ML19350D114
| ML19350D114 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 12/31/1980 |
| From: | Phillips D, Webber B, Whitney K VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | |
| Shared Package | |
| ML19350D111 | List: |
| References | |
| NUDOCS 8104130349 | |
| Download: ML19350D114 (23) | |
Text
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j VERMONT YANKEE PRIMARY CONTAINMENT LEAKAGE RATE TESTING 4
i 1980 I
i TEST COORDINATORS i
B.R. Webber S.A. Vekasy e
1 PREPARED BY e
K.A. Whitney i
D.L. Phillips j
B.R. Webber i
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INTRODUCTION During the 1980 Refuel Outage which occurred during the period from September 27, 1980 to December 28, 1980, a Type A Containment Integrated Leakage Rate Test
.was performed. Previous Leak Rate Test Reports were filed with the USNRC in January 1975, August 1978, and January 1980.
This report describes primary containment testing performed after the October 1979 Type A Test and 1979 Refuel Outage up to and including the December 1980 Type A Test. In accordance with the requirements of 10 CFR 50 Appendix J, a summary analysis of all periodic Type B and Type C tests that were performed since then is included in this report. The Type B and Type C test results included in this report are from the 1980 Refuel Outage.
All testing performed during the period covered by this. report conformed to the rules and regulations specified in 10 CFR 50, Appendix J.
SUMRRY The plant was shut down on September 27, 1980 for annual refueling and maintenance.
The Type B and C test program was started shortly before the plant shutdown. The Type A test was conducted at the end of the refuel outage.
Pressurization for the Type A test commenced on December 19, 1980 with two air compressors of 1800 SCFM total capacity and approximately a 5 psi /hr charging rate. Containment pressure was raised to the calculated peak accident pressure of 44 psig over a 7-hour and 50-minute perfele during this time period, the pressurization rate was reduced at the 5, 15, and 40 ; sig levels to facilitate investigation for con-tainment leaksge. No significan b-vere found during the pressurization period.
After stabilizing for ten hours, the 24thour test period was initiated at 1300 on December 20, 1980.
The 24-hour test was complated December 21, 1980 at 1300, i
The absolute method of leakage determination was esployed. The containment leakage rate was determined from the slope of a least squares fit of mass of air versus time (see Figure II). The measured leakage rate at the upper one sided 95% confidence level was 0.199 WT%/ Day.
The final corrected leakage rate at the upper one sided 95%
confidence level was 0.261 WI%/ Day c
y 3
1980 TYPE A TEST Description of Test The containment was made ready for the integrated leakage rate test and pressurization commenced at 1910 hours0.0221 days <br />0.531 hours <br />0.00316 weeks <br />7.26755e-4 months <br /> on December 19, 1980. Pressur-ization was accomplished by using two mobile, oil free air compressors, each with a capacity of 900 SCFM.
They were connected by hose to the nitrogen purge supply at the flange connection upstream of FCV-1-156-10 as shown on the attached Figure I.
At the 5, 15, and 30 psig containment pressure levels, leskage location survey personnel were dispatched and no significant leaks were found.
After gradual reduction of the pressurization rate, the air inbleed was isolated at 0300 on December 20, 1980, when a test pressure of 44.60 psig was attained. Data Collection to measure temperature stability began at 0400.
At 1000, investigation into a problem with containment pressure signal input to the process computer determined that the zero pot adjustment of the mercury manometer was not locked.
The zero pot was readjusted to make the process computer input accurate.
A one point calibration to the process computer was then performed to improve process computer and mercury manometer agreement.
Based on expected acceptable leakage and temperature stabilization, the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test was commenced at 1300 on December 20, 1980.
At 1900, Test Personnel noticed a sudden increase in the torus liquid level as indicated by the process computer.
Investigation determined that the torus liquid level had not changed. The process computer indicated a torus level of 1.67 FT, the torus level from LI-16-19-38B read 0.92 FT.
After the reference leg for LT-16-19-38A was backfilled at 2015, the computer indicated a level of 0.92 FT, as did LI-16-19-38B.
