 1983 to 0314 on January 10, 1983, an acceptable leakage rate for the reactor containment building was obtained. 4.3 Supplemental Leakage Rate Test Phase Following completion of the 10 hour integrated leak rate test, a leakage rate of 3.5 cfm was imposed or, the containment building through the flowmeter at 0444 on January 10, 1983. Leakage rate data was again collected at fifteen minutes for a period of 4 hours. At 0844 on January 10, 1983, the supplemental leakage rate test was successfully completed. 4.4 Depressurization Phase After all required data was obtained and evaluated, containment building depressurization to O psig was started. A post test interior inspection of the containment building at 0 psig was completed with no significant findings. 5.0 METHODS OF ANALYSIS The absolute method of leakage rate determination was employed during testing at the 60.0 psig pressure level. The Gilbert Associates, Inc. ILRT computer code was utilized which calculates the percent per day leakage rate using the mass point method. t The mass point method of computing leakage rates uses the following ideal l gas law equation to calculate the weight of air inside containment for each fifteen minute interval: y = (144) PV
- KP RT T-where, W = mass of air inside containment., lbm K = (144) V/R = 2.8341143 x 106 lbm *R - in2 lbf l
. , l l
j 5.0 (Continued) i P = partial pressure of air, psia T = average internal containment temperature, *R V = 1.05 x 106 ft3 - 1 R = 53.35 lbf - ft lbm 'R The partial pressure of air, P, is calculated as follows: P=PT-Pyw where, PT
= True corrected pressure by converting precision pressure gauge readings and averaging, psia Pwy = partial pressure of water vapor determined by converting each of the eight dewcell temperature sensors to dewpoint :
temperature, averaging the eight dewpoint temperatures and converting the average value to partial pressure of water vapor, psia. T = containment building air temperature determined by averaging the twenty-nine RTD readings, and converting to degrees Rankine, *R. The weight of air is plotted versus time for the 10 hour test and for the 4 hour supplemental test. The computer code fits the locus of these points to a straight line using a linear least squares fit. The equation of the linear least squares fit line is of the form 7 = B + At where A is the slope in lb per hour and B is the weight at time zero and are defined by the following expressions: 2 B= ItiEWi - I ti E tj Wj Sxx A= N I tj Wj - E tj E Wj Sxx where, Sxx = N I tj 2 - (I tj)2 l
t 5.0 (Continued) The weight percent leakage per day can then be determined from the following equation: wt. %/ Day = -2400 A B where the negative sign is used since A is a negative slope to express the leakage rate as a positive quantity. 6.0 DISCUSSION OF RESULTS 6.1 Results at 60 psig Data obtained during the integrated leak rate test at 60 psig indicated the
, fcllowing maximum changes (highest reading to lowest reading) during the 10 hour test period:
Variable Maximum Change PT 0.070 psia Pwy 0.002 psia T 0.62*F The method used in calculating the mass point leakage rate is defined in Section 5.0. The result of this calculation is a mass point leakage rate , of 0.043 %/ day. Corrections due to changes in net free volume, i.e., 0.005, reduce this value to 0.038 %/ day. The 95 percent confidence interval associated with this leakege rate is O.009 percent per day. Thus, the leakage rate at the upper bound of the 95 percent confidence interval becomes UCl. = 0.038 + 0.009 l UCL = 0.047 %/ day l l The measured leakage rate and the measured leakage rate at the upper bound of the 95 percent confidence level are well below the acceptance criteria of 0.075 percent per day (0.75 La). The mass point leakage rate versus time plot (see Appendix C) shows that the measured leakage rate decreased to a value below the acceptance criteria approximately 2.5 hours into the test and stabilized at a value below the acceptance ! criteria for the duration of the 10 hour leak test. Therefore, the reactor contair, ment building leakage rate at the calculated design basis accident pressure of 60.0 psig is acceptable. l l I l u
A 6.2 Supplemental Test Results Af ter conclusion of the 10 hour test at 60.0 psig, flowmeter FI-1 was placed in service and a flow rate, corrected for pressure and temperature conditions of 3.35 scfm was established. This flow rate is equivalent to a leakage rate of 0.093 percent per day. After the flow was established, it was not altered for the duration of the supplemental test. The measured leakage rate (Lc) during the supplemental test was calculated to be 0.121 percent per day using the mass point method of analysis. Correcting for changes in net free volume reduces this value to 0.111 percent by weight per day. The building leakage rate during the verification test is then determined as follows: Lam' " Lc-lo Lam' = 0.111 %/ day - 0.093 %/ day Lam' = 0.018 %/ day where: Lam' = measured leakage rate of reactor containment building for verification test Lc = measured composite leakage rate consisting of the reactor containment building leakage rate plus the imposed leakage rate to = imposed leakage rate 6.3 Results Comparison Comparing the supplemental test leakage rate with the corrected measured building leakage rate during the 10 hour test yields the following: Lam - Lam' = (0.038) J0.018) = .020 %/ day The difference betwee' T' he ' ding leakage rates is 0.020 %/ day which is below the acceptance ci kir'- af .025 %/ day. Therefore, test instrumen-3 tation acceptability ras bec. verified.
