ML17256A428
| ML17256A428 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/15/1982 |
| From: | GILBERT/COMMONWEALTH, INC. (FORMERLY GILBERT ASSOCIAT |
| To: | |
| Shared Package | |
| ML17256A427 | List: |
| References | |
| NUDOCS 8212210461 | |
| Download: ML17256A428 (108) | |
Text
ROBERT E., GINNA NUCLEAR POWER STATION REACTOR CONTAINMENT"BUILDING INTEGRATED LEAKiRATE TEST MA/III 1982 ROCHESTER GAS AND ELECTRIC CORPORATION
@NATORIJ DOCKD'Fg.E I;gPy 8212210461 821215'DR ADQCK 05000244 P
PDR Qben ICenmonweahh
4, Tpls~l
'J
TABLE OF CONTENTS Section Item Title
~Pa e
1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 5.1 5.2 5.3 5.4 5.5 5.6 6.1 6.2 6.3 8.1 8.2 8.3 SYNOPSIS INTRODUCTION GENERAL AND TECHNICAL DATA ACCEPTANCE CRITERIA TEST INSTRUMENTATION
SUMMARY
OF INSTRUMENTS SCHEMATIC ARRANGEMENT CALIBRATION CHECKS INSTRUMENTATION PERFORMANCE SYSTEMATIC ERROR ANALYSIS SUPPLEMENTAL VERIFICATION TEST PROCEDURE PREREQUISITES GENERAL DISCUSSION TEST PERFORMANCE METHODS OF ANALYSIS DISCUSSION OF RESULTS RE LTS AT P SUPPLEMENTAL TEST RESULTS SCHEDULE FOR RETESTING TYPE B AND C LEAKAGE RATE HISTORIES REFERENCES 4
8 8
9 9
12 13 13 14
,16 20 21 21 22 24 24 25 A
endices A.
SCHEMATIC ARRANGEMENT OF TEST INSTRUMENTATION B.
REDUCED LEAKAGE RATE DATA C.
WEIGHT OF CONTAINMENT AIR AND AVERAGE CONTAINMENT TEMPERATURE VERSUS TIME DE COMPUTER PRINTOUT E.
ISOLATION VALVE LEAKAGE RATES, 1979) 1980) 1981 )
1982 F.
ISOLATION VALVE DESCRIPTIONS IComnenwealth
l
1.0 SYNOPSIS The R.
E.
Ginna Nuclear Power Station reactor containment building was subjected to a periodic integrated leak rate test during the period from April 29, 1982 to May 5, 1982.
The purpose of this test was to demonstrate the acceptability of the building leakage rate at an internal pressure of 35 psig (P ).
Testing was performed in t
accordance with the requirements of 10 CFR 50, Appendix J, ANSI N45.4 - 1972 and R.E.
Ginna Nuclear Power Station Technical Specifications.
In addition, the recommendations of ANS 56.8 1981 were considered where appropriate for reduced pressure testing.
The measured leakage rate based on the mass point method of analysis was found to be 0.0076%/day 'with an associated 95% confidence interval of 0.0054%/day.
The post test repair leakage and local leakage from valves in service during the ILRT was 0.0067%/day and must be considered in the final results.
- Thus, the combined leakage rate at the upper bound of the 95% confidence interval is 0.0197 percent by weight per day which is well below the acceptance criterion of 0.1146 percent by weight. per day.
The supplemental instrumentation verification at P
demonstrated an agreement between measured reactor containment building integrated leakage rates of 8.7 percent of L which is well within the 25 percent requirement of 10 CFR 50, Appendix J,Section III A.3.b.
All testing was performed by Rochester Gas and Electric Corporation with the technical assistance of Gilbert Associates Inc.
Gilbert /Commonwealth
2.0 INTRODUCTION
The objective of the periodic integrated leak rate test was the verification of the overall leak tightness of the reactor containment building at an internal pressure of 35 psig.
The allowable leakage is defined by the design basis accident applied in the safety analysis in accordance with site exposure guidelines specified by 10 CFR 100.
For R.E.
Ginna Nuclear Power Station, the maximum allowable integrated leak rate at a pressure of 35 psig (P )t is 0.1528 percent by weight per day (L )
~
Testing was performed in accordance with the procedural requirements as stated in R.E.
Ginna Nuclear Power Station Containment Integrated Leak Rate Test Procedures RSSP-6.0, 6.1, 6.2 and 6.3.
These procedures were reviewed by the Plant Operations Review Committee and approved by the Plant Superintendent prior to the commencement of the test.
Leakage rate testing was accomplished at the pressure level of 35 psig for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, followed by a 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> supplemental test for a verification of test instrumentation.
3.0 GENERAL AND TECHNICAL DATA 3.1 GENERAL DATA Owner:
Rochester Gas and Electric Docket No.:
50-244 Location:
South shore of Lake Ontario, 16 miles east of Rochester, N.Y.
Slbert
/CommonwcalLh
I h
Containment
Description:
Reinforced concrete vertical cylinder with pre-stressed tendons in the vertical
- wall, a reinforced concrete ring anchored 1,
to bedrock and a reinforced hemispherical dome.
3.2 TECHNICAL DATA Containment Net Free Volume:
- 9. 7 x 10 cubic feet Design Pressure:
60 psig Design Temperature:
286 F
- 4. 0 ACCEPTANCE CRITERIA Acceptance criteria established prior to the test and as specified by Ginna Station Technical Specifications and an exemption to 10 CFR 50, Appendix J, dated March 28, 1978 are as follows:
a ~
The measured leakage rate (L
) for reduced pressure testing at tm 35 psig (P ) shall be less than 75 percent of the maximum allowable leakage rate (L ) specified as 0.1528 percent by t
weight of the building atmosphere per day.
The acceptance criteria is determined as follows:
pt L
= L t
a P a Q~ /Commonweal&
where L
= 0.2X/day P
= 60 psig a
P
= 35 psig Substituting the values for L,
P and P
a' L
= 0.1528% per day and
.75 L
= 0.1146X per day.
t b.
The test instrumentation shall be verified by means of a supplemental test.
Agreement between the containment leakage measured during the Type A test and the containment leakage measured during the supplemental test shall be within 25 percent of L 5.0 TEST INSTRUMENTATION 5.1
SUMMARY
OF INSTRUMENTS Test instruments employed are described, by system, in the following subsections.
An Instrumentation Selection Guide (ISG) formula, as discussed in Section 5.5 was calculated to be
+ 0.010X/day.
QlberL/Commonwealth
5.1.1 Tem erature Indicatin S stem
/
Components:
a.
Resistance Temperature Detectors (sensors)
Quantity 24 Manufacturer Leeds
& Northrup Type 100
- ohm, copper
- Range, F
0
-325 to 250
- Accuracy, F
0 Sensitivity, F
0
+0.1 b.
Temperature Indicator Quantity 1 Indicator (24 inputs)
Manufacturer Leeds and Northrup Type 24 point Speedomax G
Strip Chart Recorder 0
- Range, F
40-130
- Accuracy, F
0
+0.3X of full scale Repeatability, F
0
+0.1X of full scale 6!bete /Commonwealth
5.1.2 Dew oint Indicatin S stem Components:
a.
Dewcell Elements Quantity Manufacturer Foxboro Type Model 2711A
- Range, F
0 0-100 0
- Accuracy, F
+0.5 b.
Dewpoint Recorder Quantity Manufacturer Foxboro Type Model 9435 TM.
- Range, F
0 2-142
- Accuracy, F
0
+0.35 over range Gilbert /Commonwee le
t I 5.1.3 Pressure Monitorin S stem Precision Pressure Gauges Quantity Manufacturer Texas Instruments Type Model 144
- Range, psia 0-100 Accuracy, psia
+0.015K of indication Sensor Sensitivity,
+0.001% of full scale psia Repeatability, psia
+0.0003X of full scale 5.1.4 Su lemental Test Flow Monitorin S stem Flowmeter Quantity Manufacturer Wallace
& Tiernan Type Model 1855
- Range, scfm 0-7 at 110 F
Accuracy
+l%%d of full scale Slbett
/Commonwealth
5.2 SCHEMATIC ARRANGEMENT The arrangement of the four measuring systems summarized in Section 5.1 is depicted in App'endix A.
The 24 temperature sensors and 6 dewcells were placed throughout the reactor containment volume to permit monitoring of internal temperature and dewpoint.
A temperature survey was performed with the sensors installed which verified no large areas of temperature variation.
Placement of the temperature sensors and dewcells can be grouped into five elevations as follows:
Elevation Number of Tem erature Sensors Number of Dewcells 243'61'86'01'30'.3 CALIBRATION CHECKS Temperature,
- dewpoint, pressure and flow measuring systems were checked for calibration before the test in accordance with RG&E, procedures as recommended by ANSI N45.4-1972, Section 6.2 and 6.3.
Results of the calibration and calibration checks are on file at R.E. Ginna Nuclear Power Station.
The supplemental test at 35 psig confirmed the instrumentation acceptability.