There appeared to have been an air bubble in the reference leg of LT-16-19-38A.
At this point it was decided to manually back fit data into a modified time share calculation of the containment mass due to 1) the process computers calculated mass of air inaccuracy due to the faulty torus level transmitter, and 2) suspect. computer readings of containment pressure as compared to mercury manometer indications. Data was available from chart recordings to
v;rify that th] t rua 1 val had b2:n etnttcnt ct 0.92 ft, cinca 1300 cn December 20, 1980. Due to earlier problems with the computer indication
~
of containment pressure, the mercury manometer indication had been recorded at 10 minute intervals since the beginning of the test and was avai.
for use in the calculation.
Table 1980-A (Primary Containment Leakage Rate Data Sheet) contains
- 1) the results of the time share program (PCLRTP) ~ contained mass calculations,
- 2) the containment pressure as read from the mercury manometer local readout in the control room, and 3) weighted average drywell temperature.
The peak pressure Type A Test was completed at 1300 December 21, 1980.
A supplemental test, (required by Appendix J,10 CFR 50) to verify the accuracy of the instrumentation was conducted by metering a mass of air approximately equal to the allowable leakage back into the containment. This pump back of 227.1 lbm was completed at 1433 hours0.0166 days <br />0.398 hours <br />0.00237 weeks <br />5.452565e-4 months <br />.
Sufficient data had been gathered at 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> to determine that this verification was successful.
Containment depressurization commenced at 1815, and was completed at 0425 on December 22, 1980. All plant systems were returned to normal as required by operational needs on December 22, 1980.
Analysis and Interpretation of Test Data The total containment air mass calculation was performed for every ten minute interval of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test period.
Input data for the calculation consisted of containment pressure, drywell and torus weighted average air temperature, drywell and torus dew points, and torus water level.
The data, consisting of 145 independent calculations of contained total air mass at ten minute intervals, lends itself to a statistical analysis based upon a time dependent rate of change of the contained mass of air. A small pressure change over the test interval is the basis for the assumption that the containment leakage rate was constant with respect to time.
A linear least square fit is employed to develop the best straight line fit to the data. The slope of this least squares fit line is the leakage rate.
j
i The equation of the least squares fit line is of the form
- i Q
b +mT
=
where: Q mass of air
=
Q intercept (Q value at time 0) b
=
slope of line (leakage rate) m
=
T time
=
number of data points N
=
The values for b and m are determined from the following equations:
b IQ - MET
=
N NEQT - EQET m
=
NET 2- (IT)#
The upper one sided 95% confidence level (UCL) of the leakage rate (slope of line) may be determined from the standard error of the slope and a " Students Table of t".
The standard error is:
Standard Error, S (m) =
1 VARIANCE of Q 2
~"
N-2 VARIANCE of T
~~
2 S (m) =
1 NIQ
- (EQ)2 2
N-2 NET
- (IT)
~ "._
The upper one sided 95% confidence level on the true leakage rate (1) is:
UCL (Approx.)
Lam + 2400 * (t.95)*
(S (m) /b)
=
Where: UCL Upper Confidence Level
=
- (2400) * (m/b)
Lam
=
The t factor at the 95% confidence level for t
.95
=
l 145 Data points (143 degrees of freedom)
= 1.65 (1) ANSI /ANS 56.8--1980, Appendix B (Standard Deviation)
=I (xi - x)
- Variance
=
n 1
Tr-t Rr ult 1 A linear least square fit of the 145 data points calculated during this test (presented in Table 1980 - A), result in the following equation:
1 74777 - 6.104 T Q
=
Where:
74777 represents the initial mass of contained air in pounds 104 represents the leakage rate in the Ibm /hr.
The upper one sided 95% confidence level on the leakage rate using this data is:
- Lam + 2400 (t.95) (S (m) /b)
ULC
=
- (2400) (m/b) + 2400 (t
.95)
(S '(m) /b)
=
- (2400)
(-6.104/74777) + 2400 (1.65)
(0.066606/74777)
=
+ 0.1994 WT%/ Day
=
Correction Factors 1.
