ML20069D961
| ML20069D961 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 12/31/1982 |
| From: | STONE & WEBSTER ENGINEERING CORP. |
| To: | |
| Shared Package | |
| ML20069D957 | List: |
| References | |
| NUDOCS 8303210155 | |
| Download: ML20069D961 (60) | |
Text
{{#Wiki_filter:.- . - - k i@ ; 4 REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST s i TYPE A, B, AND C PREOPERATIONAL TEST I LONG ISLAND LIGHTING COMPANY Shoreham Nuclear 4. Power Station , Unit No. 1 4 i December 1982 4 4 PREPARED BY STONE & WEBSTER ENGINEERING CORPORATION BOSTON, MASS i 8303210155 830310 PDR ADOCK 05000322 A PDR i
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1 1 l 1 1 TABLE OF CONTENTS A., .. Section Title Page 1 FURPOSE 1-1 2
SUMMARY
2-1 2.1 Type A Test 2-1 2.1.1 Test Summary 2-1 2.1.2 Conclusions 2-4 2.1.3 Corrective Action Plan 2-5 2.2 Local Leak Rate Tests (B and C) 2-6 3 TYPE A TEST 3-1 , 3.1 Edited Log of Events 3.1-1 3.2 General Test Description 3.2-1 3.2.1 Prerequisites 3.2-1 3.2.2 Equipment 3.2-2 3.2.3 Instrumentation 3.2-3 O 3.2.4 3.2.5 Data Acquisition System Data Resolution System ; 3.2-5 3.2-6 3.3 Test Results 3.3-1 3.3.1 Analysis of Test Results 3.3-1 3.3.2 61.096 Psia ILRT Results 3.3-3 3.3.3 Verification ~ Test Results 3.3-5 4 LOCAL LEAK RATE TESTS (TYPE B AND C) 4-1 O . I
REFERENCES jr** l 1
- 1. 10CFR50,. Appendix J, Primary Reactor Containment Leakage l Testing for Water-Cooled Power Reactors, October 22, 1980. '
- 2. Shoreham Nuclear Power Station Primary Containment Preoperational Integrated Leak Rate Test, PT.654.OO1-2.
- 3. ANSI /ANS-56.8, Containment System Leakage Testing Requirements, February 19, 19811
- 4. ANSI. N45.4, American National Standard Leakage-Rate Testing of Containment Structures % for Nuclear Reactors, March 16, 1972.
1 2 This document used only as a' guideline and any reference to said document in no way implies compliance. l
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LIST OF ATTACHMENTS
* ' , Attachment Title 2.1A Corrective Action Plan Instruments
-3.2A Site Meteorology 3.2B Instrumentation
- 3.2C ILRT Temperature Detector Locations 3.2D ILRT Dew Point Temperature Detector Locations 3.3A Integrated Leak Rate Test - Input Variables 3.3B Integrated Leak Rate Test - Absolute Method Test Results 3.3C Graph 1 - Containment Air Mass vs. Time 3.3D Graph 2 - Mass vs. Time 3.3E Graph 3 - Temperature vs. Time 3.3F Graph 4 - Total Pressure vs. Time t
3.3G Graph 5 - Leak Rate and UCL vs. Time 4A Local Leak Rate Test Data 4B Leakage Penalties Added to Type A Leakage e 0 . 1 i
h SECTION 1 (;^). t j FURPOSE The purpose of this report is to present a description and analysis of the December, 1982, Type A Preoperational Integrated Leak Rate Test (ILRT), and a summary of the Type B and C tests performed at the Shoreham Nuclear Power Station Unit 1, which is owned and operated by the Long Island Lighting Company. - This report is submitted as required by 10CFR50, Appendix J, Paragraph V.B. s
,1-1
SECTION 2 SUDIARY 2.1 TYPE A TEST 2.1.1 Test Summary On December 7, 1982, pressurization of the primary containment commenced at 2340 hours. The initial drywell and suppression chamber weighted average air temperatures ~ were 64 F and 72 F, respectively. s During the initial stages of pressurization, it was discovered that certain containment isolation valves may not have been entirely closed by their motor operators. In the process of hanging tags on the valves, the potential for hand-torquing the handwheel existed. This hand-torque checking process is typically performed to verify the valve position, before the tag is hung. Since this action may have violated the intent of the test, and since a satisfactory review of each tagging request was not able to verify the closure means, 68 valves were cycled to ensure the valve closure was performed by the normal means (i.e., no hand tightening). O Several leakage investigations primary containment presurization period. the investigations, a differential pressure transmitter) were performed during the During one of 1T47-PDT028B, was observed to be leaking through the flange adapter 0-ring. One of the bolts on the flange adapter was missing. The instrument was manually isolated by closure of the instrument isolation valves. Observations of primary containment water inventory were made throughout the pressurization period. The reactor level was dropping at approximately 75 gallons per hour. It was believed to be leaking out through the Control Rod Drive System. A steady drop in the suppression pool level' was noted, but it was determined that the level loss was-due to the water being displaced into the downcomers since they were capped in the drywell. Near the end of the pressurization period, an air block of 42 psig was established between each of the Main Steam isolation valves. This was performed since these valves were not considered as Type A leakage paths in the Shoreham accident analysis. The air block pressure, later increased to approximately 46 psig, was always maintained sufficiently below the Type A test pressure so as to prevent air in-leakage. O , 2-1
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y At. 1219 hours- on December 8, 1982, the pressurization source was secured with a peak pressure of 64.479 psia. g(ag { .For,:+he purpore -of this test, the Type A Pa pressure was increased to the design pressure (46.psig). This was done to ensure that- the test was performed above the maximum calculated design-basis-loss-of-coolant-accident pressure. At 1148 hours on December 8, 1982, the mass stablization period commenced. The drywell and suppression chamber weighted average air temperatures were 65 F and 73 F, respectively. _ Since the hand-torque checking process used to verify valve position before hanging a tag may pave also been performed on those valves in the open position (i.e., valve was backseated), 7 valves were cycled to ensure they were opened by their normal mode of operation. From approximately 1300 hours on December 8, 1982, to approximately 0100 hours on December 9, 1982, an intensive leakage investigation of all the penetration areas was performed to identify leakage paths. This search was initiated due to an average mass loss slightly in excess of the procedural mass stabilization rate of 15 lbm per hour. The following leakage paths and observations were noted: a. O Suppression pool level stopped decreasing when the compressors were secured. i
- b. A significant stem packing leak was observed on 1T46*AOVO38D.
- c. A flange leak on the discharge of lEll*RV152A was observed.
- d. Relatively minor packing leaks on other containment isolation valves.
- e. Decreasing RPV water level.
The following action was taken to reduce the leakage:
- a. At approximately 2100 hours on December 8, 1982, the CRD charging header and the Flow Station manual isolation valves were closed.
- b. At approximately 0230 hours on December 9, 1982, the packing gland on 1T46*AOV038D was tightened i to stop the leakage.
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', Note rc This-repair was done to isolate and quantify
.the leakage' path.
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- c. At approximately 0230 hours on December 9, 1982,
[ the flange on 1E11*RV152A was taped to -minimize [. leakage. These actions reduced the average mass loss' from approximately 19.3 lbm/hr (between 1548 hours on December 8, 1982, and 0148 hours on December 9, 1982) to an average mass loss of approximately 9.2 lbm/hr (between 0248 - to 0651 hours. on December 9, 1982). At 0730 hours on December 9, 1982, the tape on 1E11*RV152A' was removed in order to quantify flange leakagg. The average mass loss increased by approximately.2.11 lbm/hr (from 0751 hours to 1111 hours on December 9, 1982). The following estimates of' leakage can be obtained from a-review of the Type A mass trend data:-
- a. 1T46*AOV038D packing leakage 105 scfh b .- 1E11*RV152A flange leakage 28 scfh
- c. No significant mass trend change was observed t
when the CRD manual isolation valves were opened I . at 1130 hours on December 9, 1982. The O ILRT program was initiated with the first ten minute data average taken at 0811 hours on December 9, 1982, data collected- at approximately hourly intervals until with 0810 hours on December 10, 1982. A discussion of the ILRT test results is contained in Section 3.3. At 1400 hours on December 10, 1982, depressurization of the primary containment commenced. A steady increase in the pool level was observed, verifying the premise that the pool water had been forced up into the downcomers. Pool level subsequently raturned to the initial water level for a net change of zero throughout the entire test period. (See Section 3.3.2, Item 3.111.) O . 2-3
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r: l 8 2.1.2 Conclusions f The corrective 'actien plan proposed in Section 2.1.3 will
'provent recurrence of the identified leakage paths during glant operation.