7.0 REFERENCES
, a. ST-CONT-7, " Type "A" Test (Containment", Fort Calhoun Station Unit No.1 Test Procedure.
- b. Code of Federal Regulations, Title 10, Part 50, Appendix J.
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7.0 REFERENC_E_S (Continued)
- c. ANSI N45.4-1972, " Leakage Rate Testing of Containment Structures for Nuclear Reactors", American Nuclear Society, liarch 16, 1972.
- d. ILRT, Computer Code, Gilbert Associates, Inc.
- e. ANSI /ANS-56.8-1981, " Containment System Leakage Testing Requirements," American Nuclear Society, February 19, 1981.
- f. Fort Calhoun Station Unit No.1 Technical Specifications.
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APPENDICES l
t . . e i o I APPENDIX A SCHEMATIC ARRANCEMENT OF TEST INSTRUMENTATION t i l I i t l l l I l I I I i
APPENDIX A ~ SCHEMATIC ARRANGEMENT OF TESTINSTRUMENTATION - TEST INSTRUMENTS TAG NUMBERS
*
- DEWPOINT DPT-031 1
E L E V.1096' T DPT T T DPT T TEMPERATURE THRU 040 011 035 029 030 036 009 DRYBULB T-001 , T T TEMPERATURE THRU 030 010 013 , CONTAINMENT PI-823 & PRESSURE 824 SUPERIMPOSED F1-1, Pi-1, FLOW &TI-1 T T DPT DPT T 024 025 039 037 012 i
- NOT USED FOR TEST (SEE SECTION S 4)
T T 014 015 DPT I-E L E V.1056' 040 DPT T T T DPT T 034 007 017 008 033 023 T Pl Pt ' 823 824 004 DPT T T T 038 016 028 018 T T T T T DPT E L E U.1016 003 006 022 020 005 032 1 T 06 027 5 1 T1 -- E L E V. 996 001 3 002 09 N 5 DUCT i - F1-1
9 4 e 4 1 4 .i APPENDIX B REDUCED LEAKAGE DATA 4 1 d I r ll J J
'+ '- - y-- -9wyy e-*-- p,-y e r, yyy9-p y- - - - - - - d--7y mt*7- y ya & T+ yW m we- -m wr ymw g +- - Ww-M *----^--W-"Y-$m'a-7w- T *'y == F m- v
4 i . I . APPENDIX B { REDUCED TEST DATA (1) (1) Containment (1) (2) Containment Partial Pressure Containment Weight of . Pressure Water Vapor Temperature Containment Air Date Time (psia) (psia) (OR) (1bm) i 1/9/83 1714 75.753 .231 548.97 389,886.47 a 1729 75.755 .231 548.97 389,899.69 ' 1744 75.757 .231 549.05 389,856.31 i 1759 75.760 .231 549.08 389,843.91 { 1814 75.762 .230 549.08 389,863.50 j 1829 75.764 .231 549.12 389,842.59 j 1844 75.765 .231 549.14 389,834.97 { 1859 75.763 .231 549.14 389,821.81 ] 1914 75.763 .231 549.10 389,851.03 i 1929 75.764 .231 549.09 389,867.63 } 1944 75.766 .231 549.10 389,865.66 1959 75.769 .231 549.13 389,856.47 ! 2014 75.770 .231 549.14 389,860.44 I 2029 75.773 .231 549.13 389,878.31 i 2044 75.775 .231 549.18 389,857.97 ] 2059 75.775 .231 549.22 389,825.19 2 2114 75.777 .230 549.23 389,841.78 j 2129 75.779 .230 549.22 389,846.65 i 2144 75.781 .231 549.26 389,831.28 2159 75.783 .231 549.29 389,818.69
; 2214 75.785 .231 549.29 389,828.97 1 2229 75.787 .231 549.33 389,809.00 < 2244 75.789 .231 549.32 389,830.84 m 2259 75.791 .231 549.34 389,825.72 E i 2314 75.793 .231 549.35 389,823.94 $
2329 75.795 .231 549.37 389,826.22 -. i
! (1) These values have been rounded-off for inclusion in this table.
