ML20215D809
| ML20215D809 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 06/30/1986 |
| From: | Capstick R VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| FVY-86-91, NUDOCS 8610140305 | |
| Download: ML20215D809 (44) | |
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1 9 VERMONT YANKEE PRIMARY CONTAINMENT LEAKAGE RATE TESTING-
'1986 TEST COORDINATORS
-David L. Phillips Gary Cappuccio James M. DeVincentis PREPARED BY David L. Phillips James M. DeVincentis j l
1 l 8610140305 860630 "i PDR ADOCK 05000271 ,' p PDR I f
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Introductirn During the 1985/86 refueling and recirculation pipe replacement outage which occurred during the period from September 20, 1985 to July 30, 1986, a Type A containment integrated leakage rate test was performed. The last leak rate test report'was filed with the USNRC in September, 1983. This report describes all primary containment leakage testing performed subsequent to the 1983 Type A test, and up to and including the Type A test con- ; ducted in June, 1986. . In accordance with 10CFR 50, Appendix J, a summary analy-sis of all periodic' Type B and Type C tests performed since June 1983 are included in this report. All testing performed during the period covered by this report conformed to the rules and regulation specified in 10 CFR 50, Appendix J. Summary The plant was shut down on September 20, 1985 for refueling and recir-culation pipe replacement. The Type B and C testing commenced immediately upon shutdown. The Type A test was conducted at the end of the outage. Pressurization for the Type A test commenced on June 20, 1986 with two air compressors of 1800 scfm total capacity at approximately 8 psi /hr charging rate. Containment pressure was raised to the calculated peak accident pressure of 44 psig over a 5 hour and-53 minute period. During this time, exterior containment inspections were performed at 5, 15, and 30 psig levels to attempt to' locate any abnormal containment leakage. No significant leaks were found during the pressurization period. After stabilizing for four hours, it was determined that stable conditions
- had been met to start the test at 0100. Based upon this, 0100 was declared as
) the start time for the 24 hour test. At 1115, the test was stopped due to excessive leakage. (>0.6 wt %/ day). Leaks were located from the following areas. ! 1. Drywell Head manway cover
- 2. (2) Torus /Drywell/ vacuum Breaker Shaft packings
- 3. Packing leaks on 5 valves in the Atmosphere Control System
. 4. 2 fittings on the Traversing In-core Probe System
- 5. A leaking instrument line fitting off of the torus.
All leaks were repaired and at 1500 the pressure in the containment was increased to the test pressure of 44 psig. After a four hour stabilization period, the 24 hour test was recommenced at 2006. The 24 hour test was completed satisfactorily at 2008 on June 22, 1986. The absolute method of leakage detection was employed. The ideal gas laws are utilized to find the mass of air in the containment at ten minute intervals. The containment mass was plotted against time and the absolute leakage rate was determined from the slope of the least squares fit line (See Figure 5). The measured leakage rate at the upper one sided 95% confidence level was 0.1451 wt %/ day. The final corrected leakage rate at the upper one sided 95% con-fidence level was 0.1546 wt %/ day. ____. . _ - _ _ _ ,_ _ . _ _ - . . ~ . . . _ _ _ _ _ - . _ - - - . _ _ . _ _ . . _ . _ _ . . . _ _ . . _ . _ _ _ . .
Description of Test The containment was made ready for the integrated leakage rata test and pressurization commenced at 1745 hours on June 20, 1986. Pressurization was accomplished by using two mobile, oil-free air compressors, each with a capacity of 900 scfm. They were connected by hoses to the nitrogen purge supply line at a tee, through VNP-1071, as shown on the attached figure 1. As the containment pressure reached the hold points of 5, 15, and 30 psig, survey personnel were dispatched to attempt to locate any sources of leakage. The survey personnel found no significant leakage. The test pressure was attained at 2338 hours. Pressures and temperatures in the containment were allowed to stabilize for four hours. At the end of four hours, review of the data indicated that the stabilization criteria has been met since 0100 and the decision was made to make this time the start of the 24 hour test. At 0418, RRU#1 was secured due to high amperage readings. At 1115 hours on June 21, 1986, the decision was made to stop the test due to excessive leakage. Measured leakage at tnat time was 0.78 wt %/ day (upper one sided 95% confidence level) which exceeds the 0.6 wt %/ day acceptance criteria. Local leakages were identified in the following areas.
- 1) The drywell head manway cover.
- 2) Two (2) Drywell/ Torus vacuum breaker shaft seals.
~
; 3) Packing leaks on 5 valves in the Atmospheric Control System.
- 4) Two fittings on the Traversing In-core Probe (TIP) system.
- 5) A leaking instrument line fitting off of the torus.
All leaks were repaired and at 1500 hours on June 21, 1986, the containment pressure was increased to 44 psig to recommence the test. The four hour stabi-lization period was commenced at 1515 hours. After the four (4) hour stabilization period, the twenty four (24) hour test was coerenced at 2006 hours on June 21, 1986. Table 1986-A-1 and 1986-A-2 (Primary Containment Leakage Rate Data Sheet) contains 1) the results of the contained mass calculations, 2) the containment pressure as read by the process computer, and 3) the weighted average drywell [ temperature, for the two tests. L The peak pressure Type A test was completed at 2008, June 22, 1986. A l supplemental test, (required by Appendix J, 10CFR50) to verify the accuracy of the instrumentation was coamenced by superimposing a leakage equal to La i 25% . through a calibrated flow meter. At 0825, June 23, 1986, the verification test j was completed satisfactory. Containment depressurization was commenced at 0845 hours. l l l
Analysis and Interpretation of Test Data This test employed the ideal gas laws to determine the absoluto leakage rate from primary containment. The total containment mass calculation was per-formed approximately every ten minutes during the 24-hour test on the timeshare computer. Input data for the calculation consisted of containment pressure, drywell and torus weighted average air temperature, drywell and torus dew points, and torus water level. The data (consisting of a series of independent calculations of the total contained air mass taken at ten minute intervals) lends itself to a statistical analysis based upon a time dependant rate of change of the contained mass of air. A small pressure change over the test interval is the basis for the assumption that the containment leakage is constant with respect to time. A linear least squares fit method is utilized to determine the best straight line to fit the data. The slope of the least squares fit line is the leakage rate. The equation of the least squares fit line is of the form: Q=b+mT Where: Q = mass of air b = Q intercept (Q value at t = 0) m = slope of line (leakage rate) T = time N = number of data points The values for b and m are determined from the following equations: b= EQ - MET N m= N(EOT) - EO)(ET) N(IET2) - (IT)2 l The upper one sided 95% confidence level (UCL) of the leakage rate (slope l of line) may be ' determined from the standard error of the slope and a " Students Table of t". The standard error is: Standard Error, S(m) = 1 Variance of 0 ga g _N-2 _ Variance of T __
~
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S(m) = 1 ~ NE08 - (EO)* Ma g _N-2 _ NETa - (IT)* __ The upper one sided 95% confidence level on the true leakage rate is: l UCL (approx.) = Lam + 2400 *(t.95)*(S(m)/b) (1) Where: UCL = Upper Confidence Level l
l Lam = -(2400)*(m/b) t.95 = The t factor at the 95% confidence level for 142 data points Variance = (Standard deviation)2 = E(xi - x)2 n (1) ANSI /ANS 56.8 - 1980 App. 8 Test Results A linear least squares fit of the 142 data points calculated during the second test (presented in Table 1986-A2) result in the following equation: Q = 74080 - 4.2334T Where: 74080 represents the initial mass of contained air in pounds
-4.2334 represents the slope or leakage rate in the Ibm / hour The upper one sides 95% confidence level of the leakage rate using this data is:
UCL = Lam + 2400 (t.95)(S(m)/b)
= -(2400)(m/b) + 2400 (t.95)(S(m)/b)
= -(2400) (-4.2334/74080) + 2400 (1.65) (.1449/74080)
= .1449 wt. %/ day Correction Factors
, 1. Correction for loss through isolation valves on operating system CRD-181 RCU-68 = + .0016 Wt%/ day RCU-15
- 2. Correction for increase in drywell sump levels
+ .0070 Wt%/ day
- 3. Correction for increase in reactor vessel water level
+ .0002 Wt%/ day
- 4. Correction for H202 Monitors which were secured
+ .0009 Wt%/ day The corrected leak rate at the upper one sided 95% confidence level is 0.1546 Wt%/ day. This measured value is less than the Technical Specification limit of 0.75 La, (where LA = 0.80 weight percent of contained mass per 24 hours), which is equivilent to 0.60 weight percent of contained mass per 24 hours.