The leakage paths were identified to be from IT46*AOV038D ste:n packing, 1T47-PDIO28B flange adapter, and 1 Ell *RV152A discharge flange. The Upper Confidence Level (UCL) obtained after the stem - packing adjustment and the instrument isolation was 0.217274 percent per day, which is well below the acceptance criteria. g O , ( 1
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.j 2.1.3 Corrective Action Plan fb IT/.6*A0V030D - Modify the Local Leak Rate Test (LLRT) procedure to test those containment isolation butterfly valves (IT46*AOV038D and IT46*AOV039D), which are currently reverse tested, to require pressurization from the containment side of the valves. This test will detect packing leaks as observed during the Type A test.
1T47-PDT028B - Those ' differential pressure cells, with sensing elements dismantled, will receive a hydrostatic - and/or pneumatic test to verify leaktightness of the instrument. The test pressure shall be at least equal to Pa in all cases. g Only those instruments which use a manufacturer equivalent differential pressure cell and are part of the Type a, B, and/or. C pressure boundary shall be subject to this corrective action plan. The plant specific instruments are , listed in Attachment 2.1A. Note: Instrument connections were broken numerous times during construction and startup testing for various reasons. None of these connections showed any noticeable leakage during the Type A test and are therefore not subject to this corrective action plan. 1 Ell *RV152A - Develop a special fitup procedure for the five bolted joints in the Type A boundary that cannot be Type C tested, and are not exposed to system pressure, but communicate with the primary containment (IEll*RV152A,B; 1 Ell *RV155; lEll*RV157A,B discharge flanges). The procedure will be validated using a bench test. O I 2-5 F -_. .
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2.2 LOCAL LEAK RATE TESTS (TYPES B AND C) j sur ' i/ The Local Leak Rate Tests (LLRT) of containment isolation valves and other primary containment penetrations were performed by the methods described in the plant preoperational test procedures PT.654.003-1, " Primary containment Leak Rate Test - Type C," and PT.654.002-3,
" Primary Containment Leak Rate Test - Type B."
In accordance with Appendix J to 10CFR50, Paragraph V.B, data for the Local Leak Rate Test is summarized in Section 4 of this report. s O 9 (s_ l ,2-6
,P v 'l ATTACHMENT 2.1A h* CORRECTIVE ACTION PLAN INSTRUMENTS (Rosemount "DP" Series)
! Nuclear Boiler System (IB21)
FT011A,B,C,D,E,F,G,H,J,K,L,M,N,P,R,S,T,U,V,W FT016A,B,C,D LT005
*LT154A,B,C,D
*LT155A,B,C,D
*LT157A,B,C,D
*LT159A,B FDT014 Reactor Recirculation System (1B31)
*FT011A,B
*FT012A,B
*FT013A,B
*FT014A,B PDT005A,B Control Rod Drive Hydraulic Control System (IC11) l FT001 FT005 FT006 PDT002 PDT003 Feedwater Control System (1C32)
FT001A,B FT002A,D,C,D LT008A,B,C Reactor Plant Remote Shutdown System (1C61)
*LT026 Residual Heat Removal System (1E11)
*FT001A,B Core Spray System (1E21)
*FT002A,B O ,Page 1,of 2
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(1-ATTACHMENT 2.1A (Cont'd) High Pressure Coolant Injection System (1E41)
*FT003 LT013 Reactor Core Isolation Cooling System (1E51)
*FT003 Radwaste System (1G11) s
*FT647C Reactor Water Cleanup System (1G33)
*FT091 Primary. Containment Air Cooling System (IT47)
PDT028A,B Primary Containment ILRT System (1749) PDT029 Post-Accident Tracking System (1Z93)
*LT001A,B
*LT012A,B
,Page 2 of 2 4
F~ l SECTION 3 A v' TYPE A TEST 3.1 EDITED LOG OF EVENTS This log was edited from the Test Engineer's ILRT Log. December 7, 1982 Drywell interior inspection completed at approximately 1400 hours. Inner door of Personnel Airlock, closed at 1405 hours. Type B LLRT performed on both main doors with a 0.0 scfh observed leak rate. At 2340 hours, pressurization of Primary Containment started. December 8, 1982 Between 0100 and 0440, cycled 68 isolation valves due to i operations red-tagging procedure of manually ensuring valves closed. At 0430 hours, performed gross leakage inspection. h At 0610 hours, 1T47-PDT028B was isolated due to major leakage by 0-ring. At 0800 hours, pumped approximately 1000 gallons of water from reactor building sump. At 0800 hours, reactor pressure vessel water level at 26.5 inches. Suppression pool water lovel at -18 inches. Reduced containment pressurization rate at 0934 hours. At 1045 hours, established 42 psig air block on MSIV lines A,B,C, and D. At 1119 hours, isolated containment pressurization system at a peak pressure of 64.479 psia. At 1150 hours, cycled 7 containment isolation valves due to operations red-tagging procedure of manually ensuring valves open. At 1400 hours, MSIV air block increased to 46 psig. At 1430, determined 1T46*AOV038D had leakage by stem , packing. l 3.1-1
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At 1435 hours, reactor vessel level at 23 inches. At 1600 hours, MSIV lines A,C, and D maintaining 46 psig air block. MSIV line B isolated with no air block. At approximately 2100 hours, isolated IC11-02V-0006 and j IC11-02V-0007A. December 9, 1982
- At 0230 hours, tightened 1T46*AOV038D packing gland and
( taped 1E11*RV152A discharge flange. At 0515 hours, plant computer tripped. At 0605 hours, plant computer reinitialized. At 0612 hours, suppression pool level stable at -18 inches and reactor level at 19 inches. At 0730 hours, tape was removed from 1E11*RV152A discharge flange to quantify leakage using the Type A program. At 0801 hours, satisfied stabilization requirements, started 24 hour ILRT test period. At 1130 hours, IC11-02V-0006 and 1C11-02V-0007A were re-opened. At 1431 hours, plant computer disc driver failed requiring manual input of data to back-up computer. At 1613 hours, disc driver restored. At 1711 hours, disc driver restarted, At 2010 hours, disc driver again failed. At 2151 hours, disc driver restarted at 2151 hours. December 10,1982 At 0220 hours, secured cooling water to drywell coolers. ILRT successfully completed at 0810 hours. Between 1153 and 1323 hours, successfully performed mass step change verification test with a constant flowrate of approximately 70 scfm. At 1400 hours, began containment depressurization. O 3'.1-2
f 1 At 1730 hours, depressurization stopped at 45 psia for
'd@ hydrogen recombiner system valve operability test.
5s Depressurization reinitiated at 1900 hours. December 11, 1982 At 0530 hours, containment depressurization completed. Suppression pool hatches and personnel air lock opened. At 0730 hours, primary containment post-test inspection r completed. No significant deviations from pretest inspection were noted. s 9 O , l ,3.1-3 l 1 i
3.2 GENERAL TEST DESCRIPTION 9% (_/ 3.2.1 Prerequisites In accordance with the test procedure (Reference 2), .the following is a list of significant prerequisites that were completed and documented prior to. containment pressurization.
- a. Controlled access plan in effect.
- b. General inspection of accessible interior and exterior r containment structures and components completed.
- c. All instrumentation aligned for normal operation.
- d. All test instrumentation calibrated or functionally verified.
- e. All Type B and C leak rate testing completed and/or reviewed for impact on the Type A test.
- f. All required system valve line-ups completed.
- g. All computer software used for test calculations, tested and operational.
- h. Official Log of Events book established, to be maintained by the '.'est Director or his designee.