1 (2) These values are ' computer generated utilizing double precision.
i . t e 4 APPENDIX B REDUCED TEST DATA (1) 1 (1) Containment (1) (2) Containment Partial Pressure ' Containment Weight of Pressure Water Vapor Temperature Containment Air Date Time (psia) (psia) (OR) (Ibm) l 1/9/83 2344 75.797 .231 549.38 389,829.41 2359 75.799 .231 549.40 389,825.34 1/10/83 0014 75.800 .231 549.39 389,835.53 0029 75.832 .231 549.41 389,827.56 0044 75.804 .231 549.47 389,798.78 0059 75.806 .232 549.50 389,784.75 0114 75.807 .232 549.50 389,790.88 0129 75.809 .232 549.50 389,798.09
- 0144 75.812 .232 549.52 389,802.50
, 0159 75.814 .232 549.50 389,822.50 0214 75.815 .232 549.54 389,802.34 0229 75.817 .232 549.53 389,817.09 0244 75.819 .231 549.56 389,807.69 0259 75.821 .231 549.59 389,801.44 0314 75.823 .231 549.58 389,819.03 SUPERIMPOSED TEST i ! 0444 75.832 .232 549.66 389,806.56 0459 75.834 .233 549.69 389,787.56 0514 75.835 .232 549.68 389,806.91 ! 0529 75.836 .232 549.70 389,795.59 0544 75.835 .231 549.77 389,746.31 m 0559 75.837 .231 549.77 389,756.56 E ' 0614 75.839 .231 549.75 389,773.69 $ 0629 75.840 .231 549.82 389,733.93 m
~
j (1) These values have been rounded-off for inclusion in this table. (2) These values are camputer generated utilizing double precision. I
a . n., APPENDIX B + REDUCED TEST DATA . (1) (1) Containment (1) (2) Containment Partial Pressure Contairment Weight of Pressure Water Vapor Temperature Containment Air Date Time (psia) (psia) (OR) (Ibm) 1/10/83 0644 75.840 .232 549.85 389,707.66 0659 75.842 .232 549.88 , 389,694.38
; 0714 75.840 .232 549.88 389,685.28 l 0729 75.838 .232 549.84 389,708.00 0744 75.841 .231 549.83 389,733.25 0759 75.844 .231 549.82 389,754.09 0814 75.846 .231 549.83 389,760.28 0829 75.848 .231 <
549.91 389.714.28 4 0844 75.850 .231 549.89 389,734.59 l i i i E i f, u w (1) These values have been rounded-off for inclusion in this table. (2) These values are computer generated utilizing double precision. i
- -> L - a6 4
e f 4 T i 1 1 APPENDIX C LEAKAGE RATE TEST GRAPHS 3 4 1 1 1 1 1 1 i I l i l [ 1 l i i l l l l m"*a e %wr '&m-,-s:--S-ty-rw--'m=?vqwre s'1my e a w 'ew-y#- -'rvs' yw - wr ey v 'ywwmv p-96 7msu v
- m-'w--W ~C'T-WYTww-Tew-
* +'-+'* w--Wmfr--'7y- F 'tTF-
- 7W'"*N++ e*---7***WP-*N-w-"*
APPENDIX C TABLE OF CONTENTS l Sheet 1 of 3 Weight of Containment Air and Containment Average Temperature versus Time Sheet 2 of 3 Containment Total Pressure and Containment Average Dewpoint j Temperature versus Time l l Sheet 3 of 3 Mass Point Leakage Rate l versus Time 4 e i l i l, i t
. -- - - - . - - - - -, , , _ , - , - , . _ , - , . _ . . _ _ - , _ . . . . - . . , _ _ _ - _ . -,--.-..----,---,-.-,--,..-m- . -
APPENDIX C SHEET 1 OF 3 WElGHT OF CONTAINMENT AIR AND CONTAINMENT AVERAGE TEMPERATURE VERSUS TIME l 389.900
~~~ ~~~~
LE ST5QU RES flT - 389,850 -[- o o dD '-
~=
---5g
<r'- ---- -'- -- - -"--- --- -
EQUATIOfJ W = 389,786.2-19.64 t - UC5ERZ i-[~ _l !! f III( :
!~-2 12G1 _
~" --{
Lc = 0.121% WTJDAY -i jQ#;. OTT GQ---- 389,800 -dF-- ___. . . ____ _1___ __,, n____ ___. _ ,
+--
WEIGHT OF f-I; LEAST SQUARES FIT EQUATION ~~-
---"- -~~- ---- ----
