ML19308A288
| ML19308A288 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 03/06/1979 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML19289D588 | List: |
| References | |
| NUDOCS 7903080299 | |
| Download: ML19308A288 (75) | |
Text
REACTOR CONTAl!@iENT BUILDIl0 INTEGRATED LEAK RATE TEST TYPE A, B, AND C PERIODIC TESTS FOR JANUARY 1976 'IO NOVEMBER 1978 POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 7003 080 ot99
TABLE OF CONTENTS Section Title Page I
PURPOSE.
I-1 II SUMHARY.
II-1 II 1 TYPE A TEST II-1 II.1.1 Test Procadure.
II-1 II.1.2 Conclusio s II-2 II.2 LOCAL LEAK RATE TESTS (TYPE B AND C).
II-2 III TYPE A TEST.
III-1 PART A - EDITED LOG OF EVENTS.
III.A-1 PART B - GENERAL TEST DESCRIPTION.
III.B-1 Item 1.
Prerequisites.
III.B-1 Item 2.
Equipment and Instrumentation.
III.B-2 Item 3.
Data Acquisition System.
III.B-3 Item 4.
Data Resolution System.
III.B-4 PART C - DETAILED TEST ANALYSIS.
III.C-1 PART D - TEST RESULTS.
III.D-1
........ IV-1 IV LOCAL LEAK RATE TESTS (TYPE B AND C).
ii
LIST OF ATTACHMENTS Attachment Title II.1 Summary of Test Conditions II 2 Primary Containment Integrated Leak Rate Test (PCILRT)
B1.1 Instrument Location Verification Data Summary B1.2 Site Meteorology B2.1 Temporary Piping Leak Rate Analyzer (LRA)
System No. 16-1 B2.2 Permanent Piping Leak Rate Analyzer (LRA)
System No. 16-1 B2.3 Instrumentation B2.4 LRA System No. 16-1, ILRT Temperature Detector Locations D2.5 LRA System No. 16-1, ILRT Moisture Detector Locations C.1 Primary Containment Integrated Leak Rate Test (PCILRT) from 2000 on 11-26-78 to 2200 on 11-27 Page 1
of Run 1 C.2 Primary Containment Integrated Leak Rate Test (PCILRT) from 2000 on 11-26-78 to 2200 cn 11-27 Page 2
of Run 1 C.3 Primary Containment Integrated Leak Rate Test (PCILRT) from 2000 on 11-26-78 to 2200 on 11-27 Page 3
of Run 1 C.4 Primary Containment Integrated Leak Rate Test (PCILRT) from 2000 on 11-26-78 to 2200 on 11-27 Page 4
of Run 1 C.S Primary Containment Integrated Leak Rate Test (PCILRT) from 2000 on 11-26-78 to 2200 on 11-27 Run 1
with RTD Corrections Factors Added - Page 1 of Run 2 C.6 Primary Containment Integrated Leak Rate Test (PCILRT) frem 2000 on 11-26-78 to 2200 on 11-27 Run 1
with RTD Corrections Factors Added - Page 2 of Run 2 iii
LIST OF A'ITACHMENTS (Cont)
Attachment Title C.7 Primary Containment Integrated Leak Rate Test (PCILRT) f rom 2000 on 11-26-78 to 2200 on.11-27 Run 1
with RTD Corrections Factors Added - Page 3 of Run 2 C.8 Primary Containment Integrated Leak Rate Test (PCILRT) from 2000 on 11-26-78 to 2200 on 11-27 Run 1
with RTD Corrections Factors Added - Page 4 of Run 2 C9 Summary of RTD Corrections C.10 Graph 1 - Containment Leak Rate and UCL vs Time C.11 Graph 2 - Containment Air Mass vs Time C.12 Graph 3 - Drywell Average Temperature vs Time C.13 Graph 4 - Drywell Pressure vs Time C.14 Graph 5 - Drywell Vapor Pressure vs Time C.15 Graph 6 - Torus Average Temperature vs Time C.16 Graph 7 - Torus Pressure vs Time C.17 Graph 8 - Torus Vapor Pressure vs Time D.1 Type C
Penetration Leakage to be Added to Calculated PCILRT Leak Rate IV.1 1978 Type B and C Data Summary IV.2 1977 Type B and C Data Summary IV.3 1976 Type B and C Data Summary iv
SECTION I PURPOSE The purpose of this report is to present an analysis and interpretation of the November 1978 Type A test and a summary of the last three periodic Type B and C tests performed at the James A. FitzPatrick Nuclear Power Plant (JAFNPP) between January 1976 and November 1978.
JAFNPP is owned and operated by the Power Authority of the State of New York (PASNY).
This report is submitted as required by 10CFRSO, Appendix J, Paragraph V.B, dated February 14, 1973.
I-1
SECTION II
SUMMARY
II.1 Type A Test II.1.1 Test Procedure Pressurization for the Primary Containment Integrated Leak Rate Test (PCILRT) began at 1236 on 11/24/78.
At 1320, pressurization was temporarily discontinued due to an inadvertent engineered safeguards actuation; it was found that one lead on each of the drywell pressure switches (10 PS-101A, 10 PS-101B, 10 PS-101C, and 10 PS-101D) had not been lifted, causing core spray systen actuation.
Pressurization was resumed at approximately 1445 and test pressure (Pa) was established at 2210 (11/24/78).
During the pressurization period extensive checks were made for leakage.
Several valve packing leaks were found.
The main leakage paths which were isolated were the Traverse In-Core Probe (TIP) System "D" ball check valve and the reactor recirculation pump seal mini purge lines.
The PCILRT was initiated at 0300 on 11/25/78.
After several hours it was determined that the acceptance criterion of 0.375 percent / day would appear to be exceeded (IAna
=
0.545 percent / day).
An extensive search for leakage was made be tween 0600 on 11/25/78 and 0800 on 11/26/78.
The major source of leakage seemed to be through a partially open valve in the torus fill line from the Condensate Storage Tank (CST) and the "A" main steam line isolation valves.
The torus fill valve was
- closed, and an " air plug" was established between the main steam isolation valves (MSIVs) on the "A"
- Also, during this
- period, the RHR System was started in the shutdown cooling mode.
During shutdown cooling, the containment leak rate was more than twice the original value of the leak rate before shutdown cooling.
One possible explanation for the increase in leak rate during shutdown cooling operation is that air was being aspirated from the containment through 10-MOV-18.
The reason for this supposition is as follows:
a)
There is a body-to-bonnet leak on 10-MOV-18.
b)
Air bubbles existed with samples taken on the RHR System during this period.
At 0800 on 11/26/78 it appeared that the leak rate had reduced to a level where the PCILRT could be continued.
The containment was repressurized to test pressure (Pa) and shutdown cooling was restarted to prevent reactor coolant temperature from exceeding 2120F during the test.
At this time, the " air plug", which was preventing leakage through the "A"
- MSIVs, was still intact.
After several hours of stabilization, it was decided to remove this " air plug" to determine the actual effect on the leak rate.
It appeared that approximately 4 pounds mass / hour was leaking II-1
through the "A" MSIVs, which ccutributed to an unacceptable leak rate.
The effect was later verified during local leak rate testing of the "A" main steam line MSIVs.
The " air plug" was re-established to provide an acceptable leak rate.
The PCILRT test period was continued at 2000 on 11/26/78 and completed at 2200 on 11/27/78.
The calculated leak
- rate, including the upper 95 percent confidence level, i.e.,
the upper confidence limit (UCL),
was established at 0.298 percent / day.
The overall integrated leak
- rate, which included all Type C penalties, equalled 0.336 percent / day.
The verification test was successfully completed at 0100 on 11/28/78.
II.1.2 Conclusions Attachment II.1 summarizes plant conditions during the entire test.
Attachment II.2 is a plot of containment air mass versus time for the period starting 1600 on 11/24/78 and ending 1800 on 11/28/78.
The following conclusions are made relative to this plot and other conditions noted at the time of the test:
a)
The PCILRT results during the period of 0300 to 1200 on 11/25/78 would have been acceptable (1) if an acceptance limit of 0.5 percent / day, which is the limit defined in Section 3.7 of the current JAFNPP Technical Specifications, were used rather than a
limit of 0.375 percent / day, and (2) if the " air plug" were in the "A" main steam line.
b)
The RHR System provides a
significant containment leakage path while operating in the shutdown cooling mode, possibly through the bonnet of MOV-18.
Since this leakage path will not exist during an
- accident, the actual leak rate is much less than the final reported leak rate of 0.336 percent / day.
c)
Leakage of water from the torus to the CST via the torus fill line provided approximately 0.1 to 0.15 percent / day.
7.I. 2 Local Leak Rate Tests (Type B and C) ihe program of Local Leak Rate Testing (LLRT) of containment isolation valves and other primary containment penetrations on a
surt ' 411ance basis os initiated in January 1976 as required by 10CRF50, Appendix J, and plant Technical Specifications.
The tests are accomplished by the methods described in plant surveillance procedure it. F-ST-39B Type "B"
and "C"
LLRT of Containment Penetrations.
Section IV of this report summarizes the data for the three surveillance periods (1976,
- 1977, and 1978) of LLRTs performed since the last Type A test in accordance with Appendix J to 10CFR50, Section V.3.
II-2
ATTACHMENT II.1
SUMMARY
OF TEST CONDITIONS A.
Initial Test Period Plant Conditions:
a)
Shutdown cooling secured b)
No air block in steam line 0300-1200 c)
Torus fill line isolation valve 11/25/78 partially open d)
Reactor recirculation pump seal mini purges open Results:
Average leak rate was approximately 0.545 percent / day.
The leak rate was exceeding the procedure acceptance criterion of 0.375 percent / day.
It should be
- noted, however, that this test result would have been within the Technical Specification limit of 0.5 percent / day and the PCILRT would have been acceptable particularly if the " air plug" were established in the "A" main steam line as it was during the final test period.
B.
Investigation for Leakage Paths Plant Conditions:
a)
RHR System operating in shutdown cooling mode (significant increase 1400-11/25/78 in leak rate) to 0400-11/26/78 b)
Excessive water leak through SV-35A in RHR System c)
Fill valve to torus from the CST was found to be partially open and was then closed d)
"A" Main Steam line leaking noted and air block established Results:
Test conditions were very unstable and approximately 587 lb of air were lost in 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> (average leak rate
=
1.27 percent / day).
Major contributors to excessive leak rate appear to be RHR line in shutdown cooling, the torus fill valve, which was partially open, and the "A" MSIVs.
C.