Verification of Instrument Sensitivity Section III.A.2.(b) of Appendix J to 10CFR50 requires that the accuracy of the Type A test shall De verified by a supplemental test. The superimposed leak method of verification was used for the supplemental test. In this method, a-superimposed leakage equal to La i 25% is established through a calibrated flow meter. This composite leakage rate is then determined and compared with the measured test leakage rate. Satisfactory verification is achieved if: l Lam - L'ad < 0.25 la where L'am = Las - Ls Lam = containment leak rate (Wt%/ day) Las = measured combined leak rate (WT%/ day Ls = superimposed controlled leak rate (Wt%/ day) __ = average of the 30 minute values for the last 4 hours of 24 hour test or the last 2 hours of the verification as applicable. The flow rate used for the verification test was 6sefm. The required flow was calculated to be 5.6 scfm i 1.4 scfm (La 1 25%). The average leakage rate for the last four hours of the test was .1462 Wt%/ day Lam. The combined leakage rate for the last 2 hours of the verification test was .8782 Wt%/ day L. L'am = Las - Ls L'am = .8782 .8 = 0.0782 Wt%/ day Lam - L'ad < 0.25 La 0.1462-0.07821]=.068 Wt%/ day which is < .2 Wt%/ day (0.25 La) The .068 Wt%/ day in the 1986 supplemental test was well within the accuracy limits specified in Appendix J. Instrument Selection Guide Calculation The following calculations verify the ability of the instrumentation system to measure the integrated leakage rate of the primary containment system. Instrumentation errors are combined using a root-sum-square formula. l% (2) ISG = 1 2400 {2 4p)2 + fepy)2 + 2[eT 2 ' t _ gpf ( p/ g Ta _ ISG = instrument selection guide t = minimum expected test duration (hours) p = containment atmosphere total absolute pressure pv = containment atmosphere part pressure of water vapor T = containment atmosphere weighted average absolute drybulb temperature e = error associated with measurement of change in a given parameter - -~ -
The ISO shall not exceed 0.25 La (where La is the maximum allowable primary containment integrated leak rate). (2) ANSI /ANS 56.8 - 1980 A. Test Parameters La = 0.8% day P = 58.7 psia T = 550'R drybulb Tdp = 60*F dewpoint t = 24 hours B. Instrument Parameters
- 1) Total absolute pressure No. of sensors: 1 Range 0-150" Hg absolute (0-73.68 psia)
Measurement system error: 10.002% of F.S. = 1 0.003 in Hg Abs = 1 001 psia eP = 10.001 psia
.2) Water vapor pressure No. of sensors: 4 Sensor sensitivity error (Epv) 10.5'F Measurement sensitivity error (cpv)
Computer resolution = 0.1*F Computer repeatability = (40 av scale) = 1 08% Therefore at 60*F 60'F x .0008 = 0.048'F At a dewpoint temperature of 60'F, the equivalent water vapor pressure (as determined from the steam tables) is 0.0092 psia 'F. Epv = (10.5'F) (0.0092 psia /*F) = 10.0046 psia cpv = (10.048'F) (0.0092 psia /*F) = 10.00044 psia l epv = 1 [(Epv)2 + (cpv)2] % = [(0.004dp = (0.00044)2]% [No. of sensors] % [4] % epv = 0.0023 psia
- 3) Temperature No. of sensors: 18 Sensor sensitivity error (Et) = 10.5'F Measurement sensitivity error (ET) excluding sensor Computer resolution = 0.1*F Computer repeatability (40 av scale) = 10.08%
at 100*F x 0.0008 = 10.08'F ET = 1 0.05'F = 1 0.5'R E T = 10.08'F = 10.08'R
'T = [(E, T)2,+ (cT)2]%
= [(0.5L2 = (0.082]%
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- U8 @='iaVI D J k ,15) 4
'T = 1 1194'R
- 4) ISG ISG = 1 2400 [2 g 2 + 2pv2 +2 %
t p) (p) gT4
= 1 2400 [2 0.00 2 +2[0.0023'2+2[0.1194]2]%
24 58.7 5 58.7a g 550j
= 1100 [(5.8 x 10-10 + (3.07 x 10-9 + (9.4 x 10-8)] %
= 1100 [9.76 x 10-8] % = 1 0312 ISG = 10.0312 Wt%/ day
.0312 Wt%/ day is less than 0.2 wt %/ day (.25 La); therefore, the instruments are acceptable for the test.
Corrective Action Plan The prime contributor to the failure of the initial Type A test was deter-mined by visual observation to be the Drywell Head Manway Cover. This pathway, of itself, was sufficient to result in a Type A test failure irregardless of leakages from other pathways. The Drywell Head Manway Cover had been successfully tested by local leak rate methods (Type B test) prior to the Type A test. The discrepancy between the leakages found by local leak rate test methods and that found during the Type A test are due to the area that the test i pressures are applied to, and the resulting stresses on the cover bolts. The l cover had not been removed during the past several outages and persci.nsi installing the drywell head did not see any necessity to check the torque on the cover bolts. It is felt that the thermai cycles seen by the drywell head over the past operating cycles resulted in a loss of torque on the bolts of the l Drywell head Manway Cover.
Torqueing the Drywell Head Manway Cover bolts to their required torque-values resulted in no leakage from the cover as evidenced by soap bubble and acoustic monitor tests. To prevent _re-occurence, the procedure for installing the Drywell Head will be modified to require that the Drywell head Manway Cover bolts be torqued to their required value each time the Drywell head is installed. It will be noted in the procedure that this action is required even if the cover is not removed. l
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l 1984 and 1985/86 Type B and C Testing Description of Testina During the 1984 and 1985/86 refueling outages, Type B and C primary con-tainment leak rate testing was conducted in accordance with 10 GFR 50, Appendix J. . Type B leakage tests were performed on containment penetrations utilizing gasketed seals prior to opening. This provided accurate as-found leakage data , from the previous operating cycle. After each containment penetration closeout, a Type 8 leak test.was again performed. This leakage was combined with all , measured leakage of the various containment isolation valves as a baseline for
! the upcoming operating cycle. The summary test results for type B penetrations are presented in Tables 84-B and 85/86-B.