Correction for 1 css through isolation valves V-3-181
+ 0.0289 WT%/ Day V-12-68
=
V-12-15 2.
Correction for increase in drywell sump levels
+ 0.0232 WT%/ Day 3.
Correction for increase in reactor vessel water level
+ 0.00943 WT%/ Day The corrected leak rate at the upper one sided 95% confidence level is 0.261 WT%/ Day.
This measured value is less than the Techncial Specification limit of 0.75 La, (Where La=
0.80 weight percent of contained mass per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />), which is equivalent to 0.60 weight percent of contained mass per 24 q
hours.
l
Verification of Instrumentation Sensitivity
~
l Section III.A.3 (b) of Appendix J to 10 CFR 50 requires that the accuracy of the Type A Test shall be verified by a supplemental test.
The Pumpback Method of verification was selected.
In this method, a known quantity (mass) of air is metered into the containment and is compared with the change in the calculated weight of air. The required accuracy between the metered quantity and the calculated quantity is specified in Appendix J to be +
.25 La.
The quantity metered back was selected to be approximately equivalent to the allowable leakage rate of 0.60 WT%/ Day.
The actual quantity metered was 610 FT,
At 57 psig feed pressure and 60 F, which is equivalent to 227.1 pounds mass, the air charge required 8 minutes and 5 seconds to complete.
The average of five calculated values of mass of air prior to the charge was 74621.2 lbs. The average of five calculated values of mass of air following the charge was 74855.4 lbs. During the 60 minute elapsed time between before and after average measurements at the measured leakage rate of 6.104 lbm/hr, 6.1 lbs was assumed to leak during the pump back test.
The balance is as follows:
Mass following air charge 74855.4 Mass prior to charge 74621.2 Difference 234.2
" Normal Leakage" 6.1 Total Difference 240.3 The comparison to the actual charge of 227.1 lbs is:
240.3 - 227.1 13.2 lbs. difference
=
The allowable Supplement Test error of.25 La 149.55 lbs.
=
The 13.2 lbs in the 1980 Supplement Test was well within the accuracy limits specified in Appendix J.
l
PRIMARY CONTAINMENT LEAKAGE RATE DATA SHNET
~
(TYPE A)
(
TABLE 1980 - A 5
Time Contained Pressure Temp.
Time Contained Pressure TempoI (Min)
Mass (pounds)
"Hg
- F (Min)
Mass (pounds)
"Hg
- F 1300
- 74780 119.864 85.2 1630 74750 119.898 85.8;
'I 1310 74773 119.865 85.3 1640 74750 119.898 85.8 l 85.8 1320 74774 119.866 85.3 1650 74749 119.898 5
i 1330 74768 119.868 85.4 g
1700 74749 119.898 85;8 j 5
1340 74769 119.870 85.4 1710 74748 119.898 85.8 1350 74770 119.872 85.4 1720 74748 119.896 85.8 1400 74764 119.873 85.5 1730 74747 119.895 85.8 1410 74765 119.876 85.5 1740 74748 119.896 85.8 1420 74766 119.877 85.5 1750 74740 119.896 85.9 1430 74768 119.881 85.5 1800 74741 119.898 85.9 I
(
1440 74770 119.883 85.5 1810 74742 119.899 85.9 1450 74763 119.884 85.6 1820 74743 119.900 85.9 1500 74764 119.884 85.6 1830 74743 119.900 85.9 1510 74765 119.887 85.6 1840 74743 119.901 85.9 1520 74764 119.887 85.6 1850 74737 119.902 86.0 1530 74766 119.889 85.6 1900 74737 119.903 86.0 1540 74767 119.891 85.7 k'
1910 '
74737 119.903 86.0 1550 74755 119.894 85.7 1920 74737 119.903 86.0 h
1600 74761 119.894 85.7 1930 74738 119.904 86.0 h
1610 74756 1H.896 85.7 1940 74732 119.905 86.1
=
h 1620 74749 119.897 85.8 1950 74733 119.906 86.1
- Start of 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test g gg j g
(
Date 12/20/80 Approved b h
y t Coordinator
.VYOPF 4029.04 Original
PRIMARY CONTAINMENT LEAKAGE RATE DATA SHEET (TYPE A)
/
TABLE 1980 - A i
Time Contained Pressure Temp.