Stable Conditions Plant Conditions:
a)
RHR shutdown cooling secured b)
Air block established between the 0400-0800 "A" MSIVs 11/26/78 c)
All torus to CST interconnecting lines verified closed 1 of 2
ATTACHMENT II.1 (Cont)
Results:
The average leak rate during this period was approximately 0.3 percent / day; the leak rate during the last 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> was less than approximately 0.03 percent / day (torus fill valve closed at 0430).
D.
Repressurization and Stabilization Plant Conditions:
a)
RHR operating in shutdown cooling mr '.e 0900-1500 b)
A*_r block established between the 11/26/78 "A" MSIVs Results:
There was a significant loss in air mass when the RHR System was started in shutdown cooling mode.
The leak rate stabilized at approximately 0.340 percent / day and was decreasing.
E.
Stabilization Period Plant Conditions:
a)
Removed the " air plug" that was between the "A" steam line isolation 1500-1900 valves 11/26/78 Results:
There was ein initial step drop in containment air mass and the leak rate appeared to stabilize at approximately 0.5 percent / day and was decreasing.
F.
Final Test Period Plant Conditions:
a)
The " air plug" was established in the "A" Main Steam line 2000-11/26/78 to 2200-11/27/78 Results:
The leak rate test was satisfactorily completed with UCL = 0.298 percent / day.
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SECTION III
'fYPE A TEST This section describes the Type A test in detail and is divided into four parts:
Tab Part Title A
A Edited Lug of Events B
B General Test Descriptions C
C Detailed Test Analysis D
D Test Results Part B, General Test Descriptions, is further sub-divided into four items, identified as follows:
Tab Item Title B1 1
Prerequisites B2 2
Equipment and Instrumentation B3 3
Data Acquisition System B4 4
Data Resolution III-1
PART A EDITED LOG OF EVENTS This log was edited from the PCILRT log, Shift Supervisor's log, and the Senior Nuclear Operator's (SNO) log.
November 24, 1978 Containment pressurization commenced at 1236 in accordance with surveillance procedure No. F-ST-39F entitled
" Type
'A' Test (60 psia}
Primary Containment Integrated Leak Rate Test."
Pressurization was discontinued at 1320 due to an inadvertent actuation of a portion of the engineered safeguards (core spray).
It was found that one lead on each of the drywell pressure switches (10-PS-101 A, 10-PS-101B, 10-PS-101C, and 10-PS-101D) had not been
- lifted, which caused core spray system actuation.
Pressurization was continued at 1445.
During pressurization accessible external areas of the drywell were inspected for possible leakage.
The test connection on the panecration X-26A was leaking.
Valves were improperly aligned and misalignment was corrected.
At
- 2213, with the drywell pressure at 60.4 psia pressurization, the equipment was isolated and secured.
The minimum 4-hour stabilization period began an1 leakage inspection continued.
November 25, 1978 Stabilization period continued.
The leakage was identified and secured from the Traversing In-Core Probe (TIP)
"D" ball check valve at 0100.
At 0300, the stabilization criterion was satisfied and the PCILRT was started.
At approximately
- 0500, it was determined that the procedure acceptance craterion of 0.375 percent / day would be exceeded and an extensive search for leakage paths was initiated.
Leakage Paths Located and Isolated 1.
At
- 1045, shut vents on penetrations X-31Ac (recirculation mini purge valse RWR-4 0A) and X-31Bc (recirculation mini purge valves RWR-40B and RWR-13B).
Minimal effect on leak rate was noted.
2.
Between 1650 and 2030, tightened packing on following valves:
27-AOV-113, 27-AOV-132A, 27-AOV-131A, 27-CNS-110A, 23-MOV-59, 13-MOV-27, 27-AOV-132B, III.7-1
16-1-SOV-102A, and 16-1-SOV-102B.
(This had no measurable effect on the leakaoe rate.)
At
- 1405, the "A" loop of RHR was placed in service for shutdown cooling.
During shutdown cooling operations, the leak rate increased by more than twice the original value.
At
- 1700, an
" air plug" was established between the inboard and outboard isolation valves in the "A" main steam line.
At 1955, secured RHR from shutdown cooling.
NOTE:
During total time period the torus water level was decreasing at a rate of 0.04 inch / hour.
November 26, 1978 At 0435 valve CND-102 (torus fill valve from the condensate storage tank) was found to be open a
full turn and was then closed.
At
- 0800, it appeared that the leak rate had been reduced to a point where the PCILRT could be restarted.
(Torus water level was constant.)
At 0850, repressurization of the drywell was completed.
At
- 0930, RHR was started in the shutdown cooling mode with a significant increase in the containment leak rate.
Between 0900 and 1500, the containment was allowed to stabilize with the " air plug" established between the isolation valves on the "A" main steam line.
At 1510, the " air plug" was removed from the "A" rain steam line and the leak rate allowed to stabilize.
The leak rate increased above the established acceptance criterion.
At 1945, the " air plug" was reestablished between the "A" MSIVs.
At 2000, PCILRT was continued.
November 27, 1978 At 2200, the PCILRT test period was determined completed.
Began preparation to pump back verification test.
At 2300, started pump back verification test.
At
- 2400, mass pump back completed with 4,102 scf of air pumped back into the containment as read on flow totalizer 16-1-FQT-101.
III.A-2
November 28, 1978 At
- 0100, the PCILRT and verification test were documented as complete.
Testing of penetrations for Type C penalties and depressurization of the containment commenced.
III.A-3
PART B GENERAL TEST DESCRIPTION Item 1.
Prerequisites In accordance with F-ST-39F, the following is a listing of the pertinent prerequisites completed and documented prior to pressurization:
a.
Required instrumentation calibrated and placed inservice.
b.
All Type B and Type C leak rate testing completed.
c.
Satisfactory inspection of accessible interior and exterior surfaces of the primary containment structures and components completed.
d.
Resistance Thermal Devices (RTDs) and Dewcell location survey completed ( Attachment B1.1).
e.
Temporary air compLessors and test skid ready for use as pressurization source.
f.
Two d rywell ventilation fans adjusted for continuous operation at test pressure (45 psig).
g.
All computer software used for test calculations tested and operational.
h.
Water levels recorded for the suppression pool, reactor vessel, drywell equipment sump, and drywell floor drain sump.
i.
Controlled area plan in ef fect.
j.
An official log of events ready to be maintained by the test director.
k.
Valves lined up in accordance with the valve tagout list.
1.
Site meteorology data taken 7 days prior to PCILRT and during test (Attachment B1.2).
III.B-1
ATTACHMENT B1.1 INSTRUMENT LOCATION VERIFICATION DATA
SUMMARY
Instrument Location Survey Location surveys were conducted to verify the appropriate location and/or weight factor associated with the temperature and dewpoint instrumentation.
All local readings were coordinated with the start of the plant computer 10-minute log.
The following is a
summary of the requirements of F-ST-39 F :
Temperature Each of the nine temperature zones were surveyed using thermometers.
A minimum of six temperature readings were taken in a
zone at 2-minute intervals during a 10-minute test period.
The thermometer readings were averaged and campared to the plant computer 10-minute averages for each RTD located in the applicable zone.
Thermometers were randomly located within easy access in the applicable zone but were not closer than 10 ft from each other or the zone RTDs.
Locations were acceptable if the average of the thermometer readings were within +2cF of the zone RTDs.
Thermometer RTD RTD
- Average, Average, (RTD)
- Average, (RTD)
Zone OF OF (Mark Number) 0F (Mark Number) 0 80.78 81.883 (101) 80.847 (120) 1 78.03 78.372 (102) 76.345 (119) 2 78.48 78.227 (103) 78.032 (104) 3 81.27 82.895 (105) 81.839 (106) 4 81.40 80.816 (107) 81.538 (108) 5 81.11 81.542 (109) 80.529 (117) 6 72.57 69.926 (110) 75.376 (111) 7 78.69 78.655 (112) 78.625 (118) 8 75.60 74.845 (113) 76.266 (114)
Dewcells Each of the three zones covered by the dewcells were surveyed similarly to the RTDs;
- however, the survey was made with a
portable EGSG dewpoint instrument, and the six readings were taken during a 30-minute period and compared with the plant computer average readings over the same period.
1 of 2
ATTACHMENT B1.1 (Cont)
The locations were acceptable if the average reading for the portable EGSG instrument and the computer averages were within
+50F.
EGSG Dewcell Dewcell
- Average, Average, OF Average, OF Zone OF (Comp. Pt.)
(Comp. Pt.)
A 67 66.4 (C234) 63.6 (C235) t Ar 67 64.3 (C234) 63.9 (235)
B 67 64.6 (C238) 63.7 (C239)
Be 67 64.5 (C238) 63.7 (C239)
C 73.5 74.3 (C242) 76.6 (C243)
C 74.5 75.4 (C242) 74.5 (78.4) 2 2 of 2
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Item 2.
Equipment and Instrumentation Pressurization of the containment was achieved by utilizing a temporary system consisting of four air compressors, reanifolded to an in-line water-cooled heat exchanger and a
moisture separator / cartridge filter (Attachment B2.1).
The total capacity of the air et
'essors was 3600 scfm.
The system included the necessary valving and instrumentation to maintain proper monitoring and operation.
The discharge of the uemporary system was routed to the primary containment via the drywell spray portion of the RHR System (Attachment B2.2).
The necessary variables required to calculate containment leakage during the test were monitored using a leakage monitoring system consisting of open pressure sensors, multiple RTDs and dewcells for both the drywell and torus.
The general location of the RTDs and dewcells including applicable test zones are shown in Attachments B2.4 and B2.5.
Flow instrumentation in the air supply system was used during the pump back verification test.
Pertinent data for the test instrumentation is listed in Attachment B2.3.
All test instrumentataon except that used for the pump back verification test is input to the plant computer for data acquisition and averaging.
III.B-2
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DEWCELL C2 DEWCELL Cl 235 55 AZ M TH POS T ONS AR A PRGX MATE ATTACHMENT 82.5 J.A. FITZPATRICK NUCLEAR POWER PLANT LR A SYSTEM NO.16-1,ILRT MOISTURE DETECTOR LOCATIONS DATE: NOV. 24,1978 TO NOV. 28,1978
Item 3.
Data Acquisition System The James A.
FitzPatrick plant computer system (PCS) performs reactor core calculations and provides the plant operator with current core operating data.
The PCS also scans, calculates, stores, logs, and alarms information which has been collected for the plant information.
The PCS analog scan package reads all the analog inputs in a pre-established manner, conver ts these readings into engineering units, and then stores these values into predefined locations f or use by the plant operators and by the plant application programs.
For the PCILRT, the function of the PCS is to provide sufficient sensor and zone pair information for manual entry into a
remote computer PCILRT calculation program via a terminal hookup.