- i. Site meteorology data recorded beginning at least thEee '
days prior to and during ILRT (Attachment 3.2A). 3.2-1
l a 3.2.2 Equipment f#\ Prencurizatien of_ the centairiment was achieved by utilizing two h temporary electric-driven air compressors having a total capacity i of 3600 cfm. This could have been supplemented, if necessary, with station instrument and service air compressors through temporary field installed hose. j The portable air compressors and test skid included an g aftercooler and a refrigerant air dryer with valving and j instrumentation to maintain proper monitoring and operation. J. From this, air was supplied to the containment, through the plant's permanent ILRT system, which includes additional components and instrumentation for monitoring and controlling I , containment pressurization. p i I O () !
'3.2-2 i
T l 3.2.3 Instrum;ntnticn jf h The . variables required to calculate containment leakage during the tect .;e r : .?:nitored using a leuxage raonito ring system consisting of pressure, temperature, and moisture sensors (Attachment 3.2B) for both the drywell and suppression chamber air volumes. The general locations of the temperature and moisture sensors, including applicable test zones, are shown in Attachments 3.2C and 3.2D. Flow instrumentation in the air supply system was used during the pump back verification test. In order to preclude bias associated with temperature sensor readings monitored by the plant computar data acquisition system, calculated corrections were programmed into both the plant data reduction program and the Hicksville computer program. INSTRUMENT SELECTION GUIDE (ISG) The ISG formula is used to determine the ability of an instrumentation system to measure the integrated leakage rate of the primary containment system. The ISG is only used for instrument selection prior to the test or for loss of sensor evaluation after the test.
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*ISG = i2400 I 2E a + 2Ef 2 + EPv 2 Ya O t (p j grj 2[p g j h
where t = Test Duration in hours p = 61.096 psia (Pa) T = 65*F or 525*R ISG s 0.25La which equals 0.125% per day since La = 0.5% per day
*See Reference 3 for derivation
- a. EP = error associated with absolute pressure instruments EP = i ( (Ep)2 + (ep ) 2 ) Yz / (No. of sensors) '#2 where: Ep = .05 psia eP = 0 psia r
EP = i ( (.05)2 + (0)2)
2
/(2)*'t EP = 0.035355 psia -
3.2-3
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- b. EPv = orr r ccccciated with Vrpor Proscurs instrum:nto O
V EPv = i-( (Epv)2 + (epyya) Ya /(No. of sensors) 2 where: Epv = 10.54'F (10.3*C) ePv = *0.1*F Using steam tables, a dewpoint temperature of 60*F is equivalent to water vapor pressure change of 0.0092 psia /*F. Epv = 10.54*F (0.0092 psia /*F) =.004968 psia ePv = 10.l'F (0.0092 psia /'F) =.00092 psia EPv = i( (.004968)2 + (.00092)2) '2 /(5)#2 EPv = iO.002260
- c. ET = error associated with temperature instruments
#2 ET = ( (Et)2 + (eT)2) )#2 /(No. of sensors) o :: : ::I: .
ET = i((l.0)2 + (0.2)a ) /zy(14) '/a ET = iO.272554 Using values established in a, b, and c above, calculate ISG.
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ISG = 12400 2 ,IO.035355 a + 2 I O.272554 a + a */a 2[#0.002260 24
'( 61.096 j ( 525 j (61.096j ISG = 10.110069 which is less than 0.25 La.
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3.2.4 Data Acquisition System Nj . During the ILRT, Shoreham's plant process computer was used to monitor ILRT instruments. The ILRT plant computer programs consist of data acquisition and data reduction tasks. Instruments were scanned, by the computer on' 60 second intervals, and values stored for calculation of containment parameters. A manual data log was also maintained, recording instantaneous values every 20 minutes. Readings for this log were taken from a panel located in the Secondary Containment. s The plant computer monitored the following instrumentation: Type Scan Rate 16 Temperature sensors 60 sec. 6 Moisture sensors 60 sec. 2 Pressure sensors 60 sec. As part of the data reduction program,. the plant computer stored 10 minute averages of each instrument to calculate air pressure, weighted air temperature, weighted dew point temperature, vapor pressure, and the mass for both the drywell and suppression chamber air volumes. This data was presented as a log on the O computer printer. Data calculated at hourly intervals were used in the plant computer data analysis program.
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i 3.2.5 Data Resolution System O In order to troritor leal: ace rnte trends during the ILRT, the data analysis program was used to calculate containment leakage rate,. upper confidence level, and upper confidence limit, based on stored hourly data. For periods of the test when the disc driver failure disabled the ten minute average portion of the analysis program, readings were taken at one minute intervals and reduced manually. Input of this data into the Hicksville computer provided leakage rate trend information. Both Shoreham's process computer and the Hicksville computer calculated leakage rate trend data utilizing the Absolute Method of Mass Point Analysis. g Absolute Method of Mass Point Analysis The Absolute Method of Mass Point Analysis consists of calculating air masses within the containment structure, over the test period, from pressure, temperature, and dewpoint observations made during the ILRT. The air masses are computed using the ideal gas law as follows: M = _144V(P-Pv) (Eq. 1) RT where: (f M = air mass, lbm P = total pressure, psia Pv = average vapor pressure, psia R = 53.35 ft. lbf/lbm R (for air) T = average containment temperature, *R V = containment free volume, fta The leakage rate is then determined by plotting the air mass as a function of time, using a least-squares fit to determine the slope, A = dM/dT. The leak rate is expressed as a percentage of the air mass lost in 24 hours or symbolically: Leak rate = (A/B)(-2400) (Eq. 2p 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. In general, the containment is divided into two volumes: the suppression chamber and the drywell air volumes. The mass of each volume is computed separately and added together. The result is correlated as a function of time by means of a least-squares curve fit of the form: m = At+B (Eq. 3)
,3.2-6
r l The slope A and the y-intercept B are then used in Equation 2 to q determine the leak rate. A 95 percent confidence interval is calculated using a Students T distribution. The sum of the leakage rate and the 95 percent confidence interval is the UCL. The measured leak rate may be l described as 95 percent accurate to within the value of the UCL. , I O . O 3.2-7
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O O O ATTACHMENT.3.2A SlJE METEOROLOGY - Ba rometric Primary Reactor Secondary Reactor Secondary Jteactor Pressu re Bldg. Dev Point Bldg. Wet Bulb Temp. Bldg. Temp. 911g JJ_mg iIn. Nel I'C1 f*F1 f'F1 12/6/82 0600 30.0 16.9 66.0 74.0 1030 29.95 17.1 65.0 74.0 1430 29.94 17.4 66.0 74.5 1830 30.00 17.1 65.50 74.50 2230 30.10 16.6 65.00 74.50 12/7/82 0230 30.10 16.3 62.0 75.0 0630 30.10 16.3 62.1 75.0 1030 30.30 16.3 65.50 76.0 1430 30.40 16.4 64.00 75.0 1830 30.49 16.1 63.5 74.0
=
2230 30.52 16.0 63.5 73.5 12/8/82 0230 30.6 16.7 63.5 74.0 0630 30.6 17.3 62.5 73.5 1 1030 30.7 16.8 62.5 75.0 1 1400 30.52 16.7 62.5 74.0 e 1800 30.58 16.5 62.0 74.0 2200 30.43 16.3 61.5 74.0 12/9/82 0200 30.32 16.4 61.50 74.00 0600 30.23 15.9 61.50 73.50 0800 30.24 15.7 62.5 74.0 0801 - Begin 24 hr. Test Period 0900 30.30 15.7 62.0 73.5 1000 30.30 15.8 62.0 74.0 Page 1 of 3 l