f COraT. AIR 389.750 (([1 --T To-- t B5. -__ W = 389,868.2-7.00 t . _ .. ____ __ _3 .- ___.s.][5-p-Q
"___ _y___'
Lam = 0.043% WT / DAY - -- ---- ---- -- ---- - N-+ 389,700
-- -- ~-- ---- ---- ~~-- --'~-
o ---o- --N JL i
<r_ ___
---- ---- ----'---- ~- ---- ---- ~--
389,650 389,600 b--- ~~--- ~~~ 0 1 2 3 4 5 6 7 8 9 10 0 1 2 3 4 10 HOUR LEAK TEST 4 HOUR VERIFICATION TEST 90.5 _ ___ ___ ._ ____. .. ___ __.__ ____ ____.____
.u, ,
----inn, go o no ooo*""
CONT AVE. # " o DEWPOINT o odo~W" --IT
.____i' o _. " _0, o TEMP of 89.5 __ gg>.go m ,o o
@lill((I ___.. .____ ____ IIII'2122 ' . ~ .221 22111I21 ((I[ [ 211 ((22 2 _.~2 0 1 2 3 4 5 6 7 8 9 10 0 1 2 3 4 1714 0314 0444 0844 1.9 83 1/10.83 1/10/83 1/10 83 TIME (HOU RS) TIME (HOURS)
b t r APPENDIX C - SHEET 2 OF 3 A j . CONTAINMENTTOTOL PRESSURE AND CONTAINMENT AVERAGE DEWPOINT
; TEMPER ATURE VERSUS TIME 75 85
____..o ML iroi > R ooo---- 4pA>q,Jb ___._ ____ __-- . - _ ____ . _ __ 1 ,__._._ _ - _._ i ~~~~' COMV TOTAL ~~ ~~ ~~-~ ~-~~ ~-~ ~--~~ ~'~~- -'~-- ~~~~ -~~
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0 1 2 3 4 5 6 7 8 9 10 0 1 2 3 4 10 HOUR LEAK TEST 4 HOUR VERIFICATION TEST 57.4 o.___ CONT AVE. DEWPOINT , , pg ___.____ . o ' 1>. 57 2 1> 1> __ __o. o._ o ____ i.___ _ .itit._ JL , _'_ .1L_._
.___.Jw l <
b' ar Atc __ ., p 1l o ' l
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,, IL_ ____tL yr__ ____. .,_
___+ ,, , 51 0 ___._ _.___ _.__,_. __.__
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0 1 2 3 4 5 6 7 8 9 10 0 1 2 3 4 1714 0144 na9a "** l
j SHEET 3 OF 3
- APPENDIX C MASS POINT LEAKAGE RATE VERSUS TIME i
\
\ !
.500 ' '--- UPPER CONFIDENCE 6 i / LEAKAGE RATE
/
/
,p 400 i. . . . 4 . i i. ,
/
, s
'-- MEASURED LEAKAGE i iI ; 7-RATE
.300 -" ' '
- -j:[ f $
a i e i (i 'M \
.200 ' 4 '
i i s l s I i \ l 1 x
' t '
.100 '
_ LL t I i A _L .dn._L._h.LLJ t t i _L __.1LL _._LL m 1-y y ,j ,_ , - - : .; 1 i % /Vi i i i t i t i i t i i
' "' i ' ' ' ' ' ' ' ' ' ' ' ' 3 LEAKAGE RATE O '
' i '
(% WT. PER DAY) ! \
! 1
! t
.100 i i . .. . . . . ,
- t-
= ACCEPTANCE CRITERIA LEAKAGE RATE
.200 t ' '
6 i I
.300 10 HOUR LEAK TEST
. 400 ii iii ii ii
.500 l
i i i i , , i 0 1 2 3 4 5 6 7 8 9 10 1714 0314 1,783 1/10 81 TIME (HOU RS)
_ _ _ - , - m - - - - _ - - ___ m aa 4 l 1 l APPENDIX y i
)
l
APPENDIX D I nstrument Error Analysis 1.0 INSTRUMENTATION 1.1 Drybulb Temperature Indicating System Components:
- a. Resistance Temperature Detectors Quanti ty 29 Manufacturer Hy,-Cal Engineering Type 100 ohm Platinum Range 60 to 100*F (calibrated)
Accuracy t 0.1*F
*Sensitivi ty 0.1*F 6
Repeatability t 0.1*F i
- Sensitivity is the smallest value which will cause a one digit change in the readout.
- b. Digital Temperature Indicator Quanti ty 1 Manufacturer Digi tec Type Ibdel 3000 Datalogger Accuracy 0.19'F Repeatabili ty t 0.05'F
- - - + w ----,__ -- - - - - ,, --,,.--._m - y _,-- ,,
1.2 Dewpoint Temperature Indicating System Components:
- a. Dewpoint Sensors Quantity 8 Manufacturer Foxboro Type Model 2701 RG Range 0 to 200*F Accuracy t l'F
*Sensitivi ty 0.01*F Repeatabili ty t 0.5*F
- Sensitivity is the smallest value which will cause a one digit change in the readout.