The plant computer monitored the following instrumentation:
Type Scan Rate 18 RTDs 60 sec 6 Dewcells 60 sec 4 Absolute Manometers 60 sec The PCS PCILRT sensor programs converts binary-coded decimal digital information from each manometer to an analog
- value, calculates a 10-minute rolling average of each of the 28 sensors, and calculates a zone pair average and a
zone pair difference (see Attachments B2.4 and B2.5).
These data, along with the instantaneous sensor values, are logged on the utility typer every 10 minutes.
III.B-3
Item 4.
Data Resolution System After the appropriate data have been a cquired and averaged utilizing the plant computer system, the result is input to a
renote computer system for leak rate calculat' ens utilizing the Absolute Method.
Absolute Method The Absolute Method of leakage-rate testing consists of determining and calculating air losses by the containment structure over a minimum of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by means of direct pressure, temperature, and moisture content observations during the period of
- test, with the temperature detectors properly located to provide an average air temperature.
The absolute test consists of subtracting the final mass in the containment from the initial mass; the masses are computed using the ideal gas law.
The containment mass is computed as follows:
M=
(P-Pv) Vc RT where the rightmost identity has the units:
M
= lb gas P
= total pressure, psia Pv = vapor pressure, psia R
= 53.35 ft Ibf/lbm OR (for air)
T
= containment temperature, OR Vc = containment free volume, ft3 The leakage rate is then determined by plotting the nass as a function of time, using a least-s quare s fit to determine the
- slope, dq/dt.
The leak rate is expressed as fraction of contained mass lost per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or symbolically:
Leak rate = A * -2400 (III-1)
B where A
is the slope of the least-squares curve and B is the y-intercept.
The sign convention is such that an outward leak is positive and the units are in percent / day.
Correlation of Results There are two containments in the JAFNPP: torus (suppression chamber) and drywell.
The masses for each containment are computed separately, added together, and the result is correlated as a function of time by means of a least-squares-curve fit of form:
m = At + B III.B-4
The slope A and the y-intercept B are then used in Equation III-1 to determine the leak rate.
- Thus, the least-squares fit is executed only for the total mass in both containments, i.e.,
the masses of air in the torus and drywell are summed and the result is fitted against time.
A 95 percent " Student T" confidence level is associated with each leak rate computation.
The leak rate (in percent mass loss per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) may be described as 95 percent accurate to within the value of the printed confidence level.
III.B-5
PART C DETAILED TEST ANALYSIS The test data for the period of 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> on November 26, 1978, through 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on November 27, 1978, were analyzed for the final test results using Stone & Webster's LEAKFIT program and the Power Authority's PCILRT program.
The input data and results obtained by PCILRT are shown in Attachments Col through C.8.
Test Run 1 utilized 10-minute zone averages of absolute pressure, vapor pressure, and temperature data for the drywell and torus.
These averages were generated by the Plant Data Acquisition System.
Test Run 2 utilized Test Run 1 input data except for the temperature data.
Since operational degradation of the temperature instrumentation was not specifically addressed in the RTD calibration verification process, the NRC requested that a
correction factor be applied to the plant data acquisition temperature averages.
Correction factors shown in Attachment C.9 were developed from the data obtained during the in situ RTD location survey.
The comparison of results between Test Runs 1
and 2
show that the dif fer ence in leak rates and confidence levels is negligible.
This is as expected since the RTD correction is a systematic bias and systematic bias is generally considered to be negligible in the overall calculation.
See ANSI Draft Standard N274 (Rev. 3, November 15, 1978) Section 5.2.4 and Appendix G.
Regardless of the calculation method used, the resu) re well below the test procedure acceptance criteria of 0.375 p_
. ant / day including the Type C penalties for valves not vented to the containment during the test and the technical specification limit of 0.5 percent / day.
Eight
- graphs, obtained by LEAKFIT and shown in Attachments C.10 through C.17, are provided showing the following quantities versus time:
1.
Containment Leak Rate 2.
Containment Air Mass 3.
Drywell Average Temperature 4.
Drywell Pressure 5.
Drywell Vapor Pressure 6.
Torus Average Temperature III.C-1
7.
Torus Pressure 8.
Torus Vapor The leak rate and 95 percent confidence limit were calculated only for the test period shown.
The on-site computer calculations include data for the overall test duration which began on 11/24/78; also, Attachment II.2 of Section II of this report provides a
mass versus time plot for the complete test duration.
All leak rate calculations using the Stone
& Webster "LEAKFIT" program agreed to within 0.0004 percent / day of the on-site calculations using the PASNY program in conjunction with the GE Mark III computer terminal.
The leak rate test calculations were verified during the supplemental test which used the metered pump back test method.
Approximately 75 percent of the maximum allowable 24-hour leakage (La) was inserted into the containment within 1-hour elasped time.
The calculated reading using the PCILRT computer program was within u 25 La of the metered inrut.
Water level within the primary containment was monitored during the test period.
Although the Drywell Equipment Drain Sump was pumped approximately every 40 minutes during the test, there was no significant containment free volume change during the test.
The Drywell Equipment Drain Sump is approximately 55 cubic feet, which is less than 0.02 percent of the total containment free volume.
All other water levels remained relatively constant during the final test period.
This included the
- Torus, Reactor Coolant System, and the Drywell Floor Drain Sump.
Thete were no corrections to the overall integrated leak rate due to water level changes.
Based on the data gathered during the 0300 to 1200 test period on November 25, 1978, it is felt that an acceptable leakage rate would have been obtained if the A MSIV " air plug" had been established and if the current JAFNPP Technical Specification limit of 0.5 percent / day acceptance criterion had been used.
III.C-2
G ATTACHMENT C.1 PRIMARY CCNTAINMENT INTEGPATED LEAM PATE TEST PAGE 1 CF PUN 1 PASNY JAMES A FITZPATRICK NUCLEAR PCHER PLANT FRO?f 2000 CN 11-06-78 TO 2200 CN 11-07-78 LOG 1 - TEN HItRJTE ZONE AVEPAGES TIME ABSOULTE PRESS
TEMPERATURES------------------------------
--DEKPOINT TEMPS---
HRS ORY TCR ZONE 0 ZONE 1 ZCNE2 ZCNE3 ZONE 4 ZONES ZONE 6 ZONE 7 20NE8 ZONEA ZONE 8 ZCNEC 0.0 60.277 60.301 105.49 109.83 110.74 115.44 113.97 118.27 110.34 107.60 74.22 92.71 90.29 67.27 1.000 60.281 60.309 105.64 109.94 110.91 115.62 114.18 118.54 110.20 107.77 74.08 92.84 90.39 67.46 2.000 60.266 60.293 105.67 109.86 110.88 115.49 114.05 118.11 110.00 107.00 74.30 92.78 90.29 67.08 3.000 60.262 60.292 105.74 109.99 110.99 115.62 114.14 118.30 109.80 107.80 74.32 92.04 90.45 67.45 4.000 60.268 60.293 105.84 110.31 111.10 115.81 114.39 118.53 109.71 107.90 74.35 92.86 90.36 67.42 5.000 60.238 60.268 105.66 109.91 110.91 115.52 114.15 117.97 109.42 107.73 74.35 92.67 90.50 67.51 6.000 60.239 60.270 105.68 109.94 111.00 115.65 114.21 118.02 109.09 107.72 74.37 92.73 90.35 67.44 7.000 60.042 60.270 105.75 109.99 111.05 115.84 114.29 118.27 108.90 107.72 74.39 92.81 90.72 67.50 8.000 60.030 60.258 105.80 110.02 111.03 115.73 114.31 117.90 108.76 107.83 74.39 92.67 90.38 67.55 9.000 60.223 60.051 105.80 110.10 111.11 115.87 114.35 118.13 108.63 107.84 74.41 92.66 90.44 67.50 10.000 60.223 60.250 105.87 110.12 111.20 115.84 114.41 118.05 100.47 107.94 74.41 92.69 90.46 67.59 11.000 60.221 60.251 105.95 110.25 111.22 115.95 114.53 118.22 108.35 108.00 74.43 92.69 90.43 67.70 12.000 60.219 60.250 106.01 110.31 111.36 116.09 114.59 118.36 106.35 107.10 74.47 92.78 90.62 67.92 13.000 60.213 60.242 106.03 110.35 111.36 116.15 114.76 118.36 108.35 107.04 74.46 92.73 90.27 67.79 14.000 60.213 60.242 105.99 110.30 111.43 116.24 114.82 118.49 108.41 107.86 74.47 92.62 90.27 67.84 15.000 60.207 60.234 105.96 110.48 111.46 116.08 114.06 118.51 108.48 107.89 74.51 92.65 90.33 67.96 16.000 60.203 60.230 105.88 110.54 111.47 116.32 114.91 118.48 108.48 108.14 74.52 92.70 90.48 68.09 17.000 60.199 60.027 105.98 110.63 111.57 116.46 115.00 118.72 108.55 108.03 74.52 92.72 90.30 67.96 18.000 60.199 60.227 106.00 110.65 111.59 116.50 115.01 118.78 108.61 108.06 74.54 92.65 90.35 67.97 19.000 60.191 60.219 106.10 110.63 111.60 116.52 115.12 118.62 108.70 108.37 74.49 92.73 90.37 68.02 20.000 60.188 60.215 106.16 110.68 111.68 116.57 115.09 118.62 108.69 108.41 74.49 92.79 90.70 67.91 21.000 60.181 60.211 106.16 110.72 111.69 116.52 115.11 118.61 108.74 108.48 74.52 92.69 90.55 67.97 22.000 60.180 60.203 106.00 110.77 111.74 116.55 115.15 118.62 109.01 108.59 74.56 92.90 90.71 68.08 23.000 60.175 60.201 106.26 110;74 111.78 116.64 115.08 118.59 109.27 108.62 74.57 93.00 90.90 68.12 24.000 60.172 60.199 106.21 110.79 111.84 116.70 115.3u 118.71 109.47 108.53 74.56 93.05 90.8S 68.19 25.000 60.164 60.191 106.18 110.75 111.84 116.76 115.39 116.87 109.09 108.47 74.56 92.82 90.68 68.08 26.000 60.164 60.190 106.20 110.76 111.84 116.78 115.40 118.95 109.01 108.64 74.58 92.00 90.61 68.32 1 of 17
ATTACHMENT C.2 PRI!!ARY CCNTAIt2 TENT It4TEGRATED LEAH RATE TEST PAGE 2 CF PUN 1 PASNY JAttES A FITZPATRICH NUCLEAR PCKER PLANT FPCit 2000 Ott 11-26-78 TO 2200 ON 11-27-78 LCS2 - INPUT VARIADLES TIME
CRYHELL--------------
TOPUS----------------
HRS ABS PRESS VAP PRESS AES TEMP ABS PRESS VAP PRESS ABS TDtP PSIA PSIA DEGR PSIA PSIA DEGR 0.0 60.277 0.7316 570.92 60.301 0.3305 534.22 1.000 60.281 0.7343 571.07 60.309 0.3326 534.28 2.000 60.266 0.7324 570.99 60.293 0.3306 534.30 3.000 60.262 0.7350 571.07 60.292 0.3325 534.32 4.000 60.268 0.7342 571.23 60.293 0.3322 534.35 5.000 60.238 0.7336 570.96 60.268 0.3332 534.35 6.000 60.239 0.7326 571.00 60.270 0.3324 534.39 7.000 60.242 0.7377 571.06 60.270 0.3331 534.39 8.000 60.230 0.7322 571.03 60.258 0.3337 534.39 9.000 60.223 0.7328 571.09 60.251 0.3331 534.41 10.000 60.223 0.7334 57 f.13 60.250 0.3341 534.41 11.000 60.221 0.7330 571.19 60.251 0.3354 534.43 12.000 60.219 0.7362 571.23 60.250 0.3380 534.47 11.000 60.213 0.7316 571.25 60.242 0.3364 534.46 14.000 60.213 0.7304 571.34 60.242 0.3370 534.47 15.000 60.207 0.7314 571.39 60.234 0.3384 534.51 16.000 60.003 0.7337 571.41 60.230 0.3399 534.52 17.000 60.199 0.7319 571.52 60.227 0.3384 534.50 18.000 60.199 0.7316 571.55 60.227 0.3385 534.54 19.000 60.191 0.7328 571.57 60.219 0.3391 534.49 20.000 60.188 0.7373 571.62 60.215 0.3378 534.49 21.000 60.181 0.7344 571.64 60.011 0.3385 534.52 22.000 60.180 0.7386 571.70 60.203 0.3398 534.56 23.000 60.175 0.7420 571.75 60.201 0.3403 534.57 24.000 60.172 0.7423 571.80 60.199 0.3411 534.56 25.000 60.164 0.7374 571.78 60.191 0.3422 534.56 26.000 60.164 0.7363 571.80 40.190 0.3426 534.58 INITIALIZATION DRYHELL TORUS CONTROLS OUTPUT MDATA ABS PRESS 60.277 60.301 100 27 VAP PRESS 0.7316 0.3305 ABS 70tP 570.92 534.22 VOLUt!E 154476.