Time Contained Pressure Temp.
(Min)
Mass (pounds)
"Hg
- F
{
(Min)
Mass (pounds)
"Hg
- F 2000 74733 119.907 86.1 2330 74718 119.905 86.3 _
2010 74732 119.907 86.1 2340 74712 119.905 86.4 5
2020 74714 119.908 86.1 2150 74717 119.905 86.4 2030 74733 119.907 86.1 2400 74710 119.903 86.4 2040 74732 119.907 86.2 2410 74709 119.901 86.4 2050 74733 119.907 86.1 2420 74708 119.899 86.4 E
2100 74726 119.907 86.2 2430 74708 119.899 86.4 2110 74726 119.907 86.2 2440 74708 119.899 86.4 2120 74726 119.907 86.2 2450 74708 119.899 86.4 2130 74726 119.907 86.2 0100 74708 119.899 86.4
(
2140 74726 119.907 86.2 0110 74700 119.898 86.5 2150 74728 119.907 86.2 0120 74700 119.898 86.5 2200 74726 119.907 86.2 0130 74701 119.899 86.5 2210 74719 119.907 86.3 0140 74700 119.899 86.5 2220 74719 119.907 86.3 0150 74700 119.899 86.5 2230 74718 119.906 86.3 0200 74701 119.S99 86.5 2240 74718 119.906 86.3 0210 74701 119.900 86.5 E
l 2250 74718 119.906 86.3 0220 74702 119.901 86.5 2300 74718 119.905 86.3 0230 74702 119.901 86.5 1
2310 74719 119.905 86.3 0240 74701 119.900 86.5 2320 74719 119.905 86.3 0250 74701 119.900 86.5 l
Test Asst.
b YF///r4eo
/2[0C[70 Date 12/20/80 - 12/21/80
(
Approved A
VYOPF 4029.04 Original
PRIMARY CONTAINMENT LEAKAGE RATE DATA SHEET (TYPE A)
('
TABLE 1980-A 2
Time Contained Pressure Temp.
Time Contained Pressure Temp.
g (Min)
Mass (pounds)
"Hg
- F (Min)
Mass (pounds)
"Hg
- F 0300 74701 119.899 86.5 $ 0630 74677 119.883 86.8 2
0310 74694 119.899 86.6 $ 0640 74677 119.881 86.8 2
0320 74700 119.897 86.5 $ 0650 74675 119.878 86.9 5
0330 74699 119.896 86.5 $ 0700 74668 119.878 86.9 5
0340 74698 119.895 86.6 $ 0710 74666 119.876 86.9 2
0350 74691 119.894 86.6 $ 0720 74665 119.874 86.9 E
0400 74690 119.893 86.6 $ 0730 74664 119 S73 86.9 0410 74691 119.893 86.6 $ 0740 74663 119.871 86.9 5
0420 74690 119.892 86.6 $ 0750 74662 119.869 86.9 5
0430 74690 119.892 86.6 $ 0800 74660 119,867 86.9 k
0440 74691 119.892 86.7 $ 0810 74660 119.866 86.9 5
0450 74683 119.892 86.7 $ 0820 74659 119.865 86.9 0500 74683 119.892 86.7 $ 0830 74665 119.863 86.9 3
0510 74690 119.891 86.7 $ 0840 74665 119.863 86.9 5
0520 74689 119.890 86.7 $ 0850 74663 119.861 86.9 0530 74682 119.890 86.8 $ 0900 74663 119.860 86.9 0540 74682 119.889 86.8 0910 74662 119.859 86.9 0550 74681 119.888 86.8 0920 74659 119.853 87.0 0600 74679 119.886 86.8
- 0930 74647 119.846 87.0 0610 74679 119.885 86.8
- 0940 74650 119.840 86.9 l
0620 74678 119.883 86.8
- 0950 74649 119.838 86.9 Test Asst.
b I F((t7)pof
/,2/c71]70._.,
(
Date 12/21/80 Approved est Coordinator VYOPF 4029.04 Original
PRIMARY CONTAINMENT LEAKAGE RATE DATA SHNET (TYPE A) h TABLE 1980-A 2
Time Contained Pressure Temp.