t o O-ATTACHMENT 3.2A (Cont'd) Ba rometric Primary Reactor Secondary Reactor Secondary Reactor-Pressure Bldg. Dew Point Bldg. Wet Bulb Temp. Daig Time rin. Han f*ci rari 81dg. Temp. (*r1 12/9/82 1100 30.25 15.5 62.5 74.0 1200 30.25 15.6 62.5 74.0 1300 30,24 15.6 62.0 73.0 1400 30.30 15.4 61.5 74.0 1500 30.32 15.4 61.0 73.5 1600 30.42- 15.2 60.5 73.0 1700 30.51 15.0 60.5 73.5 1800 30.56 14.9 60.0 73.5 1900 30.60 14.6 59.5 73.0 2000 33.60 14.5 60.0 73.0 2100 30.58 14.4 59.5 73.0 2?00 30.57 14.3 59.0 73.0 2300 30.58 14.3 59.5 T1.0 2400 30.57 14.2 59.0 71.5 12/10/82 0100 30.57 14.1 59.0 73.0 4 0200 30.57 14.1 59.0 7e.5 0300 30.60 14.8 59.0 73.0 0400 30.61 16.7 59.0 73.0 0500 30.59 16.8 59.0 72.5 0600 30.57 17.1 59.50 74.0 0700 30.60 17.4 59.0 73.0 0800 30.60 18.0 59.5 74.0 0810 - Complete ILRT 0900 30.58 18.2 59.0 74.0 Page 2 or 3
O . O O ATTACHMCOT 3.2A (Cont'd)
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Ba romet ric Primary Reactor Secondary Reactor Secondary Reacter Pressure Bldg. Dew Point Bldg. Wet Bulb Temp. Sieg. Temp. Date Time fin. Nel f*Cl - (*F1 f'F) 12/10/82 1000 30.56 18.3 60.0 7as. O 1100 30.54 18.6 59.5 74.0 1200 30.48 18.6 59.5 74.0 ) t ( S
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C j ATTACHMENT 3.28 INSTRCMENTA7 ION . sem V Weight computer Calculated Instrument Factor Point Range Zone Accuracy A. Temperature IT49-TE010 0.0983 L691 60-110'F A 11.0*F 1T49-TE012 0.0983 L693 60-110'F A 11.0*F 1T49-TE011 0.0000 L692 60-110*F g8 il.0*F 1T49-TE009 0.1928 L696 60-110*F B 11.0'F 1T49-TE014 0.1035 L680 60-110*F C 11.0*F iT49-TE016 0.1035 L682 60-110'F C 11.0*F 1T49-TE018 0.1035 L684 60-110*F C 11.0'F y .~ 1T49-TE013 0.1001 L679 60-110'F D 11.0'F 1T49-TE015 0.1001 L681 60-110'F D 11.0*F IT49-TE017 0.1001 L683 60-110'F D 11.0*F iT49-TE001 0.1667 L673 60-110*F E 11.0'F 1T49-TE002 0.1667 L674 60-110*F E 1.0'F ' A 1T49-TE003 0.1667 L675 60-110*F E il.0*F 9 1T49-TE004 0.2500 L676 60-110'F F 11.0'F IT49-TE005 0.2500 L677 60-110'F F 11.0*F j I* 1T49-TE006 0.0000 L678 60-110*F F 11.0'F , B. Dew Point IT49-ME024 0.0000 L685 -50 to 100'C G 1.3'C IT49-ME025 0.3094 L686 -50 to 100'C G 1.3'C IT49-ME022 0.3053 L670 -50 to 100*C H 1.3*C 1T49-ME023 0.3053 L672 -50 to 100*C H 1.3*C 1T49-ME020 0.5000 L6G8 -50 to 100*C J i.3'C 1T49-ME021 0.5000 L669 -50 to 100'C J 1.3'C 'O Page 1 of 2 I i
y-ATTACHMENT 3i2B (Crnt'd) l
- #88% Weight Computer Calculated \%st. Instrument Factor Point Range Zone Accuracy C. . Pressure 1T49-PIT 030 NA NA 0-100 psia Drywell 1.02% range IT49-PIT 031 NA NA 0-100 psia Supp. Pool 1.02% range 1T49-PIT 032 NA NA 0-100 psia Spare 1.02% range D. Pump Back Verification Test Flow s
1T49-FIT 040 NA L998 0-100 scfm NA 11% range O . O Page 2 of 2 e 8
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TE 175'p " 5 \ 355' T E, 2 NOTE ACTUAL RTD ELEVATIONS ARE t 5'
- ATTACHMENT 3.2C ILRT TEMPERATURE DETECTOR LOCATION S h .
SHOREHAM NUCLEAR POWER STATION-UNIT I
in E
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l l NOTE ACTUAL SENSOR ELEVATIONS ARE i 5' I ATTACHMENT 3.2D
' ILRT DEW POINT TEMPERATURE DETECTOR LOCATIONS SHOREHAM NUCLEAR POWER STATION-UNIT 1
) 1
l l I 3.3 TEST RESULTS 3.3.1 Analysis of Test Results ss! . l The test data for the period of 0801 hours on December 9, 1982, through 0810 hours on December 10, 1982, were analyzed for the final test results using LILCO's ILRT program. The reduced input data, mass point ; analysis results, and the representative graphs are ' contained in Attachments 3.3A through 3.3G. During the ILRT, th6 plant computer data reduction program corr'ected individual readings prior to calculation of the ten minutg averages. For those periods of the test requiring manual reduction of data, a calculated correction for instrument bias was used on the averaged value inputted into the Hicksville computer. The use of two slightly different data corrections had a negligible effect on the calculated containment parameters. This is _ graphically represented on the containment air mass versus time graph shown on Attachment 3.3C. The '.rregularities in the containment air mass versus time plot can be explained with a review of the additional trend plots shown on Attachments 3.3D through 3.3F. Attachment 3.3D shows individual plots for the drywell; and suppression chamber air masses versus time. The step! increase in total containment air mass between 2300 hours' on December 9, 1982, and 0010 hours on December 10, 1982, can be attributed to the step increase in suppression chamber mass during the same time period. The suppression chamber mass change is the result of a suppression chamber pressure increase (see Attachment 3.3F) with a constant suppression chamber temperature (Attachment 3.3E). The suppression chamber pressure instrument trended exactly with the drywell pressure instrument throughout the entire test, except for an approximately 0.05 psia step increase in suppression chamber pressure between 2350 hours on December 9, 1982, and 0010 hours on December 10, 1982. The increase in the containment air mass between 0140 hours and 0310 hou*s on December 10, 1982, and the subsequent apparent increase in leak rate immediately following is in response to the containment air temperature conditions presented by the isolation of cooling water to the drywell coolers at 0230 hours on December 10, 1982. The cooling water was secured to maintain individual drywell temperature element readings greater than 60*F, the minimum temperature with 3.3-1
p . calibration corrections. As drywell temperature jeg increased (see Attachment 3.3E), drywell and suppression chamber proccures increased '(sco Attachment 3.3F) . This resulted in an increase in suppression chamber mass since suppression chamber _ temperature remained constant (see Attachment 3.3E), and a decrease in drywell mass (see Attachment 3.3D). As conditions started to stabilize again, the leak rate returned to a level consistent with the first part of the test. The leakage rate results in Attachment 3.3B'are well below the test procedure acceptance criteria of .75 La or
.375 percent per day. The results, including corrections for Type B and C leakage, are outlined in Section 3.3.2.
The leak rate test calculations were verified during the supplemental test which used the metered pump back test method. i O 3.3-2
3.3.2 61.096 Psia ILRT Results
.^ ,
g,y The 61.096 psia ILRT was conducted in accordance with Section 8.0 of preoperational test procedure PT-654.001-2 (Reference,Section 4 and Attachment 4B).
%/ Day
- 1. Measured Leakage Rate, Lam 0.200950
- 2. 95 Percent Confidence Level 0.016324
- 3. Corrections for: g SCFD %/ Day
- i. Measured Type B 60.72 0.004443 Leakage at 43.7 psig
- 11. Measured Type C 319.274 0.023361 Leakage at 43.7 psig iii. Water Levels 0.0 0.0 iv. Hz Recombiner 222.72 0.016296 A-Loop
- v. Total Corrections 602.714 0.044099 ,
at Pa = 43.7 psig i l (Sum of 1. thru iv.) i vi. Leakage Corrected 620.795 0.045422 to Pa = 46.4 psig (Multiply v. by 1.03) vii. Measured Type B 0.0 0.0 Leakage at 46.4 psig viii. Measured Type C . 1.224 0.000090 Leakage at 46.4 psig ix. Hz Recombiner 2.496 0.000183 B-Loop
- x. Instrument Leakage 82.752 0.006055 xi. Total Corrections 63.654 0.004657 for Flowmeters See Note 1.
(Applied to Sum . l of vi. thru x.) ' 3.3-3 , I l
SCFD %/ Day %/ Day A -(;) xii. Total Corrections 770.921 0.056407 0.056407 at Pa = 46.4 psig (Sum of vi. thru xi.)