&!bert/Comaenwcal&
5,4 INSTRUMENTATION PERFOIQQQICE The twenty-four temperature
- sensors, six dewcells and rotameter performed satisfactorily during the integrated leakage rate test.
However, both bourdon capsules in the Texas Instruments precision pressure gauges failed to respond properly during the initial performance of the test.
These were eventually replaced with the two spare bourdon capsules which performed well throughout the second phase of the test.
5.5 SYSTEMATIC ERROR ANALYSIS Systematic error, in this test, is induced by the operation of the temperature indicating system, dewpoint indicating system and the pressure indicating system.
Justification of instrumentation selection was accomplished, using manufacturer's 'sensitivity, accuracy and repeatability tolerances stated in Section 4.1, by computing the instrumentation selection guide (ISG) formula.
Utilizing the methods, techniques and assumptions in Apendix G to ANS 56.8-1981, the ISG formula was computed for the absolute method as follows:
a.
Conditions L
= 0.153X/day t
P
= 50 5 psia T = 54 F = 513.69 R dry bulb T
=40F dp t = 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Slberc IComeonweelth
10 b.
Total Absolute Pressure:
e P
No. of sensors:
2 Range:
0-100 psia Sensor sensitivity error (E):
+ 0.001% of full scale Measurement system error, (<):
+ 0.0003% of full scale I
e
= +
P e
= +
P (E )
+ (< )J no. of sensors PJ (0.001)
+ (0.0003) 2 e
= + 0.00074 psia P
c.
Water Vapor Pressure:
e pv No. of sensors:
6
- Sensor sensitivity error (E):
+
0.5 F
0
- Measurement system error (<) excluding sensor:
+ 0.35 F
0
- Values given are accuracy; true sensitivity and repeatability values would be lower but are unknown.
GLlbers ICommonweaN
At a dewpoint temperature of 40 F, the equivalent water vapor pressure change (as determined from the steam tables) is 0.0048 psia/
F.
= + 0.5 F
. (0.0048 psia/
F) pv E
= + 0.0024 psia pv
= + 0.35 F
~ (0.0048 psia/
F) pv c
= + 0.00168 psia e
= +
pv e
= +
pv (E
)
+
(c
)
no. of sensors 2
2 pv pv (0.0024)
+ (0.00168) 6 e
= + 0.00119 psia pv E
Temperature No. of sensors:
24 Sensor sensitivity error (E):
+ 0.1 F = 0.1 R
Measurement system error (c), excluding sensor:
+ 0.1% full scale Range:
40-130 F
c
= 0.001 '130 F)
= 0.13 F
T e
+
e
= +
T (E )
+ (-T) no. of sensors
>r~
T (0.1)
+ (0.13) 24 eT
+00335 R
&lbertICommonwcalth
12 e.
Instrumentation Selection Guide (ISG) 2400 e
2 e
2 eT ISG= 2 ~
+2 ~v
+2 t
P P
T 2400 ISG = +
24
.00074 0.00119 0.0333 2
ISG = + 100 4.295 x 10
+ 1.110 x 10
+ 8.506 x 10 ISG = + 0.010X/day The ISG formula does not exceed 0.25 L
(0.038K/day) and it is therefore t
concluded that the instrumentation selected was acceptable for use in determining the reactor containment integrated leakage rate.
5.6 SUPPLEMENTAL VERIFICATION In addition to the calibration checks described in Section 5.2, test instrumentation operation was verified by a supplemental test subsequent to the completion of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> leakage rate test.
This test consisted of imposing a known calibrated leakage rate on the reactor containment building.
After the flow rate was established it was not altered for the duration of the test.
During the supplemental
- test, the measured leakage rate was L
= L L
c v
0
- where, L
= measured composite leakage rate consisting of the reactor c
building leakage rate plus the imposed leakage rate L
= imposed leakage rate 0
4 L '= leakage rate of the reactor building during the v
supplemental test phase Qben ICommonwealth
l I
Rearranging the above equation, L
L v
c 0
The reactor containment building leakage during the supplemental test can be calculated by subtracting the known superimposed leakage rate from the measured composite leakage rate.
The reactor containment building leakage rate during the supplemental test (L ')
was then compared to the measured reactor v
containment building leakage rate during the preceding 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test (L
) to determine'nstrumentation acceptability.
Instrumentation tm is considered acceptable if the difference between the two building leakage rates is within 25 percent of the maximum allowable leakage rate (L ).
6.0 TEST PROCEDURE 6.1 PREREQUISITES Prior to commencement of reactor containment building pressurization, the following basic prerequisites were satisfied:
a.
'roper operation of all test instrumentation was verified.
b.
All reactor containment building isolation valves were closed using the normal mode of operation.
All associated system valves were placed in post-accident positions.
c.
Equipment within the reactor containment building, subject to
- damage, was protected from external differential pressures.
d.
Portions of fluid systems which, under post-accident conditions become extensions of the containment
- boundary, were drained and vented.
GLlbere /Commonwealth
14 e.
The penetration pressurization system was depressurized and'solated with test gauges installed to detect any leakage.
f.
Pre'ssure gauges were provided on the following systems to provide a means of detection for leakage into these systems:
1.
Purge Supply 2.
Purge Exhaust 3.
Personnel Access Hatch 4.
Equipment Access Hatch g.
Containment recirculation fans were operational..
h.
Potential pressure sources were removed or isolated from the containment.
i.
A general inspection of the accessible interior and exterior areas of the containment was completed.
6.2 GENERAL DISCUSSION Following the satisfaction of the prerequisites stated in Section 6.1, the reactor containment building pressurization was initiated at a rate of approximately 5.0 psi per hour.
Building pressure and temperature were monitored continuously throughout the pressurization stage.
Leak rate testing was initiated at the 35.7 psig pressure level.
For the duration of the testing period service water flow rate to the containment recirculation fans was adjusted to control containment temperature.
&Iberia ICornnenwea! th
During the test the following occurred at fifteen minute intervals (See Appendix B-Reduced Leakage Data):
a.
The numerical values indicated by each of the two precision pressure gauges were recorded and corrected to a true pressure reading via the computer.
b.
The twenty-four RTD temperatures were recorded and the average calculated via the computer.
C ~
The six dewpoint values were recorded.
The average of the six values was calculated and converted to vapor pressure using steam tables, via the computer.
This permitted correction of the total pressure to the partial pressure of air by subtracting the vapor pressure.
The use of vapor pressure (P ), temperature (T) and the total pressure (PT) is described in more detail in Section 7.1.
All original data is on file at R.E.
Ginna Nuclear Power Station.
The plot of average temperature and weight of air was maintained for each fifteen minute reading (See Appendix C).
Throughout the test all fifteen minute interval values of P T and P
were transmitted via on-site portable computer terminal to the T
Rochester Gas and Electric Company home office for analysis.
Computer program results, including the least squares fit of the
- data, were returned to the site via the terminal.
A final computer run was made after data for a full 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period was available.
Immediately following the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> leak test, a superimposed leakage rate was established for an additional 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> period.
During this
- time, temperature, pressure and vapor pressure were monitored as described above.
delbert /Commonwealth
- 6. 3 TEST PERFORMANCE 6.3.1 Pressurization Phase Pressurization of the reactor building containment was started on April 29, 1982 at 1230.
The pressurization rate was approximately 5.0 psi per hour.
During pressurization, a buildup of pressure was observed between the purge supply and purge exhaust valves.
When containment internal pressure reached 35.7 at 2019 on April 29, 1982, pressurization was secured.
At 0030 on April 30,
- 1982, the containment stabilization criteria had been met.
6.3.2 Inte rated Leak Rate Testin Phase At 0100 on April 30, 1982, fifteen minute frequency test data collection was initiated.
Containment internal temperature was controlled throughout the test by throttling the Service Water flow to the containment vessel recirculation fans.
Subsequent to 0100, April 30,
- 1982, the following sequence of events took place:
a.
At 0110, MV'S 6151 and 6165 (Auxilliary Steam supply to the containment) were found to be not fully closed.
Both valves were tightened and a snoop check revealed no leakage.
b.
At 0315, a lineup discrepancy was noted.
Roving test personnel found a reactor support cooling valve, V-2726 closed but not
'I capped and RCDT gas header valve V-1676B capped.
At this time a cap was installed on V-2726 and the cap removed from V-1676B.
Also a leak was noted on valve V-2831, N2 to accumulators, but no action was taken to secure the leak.
G~ ICommonweslth
c ~
At 0630, test personnel entered the duct work to the purge supply and exhaust valves.
Excessive leakage was observed at both ends of the actuator pin for the supply valve and the seal area of the exhaust valve.
d.
At 0840, the decision was made to adjust the purge supply and exhaust valves for minimum leakage.
Following these adjustments the recording of official Integrated Leakage Rate Test data was resumed.
e.
At approximately 2200 a leak was found on the B Steam Generator blowdown samp'le line.
It was determined that this line had been disconnected inside containment for work being performed on the Steam Generators prior to the ILRT.
This line was eventually capped to prevent any further leakage.
f.
Prom 0900 on April 30, 1982 until 0545 on May 1,
- 1982, an excessive leakage rate of between 0.168 and 0.187X/day was indicated by the data collected.