Time Contained Pressure Temp.
(Min)
Mass (pounds)
"Hg
- F (Min)
Mass (pounds)
"Hg
- F 2
1000 74645 119.831 86.9
$1330 74626 119.835 87.0 2
1010 74643 119.829 86.9
$ 1340 74627 119.838 87.1 1020 74637 119.828 86.9
!1350 74619 119.837 87.1 1030 74635 119.826 86.9
$ 1400 74619 119.837 87.1 E
1040 74634 119.825 86.9
$1410 74620 119.839 87.1 3
1050 74633 119.824 86.9
$1420 74621 119.840 87.1 1100 74632 119.822 86.9 1430 74721 120.013 87.2 1110 74632 119.823 86.9
$1440 74858 120.255 87.3 5
1120 74625 119.823 87.0
$1450 74860 120.246 87.2 2
1130 74625 119.823 87.0
$1500 74853 120.745 R7.7 1140 74626 119.823 87.0 1510 74853 170.?45 R7.7 1150 74625 119.823 87.0
$1520 74R51 170.745 R7 7 1200 74627 119.825 87.0
$1530 74853 120.245 87.2 2
_1210 74627 119.826 87.0
$1540 1220 74629 119.829 87.0
$1550 1230 74629 119.829 87.0
$1600 1240 74629 119.830 87.0
$1610 1250 74629 119.830 87.0
$1620 1300
- 74630 119.831 87.0
$1630 1310 74631 119.833 87.0
$1640 1320 74625 119.834 87.0
$1650 Test Asst.
b YF/[o $ pf,/
/A/P//R0
- End of 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test
- Supplemental Test Pump back Date 12/21/80
(
completed at 1433 b
f Approved est coorM nator VYOPF 4029.04
-Original
AIR SUPPLY SCHEMATIC Air Purge Supply l
=
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- Disconnecting a fitting I
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1980 TYPE B AND C TESTING Introductory Description of Testing During the 1980 Refueling Outage, Type B and C primary containment leak rate testing was conducted.in accordance with 10 CFR 50 Appendix J.
Type B leakage tests were performed on containment penetrations utilizing 8asketed seals prior to being opened. This provided accurate as-found Icakage data i
from the previous operating cycle. After each containment penetration closeout, a Type B leak test was again performed. This leakage data was combined with all measured leakages of the various containment isolation valves as a baseline for the upcoming operating cycle. The summary test results for Type B gasketed seals is presented in Table 80-B.
Type C leakage tests were also conducted in accordance with 10 CFR 50 Appendix J, on containment isolation valves.
Four types of leakage tests were used, 1.) the water leakage method, 2.) the pressure drop method, 3.)
the pressure buildup method, and 4.) the in-leakage test method. All valves in excess of that allowed by the Technical-that..re found to have leakage rates Spesifications were reported to the Director of the Office of Inspection and Enforcement, Region I, in two thirty-day licensee event reports, LER 80-39/3L and LER 80-43/3L.
Following disassembly, repair, and retesting, a satisfactory leakage rate was demonstrated. The summary for Type C valves is presented in Table 80-C.
Penetrations That Exceeded the Type B Leakage Criteria On October 10, 1980, TIP Penetration Flange X-35A was leak rate tested and the test volume could not be pressurized. Disassembly of the double-gasketed flange revealed the inner 0-ring to be deformed. Primary containment isolation was maintained due to the integrity of the outer 0-ring seal. The 0-ring seals were replaced, and the leakage between the seals was verified to be 0.0 lbm/hr. on October 16, 1980.
Valves That Exceeded the Leakage Criteria 1.