Type C leakage tests were performed on containment isolation valves. Four types of leakage tests were used, 1) the water leakage method, 2) the pressure drop method, 3) the pressure buildup method, and 4) the inleakage test method. . All Tech Spec isolation valves that were found to have leakage rates in excess of.that allowed by the Technical Specifications were reported to the Director of
- the Office of Inspection and Enforcement, Region 1, in thirty-day licensee event reports, LER 84-11 and 85-07. Following disassembly, repair, and ratesting, a satisfactory leakage rate was demonstrated. The summary for Type C valves is s
presented in Tables 84-C and 85/86-C. MSIV leakages shown in these tables have been corrected to the equivalent 44 psig leakage to allow them to be included in the total. Due to maintenance requirements, some valves / penetrations were tested out- + side the refueling outages. The results of these tests are included as Table D. Valves that Exceeded the Leakaae Criteria
- 1. Tech. Spec. Isolation Valves
[ During the 1984 refueling outage (6/15/84 to 8/9/84), 4 primary i- containment isolation valves were found to have seat. leakages in excess of that permitted by the Technical Specifications. They were: (a) MSIV-86B - Main Steam Isolation I (b) CRD-412A - Recirculation Pump Seal Purge (supplied by control rod drive water system) (c) PCAC-V16-19 Primary Containment Atmospheric Control (d) CA-89C - Containment Air Compressor Discharge On all these valves, a second valve on the same line provided the proper containment isolation capability. Testing, repair and retest details for these valves is described below. l MSIV-868 f On 6/16/84, the "B" out-board main steam isolation valve was leak tested and found to have a leakage of 18.27 SCFH (greater than 11.5 SCFH allowed). The l valve was disassembled and found to have steam cuts on the disc seat. These steam cuts were attributed to normal wear. The seating surface was refinished and on 7/4/84 the valve was retested with a leakage of 0.176 SCFH.
-CRD 412A On 6/28/84,.the Recirculation system pump seal purge containment isolation check valve, CR0 412A, was tested and found to have a leakage of 5.461 lbs/hr.
~(greater than the 0.522 Lbm/hr allowable). The valve was disassembled and found to have a crud buildup in the valve that prevented proper closing of the check valve. This buildup was from the system. The check valve was cleaned and on 7/12/84 the valve was retested with a leakage of 0.020 Lbs/hr.
PCAC-V16-19-8 On 6/29/84, the containment purge isolation valve was leak tested and found to have a leakage of 7.866 Lbm/hr (>0.522 Lbe/hr). The valve was disassembled and the seating surface was found to be worn. This wear was considered to be normal. On 7/24/84, the valve was successfully retested with a leakage of 0.294 lba/hr. CA-89C On 7/12/84, the Containment air compressor discharge check valve, CA-89C, was leak tested and found to have a leakage of 0.010 Lba/hr. Although this is < 0.522 Lba/hr, the valve had to be cycled to get it to seat. For this reason, it
- was considered a failure. The valve was disassembled and found to have corro-i sion by product, from the system piping, on the seat. The valve was cleaned and on 7/24/84, successfully tested 0.001 Lbm/hr.
During the 1985/86 Refueling / Recirculation Pipe Replacement outage 9/21/85 through 6/30/86, six primary containment isolation valves were found to have seat leakage, in excess of that permitted by the Technical specifications. They were: (a) MSIV-86C Main Steam Isolation (b) MSD-77 Main Steam Drain (c) CA-89B Containment Air Compressor Discharge (d) CRD 413A, 412A, 4138 Recirculation Pump Seal Purge For MSIV-86C, MSD-77, CA-89B and CRD 4139, a second valve on the same line provided proper containment isolation capability. Although CRD 413A and CRD o 412A are on the same line, total penetration leakage did not cause Vermont Yankee to violate the total allowable B and C limit. Testing, repair and retest details for these valves is described below: MSIV 86C On 9/21/85, the "C" outboard main steam isolation valve MSIV-86C was leak tested and found to have a leakage of 21.23 SCFH. (> than the 11.5 SCFH allowed). The valve was disassembled and found to have steam cuts on the disc seat. These steam cuts were attributed to normal wear. The seating surface was , refinished and on 5/27/86, the valve was successfully retested with a leakage of 1.072 SCFH. i MSD-77 l On 9/25/85, Main Steam Drain valve, MSD-77, was leak tested and found to have a leakage of 0.670 Lbm/hr. (> than 0.522 Lbm/ allowed). The valve was
1
~ disassembled and found to have cracks on the disc seat. These cracks were
' attributed to normal wear. The seating surface was refinished and on 5/27/86 the valve was successfully retested with a leakage of 0.400 Lbs/hr.
CA 89B On 9/30/85, the Containment Air Compressor Discharge check valve, CA-898, j was leak tested. 'The test personnel were unable to pressurize the test valve to j test pressure (44 psig). The valve was disassembled and found to have a buildup of corrosion product in the valve internals. This corrosion product was from i _the system pipinq. The valve was cleaned and on 5/29/86, successfully passed a i leak test with a leakage of 0.009 Lbe/hr. CRD 413A, 412A, 413B On 10/1/85, the Recirculation Pump Seal Purge check valves (supplied by the Control rode drive water system) CRD-413A, 412A and 4138 were leak tested and found to have leakages of 1.912 Lbs/hr, 1.519 and 0.801 Lbe/hr respectively. The valves were disassembled and found to have pitting on the valve seat. This pitting was attributed to improper spring tensioning (too high) which caused the-valves to cycle. The valve seats were reworked, new springs were installed and on 11/22/85, the valves were successfully retested with leakages of 0.073 Lbe/hr, 0.005 Lbe/Hr.and 0.009 Lbe/Hr. This maintenance was also performed on CRD 412B, a similar valve that initially passed the leak test but when disassembled had the same symptoms. It was successfully retested on 11/25/86 with a leakage of 0.006 Lbe/Hr.
- 2. Non-Tech Spec. Isolation Valves During the 1984 refueling outage, there was one valve tested which was determined to have excessive leakage. This valve is included in our leak test program for good maintenance practice but is not required to be tested by our Technical Specifications. It was:
i ) (a) FDW-96A - Feedwater check valve i I For FDW-96A, containment was provided by the water seal on the
- - inboard check valve and the plant's capability to maintain a pressure greater than Pa on the feedwater system.
FDW-96A i On 7/5/84, the outboard Feedwater check valve was leak tested and found to have a leakage equal to 7.09 Lbm/hr. This failure was attributed to a known ? manufacturer's defect in the seating surface. (see LER 83-10). The Steven's J soft seat was replaced with a Stillman soft seat and on 7/13/84 was successfully retested. Leakage was determined to be 0.017 Lbe/hr. I During the 1985/86 refueling / recirculation pipe replacement outage, there were three valves which were determined to have excessive leakage. There were: 4 i s
-,_.. _ ,._ _ ,_ _ __._, -._ ,-...,-,. ,,_ ._ - _-.-- ..~,-_ _ -.__. _ ...-__ -,,_
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- (a) FDW-96A Feedwater Check Valve (b) CRD-181 Control Rod Drive Water (c) RCU-15 Reactor Water Clean Up For FDW-96A, containment was provided by the water seal on the inboard check valve and the plant's capability to maintain a pressure greater than Pa on the feedwater system. For CRD-181 and RCU-15, a second valve on the same line provided the required containment capa-
'bility. All of these valves did operate properly even though Appendix J criteria was exceeded.