- b. Digital Temperature Indicator Quantity 1 Manu facturer Digitec Type Model 3000 Datalogger Accuracy 1 0.19'F i
l Repeatabili ty 1 0.05*F t l l l l l I . - . - - ,_. . . . .-. . - . - . . _ - -. - . . . . - - . . - - - , , . . . . . . ~ . . . - - - . - . . - -
1.3 Pressure Monitoring System Precision Pressure Gauges ; Quantity 2 Manufacturer Mensor Corporation Type Model 16721 Range 0 to 100 psia Accuracy 0.015 psia
*Sensitivi ty t 0.001 psia j
Repeatabil'. ty i 0.0005 psia ,
- Sensitivity is the smallest value which will cause a one digit change in
; the readout. ,
1.4 Supplemental Testing Flow Monitoring System Flowmeter Quantity 1 Manufacturer Fisher-Porter Type Model 087-615-588 ilange 0.4 to 4 scfm at 60 psig and 80*F Accuracy 1% of full scale 1.5 Schematic Arrangement The arrangement of the four measuring system summarized above is depicted in Appendix A. Drybulb temperature sensors were placed throughout the reactor containment building volume to permit monitoring of internal temperature variations at 30 locations. Dewpoint temperature sensors were placed at 10 locations to pemit monitoring of the reactor containment partial pressure of water vapor. l l
2.0 ERROR ANALYSIS Utilizing the methods, techniques and assumptions in Appendix G to ANS 56.8-1981, the ISG formula was computed for the absolute method as
$ follows:
- a. Conditions La = 0.1%/ day P = 75.786 psia T = 89.60*F Tdp = 57.13*F t = 10 hours
- b. Total Absolute Pressure: e p ,
No. of sensors: 2 Range: 0 to 100 psia Sensor sensitivity error (E ):p 0.001 psia Measurement system error (Ep): t 0.0005 psia ep=i (Ep )2 + (Ep )2 1/2 no. of sensors 1/2
~
1/2 ep = i (1 x 10-3)2 + (5 x 10-4)2 ~2 ] 1/2 ep = t 7.91 x 10-4 psia
- c. Water Yapor Pressure: epy No. of sensors: 8 Range: 0 to 200*F Sensor sensitivity error (Ep y): ! 0.01*F Measurement system error (cpy) excluding sensor: 0.05*F
2.0 ERROR ANALYSIS (Continued)
- c. (Continued)
At a dewpoint temperature of 57.13*F, the equivalent water vapor pressure change (as determined from the steam tables) is 8.3 x 10-3 psia per *F. Ep y = t 0.01*F - (8.3 x 10-3 psia per *F) Ep y = i 8.3 x 10-5 kg/cm2 c py = 1 0.05'F - (8.3 x 10-3 psia per *F) c py = t 4.15 x 10-4 psia ey=t p (Ep y)2 + (cpy)2 ~ 1/2 no. of sensors 1/2
- ~
ey=t p (8.3 x 10-5)2 + (4,15 x 10-4)2 - 1/2 8 1/2
- -. s epy = t 1.50 x 10-4 psia
- d. Temperature No. of sensors: 29 Range (calibrated): 60 to 110*F Sensor sensitivity error (ET): t 0.01*F = i 0.01*R Measurement system error (c T), excluding sensor: 0.05'F
= 0.09*R no. of sensors ' 1/2 (ET )2 + (CT)2 - 1/2 eT = i i e -
u ~ 7 1/2 F eT = t (.01)2 + (.05)2 29 1/2 l eT = t 9.47 x 10-3 *R
2.0 ERROR ANALYSIS (Continued)
- e. Instrumentation Selection Guide (ISG)
- 2 2 2 ISG = + 2400 e e eT 1 1/2 2 h) + 2 ( py) + 2 (r) t p 2 2 2 :1/2 ISG = t 1.50x10-4 +2 2400 10 '2 (7.91x10-4 75.786 ) + 2 (75.786 ) (9.47x10-3 549.29 )
ISG = t 240 (2.18 x 10-10 + 7.84 x 10-12 + 5.94 x 10-10) 1/2 ISG = t 0.007 %/ day The ISG formula does not exceed 0.25 La (0.025%/ day) and it is therefore concluded that the instrumentation selected was acceptable for use in determining the reactor containment integrated leakage rate. 1 i
- ,., , , - . ,r., . _ . - . _ , , . . - , . . _. -...
1982/1983 Refueling Outage Type B and C Local Leak Rate Test Summa ry As pa rt of the 1982/1983 refueling outage, local leak rate tests were perfomed on the reactor containment building penetrations in accordance with the Fort Calhoun Station Technical Speci fications, (Section 3.5), and 10 CFR 50, Appen-dix J. The testing was performed to identify, measure, and if required, initi-ate maintenance on potential reactor containment leakage paths; and to ensure the total measured leakage does not exceed the Technical Specification limit of 0.6 La (la = TheLeakage Allowable and .6 La = 62,951 standa rd cubic centimeters per mi nute). initial "as found" local leakage which contributes tow 1rd the
.6 La limit and as measured fra all local leakage paths was 52,070.68 SCCM.