Tech. Spec. Isolation Valves During the 1980 refueling outage, three primary containment isolation valves were f ound to have seat leakages in excess of that permitted by the Technical Specifications. On all valves found to have leakage greater than that allowed, a second valve on the same line provided the proper primary containment isolation capability.
l The three valves and their "as-found" leakage rates are as follows:
f Valve Description As-Found Leakage Rate Date of Event V-16-20-20 (Containment Indeterminable 9/29/80 Purge Makeup Isolation Valve).
LRW-83 (Drywell Floor Indeterminable 9/30/80 l
Drain)
RCIC-15 (RCIC Steam 1.531 lbm/hr.
12/20/80 Supply) l
-~
Testing, raptir, cnd ratect dztcils for tha valvsa found to h:va excessive seat leakage are described below:
a.
Containment Purge Makeup Isolation Valve On September 29, 1980, the Containment Purge Makeup Isolation Valve V16-20-20 was leak rate tested and the test volume could not be pressurized.
Disassembly and inspection of the valve revealed that there
]
was dirt under the valve seat. The valve internals were cleaned and the valve reassembled.
Following this_ maintenance, the leakage past the seat was verified to be < 0,014 lbm/hr. V16-20-20 is an Aktomatic 1" 300 lb. gate valve, b.
Drywell Floor Drain On September 30, 1980, the Drywell Floor Drain Valve LRW-83 was leak rate tested and the test volume could not be pressurized.
Disassembly and inspection revealed the valve internals to be dirty.
The valve internals were cleaned and the valve reassembled. Following this maintenance, the leakage past the seat.was verified to be 0.234 lbm/hr on October 2, 1980. LRW-83 is a Walworth 3" 300 lb.
gate valve.
c.
RCIC Steam Supply On December 20, 1980, the RCIC Steam Supply Valve RCIC-15 was retested during the Type A test after the RCIC-16 valve had been repacked.
The leakage rate was determined to be greater than that allowed by the Technical Specifications. Disassembly and inspection of the valve revealed seating surfaces which required sanothing. The valve disk and seat were lapped and the leakage past the repaired valve was verified to be 0.112 lbm/hr. on December 23, 1980. RCIC-15 is a Walworth 3" 900 lb. gate valve.
2.
Other Isolation Valves a.
CAD Vent On September 30, 1980, the CAD Vent Valve VG-22B was leak rate tested and the test volume could not be pressurized. The plug and seat were lapped and the valve reassembled. Following this maintenance, the leakage past the seat was verified to be < 0.022 lbm/hr on October 2, 1980. VG-22B is a Crane-Flowmatics 1" 150 lb.
j globe valve.
l b.
On September 30, 1980, the Radiation Monitor Return Valve VG-76A was leak tested and the t est volume could not be pressurized.
The disk assembly was replaced and the actuator mechanism was cleaned.
l Pollowing this maintenance, the leakage past the seat was verified to be 0.089 lbm/hr. on October 2, 1980.
During the test period, VG-76A was listed in Technical Specifications Table 4.7.2.b as a primary containment isolation valve not subject to Type C leakage test.
Subsequently, an ammendment to the Technical Specifications requires that a Type C leakage test be performed.
l I
l l
Ruantative Calculations of Technical Specifications Limits 1.
The combined leak rate of all penetrations and valves subject to Type B and C testa shall be less than 0.60 La.
Sixty (60) percent of 354 lbm/ day.
La 2.
The leakage from any one isolation valve shall not exceed 5% of Ltm.
Five (5) percent of Ltm = 0.522 lbm/hr.
I 3.
The leakage from any one main steam line isolation valve shall not exceed 11.5 SCFH at 24 PSIG (Pt).
l l
G:ntrol Crnclu2itn Based on the successful completion of the Type A, B, and C leak rate test programs, along with the corrective action taken as a result of the test data, it is concluded that the condition of the Primary Containment System is acceptable for continued plant operation. The plant was returned to service with a containment leakage of less than 0.261 WT%/ Day. This compares to the allowed leakage of 0.600 WI%/ Day.