FDW-96A On 9/27/85, the outboard feedwater check valve was leak tested. Test per-sonnel were unable to pressurize to test pressure (44 psig). Since this was the third year these valves have failed (failure in past years has been attributed to a known Manufacturer's defect in.the soft seat) an investigation was ini-tiated by Vermont Yankee to determine the cause of failure. This investigation revealed that there was a misalignment of the check valve swing arm. This
- resulted in excessive leakage. This condition was corrected and on 1/9/86,
. FDW-96A was successfully retested with a leakage of 0.067 Lbe/hr. CRD-181 On 10/17/85, the control rod drive to reactor water cleanup check valve, CRD-181, was leak tested and found to have a leakage of 2.489 Lbe/hr (>0.522 Lbm/hr allowed). The valve was disassembled and found to have a very minor crud buildup on the seat. The valve was cleaned and on 6/2/86 was retested with 0.000 leakage. The initial leakage was determined to be through one of the test boundary valves (not a containment isolation valve). This valve will be repaired at the next available time. RCU-15 On 9/21/85, the inboard reactor water cleanup isolation valve was leak tested and found to have a leakage of 2.375 Lbm/hr (>0.522 Lbe/hr allowed). The valve was disassembled and found to have cracks on the valve seat. These cracks were attributed to normal wear. The valve disc was replaced and on 6/19/86, the valve was successfully retested with a leakage of 0.043 Lbm/hr. Quantitive Calculations of Technical Specifications Limits _
- 1. The combined leak rate of all penetrations and valves subject to Type B and C tests shall be less than 0.60 La. Sixty (60) percent of LA = 354 lbm/ day.
- 2. The leakage from any one isolation valve shall not exceed 5% of Ltm. Five (5) percent of Ltm = 0.522 lbm/hr.
- 3. The leakage from any one main steam line isolation valve shall not exceed 11.5 SCFH at 24 PSIG (Pt).
General Conclusion The corrective action plans implemented by Vermont Yankee focuses attention on the root cause of the inability to meet (on first attempt) the acceptance cri-teria of the Type A, B, and C tests. Based upon the above information, and suc-cessful completion of the Type A, B, and C Leak Rate Tests, along with the
' corrective actions'taken, it is concluded that the cor.dition of the Primary Containment System is acceptable for continued plant operation. The plant was returned to service with a containment leakage of less than 0.1546 wt%/ day.
This compares to the allowed leakage of 0.600 wt%/ day. The next Type A test will be performed during the 1989 Refueling Outage. r '9 -
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+- Summary Test Results for Type B Testina Table 84-B PENETRATION LEAKAGE (LBM/HR)
NUMBER DESCRIPTION INITIAL RETEST X-2 Personnel Lock 1.070 2.150 Bellows Seals . X-7A Main Steam Line A 0.000 X Main Steam Line B 0.000 X-7C Main Steam Line C 0.000 X-7D Main Steam Line D 0.000 X-9A Feedwater A 0.000
.X-98 Feedwater B 0.000 X-11 HBCI Steam Line 0.000 X-12 RHR Suction 0.000 -X-13A 'RHR Return A 0.000 X-13B RHR Return B 0.000 X-14 Cleanup Suction 0.000 X-16A Core Spray A 0.000 X-16B Core 5-ray B 0.000 Elertrical Penetrations 100A Electrical Penetration 0.000 1008 Electrical Penetration 0.001 100C Electrical Penetration 0.000 100D Electrical Penetration 0.000 101A Electrical Penetration 0.000 101C Electrical Penetration 0.051
Table 84-B (Cont'd) Summary Test Results for Type B Testina PENETRATION LEAKAGE (LBM/HR) NUMBER DESCRIPTION INITIAL RETEST 101D Electrical Penetration 0.000 102 Electrical Penetration 0.008 103 Electrical Penetration 0.001 104A Electrical Penetration 0.001 104B Electrical Penetration 0.000 104C Electrical Penetration 0.000 105A Electrical Penetration 0.000 1058 Electrical Penetration 0.000 105C Electrical Penetration 0.000 105D Electrical Penetration 0.007 214 Electrical Penetration 0.000 Double Gasketed Seals X-1 Equipment Hatch 0.002 X-4 Drywell Head Access Hatch 0.000 X-6 Control Rod Drive Removal Not Tested 0.000 Hatch prior to opening X-200A Torus Access Hatch 0.000 0.000 X-200B Torus Access Hatch 0.000 0.000 VBC-A Vacuum Breaker Access 0.000 Cover VBC-B Vacuum Breaker Access 0.000 Cover VBC-C Vacuum Breaker Access 0.000 Cover VBC-D Vacuum Breaker Access 0.000 Cover VBC-E Vacuum Breaker Access 0.000 Cover
4 Table 84-B (Cont'd) Summary Test Results for Type B Testina PENETRATION LEAKAGE (LBM/HR) NUMBER DESCRIPTION INITIAL RETEST VBC-F Vacuum Breaker Access 0.000 Cover VBC-G Vacuum Breaker Access 0.000 Cover VBC-H Vacuum Breaker Access Cover 0.000 VBC-I Vacuum Breaker Access Cover 0.000 VBC-J' Vacuum Breaker Access Cover 0.000 VBSL-A Vacuum Breaker Shaft Left 0.000
- VBSR-A Vacuum Breaker Shaft Right 0.000 VBSL-B Vacuum Breaker Shaft Left 0.074 0.000 VBSR-B Vacuum Breaker Shaft Right 0.000 VBSL-C Vacuum Breaker Shaft Left 0.000 VBSR-C Vacuum Breaker Shaft Right 0.000 - VBSL-D Vacuum Breaker Shaft Left 0.000 VBSR-D Vacuum Breaker Shaft Right 0.000 VBSL-E Vacuum Breaker Shaft Left 0.002 VBSR-E Vacuum Breaker Shaft Right 0.000 VBSL-F Vacuum Breaker Shaft Left 0.000 VBSR-F Vacuum Breaker Shaft Right 0.000 VBSL-0 Vacuum Breaker Shaft Left 0.000 VBSR-0 Vacuum Breaker Shaft Right 0.000 VBSL-H Vacuum Breaker Shaft Left 0.000 VBSR-H Vacuum Breaker Shaft Right 0.000 VBSL-I Vacuum Breaker Shaft Left 0.000 VBSR-I Vacuum Breaker Shaft Right 0.000