115800.
2 of 17
ATTACHMENT C.3 PR1!1ADY CONTAIN!!ENT INTEGUATED LEAM PATE TEST PAGE 3 OF RUN 1 PASNY JAMES A FITZPATRICH PCCLEAR PCHER PLANT FR0ff 2000 ON 11-06-78 TO 0000 ON 11-07-78 LOG 3 - ABSCULTE ttETHOD TEST RESULTS TIttE HASS OF AIR LEARRATE 95 PCT CONF UCL HOURS POUtiDS PCT / DAY PCT / DAY 0.0 78575.411 0.0 0.0 C.0 1.000 78564.906 0.0 0.0 0.0 0.000 78551.790 0.360731 0.167196 0.527907 3.000 78537.500 0.387481 0.071809 0.459310 4.000 73509.740 0.360757 0.054795 0.417551 5.000 78513.100 0.376306 0.03e501 0.4148S7 6.000 78510.789 0.348562 0.048176 0.396738 7.000 78504.114 0.304916 0.047767 0.372680 8.000 78494.451 0.311897 0.039967 0.351864 9.000 78478.916 0.314137 0.031069 0.345406 10.000 78474.804 0.306790 0.006832 0.333603 11.000 78467.439 0.299409 0.003959 0.303368 10.030 78456.037 0.096558 0.000333 0.316891 13.000 78450.074 0.091323 0.018455 0.309778 14.000 78443.418 0.085S75 0.017045 0.303100 15.000 78406.003 0.087506 0.015109 0.300615 16.000 78415.791 0.089036 0.013413 0.300649 17.000 78405.173 0.091066 0.01:064 0.303130 18.000 78401.857 0.089381 0.010934 0.300315 19.000 78391.578 0.088505 0.009854 0.098359 00.000 78380.707 0.088401 0.000081 0.097300 01.000 78372.057 0.088072 0.000056 0.096120 00.000 78355.378 0.090011 0.007769 0.097980 03.000 78343.182 0.090680 0.007693 0.300373 24.000 78336.143 0.093806 0.007004 0.301090 25.000 78330.017 0.093871 0.006634 0.300504 06.000 78307.580 0.090167 0.006456 0.098600 3 of 17
ATTACHMENT C.4 FRIttA9Y CO*4TAINMENT ItiTEGRATED LEAR RATE TEST PAGE 4 0F RUit 1 PASNY JAf:ES A FITZPATRICH F4UCLEAR PCliER PLANT FRCN 2000 CN 11-26-78 TO 2200 CN 11-27-78 LCG4 - Iti1TIALIZATICri AtID CO 4TRCL VARIALLES HEIGHTING FACTORS FOR TEl!PERATURE AND DEHPOItiT AVERAGING ZofiE0 ZCtfE1 ZCNE2 ZCNE3 ZCriE4 ZC!iE 5 ZONE 6 ZC*iE 7 ZCNE8 ZONEA ZONEB ZONEC 0.11351 0.16502 0.35604 0.13137 0.04701 0.05337 0.07153 0.06215 1.00000 0.50000 0.50000 1.00000 POLYNottIAL COEFFICENTS FOR VAPOR PRESSURE CCtNERSIO!4 0.919818D-14 0.172223D-10 0.1050150-08 0.349876D-06 0.1795850-04 0.112199D-02 0.2113970-01 STUDENT'S T CONSTANTS 1.95996 2.37226 2.82050 NITROGEN IN LEAHAGE OPTION I3 0FF 4 of 17
ATTACHMENT C.5 FRIMARY CONTAIUMENT INTEGRATED LEAM PATE TEST FAGE 1 CF RUM 0 PASNY JAMcS A FITZPATRICK NUCLEAR PCHER PLANT FFOM 0000 ON 11-06-78 TO C000 cN 11-07-78 RUM 1 HITH PTD CCPRECTICNS FACTCRS A0DED LOG 1 - TEN HINUTE ZONE AVERAGES TIME ABSCULTE FRESS
-.-----------------TEMPERATURES------------------------------
--C DPOINT TEIPS---
HPS CRY TCP ZONE 0 ZCNE1 ZCNEO ZONE 3 ZONL4 ZCtE5 ZONE 6 ZOSE7 ZCNE8 20hEA ZONEL ZONEC 0.0 60.277 60.301 104.91 310.50 110.98 114.34 114.00 118.34 110.17 107.65 74.07 92.71 90.09 67.07 1.000 60.081 60.309 105.05 110.60 111.15 114.52 114.41 118.61 110.00 107.80 74.30 90.64 90.39 67.46 0.000 60.066 60.093 105.08 110.53 111.12 114.39 114.27 118.19 109.83 107.8S 74.34 90.78 90.09 67.08 3.000 60.062 60.092 105.15 110.66 111.03 114.52 114.37 118.38 109.62 107.65 74.16 90.84 90.45 67.45 4.000 60.268 60.093 105.05 110.80 111.34 114.71 114.61 113.61 109.54 107.94 74.40 00.86 90.36 67.42 5.000 60.038 60.068 105.08 110.57 111.15 114.40 114.38 118.05 109.24 107.78 74.40 90.57 90.50 67.51 6.000 60.039 60.070 105.10 110.61 111.04 114.55 114.44 118.09 108.92 107.76 74.43 90.73 90.35 67.44 7.000 60.240 60.270 105.16 110.67 111.09 114.74 114.52 118.35 108.72 107.76 74.43 90.81 00.72 67.50 8.000 60.030 60.058 105.02 *10.69 111.27 114.63 114.53 118.98 108.58 107.8S 74.43 92.67 90.38 67.55 9.000 60.003 60.051 105.01 110.77 111.35 114.77 114.58 118.00 108.45 107.89 74.45 90.66 90.44 67.50 10.000 60.003 60.050 105.08 110.80 111.44 114.74 114.64 118.10 108.30 107.98 74.46 90.69 90.46 67.59 11.000 60.001 60.051 105.37 110.93 111.46 114.85 114.75 118.30 109.18 108.05 74.48 92.69 90.43 67.70 10.000 6 0. 219 6 0.050 10 5.43 110.9 G 111. 6 0 114.99 114.82 118.44 108.17 108.14 74.51 90.78 90.60 67.92 13.000 60.013 60.042 105.44 111.00 111.60 115.05 114.99 118.43 108.17 108.09 74.50 90.73 90.27 67.79 14.000 60.013 60.042 105.40 110.97 111.67 115.14 115.05 118.57 108.03 107.91 74.50 92.60 90.27 67.84 15.000 60.207 60.034 105.38 111.16 111.;0 115.18 115.0S 118.59 108.30 107.94 74.55 90.65 90.33 67.96 16.000 60.003 60.030 105.09 111.00 111.71 115.02 115.14 118.56 106.33 108.19 74.57 90.70 90.48 68.09 17.000 60.199 60.027 105.41 111.30 111.81 115.36 115.02 118.79 108.37 108.08 74.56 92.70 90.30 67.96 18.000 60.199 60.007 105.41 111.33 111.83 115.40 115.04 118.85 108.44 108.31 74.5S 92.65 90.35 67.97 19.000 60.191 60.219 105.50 111.30 111.84 115.40 115.34 118.70 108.53 103.30 74.54 92.73 90.37 68.02 00.000 60.188 60.015 105.57 111.35 113.91 115.47 115.3? 118.69 108.52 108.46 74.54 92.79 90.70 67.91 21.000 60.181 60.011 105.57 111.40 111.93 115.42 115.34 118.69 108.56 108.52 74.56 90.69 90.55 67.97 02.000 6 0.180 6 0. 003 105.61 111.45 111.98 115.45 115. 3 7 118.7C 108.84 108.63 74.60 90.90 90.71 68.08 23.000 60.175 60.001 105.67 111.42 112.02 115.54 115.50 118.46 109.07 103.67 74.6' 93.00 90.90 68.10 04.000 60.170 60.199 105.60 111.47 112.08 115.60 115.53 118.79 109.30 108.58 74.61 93.05 90.83 68.19 25.000 60.164 60.191 105.60 111.42 110.08 115.66 115.60 118.95 108.91 108.51 74.60 90.80 90.68 68.08 06.000 60.164 60.190 105.61 111.43 112.08 115.68 115.63 119.02 108.43 108.68 74.62 90.80 90.61 68.32 5 of 17
e ATTACHMENT C.6 PRItt.*.RY CCf4TAINffENT INTEGRATED LEAK PATE TEST PAGE 2 CF PUti 2 FASNY JAttES A FITZPATRICH ttUCLEAR POWER PLAf4T FEC*t 2000 CN 11-06-78 TO 2000 CN 11-07-78 RUN 1 HITH RTD CORRECTIONS FACTORS ADDED LOG 2 - IFFUT VARIABLES tit!E
DRYHELL----------------
TORUS----------------
HRS ABS PRESS VAP PRESS ABS TEffP ABS PRESS VAP FRESS AC3 TEMP PSIA PSIA DEGR PSIA PSIA DEGR 0.0 60.077 0.7316 570.92 60.301 0.3305 534.27 1.000 60.281 0.7343 571.06 60.309 0.3326 534.32 2.000 60.066 0.7324 570.98 A0.293 0.3306 534.34 3.000 60.062 0.7350 571.06 63.092 0.3305 534.36 a.000 60.068 0.734 571.19 60.293 0.3302 534.40 5.000 60.038 0.7336 570.96 60.068 0.3332 534.40 6.000 60.239 0.7326 570.99 60.270 0.33 4 534.43 7.000 60.042 0.7377 571.05 60.270 0.3331 534.43 8.00n 60.230 0.7322 571.07 60.258 0.3337 534.43 9.C00 60.223 0.7328 571.08 60.251 0.3331 534.45 10.000 60.223 0.7334 571.12 60.250 0.3341 534.46 11.000 40.221 0.7330 571.18 60.251 0.3354 534.48 12.000 60.219 0.7362 571.28 60.250 0.3380 534.51 13.000 60.013 0.7316 571.30 60.242 0.3364 534.50 14.000 60.213 0.7304 571.33 60.242 0.3370 534.52 15.000 60.007 0.7314 571.38 60.034 0.3384 534.55 16.000 60.203 0.7337 571.41 60.230 0.3399 534.57 17.000 60.199 G.7319 571.51 60.007 0.3304 534.56 18.000 60.199 0.7316 571.54 60.207 0.3385 534.58 19.000 60.191 0.7308 571.56 60.219 0.3391 5?4.54 20.000 60.188 0.7373 571.61 60.215 0.3378 534.54 21.000 60.161 0.7344 571.63 60.211 0.3385 534.56 22.000 60.130 0.7386 571.67 60.003 0.3398 534.60 23.000 60.175 0.7420 57] 74 60.201 0.3403 534.61 24.000 60.172 0.7403 571.79 60.199 0.3411 534.61 25.000 60.164 0.7374 571.77 60.191 0.34 2 534.60 26.000 60.164 0.7363 571.76 60.190 0.3406 534.62 INITIALIZATION ORYNELL TCRUS CONTROLS OUTPUT NDATA ABS ARESS 60.271 60.301 100 27 VAP PRESS 0.7316 0.3305 ABS TEt:P 570.92 534.27 VOLUltE 154476.