i Teblo 80-B Summary TR,t Rvulta far Typa B Tu ting i
PENETRATION LEAKAGE (LBM/HR)
NUMBER DESCRIPTION INITIAL RETEST
'X-2 Personnel Lock 0.430 Bellows Seals X-7A Main Steam Line A 0
X'-7B Main Steam Line B 0
X-7C Main Steam Line C 0
X-7D Main Steam Line D 0
X-9A Feedwater A 0
X-9B Feedwater A 0
X-11 HPCI Steam Line 0
X-12 RHR Suction 0
X-13A RHR Return A 0
X-13B RHR Return B 0
X-14 Cleanup Suction 0
X-16A Core Spray A 0
X-16B Core Spray B 0
Electrical Penetrations 100A Electrical Penetration 0
100B Electrical Penetration 0
100C Electrical Penetration 0
100D Electrical Penetration 0
l 101A Electrical Penetration 0.2987 0.00056 101C Electrical Penetration 0
101D Electrical Penetration 0
101D Electrical Penetration 0
102 Electrical Penetration 0
103 Electrical Penetration 0.0028
~... _ _ _. _ _. _..., _.
Table 80-B (cont'd)
Summary Test Results for Type B Testing
)
PENETRATION NUMBER 104A Electrical Penetration 0
104B Electrical Penetration 0.0014 104C Ele'ctrical Penetration.
0 104C Electrical Penetration 0
105A Electrical Penetration 0
105B Electrical Penetration 0
105C Electrical Penetration 0
105D Electrical Penetration 0
214 Electrical Penetration 0
NW Torus Manway Electrical Connectors 0.00014 Double Gasketed Seals X-1 Equipment Hatch 0.00087 X-4 Drywell Head Access Hatch 0.0000085 X-6 Control Rod Drive Removal Hatch 0.000036 0.000045 X-200A Torus Access Hatch 0
0.000030 X-200B Torus Access Hatch 0
0 VBC-A Vacuum Breaker Access Cover 0 0
VBC-B Vacuum Breaker Access Cover 0.00009 0.000019 VBC-C Vacuum Breaker Access Cover 0.000047 0.000028 l
VBC-D Vacuum Breaker Access Cover 0 0.000076 VBC-E Vacuum Breaker Access Cover 0.00038 0.000019 VBC-F Vacuum Breaker Access Cover 0.00017 0.000038 l
VBC-G Vacuum Breaker Access Cover 0 0.000019 l
VBC-H Vacuum Breaker Access Cover 0 0.000019 VBC-I Vacuum Breaker Access Cover 0.000038 0.0 VBC-J Vacuum Breaker Access Cover 0 0.000047 l
l
Tdla80-B (crnt'd)
Summary Test R uults for Typa B Tor. ting
-PENETRATION LEAKAGE (LBM/HR)
NUMBER DESCRIPTION INITIAL RETEST VBSL-A Vacuum Breaker Shaft Left 0.0000084 VBSR-A Vacuum Breaker Shaft Right 0.000034 VBSL-B Vacuum Breaker Shaft Left 0
VBSR-B Vacuum Breaker Shaft Right 0.000042 VBSL-C Vacuum Breaker-Shaft Left 0.0000084 VBSR-C Vacuum preaker Shaft Right 0
VBSL-D Vacuum Breaker Shaft Left 0.000084 VBSR-D Vacuum Breaker Shaft Right 0
VBSL-E Vacuum Brea'scr 31.dt Lef t.