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1 Table 84-B (Cont'd) Summary Test Results for Type B Testina PENETRATION LEAKAGE (LBM/HR) NUMBER DESCRIPTION INITIAL RETEST j l VBSL-J Vacuum Breaker Snaft Left 0.000 ; VBSR-J Vacuum Breaker Shaft Right 0.000 l SLH-A Shear Lug Access Cover 0.000 SLH-B Shear Lug Access Cover 0.000 SLH-C Shear Lug Access Cover 0.000 SLH-D Shear Lug Access Cover 0.000 SLH-E Shear Lug Access Cover 0.004 SLH-F Shear Lug Access Cover 0.000 SLH-G Shear Lug Access Cover 0.000 SLH-H Shear Lug Access Cover 0.000 Drywell Head Flange 0.001 0.002 X-213-A Torus Drain 0.000 X-213-B Torus Drain 0.000 X-35A TIP Penetration Flange 0.000 X-35B TIP Penetration Flange 0.000 X-35C TIP Penetration Flange 0.000 X-35E TIP Penetration Flange 0.000 Total B Penetration Leakage After Repairs 2.229
i Summary Test Results for Type C Testina Table 84-C LEAKAGE (LBM/HR)
- VALVE'S) TESTED DESCRIPTIDN INITIAL RETEST
- MS-77 Main Steam Drain 0.472 RV39 & 40 Recirc. Sample 0.002 RHR-57 RHR Disch. to Radwaste 0.017 LRW-83 Drywell Floor Drain 0.006 LRW-95 Drywel Equip. Drain 0.032 SB-16-19-8,9,10 & 23 Containment Purge 7.866 0.294 S8-16-19-11A, & 12A Vacuum Relief 0.259 SB-16-19-11B & 128 Vacuum Relief 0.048 S8-16-19-6,7,6A,68,7A Containment Exhause 0.572 and 7B RCU-18 Reactor Cleanup 0.007 V-16-20-20 Containment Purge Makeup 0.002 V-16-20-22A Containment Purge Makeup 0.001 V-16-20-22B Containment Purge Makeup 0.003 RCU-68 Reactor Cleanup 0.020 0.017 CRD-181 Control Rod Drive 0.011 HPCI-16 HPCI Steam Supply 0.030 RCIC-16 RCIC Steam Supply 0.111 CA-38A Cont. Air Compressor 0.007 CA-388 Cont. Air Compressor Suction 0.007 CA-898 Cont. Air Compressor Discharge 0.032 CA-89C Cont. Air Compressor Discharge 0.010 0.001 I
NG 13A & 13B, 15 CAD Injection 0,.011 NG 12A & 128 CAD Injection 0.004 , I s
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t-Table 84-C (Cont'd) Summary Test Results for Type C Testina , LEAKAGE (LBM/HR)
'/ALVE(S) TESTED DESCRIPTION INITIAL RETEST -NG 11A & 11B CAD Injection 0.017 VG-9A CAD Vent 0.003 VG-22A CAD Vent 0.004 VG-98 CAD Vent 0.010 VG-22B CAD Vent 0.013 VG-23 CAD Rad. Mon. Supply 0.007 VG-26 CAD Rad. Hon. Supply 0.018 VG-76A Rad. Mon. Return 0.012 VG-76B Rad. Hon. Return 0.010 MS-74 Main Steam Drain 0.117 HPCI-15 HPCI Steam Supply 0.030 RCIC-15 RCIC Steam Supply 0.111 RCU-15 Reactor Cleanup 0.155 LRW-82 Drywell Floor Drain 0.003 LRW-94 Drywell Equipment Drain 0.043 RHR-66 RHR Discharge to Radwaste 0.022 SB-16-19-51 PCAC 0.010 SB-16-19-52 PCAC 0.006 IA-103 Instrument Air Check Valve 0.027 FDW-27A Feedwater Check Valve 0.034 0.023 FDW-96A Feedwater Check Valve 7.090 0.017 MS80A A Main Steam Line 0.010 MS86A A Main Steam Line 2.078 MS808 B Main Steam Line 0.044
Table 84-C (Cont'd) Summary Test Results for Type C Testing LEAKAGE (LBM/HR) VALVE (S)' TESTED DESCRIPTION INITIAL RETEST MS868 B Main Steam Line 4.743 0.046 MS80C C Main Steam Line 0.000 MS86C C Main Steam Line 2.866 MS80D D Main Steam Line 0.000 MS860 C Main Steam Line 0.194 CRD-412A Recirc Pump Seal Purge 0.011 CRD-413A Recirc Pump Seal Purge 5.461 0.020 s CRD-4128 Recirc Pump Seal Purge 0.041 CRD-4138 Recirc Pump Seal Purge 0.004 l X-35A Tip Purge Check Valve 0.003 X-35A Tip Purge Solenoid Valve 0.024 X-35C Tip Ball Valve #1 0.095 i X-350 Tip Ball Valve #2 0.015 X-35E Tip Ball Valve #3 0.007 i Total Type C Leakage Following Repairs 8.062
- Total Type B & C Leakage Following Repairs 10.291 4
1
. . _ _ . . _ . - . - _ . . _ _ _ _ . . _ _ _ - . . . . _ , - - - _ . , ~ _ _ _ _ . . . _ , , - , . _ , . _ . _ . _ . _ . . _ . _ , . _ . , . - , . . . _ _
- 7. .
Summary Test Results for Type B Testina Table 85, 868 PENETRATION LEAKAGE (LBM/HR)
' NUMBER DESCRIPTION INITIAL RETEST X-2 Personnel Lock 0.258 0.860 Bellows Seals
-X-7A Main Steam Line A
- X-7B Main Steam Line B
- X-7C Main Steam Line C
- X-7D Main Steam Line D
- X-9A Feedwater A
- X-98 Feedw 'er B
- X-11 HPCI Steam Line
- X-12 RHR Suction
- X-13A RHR Return A
- X-138 RHR Return B
- X-14 Cleanup Suction
- X-16A Core Spray A
- X-16B Core Spray B
- Electrical Penetrations 100A Electrical Penetration 0.003 0.000 1008 Electrical Penetration 0.001 0.004 100G Electrical Penetration 0.001 0.000 1000 Electrical Penetration 0.003 0.000 l
- BELLOW NOT TESTED 85/86 SINCE A TYPE A TEST WAS PERFORMED AND ALL BELLOWS WERE INSPECTED IN CONJUNCTION WITH THAT TEST.
e Table 85, 86-B (Cont'd) Summary Test Results for Type B Testina PENETRATION LEAKAGE (LBM/HR) NUMBER DESCRIPTION INITIAL RETEST 101A Electrical Penetration 0.000 101C Electrical Penetration 0.061 0.000 101D Electrical Penetration 0.000 102 Electrical Penetration 0.011 103 Electrical Penetration 0.000 0.001 104A Electrical Penetration 0.000 0.000 104B Electrical Penetration 0.001 0.000 104C Electrical Penetration 0.000 0.000 105A Electrical Penetration 0.000 105B Electrical Penetration 0.001 105C Electrical Penetration 0.000 105D Electrical Penetration 0.008 214A Electrical Penetration 0.000 0.000 Double Gasketed Seals l X-1 Equipment Hatch 0.002 0.001 X-4 Drywell Head Access Hatch 0.000 X-6 Control Rod Drive Removal Hatch 0.000 0.000 X-200A Torus Access Hatch 0.000 0.000 X-2008 Torus Access Hatch 0.000 0.000 VBC-A Vacuum Breaker Access Cover 0.000 0.000 VBC-B Vacuum Breaker Access Cover 0.003 0.000 VBC-C Vacuum Breaker Access Cover 0.000 VBC-D Vacuum Breaker Access Cover 0.000 2.