115800.
6 of 17
ATTACHMENT C.7 PRIttARY CC!tTAItatENT INTEGRATED LEAM RATE TEST PAGE 3 OF RIJi 2 PASNY JAMES A FITZPATRICK NUCLEAR PCHER PLANT FRDit 2000 CN 11-26-78 TO 2000 ON 11-27-78 RUN 1 HITH RTD CORRECTICHS FACTCRS ADDED LOG 3 - ABSCULTE HETH03 TEST RESULTS TIME MASS OF AIR LEAKRATE 95 PCT CONF UCL HOURS POUNOS PCT / DAY PCT / DAY 0.0 78572.743 0.0 0.0 0.0 1.000 78562.931 0.0 0.0 0.0 2.000 78549.864 0.349411 0.205333 0.554744 3.000 78535.597 0.380292 0.084621 0.464913 4.000 78529.473 0.347822 0.069368 0.417190 5.000 78510.348 0.372306 0.055905 0.428211 6.000 78508.830 0.346134 0.053324 0.399458 7.000 78502.128 0.323447 0.049587 0.373034 8.000 78488.538 0.318969 0.037666 0.356655 9.000 78477.052 0.318428 0.029359 0.347788 10.000 78472.156 0.310461 0.025725 0.336186 11.000 78464.650 G.302743 0.023309 0.326052 12.000 78449.311 0.303542 0.019491 0.323033 13.000 78443.627 0.300334 0.017012 0.317346 14.000 78440.859 0.292858 0.017333 0.310191 15.000 78424.147 0.292654 0.015051 0.307705 16.000 78413.115 0.293382 0.013223 0.306605 17.000 78403.174 0.294074 0.011717 0.305790 18.000 78399.818 0.291546 0.010876 0.302422 19.000 78389.391 0.290090 0.009904 0.299993 20.000 78378.406 0.289602 0.000944 0.298546 21.000 78370.082 0.238817 0.008157 0.296974 22.000 78353.384 0.290622 0.007734 C.298356 23.000 78341.339 0.292785 0.007529 0.300314 24.000 78333.408 0.294003 0.007060 0.3010o3 25.000 78328.276 0.293788 0.006506 0.300295 26.000 78327.560 0.291365 0.004667 0.298032 7 of 17
ATTACHMENT C.8 PPIttARY CCliTAIretEt{T INTEGRATED LEAM PATE TEST PAGE 4 0F RUN 2 FASNY JAt!ES A FITZPATRICH NUCLEAR POWER PLANT FRCit 2000 ON 11-26-78 TO 2200 CN 11-27-78 RU*i 1 HITH RTD CCRRECTICNS FACTORS A0DED LOG 4 - INITIALIZATION AfC C0f4TRCL VARIACLES HEIGHTItiG FACTCPS FCR TEMPERATURE AfC DEWPOINT AVERAGIriG ZONE 0 ZCNEl ZONE 2 20fiE3 ZCNE4 ZONES ZONE 6 ZONE 7 ZONE 8 ZONEA ZONES 20NEC 0.11351 0.16502 0.35604 0.13137 0.04701 0.05337 0.07153 0.06015 1.00000 0.50000 0.50000 1.00000 POLYH0tlIAL COEFFICENTS FCR VAPCR PRESSURE CONVERSION 0.9198180-14 0.172223D-10 0.1050150-08 0.3498760-06 0.179585D-04 0.1121990-02 0.2113970-01 STUDENT'S T CONSTANTS 1.95996 2.37226 2.82250 NITROGEN IN-LEAHAGE OPTION IS OFF 8 of 17
ATTACIIMENT C.9
SUMMARY
OF RTD CORRECTIONS Zone Correction 0
-0.587 1
+0.672 2
+0.240 3
-1.100 4
+0.226 5
+0.076 6
-0.176 7
+0.046 8
+0.042 9 of 17
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D-
ATThCHMENT D.1 TYPE C PENETRATION LEAKAGE 'IO DE ADDED TO CALCULATED PCILRT LEAK RATE I.
Penetrations to be penalized from initial valve lineup (see Type B and C data) :
Leakage Penetration Description (scfd)
X-9A "A" Feedwater Line 23.200 X-9B "B" Feedwater Line 34.050 X-14 RWCU Supply 4.963 X-23 Drywell Cooling Equipment 2.040 X-24 Drywell Cooling Equipment 10.850 Total (percent / day) 0.007 II. Penetrations isolated during Type A Test (post-repair results added to Type A leakage) :
Pre-Repair
- Post-Repair Leakage Leakage Penetration Description (scfd)
(sctd)
X-7A "A" Main Steam 1,129.98 295.22 Line X-31Ac "A" Reactor 1.02 1.02 Recirc Pump Mini Purge Supply X-31Bc "B" Reactor 30.03 30.03 Recirc Pump Mini Purge Supply X-35D "D" TIP Ball 1.02 1.02 Check Valve Total (percent / day) 0.031 NOTE:
Repairs made to MSIV-29-AOV-80A to re-establish actuation air and cycle valve with fast closure.
MSIV-29-AOV-86A was disassembled and the seat was lapped.
The final test on the MSIVs was made during reactor heatup.
MSIV-29-AOV-86A was established to be leaking at a rate slightly greater than the 276 scf/ day maximum established by plant technical specifications.
Amendment No. 44 to the operating license has been approved to allow for plant operation with the Type C leakage for 29-AOV-86a not to exceed 300 scf/ day.
1 cf 1
PART D TEST RESULTS I.
60-psia PCILRT Results The 60 psia PCILRT was conducted in accordance with Section VII.3 of surveillance procedure No. F-ST-39F.
a.
Lam leak rate calculated (percent / day) 0.292 b.
95 percent confidence level (percent / day) 0.006 c.
UCL, leakage rate with 95 percent confidence level (percent / day) 0.298 d.
Corrections due to water level (percent / day)
None e.
Correction for Type C leakage (percent / day)
(see Attachment D 1) 0.038 f.-
Total reported Type A leak rate (c+d+e) (percent / day) 0.336 Total allowable leakage is less than 0.75 La or 0.375 percent / day.
II. Supplemental Test Results The Supplemental Verification Test was performed using the Mass Pump Back Method in accordance with Section VII.4 of F-ST-39F.
a.
Verification air inserted 307.65 lbm (4102 scf) b..
Computer calculated change in containment gas mass using Type A test instrumentation 339.79 lbm c.
Agreement between measured and calculated gas added to contain-ment (b-a) 32.14 lbm d.
0.25 La 99 lbm Results were acceptable within
+0.25 La in accordance with 10CFR50, Appendix J, Section III A.3.b.
III.D-1
SECTION IV LOCAL LEAK RATE TESTS (TYPE B AND C)
Attachments IV.1, IV.2, and IV.3, which f ollow, summarize the LLRT data which has been obtained from periodic testing performed since the last Type A Test.
Pre-repair data is provided f or surveillance testing performed in 1977 and 1978.
Pre-repair leakage data were not maintained for testing performed in 1976.
All future testing reports will include pre-repair data.
The 1978 LLRTs were performed using " Volumetric" leakage measuring equipment with a maximum calibrated range of 1,018 standard cubic feet per day (scf/ day) similarly the 1977 testing was performed using Schutte and Koerting rotometers with a
minimum range of 1,000 scf/ day.
Corrective action was taken whenever the penetration leakage was greater than the maximum ranges given above.
No attempt to establish the actual leak rate is made when the maximum range of the test instrumentation in exceeded.
In 1978 the isolation function for penetration X-13A & X-13B and X-16A S X-16B were changed from the air-operated testable check valves inside containment (ISC) to the motor-operated valves outside containment (OSC).
Also, the double "O"-ring seals on the drywell vacuum breakers were tested.
Type B testing of the drywell vacuum breaker "O" rings was inadvertently omitted from previous testing.
The acceptance criteria for Type B
and C
testing are in accordance with 10CFR50, Appendix J.
The combined leakage rate for all penetrations and valves subject to Type B and C tests shall be less than 0.6 La or less than 3,269 scf/ day.