During this time a search for possible leakage paths was conducted by all test personnel but only minor leaks were discovered.
At 0830 on May 1, 1982 a meeting was held with the plant superintendent and test personnel to discuss a possible solution.
Due to the extensive work being, performed on the Steam Generators just prior to the leak rate test it was thought that the maj or source of leakage could be into the Steam Generators.
A decision was made to pressurize the Steam Generators to a pressure approximately equal to that of the containment.
Subsequent to the
- meeting, the following sequence of events took place:
a.
At 1000 on May 1, 1982 recording of test data was resumed to establish a base line weight of the containment air prior to pressurizing the B Steam Generator.
G1beet /Commonwealth
18 b.
At approximately 1200, pressurization of the B Steam Generator was initiated.
Test data taken during and after pressurization indicated no change in the reactor containment leakage rate.
c.
At 2030 the A Steam Generator was pressurized to 35 psig.
This also showed no decrease in the containment leakage rate.
d.
At 0015 on May 2,
- 1982, a survey of the test data was performed.
At this time it was found that the Texas Instrument precision pressure gauges had drifted apart from each other by approximately 0.6 psi.
Two leak rate calculations were performed at this time using PI-3A and PI-3B independently rather than averaging the two.
A large discrepancy between the two leak rates existed.
To prove the validity of one of the Texas Instrument precision pressure gauges the following actions were taken:
1)
At 0645 a controlled leakage was established thru rotameter FI-2A to verify which pressure gauge was corresponding correctly to the changes in containment atmospheric conditions.
2)
After 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of controlled leakage data had been collected, it was determined that neither pressure instrument was responding properly to the increase in containment leakage.
3)
At 1400, both Texas Instruments pressure gauges were disconnected and preparations for changing out the bourdon capsules were made.
After the capsules were replaced, several tests were performed to determine the validity of the newly installed capsules.
4)
From 1520 til 2140 the reactor containment building was depressurized to approximately 12 psig so an inspection team could enter-to inspect the containment and Steam Generators.
Nothing unusual was found.
Gilbert ICbmmOnwCa! th
e.
At 1130 on May 3, 1982, pressurization of the reactor containment building was initiated.
By 1659, the containment internal pressure was 35.6 psig and all air compressors were secured.
f.
At 1700, 30 minute frequency test data collection was initiated and by 2100, the containment atmospheric conditions were determined to be stable.
g.
Following the sequence of events mentioned
- above, 15 minute frequency test data collection was initiated and an acceptable leakage rate of 0.0076X/day with an associated 95 percent confidence interval of 0.0054 percent by weight per day was obtained from 2100 on May 3, 1982 to 2100 on May 4, 1982.
6.3.3 Su lemental Leaka e Rate Test Phase After the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> integrated leak rate test data was obtained and evaluated, the leakage rate found to be acceptable and a release permit had been obtained, a known leak rate was imposed at 2100 on r
May 4,
- 1982, on the reactor containment building through a
calibrated flowmeter for a period of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
With an imposed leak
-rate of 0.1170X per day a measured composite leakage rate of 0.1113%
per day was obtained.
This results in a containment building leakage rate agreement within 8.7X of L with the results of the t
24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test> well within the acceptance limit of 25 percent of L 6.3.4 De ressurization Phase After all required data was obtained and evaluated, the supplemental test results were considered to be acceptable, and permission from the health physics department was obtained, depressurization of the reactor containment building was started.
A post test inspection of the building revealed no unusual findings.
&Ibett/CommonweaIth
0
20 I
Subsequent to the ILRT, maintenance was performed on the purge supply and.exhaust valves, resulting in the replacement of the valve seats.
Both valves were then tested using local leakage rate methods.
The results were a leakage rate of 96 sccm for purge supply valve AOV-5869 and 6409 sccm for purge exhaust valve AOV-5879.
The total leakage of 6505 sccm is equivalent to 0.0067X/day, which must be added to the ILRT results.
Therefore, the measured leakage rate is 0.0143%/day and the leakage rate at the upper bound of the 95 percent confidence interval is 0.0197X/day.
7.0'ETHODS OF ANALYSIS The absolute method of leakage rate determination was employed during testing at the 35 psig pressure level.
The Rochester Gas and Electric Company computer code calculates the percent per day leakage rate using the mass point method of data analysis.
The mass point method of computing leakage rates uses the following ideal gas law equation to calculate the weight of air inside containment for each fifteen minute interval:
144 PV KP W=
RT T
- where, W = mass of air inside containment, ibm ibm -
R - in.
0 2
K = 144 V/R = 2.6182 x 10 lbf P
= partial pressure of air, psia 0
T = average internal-containment temperature, R
v = 9.7 x 105 ft3 Gd~ /Commonwealth
The partial pressure of air, P, is calculated as follows:
p=p-p T
wv
- where, PT = True corrected pressure by averaging PI-3A and PI-3B, psia P
= partial pressure of water vapor determined by averaging the six dewpoint temperatures and converting to vapor pressuie with the use of steam tables, psia.
The average internal containment temperature, T, is calculated as follows:
T =
sum of 24 RTD's
+ 459 69 24 The weight of air is plotted versus time for the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test and for the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> supplemental test.
The Rochester Gas and Electric
'ompany computer code fits the locus of these points to a straight line using a linear least squares fit.
In addition the computer code also computes the upper bound of the 95X confidence interval.
8.0 DISCUSSION OF RESULTS 8.1 RESULTS AT Pt The method used in calculating the mass point leakage rate is defined in Section 7.0.
The results of this calculation is a mass point leakage rate of 0.0076X/day.
The local leakage rate of the purge supply and exhaust valves, as discussed in Section 6.3.5 must be added to the results.
In addition, the local leakage rate of the instrumentation valves which were in service during the ILRT must also be considered.
The combined leakage rate of valves MV-7448, GitberL /Commonwealth
22 7452 and 7456 is 0.000003X per day.
The addition of this negligible value does not change the results of the integrated leakage rate test.
The 95 percent confidence interval associated with this leakage rate is 0.0054 percent per day.
- Thus, the leakage rate at the upper bound of the 95 percent confidence interval becomes L
= 0.0076
+ 0.0067
+ 0.0054 tm Lt
= 0.0197X/day 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 0.1146 percent per day (0.75 L ).
Therefore, t
reactor containment building leakage at 35 psig (P ) is considered acceptable.
8.2 SUPPLEMENTAL TEST RESULTS After conclusion of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test at 35 psig, flowmeter FI-2A was placed in service and a flow rate, corrected for pressure and temperature conditions of 2.784 SCFM was established.
This flow rate is equivalent to a leakage rate of 0.117 percent per day.
After the flow was established, it'as not altered for the duration of the supplemental test.
The measured leakage rate (L ) during the supplemental test was c
calculated to be 0.1113 percent per day using the mass point method of analysis.
The 95 percent confidence interval associated with this leakage rate is 0.0218 percent per day.
Qbert ICommonwea! th
23 The building leakage rate during the supplemental test is then determined as follows:
Lv' Lc Lo L
0.1113%/day 0.117%/day v
L '
-0 0057%/day v
Comparing this leakage rate with the building leakage rate during the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test yields the following:
tm v
0'0076 0'0057 0 0869 L
0.153 The building leakage rates agree within 8.7 percent of L which is below the acceptance criteria of 25 percent of L Using the formulation of ANS 56.8 1981, (L
+ L 0.25 L )
< L (L + L
+ 0.25 L )
(0.117
+ 0.0076 0.0383)
L (0.117
+ 0.0076
+ 0.0383) 0.0863 L
0.1629 Since L
was measured to be 0.1113 percent per day, this value falls c
within the acceptable range 0.0863 to 0.1629 percent per day.
Therefore, the acceptability of the test instrumentation is considered to have been verified.
Qben ICommonweslth
24 8.3 SCHEDULE FOR RETESTING The thorough examination of the containment penetration boundaries revealed no structural deterioration or abnormalities other than the leaking purge supply and exhaust dampers.
All remaining portions of the containment were found to be in good repair.
After the identified leaks were repaired and problems with the Texas Instrument pressure gauges were corrected, the containment leakage rate was well within the allowable value.
Both of the penetrations which exhibited excessive leakage are periodically retested.
Therefore, the next periodic Type A retest is proposed to be performed in approximately four years.
9.0 TYPE B AND C LEAKAGE RATE HISTORIES 9.1 DISCUSSION OF LEAKAGE HISTORY For the years
- 1979, 1980, 1981 and 1982 all Class "B" and "C" testing was performed during the reactor shutdowns for refueling.
The shutdown for 1979 was from February 9 to April 3, the 1980 shutdown was from March 28 to May 23 and the 1981 shutdown was from April 17 to June 20.
The shutdown for 1982 was from January 25 to May 26 because of a steam generator tube rupture.
All local Type B and C tests wer'e performed at 60 psig.
The acceptance criteria for the test periods of 1979,
- 1980, 1981, per plant technical specifications 4.4.2.2 was that total leakage from all penetrations and isolation valves not exceed 0.60 La.