- 4. Lam leakage with confidence level s 0.273681 and corrections (1+2+3xii.)
Results of the ILRT are acceptable as the SAT measured leak rate, with confidence level and applicable corrections, is well below the procedural acceptance criteria oY 0.375 percent per day. NOTE 1: Corrections to the measured leakage rates should consider the. accuracy of the flow measuring device. Since calibration of the flowmeters was done periodically throughout the test program, the highest value obtained from the calibration data is conservatively applied to all the flowrate readings in lieu of making individual corrections. This results in a 9 percent correction to the measured leakage rate. t
\
l
'3.3-4 l l
l _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ l
r'- 1 3.3.3 Verification Test Results (_j The supplemental verification test was performed using the Mass Pump Back Method in accordance with Section 8.0 of PT.654.001-2
- a. Calculated change in containment gas mass (from Appendix'C, com-puter printout). 454.03 lbm
- b. Total measured gas flow into containment 496.28 lbm s
- c. Difference between measured '
gas and calculated gas (a-b) 42.25 lbm
- d. 0.25 La verification limit 124 lbm Results of the Mass Step Verification Test are acceptable as the difference between the verification test data and the Type A test data is within 0.25 La.
O . , l i l i I
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O O ATTACHMENT 3.3A INTEGRATED LEAK RATE TEST From 0811 Hours on 12/09/82 to 0810 Hours on 12/10/82 Inout Ve rlables DRYWELL SUPPRES$10N POOL Time Abs. Press. Vap. P ress. Abs Temp. Dewpoint Abs. Press. Vap. P re ss. Abs. Temp. Dewpoint ihrs) fosla) fosial l'R1 f*F) fosla1 fosia) (*R1 f*F1 0811 63.9818 0.2589 523.5370 60.3092 64.0037 0.3767 531.7053 71.0980 0911 63.9686 0.2596 523.4429 60.3841 63.9896 0.3751 531.6694 70.9714 1011 63.9537 0.2591 523.3560 60.3239 63.9743 0.3686 531.6432 70.4567 1111 63.9386 0.2584 523.2583 60.2543 63.9596 0.3748 531.6443 70.9461 1211 63.923I 0.2562 523.1847 30.0103 63.9438 0.3731 531.6305 70.8111 1311 63.9059 0.2558 523.0224 59.9608 63.9264' O.3736 531.5614 70.8533 1411 63.8889 0.2531 522.8980 59.6716 63.9094 0.3747 531.5831 70.9377 , 1511 63.8703 0.2528 522.7480 59.6349 63.8909 0.3745 531.5483 70.9208 1611 63.6500 0.2509 522.6036 59.4228 63.8700 0.3731 531.5241 70.8107 1711 63.8290 0.2492 522.4124 59.2304 63.8490 0.3724 531.5069 70.7560 1810 63.8077 0.2463 522.2290 58.9107 63.8280 0.3735 531.4816 70.8406 1910 63.7827 0.2442 522.0069 53.6627 63.8036 0.3730 531.4448 70.8027 2010 63.7587 0.2417 521.7540 58.3763 63.7785 0.3739 ' 531.4052 70.8742 2110 63.7369 0.2394 521.5572 58.1136 63.7553 0.3719 531.3877 70.7138 2210 63.7162 0.2378 521.4612 57.9252 63.7351 0.3706 531.5086 70.6122 2310 63.6990 0.2372 521.3422 57.8515 63.7190 0.3721 531.5121 70.7352 0010 63.6843 0.2351 521.2442 57.6095 63.7585 0.3717 531.4726 70.7014 0110 63.6711 0.2354 521.1764 57.6478 63.7445 0.3713 531.4530 70.6677 0140 63.6607 0.2315 521.1114 57.1847 63.7342 0.3715 531.4530 70.6889 Page 1 of 2
..eM*** , 1
O O 'D ATTACHMENT 3.3A (Cont'd) DRYWELL SUPPRESSION POOL Vap. Press. Abs Temp. Dewpoint Abs. Press. Vap. P re s s . Abs. Temp. Dewpoint Time Abs. Press. (*R) f*F) t h rs ) fosist fosial l'R1 f*F) osla) __1psisj_ 63.8483 0.2523 523.2442 59.5742 63.9167 0.3719 531.5163 70.7183 0310 i 63.9254 0.2733 524.4709 61.8322 63.9974- 0.3712 531.4632 70.6634 0410 63.9776 0.2821 525.3664 62.7299 64.0486 0.3713 531.4378 70.6677 0510 64.0154 0.2927 526.0393 63.7822 64.0893 0.3715 531.3818 70.6888 0610 64.0479 0.2986 526.5704 64.3749 64.1209 0.3717 531.3563 70.7014 0710
] 0810 64.0756 0.3054 527.0419 64.9965 64.1473 0.3718 531.3611 70.7056 r
s.- I 4 ' Pa9e 2 of 2
r .
.ATTACID!ENT 3.38 i n INTEGRATED LEAK RATE TEST
,) From 0811 Hours on 12/09/82 To 0810 Hours on 12/10/82 ABSOLUTE METHOD TEST RESULTS Time Mass of Air Leak Rate 95 Pct Conf.
(hrs) (lbm) Pet / Day Pct / Day UCL 0811 107,977.3 0.0 0.0 0.0 0911 107,969.0 0.0 Os0 0.0 1011 107,961.4 0.0 0.0 0.0 1111 107,944.0 0.239111 0.099648 0.338760
.1211 107,931.3 0.260220 0.055767 0.315987 1311 107,927.2 0.242131 0.040053 0.282184
'1411 107,913.3 0.242610 0.026879 0.269439 1511 107,903.5 0.240891 0.019450 0.260340 1611 107,891.0 0.242563 0.014815 0.257379 1711 107,882.1 0.240950 0.011734 0.252684 1810 107,872.5 0.238934 0.009694 0.248629 1910 107,862.9 0.236819 0.008282 0.245102 2010 107,857.3 0.231856 0.008642 0.240498 2110 107,848.2 0.227867 0.008416 0.236283 2210 107,817.4 0.236717 0.011593 0.248310 2310 107,802.6 0.244671 0.012927 0.257598 0010 107,833.3 0.231943 0.017169 0.249112 0110 107,820.2 0.224055 0.017148 0.241203 0140 107,814.1 0.218954 0.016323 0.235277 Page 1 of 2 !
O ' 1 l
ATTACHMENT 3.38 (C nt'd) A( x, ABSOLUTE METHOD TEST RESULTS Time Mass of Air Leak Rate 95 Pct Conf.
.(hrs) (1ba) Pet / Day Pct / Day UCL 0310 107,844.9 0.200286 0.023577 0.223863 0410 107,814.4 0.192834 0.022484 0~215318 0510 107,788.0 0.191986 0.020380 0.21E366 0610 107,767.1 0.194320 0.018539 0.213008 0710 107,754.1 0.197074 0.017296 0.214370 0810 107,736.8 0.200950 0.016324 0.217274' Page 2 of 2 O .
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RTTACHMENT 3.3D
- - TIME -
HOURS MRSS VS. TIME SHOREHRM NUCLERR POWER STRTION INTEGRRTED LERK RRTE TEST
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SECTION 4 r LOCAL LEAK RATE TEST (TYPE B AND C) Attachment 4A summarizes tne Local Leak Rate Test (LLRT) data that was established to support the overall containment leakage testing program. Attachment 48 summarizes the leakage penalties added to the Type A overall leakage for systems that were either isolated or not vented and drained during the Type A Test. These LLRTs were performed by pressurizing the listed penetrations with air or nitrogen and either measuring leakage across the containment isolation valves (Type C) or across the resilient seals (Type B). A correction factor of 1.03 was applied to those leakage ~ rates resulting from tests conducted at a pressure of 43.7 psig -prior to the Type A test. A correction factor of
'9 percent was also applied to all leakage rates for flowmeter inaccuracies.
Also included are the results of local leak rate testing performed on the Hydrogen Recombiners. This leakage, not identified as Type B or C, was added to the overall leakage to support Shoreham's Leakage Reduction Program.
' The results of local leak rate testing performed on those instrument lines which are 'an extension of the primary containment boundary, but which were isolated during the Type A Test, are also included. This leakage, not identified as Type B O or C, was added to the overall leakage for verification of the instrument lines containment capabilities.