The attachments for this section are:
Attachment No.
Title Surveillance Period IV.1 1978 Type B and C Data 9/14/78 through 11/23/78 Summary IV.2 1977 Type B and C Data 6/27/77 through 9/28/77 Summary IV.3 1976 Type B and C Data 1/8/76 thrsugh 4/19/76 Summary IV-1
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ATTACIIMEttr IV.1 (Cc at)
Type Equipment / Valves Pre-Repair Post-Repair Penetration No.
Test Tested Leakage (sef/ day)
In kage Isef/ day}
Remarks X19-Equipment Sump C
20-MOV-94 (ISC) 18.32 18.32 Pump Discharge 20 -AOV-95 (OSC)
X21-Service Air C
39-SAS-10 (ISC) 100 (S AS-10) 81.95 39-SAS-9 (OSC)
X22-Instrument Air C
IAS-22 (ISC) 4.98 4.98 IAS-21 (OSC)
IAS-23 (OSC)
X23-Cooling Water C
EWS-16B (OSC) 2.04 2.04 Supply RBC-24 A (OSC)
X24-Cooling Water C
EWS-16 A (OSC) 10.85 10.85 Supply RBC-24 B (OSC)
X25-Drywell Inerting C
27-ADV-131 A (OSC)
(AOV-131A) >1018 220.32 AOV-131A and CNS-CV-2A and CAD and Purge X71 CNS-CV-2A (OSC)
(plus CNS-CV-2A) seats repaired 27-AOV-131B (OSC)
CNS-CV-2B (OSC) 27-AOV-111 (OSC) 27-AOV-112 (OSC)
X26A-Vent from and C
27-AOV-114 (OSC) 15.73 15.73 Drywell X26B 27-AOV-113 (OSC) 27-MOV-113 (OSC) 27-SOV-120 A/B (OSC) 27-SOV-121 A/B (OSC) 27-SOV-122A/B (OSC)
X31Ac "A" Recire C
0 2-RWR-13 A (ISC)
> acceptable 20.5 RWR-40A and RWR-13A seats Pump Mini Purge 02-RWR-4 0A (OSC) repaired X31Ad-Drywell Inert C
27-SOV-135A (OSC) 6.27 6.27 and Purge 27-SOV-135B (OSC)
X31Bc "B" Recirc C
02-RWR-13B(ISC) 142 (RWR-13B) 2.17 RWR-13B and RWR-40B seats Pump Mini Purge 02-RWR-40B (OSC) repaired X35A-TIP Probe C/B Ball Valve (OSC) 5.15 5.15 "O" ring (OSC)
X35B-TIP Probe C/B Ball Valve (OSC) 2.20 2.20 "O" ring (OSC)
X35C-TIP Probe C/B Ball Valve (OSC) 2.04 2.04 "O" ring (OSC) 3 of 7
ATTACHMEtTP IV.1 (Cont)
Type Equipment / Valves Pre-Repair Post-Repair Penetration No.
Test Tested Leakage (set / day)
Leakaqe (sef/ day)
Femarks X35D-TIP Probe C/B Ball Valve (OSC) 1.76 1.76 "O"
ring (OSC)
X35E-TIP Purge C/B X-3 5E-TP-1 (OSC) 2.04 2.04 "O" ring (OSC)
X36-CRD Return C
CRD-110 (OSC ()
14.15 14.15 CRD-113 (ISC)
10-MOV-31 A (OSC) 15.07 15.07 Spray 10-MOV 26A(OSC)
RHR-52A (OSC)
10 -MOV-31B (OSC)
> 1018 (combined) 34.1 MOV-26B and MOV-31B seats Spray 10-MOV-2 6B (9SC) repaired RHR-52B (OSC)
X41-Recire Loop C
02-AOV-39 (ISC) 28.76 28.76 Sample 02-AOV-4 0 (OSC)
X42-Standby Liquid C
11-SIC-16 (OSC)
>1000 (SLC-16) 12.93 SLC-16 seat repaired Control 11-SLC-17 (ISC)
X45-Leak Rate C
LRA-18 (OSC) 2.04 2.04 Ana1yzer LRA-19 (OSC)
LRA-20 (OSC)
LRA-21 (OSC)
27-SOV-125A (OSC)
>1018 (SOV-125B) 4.04 SOV-125B seat repaired Inert and Purge 27-SOV-125B (OSC)
X59-Drywell CAD C
27-SOV-123 A (OSC) 10.10 10.10 Inert and Purge 27-SOV-12 3 B (OSC)
X61-Breathing Air C
BAS-5 (ISC) 2.93 2.93 BAS-4 (OSC)
X62-Drywell Cooling C
RBC-26B (OSC) 15.78 15.78 Return X63 "B" Recirc Pump C
15-RBC-21B (OSC) 2.04 2.04 MTR Cooling Supply 46 -ESW-15A (OSC)
X64 "A" Recirc Pump C
15-RBC-22B (OSC) 1.02 1.02 ffrR Cooling Return 4 of 7
ATTACHMENT IV.1 (Cont)
Type Equipment / Valves Pre-Repair Post-Repair Penetration ?k).
Test Tested Leakage (sef / day)
Leakage (sef / day)
Remarks X65-Equipment Drain C
15-RBC-33 (OSC) 1.02 1.02 Pump Clr Return X66 "A" Drywell Clr C
15-RBC-2 6 A (OSC)
>1018 257.05 RBC-26A seat repaired Assy Return X67 "A" Recirc Pump C
15-RBC-21 A (OSC) 2.04 2.04 PfrR Cooling Supply 46-ESW-15B (OSC)
X68 "B" Recirc Pump C
15-RBC-22A (OSC) 12.73 12.73 PfrR Cboling Return X100A-Elect B
"O" rings 0.0 0.0 X100B-Elect B
"O" rings 0.0 0.0 X100C-Elect B
"O" rings 0.0 0.0 X100F-Elect B
"O" rings 0.0 0.0 X100G-Elect B
"O" rings 0.0 0.0 X100K-Elect B
"O" rings 0.0 0.0 X101A-Elect B
"O" rings 0.0 0.0 X1018-Elect B
"O" rings 0.0 0.0 X101C-Elect B
"O" rings 0.0 0.0 X101D-Elect B
"O" rings 0.0 0.0 X101E-Elect B
"O" rings 0.0 0.0 X101F-Elect B
"O" rings 0.0 0.0 X103A-Elect B
"O" rings 0.0 0.0 X103B-Elect B
"O" rings 0.0 0.0 X104C-Elect B
"O" rings 0.0 0.0 X104D-Elect B
"O" rings 0.0 0.0 X104E-Elect B
"O" rings 0.0 0.0 X106A-Elect B
"O" rings 0.0 0.0 5 of 7
ATTACllMENT IV.*4 (Cont)
Type Equipment / Valves Pre-Repair Post-Repair Penetration No.
Test Tested Leakage (scf/ day)
Leakage (scf /da y)
Resnarks X1068-Elect B
"O" rings 0.0 0.0 X107-Elect B
"O" rings 0.0 0.0 X108-Elect B
"O" rings 0.0 0.0 X109-Elect B
"O" rings 0.0 0.0 X110C-Elect B
"O" rings 0.0 0.0 X110D-Elect B
"O" rings 0.0 0.0 X111B-Elect B
"O" rings 0.0 0.0 X200A-Torus Access B
"O" rings 1.02 1.02 X200B-Torus Access B
"O" rings 1.02 1.02 X200C-% rus Access B
"O" rings 1.02 1.02 X202BG-Va cuum C
27-AOV-101B (OSC) 12.97 12.97 Breaker VB-7 (OSC) 27-AOV-101 A (OSC) va-6 (OSC)
13-MOV-130 (OSC) 12.27 12.27 Breaker X202P-Vacuum B
"O" ring (VB-1) 14.5 14.5 Breaker X202G-Vacuum B
"O" ring (VB-2) 7.8 7.8 Breaker X202H-Vacuum B
"O" ring (VB-3) 90.6 40.8 Replaced shaft "O" rings Breaker X202I-Vacuum B
"O" ring (VB-4) 427.56 1.02 Replaced shaft "O" rings Breaker X202J-Vacuum B
"O" ring (VB-5) 81.44 12.83 Replaced shaft "O" rings Breaker X203A-0, Analyzer C
27-SOV-119A (OSC) 1.14 1.14 Sample 27-SOV-119B (OSC) 6 of 7
ATTACHMEttr IV.1 (Cont)
Type Equipment / Valves Pre-Repair Post-Repair Penetration No.
Test Tested Leakage (sef / day)
Leakage (sef/ day)
Remarks X203B-0, Analyzer C
27-SOV-124 A (OSC)
>1018 (SOV-124 A) 1.07 SOV-124A seat repaired Sample 27-SOV-124 B (OSC)
X205-Drywell Inert C
27-MOV-117 (OSC) 6.28 6.28 CAD and Purge 27-AOV-117 (OSC) 27-AOV-118 (OSC)
10-MOV-38 A (OSC) 96.7 96.7 Spray 10 -MOV-39 A (OSC) 10-MOV-34 A (OSC)
10-MOV-3 8B (OSC)
>1018 (combined) 1.53 MOV-39B valve internals Spray 10-MOV-39B (OSC) replaced; also, test 10-MOV-34B (OSC) boundary valve repaired X212-RCIC Turb C
RCIC-4 (OSC)
_1018 (both) 297.3 Both valve seats repaired Exhaust RCIC-5 (OSC)
X214-HPCI Turb C
HPI-12 (OSC)
>1018 (HPI-65) 93.15 HPI-65 seat repaired; Exhaust HPI-65 (OSC)
HPI-11 seat repaired X217-HPCI Turb C
23-MOV-59 (OSC) 32.37 32.37 Exhaust Vent 23-HPI-40 3 (OSC)
X218-Leak Rate C
LRA-13 (OSC) 2.04 2.04 Analyzer LRA-14 (OSC)
LRA-11 (OSC)
LRA-12 (OSC)
X220-Drywell CAD C
27-AOV-132A
>1018 (AOV-132B) 28.51 CNS-CV-2C, AOV-132B, Inert and Purge CNS-CV-2C (CNS-CV-2B) and CNS-CV-2D seats re-27-AOV-132B paired CNS-CV-2D 27-AOV-115 27-AOV-116 X221-Condensate C
13-RCIC-07 Gross (RCIC-07) 17.20 RCIC-06 seat and packing; facm RCIC Turb 13-RCIC-0 8 RCIC-07 seat X231-Elect B
"O" rings 0.0 0.0 Total Penetration Leak Rate, scf/ day 1986.766 7 of 7
ATTACHMEITT IV.2 1977 TYPE B AND C DATA
SUMMARY
Type Equiprnent/ Valves Pre-Repair Post-Pepair Penetration No.