(The individual leak rates for each penetration are tabulated on the attached Tables I thru VI). The final "after maintenance" leak rate was 9,848.71 SCCM. The Type B tests were conducted by pressurizing the local containment penetra-tion boundaries with air or nitrogen (air for the mechanical penetrations-nitro-gen for the electrical penetrations) to Pa, 60 psig accident pressure, and mea-suring the flow rate which is required to maintain the test volume at Pa. This flow rate is assumed to be the local containment leak rate. The leak rate mea-surement systm uses a series of calibrated rotameters to detemine the leak-age. The Type B tests were conducted to measure the leakaae through the containment mechanical and electrical penetration seals, and containment building resilient sealed penetrat ions. These tests were conducted as part of the Fort Calhoun Station Surveillance test program. All tests, by which the following leak rate data was obtained, are filed at the Fort Calhoun Station as QA documents. The Fuel Transfer Tube leak rate test (ST-C0flT-2, F.4) was conducted on 12/31/82 and on 3/22/83. The measured results are tabulated on Table I (attached ) . Measured leakage does contribute towa rd the .6 La limit. The electrical penetration leakage was measured as per ST-C0tlT-2, F.5, using nitrogen as a pressure media. Results are tabulated in Table IV (attached). l Measured leakage of the electrical penetrations also contributes to the .6 La l leakage limit. The mechanical penetration sleeving was leak tested in accorda nce with , ST-CONT-2, F.2. Results are tabulated on Table V (attached) and contribute ! to the .6 La maximum allowable leakage limit. The equipment hatch leak rate was tested as outlined in surveillance test ST-CONT-2, F.3. Tests were perfomed prior to its initial rmoval and follow-( ing each replacement; results are tabulated in Table II (attached). Leakage does contribute towards the .6 La maximum allowable leakage limit. ( The personnel air lock leak rate was tested in accordance with ST-C0ttr-2, F.1 l (the reduced pressure test); these daily tests are on file at the fort Calhoun ~ Stat ion. The personnel air lock (P. A.L.) was also tested three times since the previous refueling outage (once each six months per ST-C0flT-2, F.2). Leakage is tabulated in Table III and does contribute towards the .6 La leakage limit. Type C tests were performed to measure the leakage of containment isolation valves. (Refer to Surveilla nce Tests ST-C0tlT-3, F.1, F.2, a nd F.3). These tests are conducted using air as the test medium; with the exception of penetrations M-16, M-94, M-95, and M-97, which use water as the test medium.
Results of leak rates perfon,ed are tabulated on Table VI (attached). The mechanical sleeves, valves, or other containnent penetrations which required significant maintenance are as follows: sleeve M-383-3 and sleeve M-383-4, a nd val ve penetrat ions M-4 2, M-58-1, M-79, M-87 a nd M-88. The wort done on each of the penetrations is described below: M-383-3 - (Safety Inject ion Recirculation "Subma rine Hull" mechanical sleeve) - Measured leakage at this particular sleeve was found to be 31,148.70 SCCM on 12/18/82. Maintenance order 17707 was immediately issued to investigate and repair the leakage problem. Subsequently, it was discovered that the "subma rine hull" m nway had been leaking excessively due to very loose manway bolts. The manway flange / bolts were tightened down and a leak rate was measured again on 12/27/82. Leakage neasured 12/27/82 was found to be 0 SCCM. M-383 (Safety Inject ion Reci rculation "Subma rine Hull" mechanical sleeve) - Measured leakage at this sleeve was found to be 400 SCCM on 12/18/82. Although this leakage is not excessive and mainte-nance was not needed for leakage correction, the HCV-383-4 containment isolation valve contained within the submarine pu14 needed to have limit switch adjustment. Thus, per M.0. No. 19285, the manhole cover was taken off, ruintenance on the limit switches was accomplished, a new nunhole gasket was installed, and the manhole flange tightened. A subsequent leak rate measured 3/20/83 verified 0 SCCM leakage at this sleeve. M-42 - (200 PSI Nitrogen header to containnent) - Initial leak rate measured through this penetration (on 12/20/82) was found to be 2,000 SCCM. This is the maximum allowable leakage specified in Table I of ST-CONT-3, F.1 for penetration M-42. Thus, Maintenance Order No.17727 was written to repair isolation valve HCV-2603A. Upon completion of HCV-2603A repair, a leak rate for penetration M-42 wa s aga in obtained. Maintenance Order No.13077 was initiated for HCV-2603B valve repair. The valve was repaired and a final leak rate of 0 SCCM was measured on 2/25/83. M-58-1 (Hydrogen Analyzer Isolation Valve) - Initial leak rate measured on penetration M-58 via Test 1 (which tests the inside-reacter-containment isolation valve HCV-884A) revealed a leak rate of 4,000 SCCM. Work was performed on valve HCV-884A (basically re-setting the stroke by lengthening the valve stem) under M.0. No. 18696 and leak rate was remeasured 2/22/83. Results revealed a leakage of 5,000 SCCM. Further work on HCV-884A under M.0. No. 18696 was accomplished including a complete valve overhaul and a leak rate was measured again 3/25/83. Final leakage measured 3/25/83 was found to be 0 SCCM. M-79 (Fill and Makeup to Pressuri zed Quench Tank) - Initial leak rate ' on 12/20/82 for penetration M-79 was found to be 2,000 SCCM. Maxi-mum leakage allowable per ST-CONT-3, F.1 is 5,000 SCCM. However, M.0. No.17171 was initiated for possible valve repair. Sub-sequently, HCV-1560A was rebuilt / repaired and retested for leak-age 12/30/82. Final leakage measured on 12/30/82 was 1.37 SCCM.