The acceptance criteria for Type B ard C testing is in accordance with 1CCFR50, Appendix J. The combined leakage rate for all penetrations and valves, subject to Type B and C tests, is well below the acceptable leakage rate of 0.6 La or 4100 scfd.
'4-1
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.j ATTACHMENT 4A Local Leak Rate Test Data 1 Equipment / Valves Leakage Type iScr/ day 1 Remarks Penetration No. 1g11 _ Tested (Note 11 1821 *A0V081 A ( I PC) 24.0 X-1A Mein Steam C 1821*AOV082A (OPC) 1821*MOV061 (OPC) 1E32*MOY021 A (OPC)
C 1821*AOV081B (IPC) 95.52 X-1B Main Steam 1821*AOV082B (OPC) 1B21*MOV062 (OPC) 1E32*MOV021B (UPC) C 1B21*AOV081C ( I PC) 163.2 X-1C Main Steam 1821*AOVO82C (OPC) 1821*MOV063 (OPC) 1E32*HOV021C (OPC) C 1821*A0V081D ( I PC) 81.84 X-1D Main Steam 1821*A0V082D (OPC) -
' 1B21*MOV064 (OPC) 1E32*MOV021D (OPC) 1.224 Note 3 C 1821*18V-1103A ( I PC) Note 3 X-2A' Feedwater 1B21*A0V036A (OPC) 1821*18V-1103B ( I PC) 18.768 Feedwater C X-2B 1821*AOV036B (OPC) 1821*MOV031 (IPC) 4.56 Main Steam Drains C ,
X-3 1821*MOV032 (OPC) C 1C33*MOV033 ( IPC) 6.12 X-4 Reactor Water 1G33*MOV034 (OPC) Cleanup 1E11*MOV047 (IPC) 84.00 RHR from RPV C X-5 1E11*MOV048 (OPC) 1E11*RV163 (OPC) C 1 E11 *A0V081 A ( I PC ) 50.40 X-6A RHR Recirc. IE11*MOV081 A (IPC) Return 1E11*MOV037A (OPC) C 1E11*AOV081B (IPC) 33.84 X-6B RHR Recirc. 1E11*MOV081B (IPC) Return 1E11*MOV037B (OPC) ~
.._Page 1 of 12
i + O O <D ATTACHMENT 4A (Con't) Type Equipment / Valves Leakage Penetration No. Test Tested (Note 11 LScf/ day) Rema rks X-7A RHR D rywe l l C 1E11*MOV038A (OPC) 5.04 Spray 1E11*Mov039A (OPC) X-78 RHR D rywe l l C IE11*MOV0388 (OPC) 0.40 Spray 1E11*MOV039B (OPC) X-8A RHR Pool Spray C 1E11*MOV040A (OPC) 24.672 1E11*MOV041 A (OPC) 1E11*MOV042A (OPC) X-8B RHR Pool Spray C IE11*MOV0408 (OPC) 19.20 Note 2 1E11*MOV041B (OPC) 1E11*MOV042B (OPC) X-9A RHR Suction C 1E11*MOV031 A (OPC) 74.40 X-9B RHR Suction C 1E11*MOV031B (OPC) 45.17 X-9C RH9 Suction C IE11*MOV031C (OPC) 2.352 X-9D RHR Suction C IE11*HOV031D (OPC) 6.24 X-10A RHR fest Line Return, C 1C11*MOV639C (OPC) 57.888 RHR Test, Pass, 1G41*MOV033A (OPC) Radwaste, Fuel Pool 1C11*03V-2110C (OPC) Cooling and Cleanup, 1E21*MOV035A (OPC) Core Spray 1C41*HOV0330 (OPC) 1E11*MOV044A (OPC) 1E11*MOV045A (OPC) 1E21*MOV034A (OPC) 1E11*SOV168 (OPC) 1E11*01V-0047 (OPC) p X-10B RHR Test Line Return, C 1E11*MOVO448 (OPC) 9.836 HPCI, RCIC, Core Spray, IE11*MOV0458 (OPC) PASS, Relier to RCIC 1E41*MOV036 (OPC) Pump Suction IE51*MOV036 (OPC) Note 3 1E21*HOV034B (OPC) 1E21*MOV0358 (OPC) Note 3 1E11*SOV169 (OPC) 1E11*C1V-0048 (OPC) 1E11*RV155 (OPC) X-11 RHR Head Spray C 1E11*HOV054 (IPC) 3.672 Note 3 , IE11*MOV053 (OPC) 1E11*RV164 (OPC) Page 2 of 12 I
ATTACHMENT 4A (Con't) { . _ . _ Type Equipment / Valves Leakage Penet ra t ion No. 1311 Tested (Note 11 (Scffday) Rema rks X-12 HPCI Tu rbir.s C 1E41*Mov041 ( I PC) 49.032 Steam 1E41*MOV042 (OPC) 1E41*MOv047 ( I PC) 1E41*MOV048 (OPC) X-13 HPCI Turbine C 1E41*MOV044 (OPC) 36.72 Exhaust 1E41'18V-0021 (OPC) 1E41*18V-OO22 (OPC) X-14 Spa re C O.0 X-15 H PCI Pump C 1E41*MOY032 (OPC) 0.24 Note 3 Suction X-16 RCic Turbine C 1E51*MOV041 (IPC) 0.00 Steam 1 E51 *MOV042 ( OPC ) ' 1E51*MOV04 7 ( I PC) 1E51*MOV048 (OPC) X-17 RCIC Turbine C 1E51*MOV045 (OPC) 146.4 Exhaust 1E51*08V-0020 (OPC) , IE51*08V-0021 (OPC) X-18 RCIC Vacuum C 1E51*MOV046 (OPC) 0.0 Pump IE51*02V-0025 (OPC) X-19 RCIC Pump C IE51*FDV032 (OPC) 1.68 Suction X-20A Core Spray C 1E21*A0V081A (IPC) 36.00 1E21*HOV081 A ( I PC) 1E21*MOV033A (OPC) , X-208 Core Spray C 1E21*A0V081B (IPC) 53.76 I E21 *MOV0818 ( I PC) 1E21*MOV0338 (OPC) X-21A Core Spray Suction C 1E21*MOV031A (OPC) 8.856
~ ~~
X-218 Core Spray Suction C 1E21*MOV031B (OPC) 19.44 X-22A RBCLCW C IP42*MOV035 (OPC) 1.618 X-22D RBCLCW C 1P42*MOV047 (OPC) 0.192 X-23A RBCLCW C 1P42*MOV036 (OPC) 3.552 Page 3 of 12
O O- 0D ATTACHMENT 4A (Cors't) Type Equipment / Valves Leakage ' Penet ration No, Teil Tested (Note 11 [Scffdag} Rema rks X-238 RBCLCW C 1P42*MOVO48 (OPC) 0.192 X-24A RBCLCW to C 1 P42'03V-0037AA ( I PC) 14.88 Drywe l l Coole rs IP42*MOV232 (OPC) X-248 RBCLCW to C - 1 P42'03V-0037A8 ( I PC) 36.48 D rywe l l Coo le rs IP42*MOV233 (OPC) 5 X-24C RBCLCW to C I P42'03V-0037AC ( I PC) 6.864 D rywe l l Coo le rs IP42*MOV234 (OPC) X-24D RBCLCW to C 1P42'03V-0037AD ( IPC) 2.424 D rywe l l Coo le rs IP42*MOV235 (OPC) X-24E RDCLCW to C IP42'03V-0037BA (IPC) 12.00 Drywell Coolers I P42*MOV23 7 ( O PC) X-24F RBCLCW to C 1 P42'03V-0037BB ( I PC) 0.00 Drywell Coolers IP42*MOV238 (OPC) X-24C RBCLCW to C 1 P42'03V-0037BC ( I PC) 6.624 D rywe l l Coolers 1P42*MOV239 (OPC) X-24H RBCLCW to C 1 P42'03V-0037BD ( I PC) 0.00 Drywell Coolers IP42*MOV240 (OPC) X-25A RBCLCW from C I P42*MOV147 ( I PC) 49.82 D rywe l l Coolers 1P42*MOV231 (OPC) IP42*RV291 A (OPC) X-258 RBCLCW from C IP42*MOV148 (IPC) 12.312 D rywe l l Coole rs IP42*MOV236 (OPC) # 1P42*RV2918 (OPC) X-26 Purge Ai r C IT46*AOV038A ( IPC) 59.784 1T46*AOV038B (OPC) X-27 Pu rge Ai r C IT46*A0VO39A ( I PC) 15.76 1746*A0V039B (OPC) X-28 Pu rge Ai r C 1T46*A0V038C (OPC) 103.68 IT46*AOV0380 (OPC) 1T24*AOV004A (OPC) IT24*ADV0048 (OPC) Page 4 of 12