Test Tested Leakage (sef /da y)
Leakage (scf/ day)
Reraarks Drywell Stabilizer 00 (GE-900)
B "O" rings 0.0 0.0 450 (GE-13 50)
B "O" rings 0.0 0.0 900 (GE-18 00)
B "O" rings 0.0 0.0 1350 (GE-22 58)
B "O" rings 0.0 0.0 1800 (GE-270 0)
B "O" rings 0.0 0.0 2250 (GE-315*)
B "O" rings 0.0 0.0 2700 (G E-0 0)
B "O" rings 0.0 0.0 3150 (GE-4 50)
B "O" rings 0.0 0.0 X1A-Equiptient and B
"O" rings 0.0 0.0 Emergency Escape Hatch X1B-Equipment Hatch B
"O" rings 1.28 1.28 X2A-Personnel Access B
- O" rings 9.17 9.17 Hatch X4-Drywell Head Man-B "O" rings 0.0 0.0 hole X6-CRD Removal llatch B
"O" rings 0.0 0.0 X7A "A" Main Steam C
29-AOV-8 0A (ISC) 54.92 54.92 Line 2 9-AOV-8 6 A (OSC)
X7B "B" Main Steam C
29-AOV-8 0B (ISC)
>1000 (both) 110.0 AOV-80B repacked and seat Line 29-AOV-86B (OSC) repaired: AOV-86B repacked X7C "C" Main Steam C
29 -AOV-8 0C (ISC)
>MJO (AOV-86C) 242.m AOV-86C seat repaired Line 29-AOV-8 6C (OSC)
X7D "D" Main Steam C
23-AOV-8 0D (ISC)
>1000 ( AOV-8 6D) 172.11 AOV-86D repacked and seat Line 29 -AOV-86D (OSC) repaired X8-Condensate Drain C
29-MOV-74 (ISC) 11.30 11.30 29-MOV-77 (OSC) 1 of 7
ATTACHMENT IV.2 (Cont)
Type Equipment / Valves Pre-Repair Post-Repair Penetration No.
Test Tested Leakage (scf/ day)
Leakage (sef/ day)
Remarks X9A-Feedwater C
34 -FWS-28 A (ISC) 155.40 155.40 NRV-111 A (OSC)
MOV-21 (OSC)
RWC-62 (OWC)
34-FWS-2 8 B (ISC) 295.52 295.52 tmV-111B (OSC)
MOV-19 (OSC)
X10-Steam to RCIP C
13 -MOV-t 6 (ISC)
>200 (MOV-15) 0.0 MOV-15 binding stesu Turb.
13-MOV-15 (OSC) repaireM X11-Steam to HPCI C
23-MOV-15 (ISC) 10.12 10.12
'mrb.
23-MOV-16 (OSC) 23-MOV-60 (OSC)
X12 -Shutdown Supply C
10-MOV-17 (ISC)
>380 (MOV-18) 22.28 MOV-17 seat repaired; to RHR 10-MOV-18 (OSC)
>1000 (MOV-17)
MOV-18 limit torque reset X13A-RHR Return C
10-AOV-68 A (ISC)
>1000 (MOV-6 BA) 186.45 MOV-68A seat repaired 10-MOV-25A (OSC)
X13B-RHR Return C
10-AOV-68 B (ISC)
Gross (MOV-68B) 175.10 MOV-68B seat repaired 10-MOV-258 (OSC)
X14-RWCU Supply to C
12-MOV-15 (ISC) 1.24 1.24 Recirc Pumps 12-MOV-18 (OSC) 12-MOV-80 (OSC)
X16A-Core Spray C
14 -AOV-13A (ISC)
>1000 (AOV-13A) 71.60 f.OV-13A seat repaired Pump Disch 14 -MOV-12A (OSC)
X16B-Core Spray C
14-AOV-13B (ISC)
>1000 (AOV-13B) 54.41 AOV-138 seat repaired Tamp Disch 14-MOV-12B (OSC)
X17-RPU Head Spray C
10-MOV-32 (ISC) 80 (MOV-33) 59.70 MOV-33 seat repaired 10-MOV-33 (OSC)
X18-Floor Sump Pump C
20-MOV-8 2 (ISC) 2.77 2.77 Disch 20-AOV-83 (OSC)
X91-Equipment Sump C
20-MOV-94 (ISC) 9.96 9.96 Pump Disch 20-AOV-95 (OSC)
X21-Service Air C
39-SAS-10 (ISC) 29.36 29.36 39-SAS-9 (OSC) 2 of 7
ATTACHMENT IV.2 (Cont)
Type Equipment / Valves Pre-Repair Post-Repair Penetration No.
Test Tested Leakage (sef/ day)
Jeakage (sef / day)
Remarks X22-Instrument Air C
IAS-22 (ISC) 720 (IAS-22) 0.793 IAS-22 seat repaired IAS-21(OSC)
IAS-23 (OSC)
X23-Cooling Water C
EWS-16B (OSC) 0.0 0.0 Supply RBC-24 A (OSC)
X24-Cooling Water C
EWS-16 A (OSC) 6.9 6.9 Supply RBC-24 B (OSC)
X25-Drywell Inerting C
27-AOV-131 A (OSC)
Gross (AOV-131A) 37.16 CNS-CV-2A and AOV-112 seats and CAD Purge X71 CNS-CV-2A (OSC)
(CNS-CV-2A) repaired 27-AOV-131B (OSC)
CNS-CV-2B (OSC) 27-AOV-I I I (OSC) 27-AOV-112 (OSC)
X26A-Vent from and C
27-AOV-114 (OSC)
>1000 44.59 A-11 SOVs cleaned; AOV-112 Drywell X26B 27-AOV-113 (OSC) seat repaired 27-MOV-113 (OSC) 27-SOV-120A/B (OSC) 27-SOV-121 A/B (OSC) 27-SOV-122A/B (OSC)
X31Ac "A" Recirc C
02-RWR-13A (ISC)
>1000 (RWR-13A) 12.88 RWR-13A seat repaired Pump Mini Purge 02-RWR-40A (OSC)
X31Ad-Orywell Inert C
27-SOV-135 A (OSC)
>1000 (CNS-6) 11.95 Packing leak on test and Purge 27-SOV-135B (OSC) boundary v/v X31Bc "B" Recire C
02-RWR-13B (ISC)
>1000 (RWR-13B) 16.43 RWR-13B seat repaired Pump Mini Purge 02-RWR-40B (OSC)
X35A-TIP Probe C/B Ball Valve (OSC) 2.96 2.96 "O" ring (OSC)
X35B-TIP Probe C/B Ball Valve (OSC) 1.23 1.23 "O" ring (OSC)
X35C-TIP Probe C/B Ball Valve (OSC) 1.28 1.28 "O" ring (OSC)
X35D-TIP Probe C/B Ball Valve (OSC) 1.09 1.09 "O" ring (OSC)
X35E-TIP Purge C/B X-3 5E-TP-1 (OSC) 0.0 0.0 "O" ring (OSC) 3 of 7
ATTACHMENP IV.2 (Cont)
Type Fquipment/ Valves Pre-Repair Post-Repair Penetration No.
Test Tested Leakage (scf / day)
Leakage (scf/ day)
Femarks X36-CRD Return C
CRD-110 (OSC)
>1000 (combined) 11.16 CRD-110 and CRD-113 seats CRD-113 (ISC) repaired X39A-Containment C
10-MOV-31 A (OSC) 49.80 49.80 Sprav 10-MOV-26A (OSC)
RHR-52A (OSC)
X39B.
tainment C
10-MOV-31B (OSC) 40.84 40.84 Spray 10-MOV-26B (OSC)
RHR-52B (OSC)
X41-Recirc Loop C
02-AOV-39 (ISC) 6.96 6.96 Sample 02-AOV-40 (OSC)
X42-Standby Liquid C
11-SIf-16 (OSC) 6.55 6.55 Control 11-SLC-17 (ISC)
X45-Leak Rate C
LRA-18 (OSC) 0.0 0.0 Analyzer LRA-19 (OSC)
LRA-20 (OSC)
LRA-21 (OSC)
27-SOV-12 5A (OSC) 3.67 3.67 Inert and Purge 27-SOV-125B (OSC)
X59-Drywell CAD C
27-SOV-123A (OSC) 0.0 0.0 Inert and Purge 27-SOV-123B (OSC)
X61-Breathing Air C
BAS-5 (ISC) 20 (BAS-5) 8.76 BAS-5 seat repaired BAS-4 (OSC)
X62-Drywell Cooling C
RBC-26B (OSC) 7.43 7.43 Return X63 "B" Recirc Pump C
15-RBC-218 (OSC) 4.35 4.35 MTR Cooling Supply X64 "A" Recirc Pump C
15-RDC-22B (OSC) 0.0 0.0 MTR Cooling Return X65-Equipment C
15-RBC-33 (OSC) 2.70 2.70 Drain Pumo Clr Return X66 "A" Drywell C
15-RBC-26A (OSC) 700 0.0 RBC-26A seat repaired Cir Assy Return 4 of 7
ATTACHMENT IV.2 (Cont)
Type Equipment / Valves Pre-Repair Post-Repair Penetration No.
Test Tested Leakage (s cf / day)
Leakage (sef / day)
Remarks X67 "A" Recirc C
15-RBC-21 A (OSC) 6.33 6.33 Pump MTR Cooling 4 6 -ESW-15B (OSC)
Supply X68 "B" Recire C
15-RBC-22 A (OSC)
>1000 0.0 RBC-22A seat repaired Pump MTR Cooling Return X100A-Elect B
"O" rings 0.0 0.0 X100B-Elect B
"O" rings 0.0 0.0 X100C-Elect B
"O" rings 0.0 0.0 X100P-Elect B
"O" rings 0.0 0.0 X100G-Elect B
"O" rings 0.0 0.0 X100K-Elect B
"O" rings 0.0 0.0 X101A-Elect B
"O" rings 0.0 0.0 X101B-Elect B
"O" rings 0.0 0.0 X101C-Elect B
"O" rings 0.0 0.0 X101D-Elect B
"O" rings 0.0 0.0 X101E-Elect B
"O" rings 0.0 0.0 X101F-Elect B
"O" rings 0.0 0.0 X103A-Elect B
"O" rings 0.0 0.0 X103B-Elect B
"O" rings 0.0 0.0 X104C-Elect B
"O" rings 0.0 0.0 X104D-Elect B
"O" rings 0.0 0.0 X10.4E-Elect B
"O" rings 0.0 0.0 X106A-Elect B
"O" rings 0.0 0.0 X106B-Elect B
"O" rings 0.0 0.0 X107-Elect B
"O" rings 0.0 0.0 5 of 7
ATTACHMENT IV.2 (Cont)
Type Equirr.Ont/ Valves Pre-Repair Post-Repair Penetration No.