M-87 and M (Containment Purge Inlet and Exhaust Valves) - Initial leak rates for these penetrations were measured 12/10/82 and were as follows: M-87-2,400 SCCM, M-88-900 SCCM. The purge valves were then opened for operational requirements and again closed just prior to the Type A integrated leak rate test. At that time (1/6/83) leak rates were again measured for the pene-trations M-87 and M-88 are tabulated as follows: M-87-2,900 SCCM, M-88-6,050 SCCM. After the integrated leak rate test the purge valves were again opened. for operational needs, and closed for the final time 3/28/83. At this time, the penetrations were unable to hold 60 psig as required for the Type C leak rate tests. Therefore, the valve seats were ad-justed on valves HCV-742A/8/C and D and the leak rates were remeasured. Final results of the 3/28/83 leak rate were as follows: M-87-9 SCCM, M-88-1,000 SCCM. l l
TABLE I TYPE B TEST Fuel Transfer Tube Leak Rate Test - (ST-CONT-2, F.4) As found leakage measured 12/31/82 = 3.84 SCCM As left leakage measured 3/22/83 = 3.10 SCCM i i
TABLE II TYPE B TEST Equipment Hatch "0" Seal Test - (ST-CONT-2, F.3) As Found As Left 12/16/82 - 0 SCCM 0 SCCM 01/14/83 - 0 SCCM 0 SCCM 01/19/83 - 0 SCCM 0 SCCM 03/26/83 - 3.44 SCCM 3.44 SCCM
TABLE III TYPE B TEST Personnel Air Lock Leak Rate' Test (ST-CONT-2, F.2) Date Tested Leakage Measured 1/29/82 3,200 cc 7/27/82 4,200 cc 4/12/83 3,150 cc l l I
4 , TABLE IV TYPE B TEST Electrical Penetrations - (ST-CONT-2, F.5) Penetration As Found (SCCM) As Left (SCCM) I A-1 0 0 A-2 0 0 A-4 0 0 A-5 0 0 1 A-6 0 0 i A-7 0 0 A-8 0 0 A-9 0 0
*A-10 0 0 A-11 0 0 i B-1 0 0 B-2 0 0 B-4 40.3 0 B-5 0 0 I B-6 0 0 I B-7 0 0 l B-8 0 0 B-9 0 0 B-10 0 0 l B-11 0 0 C-l' 0 0
! C-2 0 0 l : C-4 0 0 C-5 0 0 C-6 0 0 i
Penetration As Found (SCCM) As left (SCCM) C-7 0 0 C-8 0 0 C-9 0 0 C-10 0 0 C-11 0 0 D-1 0 0 0-2 0 0 0-4 0 0 0-5 0 0 0-6 0 0 D-7 0 0 0-8 0 0 D-9 0 0 D-10 0 0
*D-11 0 0 E-1 0 0 E-2 0 0 E-4 0 0 E-5 0 0 E-6 0 0 E-7 0 0 E-8 0 0 E-9 0 0 E-10 0 0
**E-11 0 0 F-1 0 0 F-2 0 0 F-4 0 0
. -. .. _ .. - ._- - . . - - - - -. .-= - . -- -. .. - - . . - - - -
, I Penetration As Found (SCCM) As left (SCCM)
F-5 0 0 4 s F-6 0 0 ; I F-7 0 0 i i F-8 0 0 F-9 0 0 F-10 0 0 F-11 0 0 G-1 0 0 s G-2 0 0 G-3 0 0 G-4 0 0 H-1 0 0 H-2 0 0 H-3 0 0 H-4 0 0 E-HCV-383-3A 0 0 ! E-HCV-383-38 0 0 E-HCV-383-4A 0 0 E-HCV-383-4B 0 0 TOTALS 40.3 0 i
- These penetrations were tested per ST-CONT-2, F.5 and also tested after installation of the penetrations installed as part of modification MR-FC-81-99, Part III.