(Equivalent to 22,930 cc/min.).
Qbcrt
/Commonwealth
0
25 The 1982 leakage tests were performed with a leak rate monitor instead of rotameters as in previous tests.
The criteria of technical specification 4.4.2.2 was adhered to.
Tabulation of the leakage rate results during the
- 1979, 1980, and 1981 teting periods indicates that the acceptance criterion was not exceeded.
The following is a summary of the total leakage tabulated during the reporting period of 1979,
- 1980, and 1981:
HIGHEST KNOWN LEAKAGE DURING TEST YEAR CLASS B
348.43 CLASS C
4267.89 TOTAL 4616.32 1979 KNOWN LEAKAGE AS OF YEAR END 298.79 1276.42 1575.21 1980 HIGHEST KNOWN LEAKAGE DURING TEST YEAR CLASS B
899.242 CLASS C
3725.80 TOTAL 4625.042 KNOWN LEAKAGE AS OF YEAR END 790.94 1752.75 2543.69 1981 HIGHEST KNOWN LEAKAGE DURING TEST YEAR CLASS B
1071.9085 CLASS C
3756.881 TOTAL 4828.7895 KNOWN LEAKAGE AS OF YEAR END 910.8859 1016.424 1927.3099 Gitoete /Commonwealth
26 Tabulation of the leakage rate results during the 1982 testing period indicates that the acceptance criterion was exceeded prior to repairs.
The following is a summary of the total leakage tabulated during the test period.
- 1982, HIGHEST KNOWN LEAKAGE DURING TEST YEAR CLASS B
3155.234 CLASS C
307809.15 TOTAL 310964.384 KNOWN LEAKAGE AS END OF ILRT 3155.234 5946.71 9101.944 The excessive leakage during this test period was attributed to check valve
- 1599, purge exhaust valve 5878 and purge supply valve 5870.
A new check valve (1599) was installed prior to the test and the seats replaced on the purge supply and exhaust valves, after the ILRT.
A Licensee Event Report (LER 82-11) was submitted regarding check, I valve 1599.
Check valve 1599 was subsequently replaced in November 1982 with an AOV to give greater assurance of proper valve operability.
Penetration and manifold leakage histories since the Integrated Leak Rate Test in 1978 are given in Appendix E.
A description of the isolation valves for each test with the corresponding penetration number is contained in Appendix F.
Qbert
/Commonweal&
27
10.0 REFERENCES
1)
RSSP 6.0, 6.1, 6.2 and 6.3, "Containment Integrated Leakage Rate Test Procedure" 2)
Code of Federal Regulations, Title 10, Part 50, Appendix J, (1-1-82).
3)
ANSI N45.4 1972, "Leakage Rate Testing of Containment Structures for Nuclear Reactors,"
American Nuclear Society, (March 16, 1972).
4)
Steam Tables, American Society of Mechanical Engineers, (1967).
5)
Rochester Gas and Electric Corporation Computer Code.
6)
ANS 56.8 1981a N274, "Containment System Leakage Testing Requirements,"
American Nuclear Society, (February 19, 1981)
~
7)
"Rochester Gas and Electric Corporation" Reactor Containment Building Integrated Leak Rate Test, R.E. Ginna Nuclear Power
- Plant, (March 1978).
Githete ICommonwealth
APPENDICES Grfbert /Commonwealth
APPENDIX A SCHEMATIC ARRANGEMENT OF TEST INSTRUMENTATION Q~ /CofMenweblth
TEST INSTRUMENTS TAG NUMBERS DEWPOINT TEMPERATURE DPTE-1 THRU 6 ELEV. 330'E TE TE TE TE TE DRYBULB TEMPERATURE CONTAINMENT PRESSURE SUPERIMPOSED FLOW TE-1 THRU 24 PI-3A
& 38 FI-2A & 28 ELEV.
301'LEV.286'E TE TE Tl DP TE DP PI 3A PI 38 Q
ChO M
H O
M Fl H0 ELEV. 261'E TE TE TE TE TE ELEV.
243'LEV.235'E TE DP TE TE TE TE FI-2A FI-28
APPENDIX B REDUCED TEST DATA
Time Partial Pressure of Containment Air ( sia)
APPENDIX B REDUCED TEST DATA Average.
Containment Temperature (oR)
Sheet 1 of 6 Weight of Containment Air (1bm) 5/3/82 5/4/82 2100 2115 2130 2145 2200 2215 2230 2245 2300 2315 2330 2345 2400 0015 0030 0045 0100 0115 0130 0145 0200 50.430 50.425 50.420 50.422 50.423 50.419 50.418 50.422 50.424 50.425 50.427 50.421 50.426 50.425 50.426 50.426 50.417 50.414 50.417 50.420 50.419 514-50 514.44 514.43 514.45 514.43 514.41 514.37 514.42 514.43 514.46 514.45 514.45 514.45 514.47 514.50 514.51 514.42 514.39 514.37 514.42 514.43 256,630 256,635 256,617 256,615 256,631 256,616 256,635 256,628 256,630 256,622 256,635 256,609 256,632 256,618 256,610 256,604 256,603 256,602 256,628 256)618 256,605
e
APPE B (Cont 'd)
REDUCED TEST DATA Sheet 6
Partial Pressure of Containment Air ( sia)
Average Containment Temperature (oR)
Weight of Containment Air ( ibm) 0215 0230 0245 0300 0315 0330 0345 0400 0415 0430 0445 0500 0515 0530 0545 0600 0615 0630 0645 0700 0715 0730 0745 0800 50.422 50.422 50.422 50.419 50.416 50.417 50.415 50 '15 50.415 50 '14 50.413 50.413 50.412 50.415 50.416 50.416 50.413 50.405 50.407 50.410 50.416 50.410 50.412 50.415 514.43 514.44 514.46 514.42 514.41 514.41 514.41 514.40 514.37 514.37 514.35 514.34 514.38 514.39 514.41 514.42 514.38 514.33 514.30 514.35 514.38 514.38 514.34 514.37 256,627 256,620 256,607 256,617 256,605 256,607 256,598 256,602 256,615 2561612 256,616 256,620 256,602 256,610 256,605 256,600 256,601 256,583 256)614 256,604 256,620 256)588 256,617 256,619
APPE B (Cont'd)
REDU TEST DATA Sheet Time Partial Pressure of Containment Air ( sia)
Average Containment Temperature (oR)
Weight of Containment Air (ibm) 0815 0830 0845 0900 0915 0930 0945 1000 1015 1030 1045 1100 1115 1130 1145 1200 1215 1230 1245 1300 1315 1330 1345 50.413 50.417 50.417 50.418 50.427 50.433 50.438 50.442 50.445 50.437 50.425 50.427 50.426 50.426 50.422 50.427 50.437 50.449 50.450 50.458 50.467 50.467 50.470 514.36 514.40 514.37 514.38 514.49 514.52 514.60 514.65 514.65 514.65 514.51 514.45 514.47 514.49 514.46 514.51 514.63 514.69 514.71 514.77 514.88 514.88 514.89 256,616 256,615 256,628 256,631 256,620 256,636 256,624 256,615 256,627 256,589 256,598 256,643 256,626 256,612 256,611 256,605 256,603 256,631 256,628 256,637 256)624 256,627 256,640
APPE B (Cont'd)
REDU TEST DATA Sheet 6
Time Partial Pressure of Containment Air ( sia)
Average Containment Temperature (oR)
Weight of Containment Air (1bm) 1400 1415 1430 1445 1500 1515 1530 1545 1600 1615 1630 1645 1700 1715 1730 1745 1800 1815 1830 1845 1900 1915 1930 50.465 50.463 50.453 50.440 50.427 50.416 50.410 50.399 50.395 50.393 50.418 50.435 50.410 50.401 50.401 50.404 50.406 50.410 50.411 50.409 50.410 50.413 50.415 514.91 514.86 514.82 514.70 514.64 514.42 514.42 514.30 514.23 514.12 514.32 514.55 514.48 514.27 514.21 514.24 514.25 514.27 514.32 514.35 514.30 514.35 514.37 256,603 256,618 256,583 256,577 256,540 256,597 256,569 256,570 256,584 256,631 256,655 256,632 256,540 256,597 256,625 256,628 256,632 256,640 256)623 256,598 256,628 256,618 256,621
I)
APPE 8 (Cont 'd)
REDUC TEST DATA Sheet 6
Time Partial Pressure of Cont a inmen t Air ( sia)
Average Containment Temperature (oR Weight of Containment Air (ibm) 1945 2000 2015 2030 2045 2100 50.417 50.420 50.416 50.415 50.414 50.417 514.48 514.52 514.45 514.45 514.43 514.44 256,575 256,571 256,583 256,575 256,579 256,595 SUPERlMPOSED TEST 5/5/82 2115 2130 2145 2200 2215 2230 2245 2300 2315 2330 2345 2400 0015 0030 0045 50.420 50.417 50.413 50.411 50.416 50.416 50.418 50.421 50.417 50.414 50.431 50.424 50.407 50.400 50.400 514.48 514.51 514.45 514.43 514.46 514.50 514.55 514.55 514.51 514.52 514.64 514.61 514.46 514.42 514.37 256,584 256,561 256,566 256,568 256,578 256,560 256,547 256,561 256,557 256,541 256,568 256,547 256,529 256,516 256,542
APPE B (Cont 'd)
REDU TEST DATA Sheet Time Partial Pressure of Containment Air ( sia)
Average Containment Temperature (oR)
Weight of Containment Air (ibm) 0100 0115 0130 0145 0200 0215 0230 0245 0300 0315 50.416 50.419 50.419 50.419 50.417 50.414 50.412 50.409 50.409 50.406 514.54 514.56 514.60 514.58 514-57 514.57 514.55 514.54 514.52 514.52 256,538 256,541 256,524 256,532 256,526 256,513 256,514 256,504 256,515 256,496
APPENDIX C
WEIGHT OF CONTAINMENT AIR AND'VERAGE CONTAINMENT TEMPERATURE VERSUS TIME Gilbert /Commonwealth
I J
Arrf3(VIXC WFICI(T Of COt(TAIttttf3(T AIR AN(t AVKRACK CONTAINttft(T TKt(PKRATVRK VKRSUS Tltlf.