Tes t-hated Leakage (seffday)
Leakage (s cf / day)
Reraarks X108-Elect B
"O" rings 0.0 0.0 X109-Elect B
"O" rings 0.0 0.0 X110C-Elect B
"O" rings 0.0 0.0 X110D-Elect B
"O" rings 0.0 0.0 X111B-Elect B
"O" rings 0.0 0.0 X200A-Torus B
"O" rings 0.0 0.0 Access X200B-Torus B
"O" rings 0.0 0.0 Access X200C-Torus B
"O" rings 0.0 0.0 Access X202BG-Vacuum C
27-AOV-101B (OSC) 10.22 10.22 Breaker VB-7 (OSC) 27-AOV-101 A (OSC)
VB-6 (OSC)
X2028-Vacuum C
13-MOV-130 (OSC) 0.0 0.0 Breaker X202G-Vacuum B
"O" ring (VB-1)
Not Tested Breaker X202G-Vacuum B
"O" ring (VB-2)
Not Tested Breaker X202H-Vacuum B
"O" ring (VB-3)
Not Tested Breaker X202I-Vacuum B
"O" ring (VB-4)
Not Tested Breaker X202J-Vacuum B
"O" ring (VB-5)
Not Tested X203A-Or Analyzer C
27-SOV-119 A (OSC) 0.0 0.0 Sample 27-SOV-119B (OSC)
X2033-0, Analyzer C
27-SOV-124 A (OSC) 0.0 0.0 Sample 27-SOV-12 f4 B (OSC) 6 of 7
ATTACHMENT IV.2 (Cont)
Type Equipment / Valves Pre-R epair Post-Repair Penetration No.
Test Tested Leakage (scf/ day)
Leakage (set / day)
Remarks X205-Orywell Inert C
27-MOV-117 (OSC) 1.143 1.143 CAD and Purge 27-AOV-117 (OSC) 27-AOV-118 (OSC)
10-MOV-38 A (OSC) 79.6 79.6 Spray 10 -MOV-39 A (OSC) 10-MOV-34 A (OSC)
10-MOV-38B (OSC)
>1000 (MOV-39B) 649.5 MOV-39B seat repaired Spray 10-MOV-39B (OSC) 10-MOV-3 4 B (OSC)
X212-RCIC Turb C
RCIC-4 (OSC)
>1000 (combined) 33.70 PCIC-4 and RCIC-5 seats Exhaust RCIC-5(OSC) repaired X214-HPCI Turb C
HPI-12 (OSC)
>1000 (combined) 236.90 HPI-12 and ITI-65 seats Exhaust HPI-65 (OSC)
Iepaired X211-HPCI Turb C
23-MOV-59 (OSC) 13.9 13.9 Exhaust Vent 2 3-HPI-4 0 3 (OSC)
X218-Leak Rate C
LRA-13 (OSC) 0.0 0.0 Analyzer LRA-14 (OSC)
LRA-11 (OSC)
LRA-12 (OSC)
X220-Drywell CAD C
27-AOV-132A 15.71 15.71 Inert and Purge CNS-CV-2C 27-AOV-132B CNS-CV-2D 27-AOV-115 27-AOV-116 X221-Condensate C
13-RCIC-52B (OSC)
>1000 (RCIC-07) 3.48 RCIC-07 seat repaired from RCIC Turb 13-RCIC-3 8 (OSC)
X231-Elect B
"O" rings 0.0 0.0
'Ibtal Penetration Leak Rate (scf/ day) 3005.256 7 of 7
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ATTACHMENT IV.3 (Cont)
Type Equipment //alves Pre-Repair Post-Repair Penetration No.
Test Tested Leakage (sef / day)
Leakage scf / day)
Remarks X19-Equipment C
20 -MOV-9 4 (ISC) 5.4 Sump Pump Disch 20-AOV-95 (OSC)
X21-Service Air C
39-SAS-10 (ISC) 32.8984 39 -SAS-9 (OSC)
X22-Instrument Air C
IAS-22 (ISC) 17.068 IAS-21 (OSC)
IAS-23 (OSC)
X23-Cooling Water C
EdS-16B (OSC) 26.05 Supply RBC-24 A (OSC)
X24-Cooling Water C
EWS-16A (OSC) 6.12 Supply RBC-24 B (OSC)
X25-Orywell Inerting C
27-AOV-131 A (OSC) 75.500 and CAD and Purge CNS-CV-2 A (OSC)
X71 27-AOV-131B (OSC)
CNS-CV-2B (OSC) 27-AOV-111 (OSC) 27-AOV-112 (OSC)
X26A-Vent from C
27-AW-114 (OSC) 42.9188 and Drywell 27-AOV-113 (OSC)
X26B 27-MOV-113 (OSC) 27-SOV-120 A/B (OSC) 27-SOV-121 A/B (OSC) 27-SOV-122A/B (OSC)
X31Ac "J." Recire C
02-RWR-13 A (ISC) 0.0 Pump Mini Purge 02-RWR-4 0A (OSC)
X31Ad-Drywell Inert C
27-SOV-135A (OSC) 9.49625 and Purge 27-SOV-13 5B (OSC)
X31Bc "B" Recire C
02-RWR-13B (ISC) 0.0 Pump Mini Purge 0 2-RWR-4 0B (OSC)
X35A-TIP Probe C/B Ball Valve (OSC) 0.0 "O" ring (OSC)
X35B-TIP Probe C/B Ball Valve (OSC) 0.0 "O"
ring (OSC)
X35C-TIP Probe C/B Ball Valve (OSC) 0.0 "O" ring (OSC) 3 of 7
ATTACHME!Tr IV.3 (Cont)
Type Equiptnent/ Valves Pre-Repair Post-Repair Penetration No.
Test Tested Leakaqe (sef/ day)
Leakage scf/ day)
Remrks X35D-TIP Probe C/B Ball Valve (OSC) 0.0 "O" ring (OSC)
X35E-TIP Purge C/B X-3 5E-TP-1 (OSC) 0.0 "O" ring (OSC)
X36-CRD Return C
CRD-110 (OSC) 11.1888 CRD-113 (ISC)
10-MOV-31 A (OSC) 1.3 Spray 10-MOV-2 6A (OSC)
RHR-52A (OSC)
10-MOV-31B (OSC) 18.00 Spray 10 -MOV-2 6B (OSC)
RifR-52 B (OSC)
X41-Recire Loop C
02-AOV-39 (ISC) 16.36 Sample 02-AOV-4 0 (OSC)
X42-Standby Liquid C
11 -SLC-16 (OSC) 5.8 Oontrol 11-SLC-17 (ISC)
X45-Ieak Rat?
C LRA-18 (OSC) 0.0 Analyzer LRA-19 (OSC)
LRA-20 (OSC)
LRA-21 (OSC)
27-SOV-125A (OSC) 9.4376 Inert and Purge 27-SOV-125B (OSC)
X59-Drywell CAD C
27-SOV-123A (OSC) 0.0 Inert and Purge 27-SOV-123B (OSC)
X61-Breathing Air C
BAS-5 (ISC) 8.4 BAS-4 (OSC)
X62-Drywell Cooling C
REC-26B (OSC) 27.9 Return X63 "B" Recirc Pump C
15-RBC-21B (OSC) 18.6372 KrR Cooling Supply 46-ESW-15A (OSC)
X64 "A" Recirc Pump C
15-RBC-22B (OSC) 8.894 MTR Cooling Return 4 of 7
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ATTACHMENT IV.3 (Cont)
Type Equipnent/ Valves Pre-Repair Post-Repair Penetration No.
Test Tested Leakage (scf/ day) leakaga scf/ day)
Remarks X106B-Elect B
"O" rings 0.0 X107-Elect B
"O" rings 0.0 X108-Elect B
"O" rings 0.0 X109-Elect B
"O" rings 0.0 X110C-Elect B
"O" rings 0.0 X110D-Elect B
"O" rings 0.0 X111B-Elect B
"O" rings 0.0 X200A 'Ibrus Access B
"O" rings 0.0 X200B 'Ibrus Acess B
"O" rings 0.0 X200C-Torus Access B
"O" rings 0.0 X202BG-Vacuum C
27-AOV-101B (OSC) 25.0 Breaker VB-7 (OSC) 27-AOV-101 A (OSC)
VB-6 (OSC)
13-MOV-130 (OSC) 25.9 Breaker X202F-Vacuum B
"O" ring (VB-1)
Not tested Breaker X202G-Vacuum B
"O" ring (VB-2)
Not tested Breaker X202H-Vacuum B
"O" ring (VB-3)
Not tested Breaker X202I-Vacuum B
"O" ring (VB-4)
Not tested Breaker X202J-Vacuum B
"O" ring (VB-5)
Not tested X203A-0, Analyzer C
27-SOV-119 A (OSC) 0.0 Sample 27-SOV-119B (OSC)
X203B-0, Analyzer C
27-SOV-12 4 A (OSC) 1.0 Sample 27-SOV-124 B (OSC) 6 of 7
)
ATTACHMEITT IV.3 (Cont)
Type Equipment / Valves Pre-Repair Post-Repair Penetration No.
Test Tested Leakage (scf / day)
Leakage scf fday)
Remarks X205-Drywell Inert C
27-MOV-117 (OSC) 1.25 CAD and Purge 27-AOV-117 (OSC) 27-AOV-118 (OSC)
10-MOV-3 8 A (OSC) 24.024 Spray 10 -MOV-39 A (OSC) 10-MOV-34 A (OSC)
10-MOV-38 B (OSC) 48.4 Spray 10-MOV-39B (OSC) 10-MOV-34 B (OSC)
X212-RCIC Turb C
RCIC-4 (OSC) 80.0 Exhaust RCIC-5 (OSC)
X214-HPCI Turb C
HPI-12 (OSC) 216.00 Exhaust HPI-65 (OSC)
X217-HPCI Turb C
23-MOV-59 (OSC) 21.2 Exhaust Vent 23-HPI-4 03 (OSC)
X218-Leak Rate C
LRA-13 (OSC) n.0 Analyzer LRA-14 (OSC)
LRA-11 (OSC)
LRA-12 (OSC)
X220-Drywell CAD C
27-AOV-132A 34.9 Inert and Purge CNS-CV-2C 27-AOV-132B CNS-CV-2D 27-AOV-115 27-AOV-116 X221-Condensate C
13-RCIC-52B (OSC) 21.084 from RCIC Turb 13-RCIC-3 8 (OSC)
X231 -Elect B
"O" rings 0.0 Total Penetration Leak Rate (sef/ day) 1809.501 7 of 7