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O O O_ ?4 __ _ ATTACHMENT 4A (Con't) Type Equipment / Valves Leakage Penet ra t ion No. 1g11 Tested ( No_0s 11 (Scr/ day 1 ' Rema rks X-29 Purge Air G 1746*AOV039C (OPC) 90.384 1746*A0V039D (OPC) 1T46*ADVO79A (OPC) IT46*A0V0798 (OPC) X-30 Reactor Reci rc. C 1831*A0V081 ( I PC) 0.168 - Sample 1831*A0V082 (OPC) X-31 Equip. Dra ins C 1C11*MOV248 (OPC) 61.704 IG11*MOV249 (OPC) X-32 Floor Drains C 1C11*MOV246 (OPC) 46.32 1C11*MOV247 (OPC) X-33 Spare C 0.0 Note 4 X-34 Spa re C 0.0 Note 4 X-35 Spa re C 0.0 Note 4 X-36 Standby C 1C41'02V-0008 (IPC) 41.28 Liquid Control 1C41*02V-0010 (OPC) X-37A TIP C 1C51*SOV801 A (OPC) 3.41 "O" Rings B 0.0 l X-378 TIP C IC51*SOV801B (OPC) 0.0 8 "O" Rings 0.0 X-37C TIP C IC51*SOV801C (OPC) 0.0 B "O" Rings 0.0 r X-37D TIP C IC51*SOV801D (OPC) 0.0 B "O" Rings 0.0 X-38 TIP C IC51*SOV028 (OPC) 23.568 1C51*01V-0867 (OPC) B "0" Rings 0.0 X-39A . instrument Ai r C 1 P50*01V-698A ( I PC) 2.58 1 P50*Mov106 ,( O'PC) X-39B Instrument Air C 1 P50*01V-6988 ( I PC) 0.984 IP50*MOV104 (OPC) X-40 Spa re C 0.0 Note 4 Page 5 of 12
O O O " ATTACHMENT 4A (Con't) . Type Equipment / Valves Leakage Penet ra t ion No. Test Tested (Note Il (SCf/ day 1 Rema rks X-41 HPCI Vacuum C 1E41*Mov049 (OPC) Tested with X-13 Breaker X-42 RCIC Vacuum C IE51*Mov049 (OPC) Tested with X-17 Breaker i X-43 RHR Tested with XS-5 X-44 Cont. Atmos. Cntri., C IT48"MOV033A (OPC) 8.002 D rywe I I Floor 1148*MOV038A (OPC) Seal Pre ssu riza t ion 1T23*MOVO31A (OPC) X-45 Cont. Atmos. Cntri., C IT48'MOV0338 (OPC) 12.54 D rywe l l Floor IT48'MOV038B (OPC) Seal Pressurization 1T23*MOV0318 (OPC) X-46 Cont. Atmos. C 1T48'MOV031A (IPC) 2.33 Control 1T48"MOV035A (OPC) 1T24*AOV001 A (OPC) 1T24*AOV0018 (OPC) X-47 Cont Atmos. C IT48"MOV0318 ( I PC) 1.95
- Cont ro l IT48'MOV0358 (OPC)
XS-1 Spa re C 0.0 Note 4 XS-2 Spare C O.0 Note 4 XS-3 Spa re C O.0 Note 4 XS-4 Spare C 0.0 Note 4 r XS-5 RHR C 1E11*MOV055A (OPC) 22.944 IE11*Mov055B (OPC) 1E11*MOV056A (OPC) 1E11*MOV0560 (OPC) 1E11*RV157A (OPC) 1E11*RV1578 (OPC) 1E11*RV152A (OPC)
, IE11*RV1528 (OPC) 1E11*01V-3144 (OPC) 1E11*01V-3145 (OPC)
XS-6 Supp. Pool C 1G41*MOV034A (OPC) 8.76 Pump Down 1G41*MOV034B (OPC) Page 6 of 12 _______..__._______2l____ __._. ___
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ATTACHMENT 4A (Con't) Type Equipment / Valves Leakage Penetration No. Test Tested (Note 11 (Scr/ day 1 Rema rks XS-7 Cont. Atmos. C 1T48'MOV034B (OPC) 0.0 Clean-up IT48'MOV0408 (OPC) XS-8 Cont. Atmos. C 1T48*Mov034A (OPC) 49.2 Clean-up IT48*MOVO40A (OPC) XS-11 Spa re C 0.0 Note 4 XS-12 Spa re C 0.0 Note 4 XS-13 Spare C 0. 0 ~ Nott 4 XS-14 Spa re C 0.0 Note 4 XS-15 Spare C 0.0 Note 4 . XS-16A Service Ai r C 1 P50'02V-0603 ( I PC) 9.12 1 P50'02V-0601 - ( O PC) XS-168 Rad. Hon. C 1D11*MOV032A (IPC) 0.984 1011*MOV0328 (OPC) XS-16C Rad. Mon. C 1D11*MOV033A ( I PC) 0.0 1D11*MOV0338 (OPC) XS-17 Spare C 0.0 Note 4 XS-18 Spa re C 0.0 Note 4 XS-19 Spare C 0.0 Note 4 s XS-20 Cont. Atmos. C 1T48'HOV032A (IPC) 16.15 Con t ro l IT48'MOV037A (OPC) XS-21 Cont. Atmos. C 1T48'HOV032B ( I PC) 7.056 Cont rol IT48'MOV0378 (OPC) XS-22 DW Vent C 1T46*A0V078A ( I PC) 18.72 - - - - - - IT46*A0V0788 (OPC)
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XS-23 Spa re C 0.0 Note 4 XS-24 Spare C 0.0 Note 4 XS-25 Spere C 0.0 Note 4 XS-26 Spa re C O.0 Note 4 Page 7 of 12
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.J ATTACHMENT 4A (Con't)
Type Equipment / Valves Lea kage Pene t ra t i on No. -))31 Tested (Note 11 IScr/ day 1 Rema rks XS-27 Spare C 0.0 Note 4 XS-29 Spare C 0.0 Note 4 XS-30 PASS C 1T48'SOV131 (OPC) 2.208 1T48*01V-00168 (oPC) F-10 Reactor Reci rc. C IB31'01V-0002A ( I PC) 91,68 Pump Seal 1831'01V-1028A (OPC) F-11 Reactor Reci rc. C 1B31*01V-00028 ( I PC) 48.24 Pump Seal 1831*01V-10288 (OPC) B-3 PASS C 1T48*SOV128A (OPC) 0.166 1T48'SOV1288 (OPC) B-7 Inst. Air C 1P50*02V-6958 (IPC) 0.0 to D rywe l l 1P50*MOV103A (OPC) C-2 PASS C 1821*SOV313A (OPC) 0.0 1821*SOV313P (OPC) D-5 Inst. Air C I P50*02V-0695A ( I PC) 0.36 to D rywe l l IP50*MOV1038 (OPC) J-2 PASS C IT48*01V-0016A (OPC) 4.60 1T48'SOV130 (OPC) J-10 PASS C IT48'SOV126A (OPC) 0.166 IT48*SOV1268 (OPC) SP-SE PASS C 1T48'SOV129A (OPC) 0.0 Note 3 1T48'SOV1298 (OPC) Note 3 SP-NW PASS C IT48'SOV127A (OPC) 0.190 Note 3 IT48'SOV1278 (OPC) Note 3 Hyd rogen 222.72 Tested under Leakage Recombiner Reduction Program Loop A Hyd rogen 2.496 Tested under Leakage Recombiner Reduction Program Loop B Note 3 IT23-Z-WA1-Spare B Epoxy Seal 0.0 Page 8 of 12
ATTACHMENT 4A (Con't) Type Equipment / Valves Leakage ; Pene t ra t ion No. . Test Tested (Note Il (Scr/dayl Remarks ' IT23-Z-WA2 l B Welded Seal 0.0 1T23-Z-WA3 8 Welded Seal 0.0 1T23-Z-WB1 B Epoxy Seal 0.0 1T23-Z-WB2 B Epoxy Seal - 0. 0 1T23-Z-WB3 8 Epoxy Seal 0.0 1T23-Z-WB4 8 Epoxy Seal 0.0 1T23-Z-WB5 8 Epoxy Seal 0.0 1T23-2-WB6 B Epoxy Seal 0.0 1T23-2-WC1 B Epoxy Seal 0.0 1T23-Z-WC2 Spa re B Epoxy Seal 0.0 1T23-Z-WC3 Spare B Epoxy Seal 0.0 1T23-Z-WC4 8 Epoxy Sea l -0.0 1723-Z-WC5 B Epoxy Seal 0.0 1T23-Z-WC6 B Epoxy Seal 0.0 1T23-Z-WD1 B Epoxy Seal 0.0 1T23-Z-WD2 B Epoxy Seal 0.0 s IT23-Z-WD3 8 Epoxy Seal 0.0 IT23-Z-WD4 B Epoxy Seal 0.0 1T23-Z-WD5 B Epoxy Seal 0.0 1 T23-Z ,WD6 Spa re B Epoxy Seal 0.0 1T23-Z-EA1 8 Epoxy Seal - 0.0 1T23-Z-EA2 B Epoxy Seal 0.0 1T23-Z-EA3 8 Epoxy Seal 0.0 1T23-Z-EB1 B Epoxy Seal 0.0 Page 9 or 12 MP