256>675 I.FAST SQVARFS FIT KqVATION W ~ 256,621-.8It 256,625 256,575
~
~
~ ~ ~
~ ~
~
~
~
~
~
~ \\ ~
~ 0 ~
~
~
~ ~ ~
~
~
~
~
~
~ ~
~
4
~
~
~ 0
~ ~
~ ~
~ ~
~
~
~ e ~
~
~
~ ~
256,525 24 IIOVR INTFSRATFD I.FA(( RATf. TFST 515.00 514i.75 514.50 514.25 514.00
~ ~ ~ ~
~ ~
~ ~
~ ~ ~ ~
~ ~ ~ ~ ~
~
~ ~
~
~ ~
~ ~
~
~ ~ ~ ~ ~ o ~ ~
~
'> ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~
~
~ ~
~
~
~ ~
~
~ ~
~
~ ~ ~ ~
~
~ ~
~
~ ~
~ ~ ~
0 2100 5/3/82 2
3 Ai 5
6 7
8 9
10 II 12 13 lhi Tlttf (t(OURS) 15 16 17 18 19 20 21 22 23 24 2 100 5/4/82
APPE C
WEIGNT OF CONTAINHENT AIR AND AVERAGE CONTAINHENT TEHPERATURE VERSUS TINE 256,600 M
0 H
~ g 256,550 N r 0 P~
M M 43 ~
256,500 O
C3 256,450
~
~
6 HOUR SUPERIHPOSED LEAK RATE TEST LEAST SQUARES FIT EQUATION M=256,577-11.89t
~
~
~
~
r4 Kz WO r ~
0 C (3
Q 4l teal 514 '0 514.60 514.50 514.40 514.30
~
0
~
0
~
~
~
~
~
~
0 2115 5/4/82 TIME (llOURS) 6 0315 5/5/82
APPENDIX D COMPUTER PRINTOUT Qbert /Commonwealth
APPENDIX D COMPUTER PRINTOUT R.E.
GINNA ILRT TEST 2100 5/3/82 -THRU 2100 5/4/82 LEAST SQUARES RESULTS. BASED ON 97 DATA POINTS THE LEAST SQUARES SLOPE OF THE WEIGHT LINE IS -.8118 LBS.
PER HOUR.
N THE INTERCEPT OF THE LINEAR LEAST SQUARES FIT OF THE WEIGHTS IS 256,621 LBS.
THE LINEAR LEAST SQUARES WEIGHT 24 HOURS INTO THE TEST IS 256,602 LBS.
LEAST SQUARES SLOPE OF WEIGHT LINE:.0076%/DAY.
THE 95 0
CONFIDENCE BARS IS
~ 0054%
PER DAY~
~.THE 95.0 CONFIDENCE BAR IS.5821 LBS PER HR.
WITH 95.0 CONFIDENCE, THE MASS CHANGE RATE IS BETWEEN -.0130 AND -.0021%
PER DAY WITH 95.0 CONFIDENCE, THE MASS CHANGE RATE IS BETWEEN -1.3939 AND -.2297 LBS.
PER HOUR.
t R.E.
GINNA SUPERIMPOSED ILRT 2115 5/4/82 THRU 0315 5/5/82 LEAST SQUARES RESULTS BASED ON 25 DATA POINTS.
THE LEAST SQUARES SLOPE OF THE WEIGHT LINE IS -11.8939 LBS.
PER HOUR.
THE INTERCEPT OF THE LINEAR LEAST SQUARES FIT OF THE WEIGHTS IS 256,577 LBS.
THE LINEAR LEAST SQUARES WEIGHT 6 HOURS INTO THE TEST IS 256)505 LBS.
LEAST SQUARES SLOPE OF WEIGHT LINE.1113%/DAY.
THE 95.0 CONFIDENCE BAR IS.0218%
PER DAY.
APPENDIX D (Cont '
)
COMPUTER PRINTOUT THE 95.0 CONFIDENCE BAR IS 2.3353 LBS.
PER HOUR WITH 95.0 CONFIDENCE)
THE MASS CHANGE RATE IS BETWEEN.1331 AND.0894'ER DAY WITH 95.0 CONFIDENCE, THE MASS CHANGE RATE IS BETWEEN -14.2292 AND -9.5586 LBS.
PER HOUR.
APPENDIX E
'SOLATION VALVE LEAKAGE RATE Gilbert /Commonweal&
APPENDIX E ISOLATION VALVE LEAKAGE RATE (cc/min. at 60 psig)
TEST PERIOD:
1979 OUTAGE Page 1 of 20 PRIMARY ISOLATION BOUNDARY SECONDARY ISOLATION BOUNDARY TEST NO.
VALVE NO.
OR BOUNDARY AS FOUND LEAKAGE RATE cc/min.
AS LEFT LEAKAGE RATE cc/min.
VALVE NO.
OR BOUNDARY AS FOUND LEAKAGE RATE cc/min.
AS LEFT LEAKAGE RATE cc/min.
9A 9B 10 12A 12B 12C 13A 13B 14 15 16A 16B 17A 539 528 529 371 370B 304A 304B 383B 313 966A 966B 966C 5735 5736 1599 1597 5738 5737 PT-945 PT-946 2.03 1.09 1.09 1.09 1.09 Not Determined 26.57 1.09 2.01 2.01 2.01 2.01 1.08 1.08 1.09 2.03 1.09 1.09 1.09 1.09 145 26.57 1.09 2.01 2.01 2.01 2.01 1.08 1.08 1.09 508 1598 1.09 1.09
APPEND (Cont'd)
Page 2 o 0
PRIMARY ISOLATION BOUNDARY SECONDARY-ISOLATION BOUNDARY TEST NO.
17B 17C 18A 18B 19 20 21 22 23 24 26 27 VALVE NO.
OR BOUNDARY PT-947 PT-948 PT-944 PT-949 PT-950 864A 862A 862B 889A 889B 870A 870B 879 1787 1713 1789 1721 1728 813 814 750A 750B AS FOUND LEAKAGE RATE cc/min.
1.09
- 2. 01 2.01 2.02 2.02 2.03 2.03 2.03 1.09 1.09 1.09 1.09 1.09 AS LEFT LEAKAGE RATE cc/min.
1.09 2.01 2.01 2.02 2.02 2.03 2.03 2.03 1.09 1.09 1.09 1.09 1.09 VALVE NO-OR BOUNDARY 1786 1003A 1003B 1723 AS FOUND LEAKAGE RATE cc/min.
2.03 0.54 0.54
- 1. 09 AS LEFT LEAKAGE RATE cc/min.
2.03 0.54 0.54 1.09
APPEND (Cont'd)
Page 3
20 PRIMARY ISOLATION BOUNDARY SECONDARY ISOLATION BOUNDARY TEST NO.
VALVE NO.
OR BOUNDARY AS FOUND LEAKAGE RATE cc/min.
AS LEFT LEAKAGE RATE cc/min.
VALVE OR BOUNDARY AS FOUND LEAKAGE RATE cc/min.
AS LEFT LEAKAGE RATE cc/min.
28 29 30 32 33 34 35 36 37 38 39 40 42 43 44 4SA 759A 759B 743 745 5393 7226 7970 5870 5878 8419 6151 6175 B.F.'.F.
B.F.
3 Separate Lines with 1.09 1.09 1.09 1.09 1.08 1.08 1.0 399.25 226.8 19.1 130 1.09 1.09 1.09 1.09 1.08 1.08 1.0 399.25 226.8
'19.1 1.08 1.08 5392 7971 5869 5879 4757 4758 4635 4636 8418 7444 7443 7445 1.08 1.0 3.94 2.25 2.38 2.38 1.08 1.0 3.94 2.
