ML20032C292
| ML20032C292 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 10/31/1981 |
| From: | SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML13323A173 | List: |
| References | |
| NUDOCS 8111090612 | |
| Download: ML20032C292 (4) | |
Text
. -. _
t SAN CNOFRE NUCLEAR E NERATING-STATION LNIT 2 DOCKET NINBER 53-361 Revised Pages 5, Q-1 and R-4 to Reactor Containme.it building Integrated leak Rate Test Report 1
Febmary 1981 f
Revision 1 October, 1981 i
PDR i
l l
l IACAL LEAKAGE RATE I
,l PENETRATION I SYSTEM / VALVE SCCM l
l l
l l
l 45 l Normal A/C Chill Water /2HV-9990 & 2HV-9920 1 1267.5-l l
l 1
l l
46 l Normal A/C Chill Water /2HV-9971 & 2HV-9921 1 0+2.0 l
l 1
l l
l 10B l
ILRT Pressure Sensor /S21500HUO38 l
0+2.0 1
I l
1 l
l 10B l
ILRT Pressure Sensor /S21500 MUO39 l
0+2.0 l
l l
l l
l 34 l
ILRT Test Connection 1
0+0.2 l
l 1
I l
J 68
!! Manual Aux Spray Bypass /S21208MU 129 & 130 l' 637 l
l l
l l
l l
Total 1910.7 I
l l
l l
l
%/ Day l
0.000864 l
E.
Integrated Leakage Rate Measurement Systesi
- 1. Absolute Pressure (1 + 1 backup)
Make:
Mensor Mod el:
10100-001 Range:
0-100 psia Accuracy:
1015% of reading Repeatability:
1 0005% of full scale Cage S/N 1487, Capsule S/N 2317 Calibration Due Date: May 14, 1981 Cage S/N 1489, Capsule S/N 2349 Calibration Due Date: May 14, 1981 Calibration Standard:
Texas Instruments S/N 2741, Capsule 834 Calibration Due Date: May 10, 1981
- 2. Drybulb Temperature (18 plus 2 spares)
Make:
Ku:= mount 100 ohm platinum Mod el:
78-65-17 Range:
0-150' F A.: curacy:
+ 0.1*F (60-120*F)
I 0.15'F (0-150*F)
Repeatability:
_I.1*F S/N S/N S/N S/N S/N 120063 116020 120071 120070 120064 117228 116025 120058 117227 117238 4
120060 117233 117244 117240 120061 120073 120062 117241 117229 117230 Calibration Due Date: April 23, 1981 Calibration Standard:
Burns RTD S/N 84939 and VMC 202 Keithley 191 DMH r DH-037 pevision 1
~-
APPENDIX Q
~
1NSTRUMENT SYSTEM ERROR ANALYSIS The instrument system error analysis is based on the Figure of Merit, also known as instrument Selection Guid - (ISG), formula in BN-TOP-1, " Testing Criteria for integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants." The formula is:
1/2 2
2 2
2400
[p /
g,,,1 27,3\\
g/p y egt
+
+2 gp j +
2 ISC
=
7 g
t
- where, ep = absolute pressure measurement repeatability error divided by the square root of the number of sensors.
= (.0005%) (100 psia)/(1)l/2
=.0005 psia epv = vapor pressure measurement accuracy error divided by the square root of the number of sensors.
(NOTE:
Accuracy is conservatively used rather than repeatability.)
= (.54*F) (0.0124 psia /*F)*/(4)1/2
=.00335 psia
- From steam tables at dewpoint temperature range 69-71*F et = drybulb temperature measurement repeatability error divided by the square root of the number of sensors.
- (0.1*F)/(18)1/2 =.0236*F P
= Test pressure
= 71.9 psia T
= Test temperature
= 540' R DH-037 Q-1 of 2 Revision 1
o 4
b.
Calculated leakage rate from regression analysis:
I = a + bk
(.5)
N where:
L = Calculated leakage rate, %/ day, as determined from the regression line.
2 (EL ) (Ekg ) - (Ek ) (EL k )
g g
gg a =
N (Ekg ) - (Ek )2 (6) 2 g
N(ELgk ) - (ELg) (Ek )
i i
N(Ek )Z - Gk )#
g g
th g
Elapsed time at time of i data point k
=
N=
Number of data points N
I I
=
i=1 c.
Calculated leakage rate at the 95% confidence level including error associated with the test).
Total-Time Method per BN-TOP-1.
L95 = a + bk + S-(8)
L where:
L95 = calculated leakage rate at the 95% confidence level,
%/ day, at elapsed time k.
For kN < 24 I
I(L -E )2 1 + 1 + (k
)
g g N
S
. t0.025;N-2 j
(9a)
U N-2 y
N I(k 4)2 g
2.37 2.82 where, t0.025;N-2 = 1.96 +
+
3 N-2 (N-2)2 R-4 of 7 DH-039 Revision 1