7 ;- -
' Table 85,86-B (Cont'd) Summary Test Results for Type B Testina PENETRATION LEAKA0E (LBN/HR)
NUMBER DESCRIPTION INITIAL RETEST EVBC-E Vacuum Breaker Access Cover 0.000 VBC-F Vacuum ~ Breaker Access Cover 0.000 VBC-G Vacuum Breaker Access Cover 0.000 VBC-H Vacuum Breaker Access Cover 0.000 VBC-I Vacuum Breaker Access Cover 0.000 0.000 VBC-J Vacuum Breaker Access Cover 0.000 0.000 VBSL-A Vacuum Breaker Shaft Left 0.132 0.000 VBSR-A Vacuum Breaker' Shaft Right 0.006 0.000 VBSL-B Vacuum Breaker Shaft Left 2.419 0.000 VBSR-B Vacuum Breaker Shaft Right- 0.001 0.000 VBSL-C Vacuum Breaker Shaft Left 0.042 0.000 VBSE-C Vacuum Breaker Shaft'Right 0.007 0.000 VBSL-D Vacuum Breaker Shaft Left 0.007 0.000 VBSR-D Vacuum Breaker Shaft Right 0.001 0.000 VBSL-E Vacuum Breaker Shaft Left 0.002 0.000 VBSR-E Vacuum Breaker Shaft Right 0.003 0.000 VBSL-F Vacuum Breaker Shaft Left 0.002 0.000 VBSR-F Vacuum Breaker Shaft Right 0.000 0.000 VBSL-G Vacuum Breaker Shaft Left 0.006 0.000 VBSR-G Vacuum Breaker Shaft Right 0.000 0.000 VBSL-H Vacuum Breaker Shaft Left 0.000 0.000 VBSR-H Vacuum Breaker Shaft Right 0.000 0.000 VBSL-I Vacuum Breaker Shaft Left 0.002 0.000 VBSR-I Vacuum Breaker Shaft Right 0.000 0.001
T Table 85,86-8 (Cont'd) Summary Test Results for Type B Testina PENETRATION LEAKAGE (LBM/HR) NUMBER DESCRIPTION INITIAL RETEST VBSL-J Vacuum Breaker Shaft Left 0.000 0.000 VBSR-J Vacuum Breaker Shaft Right 0.000 0.000 SLH-A Shear Lug Access Cover 0.000 SLH-B Shear Lug Access Cover 0.000 SLH-C Shear Lug Access Cover 0.000 SLH-D Shear Lug Access Cover 0.000 SLH-E Shear Lug Access Cover 0.004 SLH-F Shear Lug Access Cover 0.000 SLH-G Shear Lug Access Cover 0.001 SLH-H Shear Lug Access Cover 0.000 Drywell Head Flange 0.012 0.005 X-213-A Torus Drain 0.000 X-213-B Torus Drain 0.000 X-35A TIP Penetration Flange 0.000 X-358 TIP Penetration Flange 0.000 X-35C TIP Penetration Flange 0.000 X-35E TIP Penetration Flange 0.000 Total B Penetration Leakage After Repairs 0.897
I Table 85,86-C Summary Test Results for Type C Testina LEAKAGE (LBM/HR) VALVE (S) TESTED DESCRIPTION INITIAL RETEST MS-77 Main Steam Drain 0.670 0.400 RV39 & 40 Recirc. Sample 0.001 RHR-57 RHR Disch. to Radwste 0.003 LRW-83 Drywell Floor Drain 0.011 0.228 LRW-96 Drywell Equip. Drain 0.013 0.033 SB-16-19-8,9,10 & 23 Containment Purge 0.371 SB-16-19-11A & 12A Vacuum Relief 0.069 SB-16-19-11B & 128 Vacuum Relief 0.066 SB-16-19-6,7,6A,68,7A Containment Exhaust 0.198 and 78 RCU-18 Reactor Cleanup 0.000 V-16-20-20 Containment Purge Makeup 0.117 V-16-20-22A Containment Purge Makeup 0.142 V-16-20-22B Containment Purge Makeup 0.001 RCU-68 Reactor Cleanup
- 0.000 CRD-181 Control Rod Drive 2.489 0.000 HBCI-16 HPCI Steam Supply 0.004 0.048 RCIC-16 RCIC Steam Supply 0.062 CA-38A Cont. Air Compressor 0.001 CA-388 Cont. Air Compressor Suction 0.070 CA-89B Cont. Air Compressor Discharge ** 0.009 CA-89C Cont. Air Compressor Discharge 0.016 NO 13A & 13B CAD Injection 0.001
*Not tested before removal, valve was replaced during the outage. ** Unable to pressurize to test pressure (44 psig)
Table 85,86C (Cont'd) Summary Test Results for Type C Testina LEAKAGE (LBM/HR) VALVE (S) TESTED DESCRIPTION INITIAL RETEST NG 12A & 128 CAD Injection 0.001 NG 11A & 11B CAD Injection 0.003 VG-9A CAD Vent 0.004 VG-22A CAD Vent 0.250 VG-98 CAO Vent 0.001 VG-228 CAD Vent 0.001 VG-23 CAD Rad. Mon. Supply 0.001 VG-26 CAD Rad. Hon. Supply 0.001 VG-76A Rad. Mon. Return 0.010 VG-76B Rad. Mon. Return 0.006 MS-74 Main Steam Drain 0.033 HPCI-15 HPCI Steam Supply 0.004 RCIC-15 RCIC Steam Supply 0.062 RCU-15 Reactor Cleanup 2.375 0.043 LRW-82 Drywell Floor Drain 0.012 0.003 LRW-94 Drywell Floor Drain 0.004 0.228 RHR-66 RHR Discharge to Radwaste 0.009 S8-16-19-51 PCAC 0.012 S8-16-19-52 PCAC 0.029 IA-103 Instrument Air Check VL"ve 0.094 FDW-27A Feedwater Check Valve 0.102 0.045 FDW-96A Feedwater Check Valve ** 0.067 CRD-413B Recirc Pump Seal Purge ISO 0.801 0.009 Valves (check)
** Unable to pressurize to test pressure (44 psig)
(( Table 85,86C (Cont't) Summary Test Results for Type C Testina LEAKAGE (LBM/HR) VALVE (S) TESTED DESCRIPTION INITIAL RETEST CRD-413A Recirc Pump Seal Purge ISO 1.912 0.073 Valves (check) CRD-412A Recirc Pump Seal Purge ISO 1.519 0.005 Valves (check) CRO-412B Recirc Pump Seal Purge ISO 0.162 0.006 Valves (check) MS80A A Main Steam Line 0.039 MS86A A Main Steam Line 1.610 MS808 B Main Steam Line 0.111 MS808 B Main Steam Line 0.782 MS80C C Main Steam Line 0.000 MS86C C Main Steam Line 5.462 0.080 MS800 D Main Steam Line 0.000 MS86D D Main Steam Line 1.192 X-35A TIP Purge Check Valve 0.000 X-35A TIP Purge Solenoid Valve 0.412 X-35C TIP Ball Valve #1 0.009 X-35D TIP Ball Valve #2 0.001 X-35E TIP Ball Valve #3 0.000 Total Type C Leakage Following Repairs 7.072 Total Type B & C Leakage Following Repairs 7.969
TABLE D Leakage Test Performed Outside of Shutdown Type B Penetration Description Date Leakaae (lbe/hr) X-2 Personnel Lock 08/13/84 3.44 X-2 Personnel Lock 09/29/84 2.706 X-2 Personnel Lock 10/02/84 1.692 X-2 Personnel Lock 02/07/85 1.734 X-2 Personnel Lock 08/07/85 0.172 N/A Drywell Head Flange 09/19/84 0.006 N/A Drywell Head Flange 09/27/84 0.009 X-2 Personnel Lock 08/20/86 2.79 l DLP/meh:ES60814.1/DLP
AIR SUPPLY SCilEMATif* ____ g r _, __ .__ Air Purge Supply l _ d .. . .