25'.38 2.38 Tubing Cap 0
on each
APPENDIX E (Cont'd)
Page 4 of 20 PRIMARY ISOLATION BOUNDARY SECONDARY ISOLATION BOUNDARY TEST NO ~
VALVE NO ~
OR BOUNDARY AS FOUND LEAKAGE RATE cc/min.
AS LEFT LEAKAGE RATE cc/min.
VALVE OR BOUNDARY AS FOUND LEAKAGE RATE.
cc/min.
AS LEFT LEAKAGE RATE cc/min.
46 846 48 Tubing Cap 49 Pipe Cap 50A 1554 1557 1560 1.09 2.01 1.09 1.09 1.09 1.09
- 2. 01 1.09 1.09 1.09 549A 193.5
- 2. 38 50B 50C 1563 1566 1569 1572 1.08 1.01 1.09 1.09 1.08 1.01 1.09 1.09 51A 1076A 1084A 1.08 1.08 IV-3A IV-5A 9.35 1.08 9.35 1.08 51B 51C 1076B 1084B 1080A IV-3B IV-5B IV-2A IV-2B 1.0 1.0 1.0 1.0
APPENDIX E (Cont'd)
Page 5 of 20 Pressure decay tests performed in 1979 subsequent to the value listed for Test No.
35 on the containment purge supply dampers are as follows.
3-24-79 5-15-79 8-1 11-15-79.
12-14-79 12-18-79 231.1 cc/min.
128.42 cc/min.
129.33 cc/min.
19.26 cc/min.
474.14 cc/min.
32.14 cc/min.
Pressure decay tests performed in 1979 subsequent to the value listed for Test No.
36 on the Containment purge exhaust dampers are as follows:
3-24-79 5-15-79 8-1-79 11-15-79 12-14-79 12-18-79 227.51 cc/min.
163.8 cc/min.
163.96 cc/min.
-56.17 cc/min.
1336.16 cc/min.
326.97 cc/min.
APPE DIX E ISOLATION VALVE LEAKAGE RATE (cc/min. at 60 psig)
TEST PERIOD:
1980 OUTAGE Page 6
o 20 PRIMARY ISOLATION BOUNDARY SECONDARY ISOLATION BOUNDARY TEST NO.
- VALVE NO.
OR BOUNDARY AS FOUND LEAKAGE RATE cc/min.
AS LEFT LEAKAGE RATE cc/min.
VALVE NO.
OR BOUNDARY AS FOUND LEAKAGE RATE cc/min.
AS LEFT LEAKAGE RATE cc/min.
1 539 2
528 3
529 7
371 8
3708 9A 304A 9B 304B 10 383B 11 313 0.4 1.45 1.45 1.46 1.45 1.45 1.45 1.45 1.45 0.4 1.45 1.45 1.46 1.45 1.45 1.45 1.45 1.45 508 0.4 0.4 12A 12B 12C 13A 13B 14 15 16A 16B 17A 966A 966B 966C 5735 5736 1599 1597 5738 5737 PT-945 PT-946 0.4 0.4 1.45 0.4 0.4 1.45 1.45 139.38 1294.26 1.45 0.4 0.4 1.45 0.4 0.4 1.45 1.45 139.38 1.45 1598 1.45 1.45
APPENDI E (Cont'd)
Page 7 o 20 PRIHARY ISOLATION BOUNDARY SECONDARY ISOLATION BOUNDARY TEST NO.
VALVE NO.
OR BOUNDARY AS FOUND LEAKAGE RATE cc/min.
AS LEFT LEAKAGE RATE cc/min.
VALVE NO.
OR BOUNDARY AS FOUND LEAKAGE RATE cc/min.
AS LEFT LEAKAGE RATE cc/min.
17B 17C 18A 18B 19 20 21 PT-947 PT-948 PT-944 PT-949 PT-950 864A 862A 862B 889A 889B 870A 870B 879 1787 1713 1789 1.45 1.45 0.39 0.39 0.39 0.39 0'9 0.39 0.39 0.39 0.4 1.45 1.45 0.39 0.39 0.39 0.39 0.39 0.39 0.39 0.39 0.4 1786 0.39 0.39 22 1721 23 1728 24 813 814 1.45 1.45 1.46 1.46 1.45 1.45 1.46 1.46 1003A 1003B 1723 0.725 0.725 1.45 0.725 0.725 1.45 26 750A 1.45 1.46
APPEN (Cont'd)
Page 8
0 PRIMARY ISOLATION BOUNDARY SECONDARY ISOLATION BOUNDARY TEST NO.
VALVE NO.
OR BOUNDARY AS FOUND LEAKAGE RATE cc/min.
AS LEFT LEAKAGE RATE cc/min.
VALVE NO.
OR BOUNDARY AS FOUND LEAKAGE RATE cc/min.
AS LEFT LEAKAGE RATE cc/min.
27 28 29 30 32 33 34 35 36 37 38 39 40 42 43 44 45A 7508 759A 759B 743 745 5393 7226 7970 5870 5878 8419 6151 6175 B.F.
B.F.
B.F.
3 Separate Lines with Tubing Cap on each 1.45 1.45 1.45 1.45 1.45 2.24 2.24 0.2 47.3 241. 1 2.24 1.45 1.45 2.22 2.22 2'2 1.45 1.45 1.45 1.45 1.45 2.24 2.24 0.2 47.3 241.1 2.24 1.45 1.45 2.22 2.22 2.22 5392 7971 5869 5879 4757 4758 4635 4636 8418 7444 7443 7445 54.23 0.2 0
7.94 0.41 2.24 2.25 2.25 54.23 0.2 7.94 0.41 2.24 2.25 2.25
APPENDI (Cont'd)
Page 9 o PRIMARY ISOLATION BOUNDARY SECONDARY ISOLATION BOUNDARY TEST NO ~
VALVE NO.
OR BOUNDARY AS FOUND LEAKAGE RATE cc/min.
AS LEFT LEAKAGE RATE cc/min.
VALVE NO ~
OR BOUNDARY AS FOUND LEAKAGE RATE cc/min.
AS LEFT LEAKAGE RATE cc/min.
46 48 49 50A 50B 50C 51A 51B 51C 52 846 Tubing Cap Pipe Cap 1554 1557 1560 1563 1566 1569 1572 1076A 1084A 1076B 1084B 1080A 9229 1.45
- 2. 22 0.39 1.45 1.45 1.45 1.45 1.45 1.45 1.45 1.44 1.44 1
~ 45 1.45 1.45 17.5 1.45
- 2. 22 0.39 1.45 1.45 1.45 1.45 1.45 1.45 1.45 1.44 1.44 1.45 1.45 1.45 17.5 IV-3A IV-5A IV-3B IV-5B IV-2A IV-2B 9227 1.44 1.44 1.45 1.45 0.72 0.72 17.5 1.44 1.44 1.45 1.45 j
0.72 0.72 17.5
APPENDIX E (Cont d)
Page 10 o
20 Pressure decay tests performed in 1980 subsequent to the value listed for Test No.
35 on the containment purge supply dampers are as follows:
5-5-80 11-20-80 419.28 cc/min.
481.82 cc/min.
Pressure decay tests performed in 1980 subsequent to the value listed for Test No.
36 on the Containment purge exhaust dampers are as follows:
5-5-80 11-20-80 259.6 cc/min.
648 cc/min.
~ h
APPENDIX E ISOLATION VALVE LEAKAGE RATE (cc/min. at 60 psig)
TEST PERIOD:
1981 OUTAGE Page 11 of 20 PRIMARY ISOLATION BOUNDARY SECONDARY ISOLATION BOUNDARY TEST NO.
VALVE NO.
OR BOUNDARY AS FOUND LEAKAGE RATE cc/min.
AS LEFT LEAKAGE RATE cc/min.
VALVE NO.
OR BOUNDARY AS FOUND LEAKAGE RATE cc/min.
AS LEFT
.LEAKAGE RATE cc/min.
10 12A 12B 12C 13A 13B 14 15 16A 16B 17A 539 528 529 371 3708 304A 3048 383B 313 966A 966B 966C 5735 5736 1599 1597 5738 5737 PT-945 PT-946 1.417 28.68 0.41 1659.02 0-0 1.417 28.68 0.41 508 956C 956A 9568 1598 1596 0.41 2.5 0.41 0.41 1.42 0
0.41 2.5 0.41 0.41 1.42
APPENDIX E (Cont'd)
Page 12 of 20 PRIMARY ISOLATION BOUNDARY SECONDARY ISOLATION BOUNDARY TEST NO.
VALVE NO.
OR BOUNDARY AS FOUND LEAKAGE RATE cc/min.
AS LEFT LEAKAGE RATE cc/min.
VALVE NO.
OR BOUNDARY AS LEFT LEAKAGE RATE cc/min.
17B 17C 18A 18B 19 20 21 22 23 24 26 PT-947 PT-948 PT-944 PT-949 PT-950 864A 862A 862B 889A 889B 870A 870B 879 1787 17-13 1789 1721 1728 813 814 750A 2.24 0.41 32.54 0.26 0.41 0.41 r
0 1.4 1.4 1.417 2.24 0.41 32.54 0.26 0.41 0.41 1.4 1.4 1.417 1786 1003A 1003B 1723 1.4 1.4 1.41 1.4 1.4 1.41
APPEN (Cont'd)
Page 1
20 PRIMARY ISOLATION BOUNDARY SECONDARY ISOLATION BOUNDARY TEST
'NO.