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] g A. 1 l ATTACHMENT 4A (Con't) Leakage Leakage MSIV's (Scr/ day) Tvoe C f5cr/ day 1 X-1A Total Leakage-including 26.16 Total Type C Lea kage-I nc l ud ing . 8 9% Flowmeter inaccuracy 1920.087 Correction to 46.4 psig for valves tested 4 43.7 psig and 9% riowmeter inaccuracy X-18 Total Leakage-including 104.117 Hyd rogen 9% Flowmeter inaccuracy Recombine r Loop A 7 s Total Leakage-Including 250.048 X-1C Correction to 46.4 psig
' Total Lea ka ge-inc l ud ing 177.888 ano 9% Flowmoter Correction to 46.4 psig inaccuracy plus 9% Flowmeter inaccuracy Hyd rogen X-1D Recombiner Total Leakage-Including $9.206 Loop B 9% Flowmeter inaccuracy Total Leakage-Including 2.721 s
9% Flowmeter inaccuracy i Type B Total Type B Leakage- 159.244 including Correction to 46.4 psig and 9% Flowmeter Inaccuracy r i Page 12 of 12
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_r% T ) ATTAC6 MENT 48 Leakage Penalties Added to Type A Leakene Type Equipeent/ Valves Leakage Penetrotton No. Test Tested Qcf/ day) Remarks X-2A Feedwater C 1821*18V-ff03A (IPC) 1.224' Water filled 1821*A0VO364 (OPC) during Type A Test X-28 Feedwater C 1821*tSV-it038 (IPC) 18.768 Water f4Iled IB2f'A0VO368 (OPC) durIng Type A Test X-4 Reactor Water C tG33*MOVO33 (IPC) 6.12 Water filled Cleanup 1G33*MOVO34 (OPC) c>seing Type A Test X-22A RSCLCW C 1P42*MOVO35 (DPC) 1.618 Operating durIng Type A Test X-228 RBCLCW C 2 1P42*MOVO47 (OPC) O.192 Operating during Type A Test X-23A RBCLCW C fP42*MOVO36 (OPC) 3.552 Operating durIng s Type A Test X-236 RBCLCW C 1P42*MOVO48 (OPC) i 0.192 Operating during Type A Test X-244 RBCLCW to Dry- C 1P42'03V-OO37AA (IPC) well Coolers 14.88 Operating ductng IP42*M0v232 (OPC) Type A Test X-248 RBCLCW to Dry- C iP42'03V-OO31A8 (IPC) well Coolers IP42*MOV233 (OPC) 36.48 Operattnj during
' Type A Test X-24C RBCLCW to Dry- C 1P42'03V-OO37AC (IPC) 6.864 well Coolers Operating during IP42*MOV234 (OPC) Type A Test X-24D WBCLCW to Dry- C 1P42'03V-OO37AD (IFC) 2.424 well Coolers operating during 1P42*MOV235 (OPC) Type A Test X-24E RBCLCW to Dry- C 1P42'03V-OO37BA (IPC) well Coolers 12.0 Operating during 1P42*MOV237 (OPC) Type A Test X-24F RBCLCW to Dry- C 1P42'03V-OO3788 (IPC) 0.0 well Coolers Operating during i 1P42*MOVO238 (OPC) Type A Test X-24G RBCLCW to Dry- C 1P42*03V-OO378C (IPC) 6.624 well Coolers Operating during' fP42*MOV239 (OPC) Type A Test Page 1 of 4
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O .- r ATTACHMENT 43 (Con't) Typan Equipment / valves Leakage Penetratton No._ _ Test Tested (Scf/ day) Romarks X-24H RBCLCW to Dry- C tP42'03V-0037BD (IPC) 0.0 well Coolers Operating during. IP42'Mov240 (OPC) Type A Test X-254 RBCLCW from C 1P42*MOV147 (IPC) 49.82 Drywell Coolers Operating during 1P42*MOV231 (OPC) Type A Test 1P42*RV29tA (OPC) X-258 RBCLCW from C IP42*MOV148 (IPC) 12.312 Drywell Coolers Operating during IP42*MOV236 (OPC) Type A Test 1P42*RV2918 (OPC) X-30 Reactor Rectrc. C 183t'A0VO61 (IPC) 0.168 Semple Water filled 1831*ADVOS2 (OPC) during Type A Test XS-30 PASS C 1748'50V131 (OPC) 2.208 Isolated during 1T48'01V-OOtGB (OPC) Type A Test F-tO Reactor Rectrc. C 1831*0tV-OOO2A (IPC) 91.68 Water filled Pump Seal 1831*0tV-1028A (OPC) during Type A, Test F-11 Reactor Rectrc. C fB31*0tV-OOO2B (IPC) 48.24 Water filled Pump Seal 1831*O1V-10288 (OPC) during Type A Test B-3 PASS C 1T48'50V128A (OPC) 0.166 Isolated ductng 1T48'SOV1288 (OPC) Type A Test d-2 PASS C 1T48*0tV-OOtGA (OPC) 4.80 Isolated during IT48'50Vt30 (OPC) Type A Test r J-10 PASS C ST48*SOVt26A (OPC) 0.166 Isolated during 1T48'50V1268 (OPC) Type A Test Hydrogen LLRT Recombtner 222.72 Added under Leakage Loop A Reduction Progree Hydrogen LLRT "** 2.4968 Recombtnor Added under Leakage Loop B Reduction Program Page 2 of 4
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h F.TTACHMENT 48 (Con't) Type Estpoent/ valves Leakage Penetration No. Test Tested (Scf/dev) Remarks 1T48'PNL-068A 8 *O* Ringe 0.24 Isolated during Type A test 1T48'PNL-0688 8 'O' Rings 48.0 Isolated during Type A test 1748*PNL-069A 8 "O" Rings 3.16 Isolated dur1ng Type A test 1748*PNL-0698 8 *O* Rings 4.32 Isolated during Type A test Instrumentetion ' 1T47-PDTO288 LLRT 1.008' Isolated ouring Type A test
, 1293*LTO12A LLRT .49.9685 Vented dJring Type A test 1293*LTOt28 LLRT 29.808' Vented during Type A test Manometer LLRT Manifold 1.968. Isokted during Type A Test 1T48*FT OO6A.8 LLRT O.O' '
Installatton not complete for He Re-combiner test ' 1T48,*FT-OO7A.8 LLRT O.O' Installetton
. not complete for He Re-Combiner test 1T48'PT-007A.8 LLRT O.O' Installation not complete for He Re-combiner test Page 3 of 4 T
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