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V-16-l' -8 l Air Compressors FT-1-156-2 i
"2 Bulk storage Tank TI-1-156-9
- Disconnecting a fitting on FT-1-156-2 following
. Isolation and depressur-ization of charging iine i provides required vent path l V-16 ,19-23 Torus
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i 1 lD g O + q O ri e og ab- i se . d v ct
s PRIMARY CONTAINMENT LEAKAGE RATE DATA SHEET Table 1986-Al Time Contained Pressure Temp.
- Time Contained Pressure Temp (Min Mass (pounds in. Ha *F * (Min) Mass (pounds) in. Ha 'F O 73598.273 119.730 85.0
- 212 73575.741 119.280 84.7 10 73601.306 119.700 84.9
- 222 73549.836 119.250 84.9 20 73615.885 119.670 84.9
- 232 73515.525 119.250 85.2 30 73607.583 119.630 84.8
- 242 73511.884 119.210 85.1 40 73590.142 119.610 84.9
- 253 73519.617 119.210 85.1 51 73609.492 119.610 84.9
- 263 73531.766 119.210 85.1 61 73577.568 119.580 85.1
- 273 73513.940 119.190 85.2 71 73591.150 119.580 85.1
- 283 73501.451 119.160 85.2 81 73599.114 119.580 85.1
- 293 73476.280 119.120 85.2 91 73856 813 119.520 85.2
- 303 73485.662 119.120 85.2 101 73575.173 119.490 85.2
- 313 73491.943 119.120 85.1 111 73577.986 119.460 85.1
- 323 73494.203 119.120 85.2 121 73577.330 119.460 85.2
- 333 73481.310 119.090 85.2 131 73566.839 119.420 85.2
- 343 73474.406 119.090 85.2 141 73558.963 119.400 85.1
- 354 73474.417 119.070 85.3 152 73570.208 119.400 85.1
- 364 73481.924 119.070 85.2 162 73565.036 119.370 85.1
- 374 73495.526 119.070 85.1 172 73561.102 119.370 85.1
- 384 73463.570 119.040 85.3 182 73534.790 119.250 84.7
- 394 73434.339 119.000 85.3 192 73569.552 119.250 84.4
- 404 73448.141 119.000 85.2 202 73553.416 119.210 84.2
- 414 73455.836 119.000 85.1 Test Asst. -
Date 2 M , Approved VYOPF 4029.04A Riv. 3
3 PRIMARY CONTAINMENT LEAKAGE RATE DATA SHEET Table 1986 A-1 Time Contained Pressure Temp.
- Time Contained Pressure Temp (Min Mass (pounds in. Ha 'F * '(Min) Mass (pounds) in. Ha 'F 424 73442.264 118.980 85.3
- 434 73442.450 118.980 85.2
- 445 73443.968 118.950 85.1
- 455 73457.855 118.980 85.0
- 465 73438.489 118.950 85.2
- 475 73451.282 118.950 85.1
- 485 73426.187 118.920 85.0
- 495 73435.298 118.920 85.0
- 505 73425.998 118.920 85.1
- 515 73401.230 118.880 85.2
- 525 73403.231 118.880 85.1 *
'73414.813 118.880 85.0
- __E36 546 73410.545 118.860 85.1
- 556 73396,137 118.860 85.1
- 566 73391.945 118.830 85.0
- 576 73393.547 118.830 85.0
- 586 73385.258 118.830 85.1
- 596 73392.747 118.830 85.0
- Test Stopped
- k i Test Asst. /*#1
- si Date $'d? 'N Approved VYOPF 4029.04A Rsv. 3 i
i L.
PRIMARY CONTAINMENT LEAKAGE RATE DATA SHEET Table 1986-A2 Time Contained Pressure Temp.
- Time Contained Pressure Temp (Min Mass (pounds in. Ha 'F * (Min) Mass (pounds) in. Ha 'F O 74073.240 119.870 85.2
- 213 74070.919 119.820 85.2 10 74073.639 119.870 85.2
- 223 74032.424 119.790 85.3 20 74080.210 119.870 85.2
- 234 74039.786 119.790 85.3 31 74072.665 119.870 85.3
- 244 74085.434 119.820 85.1 41 74072.440 119.870 85.2
- 254 74060.272 119.790 85.2 51 74074.436 119.870 85.2
- 264 74053.501 119.790 85.2 61 74081.007 119.870 85.2
- 274 74059.683 119.790 85.2 71 74062.408 119.840 85.2
- 284 74059.683 119.790 85.2 81 74080.609 119.870 85.2
- 295 74052.936 119.790 85.3 91 74068.182 119.840 85.2
- 305 74043.028 119,750 85.2 102 74061.610 119.840 85.2
- 315 74092.416 119.790 85.1 112 74068.581 119.840 85.2
- 325 74049.182 119.750 85.1 122 74055.661 119.840 85.3
- 335 74055.416 119.730 85.2
-132 74054.067 119.840 85.3
- 345 74054.033 119.730 85.2 142 74061.835 119.840 85.3
- 355 74047.685 119.730 85.3 152 74054.812 119.820 85.3
- 366 74060.380 119.730 85.1 163 74082.700 119.840 85.1
- 376 74075.389 119.750 85.2 173 74058.561 119.820 85.2
- 386 74062.784 119.730 85.2 183 74071.710 119.820 85.2
- 396 74056.396 119.730 85.2 193 74064.739 119.820 85.2
- 406 74068.191 119.730 85.2 203 74064.739 119.820 85.2
- 416 74063.763 119.730 85.2 Test Asst. M/
Date 2.54 Approved VYOPF 4029.04A Rsv. 3
PRIMARY CONTAINMENT LEAKAGE RATE DATA SHEET Table 1966-A2 Time Contained Pressure Temp.