VALVE NO.
OR BOUNDARY AS FOUND LEAKAGE RATE cc/min.
AS LEFT LEAKAGE RATE cc/min.
VALVE NO.
OR BOUNDARY AS FOUND LEAKAGE RATE cc/min.
AS LEFT LEAKAGE RATE cc/min.
27 28 29 30 32 33 34 35 36 37 38 39 40 42 43 44 45A 750B 759A 759B 743 745 5393 7226 7970 5870 5878 8419 6151 6175 B.F.
B.F.
B.F.
3 Separate Lines with Tubing Cap on each 1.4 1.4 94.82 214.85 1.4 1.42 1.32 1.4 1.4 94.82 214.85 1.4 1.42 1.32 5392 7141 7971 5869 5879 4757 4758 4635 4636 8418 7444 7443 7445 5.5 1.31 0.41 0.41 0.41 1.4 1.32 0
1.32 5.5 1.31 0.41 0.41 0.41 1.4 1.32 1.32
APPENDI
~ (Cont'd)
Page 14 0
PRIMARY ISOLATION BOUNDARY SECONDARY ISOLATION BOUNDARY TEST NO.
VALVE NO-OR BOUNDARY AS FOUND LEAKAGE RATE cc/min.
AS LEFT LEAKAGE RATE cc/min.
VALVE NO ~
OR BOUNDARY AS FOUND LEAKAGE RATE cc/min.
AS LEFT LEAKAGE RATE cc/min.
46 48 49 50A 50B 50C 846 Tubing Cap Pipe Cap 1554 1557 1560 1563 1566 1569 1572 15.4 1.42 1.4 1.4 0
15.4 1.42 1.4 1.4 51B 51C 1076B 1084B 1080A 52 9229 51A 1076A 1084A 0
1.4 1.4 IV-3A IV-5A IV-3B IV-5B IV-2A IV-2B 9227 1.43 35.52 1.41 10.88 0.2 0.2 1.4 1.43 1.31 1.41 10.88 0.2 0.2 1.4
APPENDIX E (Cont'd)
Page 15 of 20 Pressure decay tests performed in 1981 subsequent to the value listed for Test No.
35 on the containment purge supply dampers are as follows:
5-16-81 8-19-81 11-18-81 394.61 cc/min.
264.547 cc/min.
173.59 cc/min.
Pressure decay tests performed in 1981 subsequent to the value listed for Test No.
36 on the Containment purge exhaust dampers are as follows:
5-16-81 8-19-81 11-18-81 331.8 cc/min.
90.48 cc/min.
361.73 cc/min.
APP IX E ISOLATION VALVE LEAKAGE RATE (cc/min. at 60 psig)
'EST PERIOD:
1982 OUTAGE page 16 20 PRIHARY ISOLATION BOUNDARY SECONDARY ISOLATION BOUNDARY TEST NO.
VALVE NO.
OR BOUNDARY AS FOUND LEAKAGE RATE cc/min.
AS LEFT LEAKAGE RATE cc/min.
VALVE NO.
OR BOUNDARY AS FOUND LEAKAGE RATE cc/min.
AS LEFT LEAKAGE RATE cc/min.
539 528 529 371 8
370B 9A 304A 9B 304B 10 383B 11 313 12A 12B 966A 966B 12C 966C 13A 5735 13B 5736 14 *
~
1599 15 1597 16A 5738 16B 5737 17A PT-945 0.18
- 0. 69 2556.12
~
15.3 4.53 1.413 1.413 Unmeasurable 0.2 7.9 0.18 0.69 304-87 15.3 4.53 15.89 1.37 0.3 0.2 546 547 508 820 204A 956F 956E 956D 5733 5734 1598 1596 5701 5702 1819A 1.413 1.413 1.2 0.45 2.76 1.97 0.3 551.2 94.5 7.9 0.12 0.2 1.2 0.45 2.76 1-97 0.3 551.2 631.71 0.19
- Refer to Section 9.1 (page
- 26) for explanation
APPEND (Cont'd)
Page 17 0
PRIMARY ISOLATION BOUNDARY SECONDARY ISOLATION BOUNDARY TEST NO.
VALVE NO ~
" BOUNDARY AS FOUND LEAKAGF.
RATE cc/min.
AS LEFT LEAKAGE RATE cc/min.
VALVE NO.
OR BOUNDARY AS FOUND LEAKAGE RATE cc/min.
AS LEFT LEAKAGE RATE cc/min.
17B 17C 18A 18B*
19 20 21 22 23 24 26 PT-946 PT-947 PT-948 PT-944 PT-949 PT-950 862A 862B 889A 889B 870A 870B 879 1787 1713 1789 1721 1728 813 814 750A 7.9 1.57 Unmeasurable 0.39 98.15 3.93 2.47 2.0 0.99 1.57 0.4 0.39 98.15 3.93 2.0 0.99 1819B 1819C 1819D 1819E 1819F 1819G 1786 1655 1003A 1003B 1723 749A 7.9
~ 0 432.26 432.26 3.0 0.19 432.26 432.26 3.0
- Valve would not seat.
Valve was disassembled,
- cleaned, reassembled and tested satisfactorily.
APPENDIX E (Cont'd)
Page 18 o
20 PRIHARY ISOLATION BOUNDARY SECONDARY ISOLATION BOUNDARY TEST NO.
VALVE NO.
OR'OUNDARY AS FOUND LEAKAGE RATE cc/min.
AS LEFT LEAKAGE RATE cc/min.
VALVE NO.
OR BOUNDARY AS FOUND LEAKAGE RATE cc/min.
AS LEFT LEAKAGE RATE cc/min.
27 28 29 30 32 33 34 35 36*
37 38 39 40 750B 759A 759B 743 745 5393 7226 7970 5870 5878 8419 6151 6175 40.27 0
'2.32 15,593.4 244,141.7 9.5 5.0 40.27 158.55 741.32 9.5 5.0 749B 5392 7141 7971 5869 5879 4757 4758 4635 4636 8418 6165 6152 316 353 353 39.22 316 353 353 0
42 B.F.
43 B.F.
44 B.F.
Q ~ 98>'r -*
1.57 7444 7443 7445 4.53 Pm Qw PA
- Pefer to Section 9.1 (page 26) for explanation
- ~ Post ILRT value
APPEND (Cont'd)
Page 19 0
PRIMARY ISOLATION BOUNDARY SECONDARY ISOLATION BOUNDARY TEST NO ~
VALVE NO ~
OR BOUNDARY AS FOUND LEAKAGE RATE cc/min.
AS LEFT LEAKAGE RATE cc/min.
VALVE NO.
OR BOUNDARY AS FOUND LEAKAGE RATE cc/min.
AS LEFT LEAKAGE RATE cc/min.
45A 46*
49 50A 50B 50C 51A 51B 51C 52 3 Separate Lines with Tubing Cap on each 846 Pipe Cap 1554 1557 1560 1563 1566 1569 1572 1076A 1084A 1076B 1084B 1080A 9229 1.34 1.34 1.34 1.34 Unmeasurable 0.55 0.3 0.4 0.39 0.39 0.4 0.6 2.5 1.34 1.34 1.34 1.34 10 0.55 0 '
0.4 0.39 0.39 0.4 0.6 2.5 8623 5129 1556 1559 1562 1565 1568 1571 1574 IV-3A IV-5A IV-3B IV-5B IV-2A IV-2B 9227 Unmeasurable 3.53 0
- 0. 39 0.49 5.96 556.5 8.3 0.9 0.4 43.66 16.92 3.53 0'9 0.49 5.96 38.03 8.3 0.9 0.4 43.66
- Valves could not be tested because downstream boundary valve 8624 was leaking.
After 8624 was replaced the Containment Isolation valves were tested satisfactorily.
APPENDIX E (Co d)
.Pag'e 20 of Following the 1982 Integrated Leak Rate Test the purge supply and exhaust valves were retested
. with the following results:
Purge Supply:
5-5-82 5-19-82 88.45 cc/min. Post ILRT 19.16 cc/min. Post Maintenance Purge Exhaust:
5-5-82 5-6-82 5-17-82 5-19-82 39,759 cc/min. Post ILRT 193.83 cc/min. Post Maintenance 646.6 cc/min.
New Seats 1261.7 cc/min. Post Maintenance
APPENDIX E (Cont'd)
TYPE B PENETRATION MANIFOLD DESIGNATION AND LEAKAGE RATES l
NOTE:
Where applicable, significant leakage comments follow test data listing for manifold and/or penetrations.