O VBSR-E Vacuum Breaker Shaft Right 0.0000084 VBSL-F-Vacuum Breaker Shaft Left 0.00021 VBSR-F Vacuum Breaker Shaft Right 0.0000084 VBSL-G Vacuum Breaker Shaft Left 0
VBSR-G Vacuum Breaker Shaft Right 0.0000084 VBSL-H Vacuum Breaker Shaft Left 0
VBSR-H Vacuum Breaker Shaf t Right 0.0000084 VBSL-I Vacuum Breaker Shaft Left 0.0000084 VBSR-I Vacuum Breaker Shaft Right 0-VBSL-J Vacuum Breaker Shaf t Left 0
VBSR-J Vacuum Breaker Shaft Right 0
SLH-A Shear Lug Access Cover 0.00037 SLH-B Shear Lug Access Cover 0
SLH-C Shear Lug Access Cover 0.000010 SLH-D Shear Lug Access Cover 0
SLH-E Shear Lug Access Cover 0.00029 SLH-F Shear Lug Access Cover 0.00010 SLH-G Shear Lug Access Cover 0.000015 SLH-H Shear Lug' Access Cover 0.000022 Drywell Head Flange 0.0323 0.0027 X-213-A Torus Drain 0.000004 0.000004 X-213-B Tour Drain 0.000011 0
X-35A TIP Penetration Flange Could not Pressurize 0 X-35B TIP Penetration Flange 0
X-35C TlP Penetration Flange 0
X-35E TIP Penetration Flange 0
Total B Penetration Leakage After Repairs 0.4399827 lbm/hr
v
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Summary Test Results for Type C Testing Table 80-C LEAKACE (LBM/HR)
VALVE (S) TESTED DESCRIPTION INITIAL RETEST MS-77 Main Steam Drain 0.113 RV39 & 40 Recire. Sample
<0.022 RHR-57 RHR Disch.to Radwaste 0.009 LRW-83 Drywell Floor. Drain Could Not Pressurize 0.234 LRW-95 Drywell Equip. Drain 0.207 SB-16-19-8,9,10 & 23 Containment Purge O
SB-16-19-11A & 12A Vacuum Relief 0
SB-16-19-11B & 12B Vacuum Relief 0.009 SB-16-19-6,7,6A,6B,7A&7B Containment Exhaust 0.433 RCU-18 Reactor Cleanup 0.022
<0.003 V-16-20-20 Containment Purge Could not pressurize <0.014 Makeup V-16-20-22A Containment Purge Makeup 0.053 V-16-20-22B Containment Purge 0.015 Makeup RCU-68 Reactor Cleanup 0.231 HPCI-16 HPCI Steam Supply 0.015 RCIC-16 RCIC Steam Supply 0.888 0.112 CA-38A Cont. Air Compressor <0.022 CA-38B Cont. Air Compressor <0.022 Suction CA-89B Cont. Air Check 0.458 0.404 Valve CA-89C Cont. Air Check 0.089 0.390 Valve NG 13A & 13B CAD Injection
<0.015 NG 12A & 12B CAD Injection
<0.015 NG 11A & 11B CAD Injection 0.266 VG-9A CAD Vent
<0.022 VG-22A CAD Vent
<0.022 VG-9B CAD Vent 0.056
Table 80-C (cont'd)
Summary Test Results for Type C Testing LEAKAGE
( LBM/HR)
VALVE (S) TESTED DESCRIPTION INITIAL RETEST VG-22B CAD Vent Could not pressurize < 0.022 VG-23 CAD Rad. Mon. Supply
< 0.022 VG-26 CAD Rad. Non. Supply
< 0.022 VG-76A Rad. Mon.. Return Could not pressurize 0.089 VG-76B Rad. Mon. Return
<0.015 CRD-181 CRD Return Check Valve 0.231 MS-74 Main Steam Drain
<0.023 HPCI-15 HPCI Steam Supply
<0.015 RCIC-15 RCIC Steam Supply 0.112 0.112 RCU-15 Reactor cleanup 0
0.439 LRW-82 Drywell Dloor Drain 0.037 LRW-94 Drywell Equipment Drain 0.015 RHR-66 RHR Discharge to Radwaste 0.045 3.791 lbm/br Total Type C Leakage Following Repairs 4.231 lbm/hr Total Type B & C Leakage Following Repairs LEAKAGE (SCFH)
VALVE (S) TESTED DESCRIPTION INITIAL RETEST MS80A A Main Steam Line 1.64 MS86A A Main Steam Line 4.95 MS80B B Main Steam Line 2.03 MS86B B Main Steam Line 1.98 MS80C C Main Steam Line 0
MS86C C Main Steam Line 7.29 MS80D D Main Steam Line 0.44 MS86D D Main Steam Line 7.55