This penetration was tested per ST-CONT-2, F.5 and also as per part of modification FC-82-123. However, in both cases leakage is 0 SCCM. b
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TABLE V TYPE B TEST Mechanical Sleeve Leak Rate (ST-CONT-2, F.6) Penetration As Found (SCCM) As Left (SCCM) M-1 0 0 M-2 0 0 M-3 0 0 M-4 0 0 M-5 0 0 M-6 0 0 M-7 0 0 M-8 0 0 M-9 0 0 M-10 0 0 M-11 0 0 M-12 0 0 M-13 0 0 M-14 0 0 M-15 0 0 M-16 0 0 M-17 0 0 l M-18 0 0 M-19 0 0 M-20 0 0 M-21 0 0 M-22 0 0 M-23 0 0 M-24 0 0
^
Penet ration As Found (SCCM) As Left (SCCM) M-25 0 0 M-26 0 0 M-27 0 0 M-28 0 0 M-29 0 0 M-30 0 0 M-31 2.06 2.06 M-3 2 0 0 M-33 0 0 M-34 0 0 M-35 0 0 M-36 0 0 M-37 0 0 M-38 0 0 M-39 0 0 M-40 0 0 t M-41 0 0 I 1 M-42 0 0 M-4 3 0 0 M-4 4 0 0 M-45 0 0 M-4 6 0 0 M-47 0 0 M-48 5.51 5.51 M-49 0 0 1 M-50 0 0 M-51 0 0 M-52 38.62 38.62 M-53 0 0
Penetration As Found (SCCM) As Left (SCCM) M-54 0 0 M-55 0 0 M-56 0 0 M-57 0 0 M-58 0 0 M-59 0 0 M-60 0 0 M-61 0 0 M-62 0 0 M-63 0 0 M-64 0 0 M-65 0 0 M-66 0 0 M-67 0 0 M-68 0 0 M-69 0 0 M-70 0 0 M-71 0 0 M-72 0 0 M-73 0 0 M-74 0 0 M-75 0 0 M-76 0 0 M-77 0 0 M-78 0 0 M-79 0 0 M-80 0 0
Penetration As Found (SCCM) As left (SCCM) M-81 , 0 0 M-82 0 0 M-83 0 0 M-84 0 0 M-85 13.20 13.20 M-86 0 0 M-87 0 0 M-88 0 0 M-89 0 0 M-90 0 0 M-91 0 0 M-92 0 0 M-93 0 0 M-94 300 300 M-95 1000 1000 M-96 500 500 M-97 0 0 l M-98 0 0 i 1 M-99 0 0 M-383-3 31,148.7 0 l l M-383-4 400 0 1 l TOTALS 33,408.09 SCCM 1,859.39 SCCM l
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TABLE VI PIPING TYPE C TEST As Left/After Penetration As Found (SCCM) fiaintenance (SCCM) M-2 0 0 M-7 0 0 M-8 0 0 M-11 80.0 0 M-13 80.0 0 M-14 23.52 23.52 M-15 4.11 0 f1-18 150 0 M-19 5.88 0 M-20 0 0 M-22 0 0 M-24 0 0 M-25 3.52 3.52 M-30 35.51 35.0 M-31-1 2.06 2.06 M-31-2 0 0 M-38-1 0 0 M-38-2 5.0 5.0 M-39 17.58 3.79
l As lef t/After Penetration As Found (SCCM) Maintenance (SCCM) M-40-1 0 0 M-40-2 0 0 M-42 2000 0 M-4 3 0 0 M-45 1.03 5.38 M-4 6-1 5.0 5.0 M-4 6-2 3.46 3.46 M-47-1 0 0 M-47 -2 0 0 M-48-1 280 28 0 , M-48-2 5.33 5.38 M-50-1 0 0 M-50-2 31.35 31.35 M-51-1 0 0 M-51-2 22.69 22.69 M-52-1 5.0 0 M-5 2-2 0 0 M-53 4.82 2.75 M-57-1 0 0 M-57-2 0 0 M-5 8-1 4000 0 M-58-2 0 0 M-69 0 0 M-72 0 0 M-73 0 0 i M-74 2.06 2.06
As left/After Penetration As Found (SCCM) Maintenance (SCCM) M-79 2000 1.37 M-80 .68 .68 M-86 2100 2100 M-87 2400 0 M-88 900 1000 M-89 1300 1300 HCV-383-3 0 0 HCV-383-4 0 0 TOTALS 15,468.45 SCCM 4,832.88 SCCM t l l l l l l l}}