MANIFOLD A Penetrations Included:
Date Tested:
2/20/79 11/5/79 4/7/80 4/29/81 3/15/82 MANIFOLD B Penetrations Included:
Date Tested:
2/20/79 4/3/80 4/29/81 3/15/82 MANIFOLD C Penetrations Included:
Date Tested:
2/20/79 4/3/80 4/30/81 3/8/82
'otal Volume 21.88 ft..3 312)
- 309, 332, 310, '317,
- 318, 321,
- 322, 306,
- 316, 319, 304 and 313 Leakage Rate cc/min. (at 60 psig) 2.39 1.20 7.19 3.208 0
Total Volume 25.24 ft.3 323 )
324
~
325
~
326 )
336
~
320 )
315
~
307
~
305~
- 311, 308, 303 and 301 Leakage Rate cc/min. (at 60 psig) 2.08 0
0 0
Total Volume 45.92 ft."
- 300, 401 and 403 Leakage Rate cc/min. (at 60 psig) 0 14.13 58.16 6.97
APPENDIX E (Cont'd)
TYPE B PENETRATION MANIFOLD DESIGNATION AND LEAKAGE RATES MANIFOLD D Penetrations Included:
Date Tested:
5/10/79 11/6/79 3/26/80 9/26/80 4/1/81 9/23/81 5/21/82 MANIFOLD E Penetrations Included:
Date Tested:
2/20/79 4/7/80 4/30/81 3/16/82 MANIFOLD F Penetrations Included:
Date Tested:
2/20/79 4/15/80 4/30/81 3/9/82 MANIFOLD G Penetrations Included:
Date Tested:
2/20/79 11/5/79 4/15/80 4/30/81 3/9/82 Total Volume 636 ft.3 Personnel Hatch Personnel Access Lock Leakage Rate cc/min. (at 60 psig) 148.95 183.57 0
283. 6 297.3935 300.63 2440.1 Total Volume 37.67 ft.3
- 202, 203,
- 209, 201,
- 204, 210,
- 206, 205 and 207 Leakage Rate cc/min. (at 60 psig) 1.13 0
17.92 2.56 Total Volume 7.4 ft.3
- 119, 129,
- 123, 133 Leakage Rate cc/min. (at 60 psig) 0 1.58 0
0 Total Volume 15.25 ft. 3
- 120, 121,
- 124, 125,
- 126, 127)
- 128, 130,
- 131, and 132 Leakage Rate cc/min. (at 60 psig) 12.26 3.8 1.33 0
1.004
T
APPENDIX E (Cont'd)
TYPE B PENETRATION MANIFOLD DESIGNATION AND LEAKAGE RATES MANIFOLD H Penetrations Included:
Date Tested:
2/20/79 ll/15/79 4/15/80 5/1/81 3/15/82 MANIFOLD I Penetrations Included:
Date Tested; 5/11/79 11/8/79 3/27/80 10/1/80 4/2/81 9/24/81 5/20/82 MANIFOLD J Penetrations Included:
Date Tested:
2/20/79 11/15/79 4/15/80 5/1/81 3/15/82 MANIFOLD K Penetrations Included:
Date Tested:
2/20/79 4/15/80 5/1/81 3/15/82 Total Volume 29.31 ft'3 402) 404 Leakage'Rate cc/min. (at 60 psig) 3.10 5.65 0
0 0
Total Volume 1065 ft.3 Equipment Hatch Personnel Access Lock Leakage Rate cc/min. (at 60 psig)
-118.98
-151.09 108.7742 121.8
-136.3709 184.2079 413.47 Total Volume 22.22 ft.3 102)
- 111, 101,
- 113, 118~
105) 109) 99~
103 and 107 Leakage Rate cc/min. (at 60 psig) 1.92 0
1'3 0
3.5 Total Volume 20.88 ft.3
- 104, 106,
- 108, 110,
- 112, 100 and 140 Leakage Rate cc/min. (at 60 psig) 1.80 7.92 0
12.75
0
APPENDIX E (Cont'd)
TYPE B PENETRATION MANIFOLD DESIGNATION AND LEAKAGE RATES MANIFOLD L Penetrations Included:
Date Tested:
3/15/79 4/21/80 6/12/81 4/16/82 Total Volume 3 ft.3 29, 141) 142) 143 Leakage Rate cc/min. (at 60 psig) 4.36 5.8 5.64 1.28 FUEL TRANSFER TUBE Date Tested:
3/19/79 5/1/80 6/12/81 4/1/82 MANIFOLD:
ELECTRICAL 1 Penetrations Included:
Date Tested:
2/19/79 4/3/80 5/1/81 3/16/82 Leakage Rate cc/min. (at 60 psig) 1.08 1.45 32'5
- 5.94 Total Volume 102 ft.3 CE 1) 2)
- 3) 4) 5) 6)
7) 8)
9)
- 10) ll) 12) 13) 14) 15) 16) 17) 18) 19) 20) 21 ) 22) 23) 24) 25) 27) 29) 30) 31 ) 32) 33) 34 Leakage Rate cc/min. (at 60 psig) 212.99 281.90 278.58 221.9 MANIFOLD:
ELECTRICAL 2 Penetrations Included:
Date Tested:
2/19/79 4/7/80 5/2/81 3/16/82 Total Volume 15 ft. 3 BE-l, 2, 3, 4
Leakage Rate cc/min. (at 60 psig) 0 0
2.8 0
- NOTE:
THE INITIALLEAKAGE WAS BEYOND THE RANGE OF THE ROTAMETER.
ATTEMPTS MERE MADE TO TIGHTEN FLANGE BOLTS, BUT LEAK RATE COULD NOT BE REDUCED TO AN ACCEPTABLE LEVEL UNTIL GASKET WAS REPLACED.
APPENDIX E (Cont'd)
TYPE B PENETRATION MANIFOLD DESIGNATION AND LEAKAGE RATES MANIFOLD:
ELECTRICAL 3 Penetrations Included:
Date Tested:
2/22/79 4/15/80 5/2/81 3/10/82 Total Volume 36 ft.3 AE-l, 2, 3, 4, 5, 6, 7, 8,
9, 10, 11,.
12, 13 and 14 Leakage Rate cc/min. (at 60 psig) 32.22 62.22 27.49 45.76
APPENDIX F ISOLATION VALVE DESCRIPTIONS
APPENDIX F DESCRIPTION OF ISOLATION VALVES Page 1 of 3 TEST NO.
DESCRIPTION/IDENTIFICATION PENETRATION NO ~
9A 9B 10 12A 12B 12C i~A 13B 14 15 16A 16B 17A 17B 17C 18A 18B 19 PRT to Gas Analyzer Nitrogen to PRT Makeup to PRT Letdown to Non-Regen HX Charging Line to "B" Loop "A" RCP Seal Water Inlet "B" RCP Seal Water Inlet Alternate Charging to "A" Cold Leg RCP Seal Rt. and Excess Letdown Pressurizer Steam Space Sample Pressurizer Liquid Space Sample Hot Leg Loop Sample "A" S/G Sample "B" S/G Sample Radiation Monitors R-ll, R-12 6 R-10A Outlet Radiation Monitors R-ll, R-12 6 R-10A Inlet "A" S/G Blowdown "B" S/G Blowdown C.V. Press.
Trans.
PT-945 6 PT-946 C.V. Press.
Trans.
PT-947 6 PT-948 C.V. Press.
Trans.
PT-944, PT-949
& PT-950 Containment Spray Pump 1A "Containment Spray Pump 1B S.I.
Pumps 1A and 1B Discharge and S.I. Test Line RCDT to Vent Header RCDT to Gas Analyzer RCDT Pump Suction 120 121 121 112 100 106 110 102 108 207 206 205 206 207 305 305 321 322 121 203 322 105 109
)Ol, 113 11'0 129 123 143
Ig gr i 4
APPENDIX F (Cont'd)
Page 2 of 3 NO ~
DESCRIPTION/IDENTIFICATION PENETRATION NO.
23 24 26 27 28 29 30 32 33 34 36 39 40 42 43 44 45A 46 49 50A 50B 50C 51A Sump to Waste Holdup Tank CCW to Reactor Support Cooling CCW to Reactor Support Cooling CCW to lA RCP CCW to 1B RCP CCW from lA RCP CCW from 1B RCP Excess Letdown HX Supply
& Return Instrument Air to Containment Service Air to Containment Depressurization at Power Purge Supply Purge Exhaust Reactor Compt. Cooling Units Reactor Compt. Cooling Units DW to Containment Aux Steam to and from Containment Leakage Test Depressurization Leakage Test Supply Leakage Test Depressurization Leakage Test and Hydrogen Monitors Instrument Lines Nitrogen to Accumulators Construction Fire Service Post Accident Air Sample (Containment)
Post Accident Air Sample to "B" Fan Post Accident Air Sample to "C" Fan "A" Hydrogen Recombiner (pilot and main) 107 130 131 127 128 126 125 124 310 310 132 204 300
- 201, 209
- 201, 209 324
- 301, 303 313 317 309 332 120 103 305 203 124 304
I
APPENDIX F (Cont'd)
Page 3 of 3 TEST NO.
DESCRIPTION/IDENTIFICATION PENETRATION NO.
51B 51C 52 "B" Hydrogen Recombiner (pilot and main)
Oxygen Makeup to Recombiners Fire Service Water 202 210 307
~
L