- Time Contained Pressure Temp (Min Mass (pounds in. Ha 'F * (Min) Mass (pounds) in. Ha 'F 426 74045.147 119.700 85.2
- 640 74024.958 119.630 85.2 437 74061.800 _119.730 85.2
- 650 74031.932 119.630 85.2 447 74069.172 119.730 85.2
- 660 74013.699 119.610 85.2 457 74052.512 119.700 85.2
- 670 74031.159 119.630 85.2 467 74036.997 119,700 85.2
- 680 74019.131 119.610 85.2 477 74052.902 119.700 85.2
- 690 74026.107 119.610 85.2 487 74050.753 119.700 85.2
- 701 74036.560 119.610 85.2 498 74042.975 119.670 85.1
- 711 74024.571 119.630 85.2 508 74068.019 119.700 85.2
- 721 74037.039 119.610 85.4 518 7A040.870 119.670 85.2
- 731 74012.001 119.610 85.3 528 74048.007 119.670 85.1
- 741 74050.520 119.610 85.2 538 74066.467 119.700 85.2
- 751 74045.127 119.610 85.3 548 74040.090 119.670 85.2
- 762 74036.795 119.610 85.3 558 74033.346 119.670 85.3
- 772 74041.839 119.610 85.3 569 74043.582 119.670 85.2
- 782 74044.931 119.610 85.3 579 74042.424 119.670 85.2
- 792 74031.209 119.610 85.4 589 74049.785 119.670 85.2
- 802 74031.592 119.610 85.4 599 74047.652 119.670 85.2
- 812 74038.439 119.610 85.4 609 74023.408 119.630 85.2
- 823 74037.952 119.610 85.3 619 74025.351 119.630 85.2
- 833 74044.608 119.630 85.4 630 74017.053 119.640 85.3
- 843 74024.232 119.610 85.4 d
y m Test Asst.
,a Oate d -23 ,d_
Approved M.-,b VYOPF 4029.04A R;v. 3
PRIMARY CONTAINMENT LEAKAGE RATE DATA SHEET TABLE 1986-A2 Time- Contained Pressure Temp.
- Time Contained Pressure -Temp (Min Mass (pounds in. Ha 'F * (Min) Mass (pounds) in. Ha 'F 853 74023.699 119.610 85.5
- 1066 73991.834 119.630 85.7 863 74023.699 119.610 85.5
- 1076 73984.962 119.630 85.9 873 74030.439 119.610 85.4
- 1087 74005.929 119.630- 85.6 883 74030.824 119.610 85.4
- 1097 74009.777 119.670 85.9 894 74029.281 119.610 85.4
- 1107 73992.806 119.630 85.7 904 74028.606 119.630 85.6
- 1117 73991.300 119.630 85.8 914 74014.011 119.610 85.5
- 1127 73983.934 '119.630 85.8 924 74023.314 119.610 85.5
- 1137 73990.128 119.630 85.8 934 74043.046 119.630 85.4
- 1148 73969.454 119.630 85.9
'944 74015.420 119.610 85.6
- 1158 73983.934 119.630 85.8 955 74021.961 119.610 85.5
- 1168 74008.358 119.670 85.8 i
- 965 74014.846 119.630 85.6
- 1178 74001.382 119.670 85.8 975 74007.083 119.610 85.6
- 1188 74001.240 119.670 85.9 985 74008.779 119.610 85.5
- 1198 73988.072 119.670 85.9 995 74000.882 119.610 85.5
- 1208 73976.428 119.630 85.9 1005 74000.104 119.610 85.6
- 1219 73970.236 119.630 85.9 1015 74012.516 119.630 85.6
- 1229 73995.046 119.670 85.9 1026 73999.197 119.630 85.7
- 1239 73994.407 119.670 85.8 1036 74024.016 119.670 85.7
- 1249 73994.264 119.670 85.9 1046 74005.395 119.630 85.7
- 1259 73999.868 119.670 85.9 1056 74000.746 119.630 85.7
- 1269 73986.756 119.670 86.0 Test Asst, b hw' t' l' Date /i d.79/l Approved _g@ p VYOPF 4029.04A Rsv. 3
, PRIMARY CONTAINMENT LEAKAGE RATE DATA SHEET TABLE 1986-A2 Time Contained Pressure l Temp.
- Time Contained Pressure Temp (Min ~ Mass (pounds in. Ha *F * (Min) Mass (pounds) in. Ha 'F 1280 73978.600 119.670 86.0
- 1290 73973.061 119.670 86.1
- 1300 73992.197 119.670 86.0
- 1310 73996.481 119.670 86.1
- 1320 73966.676 119.670 86.1
- 1330 74005.538 119.670 86.0
- 1340 73965.501 119.670 86.1
- 1351 73997.973 119.670 86.0
- 1361 73990.860 119.670 86.1
- 1371 73991.055 *19.670 86.1
- 1381 73977.758 119.670 86.2
- 1391 73931.645 119.670 86.1
- 1401 739?9.071 119.670 86.1
- 1412 73985.260 119.670 86.1
- 1422 73991.842 119.670 86.1
- 1432 73979.071 119.670 86.1
- 1442 73970.650 119.670 86.3
- FINISH
- 24 HOUR TEST
- Test Asst.
/
bc ['
= -
Oate d=2,7 Approved M/ga.
- VYOPF 4029.04A R v.-3
PRIMARY CONTAbNENT LEAKAGE RATE 04TA SHEET TABLE 1986-A2 VERIFICATION TEST Tine Contained Pressure Temp.
- Time Contained Pressure Temp (Min Mass (pounds in. Hg F * (Min) Mass (pounds) in. Hg F 0 73881.872 119.490 86.4
- 212 73814.407 119.370 86.4 10 73905.000 119.540 86.5
- 222 73822.674 119.370 86.3 20 73895.151 119.490 86.3
- 232 73790.772 119.330 86.4 30 73881.996 119.490 86.3
- 242 73791.166 119.330 86.4 40 73888.967 119.490 86.3
- 252 73815.586 119.370 86.4 50 73862.870 119.460 86.4
- 262 73789.594 119.330 86.4 60 73871.538 119.460 86.3
- 272 73796.560 119.330 86.4 70 73870.751 119.460 86.3
- 283 73789.988 119.330 86.4 80 73869.958 119.460 86.3
- 293 73764.298 119.300 86.5 __
91 73879.096 119.460 86.3
- VERIFICATION TEST #2 00MPLETE 101 73856.295 119.460 86.4
- 111 73864.445 119.460 86.4
- 121 73832.154 119.420 86.5
- 131 73838.972 119.420 86.3
- 141 73851.211 119.420 86.4
- 151 73846.602 119.420 86.4
- 161 73820.143 119.400 86.5
- 171 73825.654 119.400 86.4
- 182 73813.618 119.370 86.4
- 192 73808.228 119.370 86.4
- 202 73840.772 119.400 86.4
- Test Asst.
yj I.s ya[us' Date 4-It -// Approved , VYOPF 4029.04A Rev. 3 OLP/gnv.ES60815.1/t1_P
I VERMONT YANKEE
. NUCLEAR POWER CORPORATION
. RD 5, Box 169, Ferry Road, Erattleboro, VT 05301 REPLY TO:
y ENGINEERING OFFICE 1671 WORCESTER ROAD
- FRAMINGHAM, M ASSACHUSETTS 01701 October 3, 1986 TELEPHONE 617-872-6100 nY 86 United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Office of Nuclear Reactor Regulation Harold R. Denton, Director
Reference:
(a) License No. DPR-28 (Docket No. 50-271)
Subject:
Primary Containment Leak Rate Test Report
Dear Sir:
In accordance with the requirements of Appendix J to 10CFR50, we hereby submit a copy of the report entitled, " Vermont Yankee Primary Containment Leakage Rate Testing 1986." We trust this information is acceptable to you; however, should you have any questions, please contact us. Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION Robert W. C pstick Licensing Engineer RWC/bil Enclosure Oh
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