Text

Reactor Bldg Containment Integrated Leak Rate Test
	ML20245B363
Person / Time
Site:	Sequoyah
Issue date:	03/18/1989
From:	; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML20245B357	List: ML20245B355; ML20245B363;
References
	NUDOCS 8906230146
	Download: ML20245B363 (143)
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f ENCLOSURE f ?'

TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER t'

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REACTOR' BUILDING CONTAINMENT '

INTEGRATED LEAK RATE TEST SEQUOYAH NUCLEAR PLANT UNIT 2 CONDUCTED MARCH 18-19, 1989

'iI Submitted to The United States Nuclear Regulatory Conunission Pursuant to Facility Operating License I

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TABLE OF CONTENTS I

Section Title '. Page .'

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Table of. Contents. . .. . . . . . .. . . . . . . . . .. . .

1.0

SUMMARY

. . . . . .... . . . . . . . . . . . .. . . . . . . 3

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2.0 INTRODUCTION

. . . . ... . . . . . . . . .'. . . .. . . . . . 4 3.0 TEST PURPOSE . .-. . . .:.. . . . . .-. . . . . . . . . .. . 5.

4 '. 0 CONDUCT OF. TEST. . . .. . . . . . . . . . . . . . . . . . . . . . . S' 5.0 TEST RESULTS . . . . . . . . . . . . . . . . . . . . . . . . . . 12 6.0 MEASUREMENTS AND CALCULATIONS. . . . . . . .. . . . . . . . . 13 6.1 Test Equipment'. ... . . . .. . . . . . . . . , . . . . . . .. 13 6.2 Sensor Location. . . . .. . . . . . . . . . . . . . . . . . . . 14 6.3 . Computer-Based Data Acquisition and Data Reduction . . . . .. . 14 6.4 Reactor Building Containment Model . . . . . . . . . . . . . .- 14 7.0 ANALYSIS OF TEST DATA. .. . ' . . . ... . . . . . . . . . . . . 15 7.1 Instrument' Check . . . . . . . . . . . . . . . . . . . ... . . . 15 7.2 Discussion of Graphical and Tabular Results. . . . . . . . . . . 16-7.3- Disc'tssion of Agreement (Verification Test). . . . . . . . . . 16

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8.0' CONCLUSIONS. . . . . . . . . . . . . . . . . . . . . . . . . . 17'

. TABLES . . . .. .. . .. . . . . .. . ... . . . . . . . . . 19

- FIGURES.=, . . . .. ... . . . . . . . . . . . . . . .. . . . . . '20 APPENDICES

-Appendix At Instrument Error Analysis Appendix Bt Calculations of Verification Agreement Appendix C: ' Special Test Instrumentation Guide Appendix D Local Leak Rate Summary, Appendix Es- References 9

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DEFINITION OF SYMBOLS AND ABBREVIATIONS AF As Found AL As Left ,

CILRT Containment Integrated Leak Rate Test E Repeatability Error e Absolute Error

u. Measurement System Error

F Temperature, degrees Fahrenheit ISG Instrument Selection Guide.

LA Full-Pressure Dewign Basis Leakage LAM Containment Leak Rate.During Full-Pressure CILRT LR IPF> sed Leak Rate for Verification LRN Containment Leak Rate During Verification- H LLRT Local Leak Rate Test P Pressure Pa Design Accident Pressure psia Absolute Pressure psig. Gauge Pressure

'R Temperature, degrees Rankine T- Temperature Top Dewpoint Temperature t Time UCL Upper Confidence Limit V ' Containment Volume, Cubic Feet MLR Mass Leak Rate TTLR Total Time Rate Leak 0243C/COC3

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SUMMARY

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A reactor building' containment integrated leak rate: test (CILRT) was "successfully coeducted at Sequoyah Nuclear-Plant (SON) unit 2' March 19, 1989,.in conjunction withithe cycle 3 outage.- The CILRT was concluded in 10' hours and 40 minutes and included 65 samples. The measured total. time-leak rate was' 0.011326: percent per day.

The "as-found" condition of the reactor building primary containment-(the condition'of the. containment at the end of the operating cycle) proved to-be. leak-tight and demonstrated the-leak-tight integrity of unit 2. The "as-found". reportable 95 percent UCLi including the addition of.the local '

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. leak: rate test _(LLRT) " leakage savings", was only 0.079' percent / day.and' 1 is.~1ess than half of the allowable 0.1875 percent per day.. This- !

., improvement;over.the previous leakages' recorded for. unit 2'is attributed to improved maintenance and expansion of'the LLRT program.

The initial'CILRT attempt'after 23 samples ~taken at 12:04-March 17, 1989-measured a leakage rate.of approximately 6.24 percentage of, containment air mass per day.(percent per day) as. calculated by the total time leak rate (TTLR). method procedure outlined in Bechtel's topical report,

" Testing Criteria for Integrated Leakage. Rate Testing of Primary Containment Structures for Nuclear Power Plants" (BN-TOP-1, Revision 1).

' Operations and Test personnel discovered two penetrations causing the 9xcessivelleakage problem and had operations personnel isolate them.

First,.tho' Reactor Coolant Drain Tank (RCDT) outboard FCV, 3-77-10, on penetration number X-46 was-found:in the open' position'. .The.CILRT.

procedure listed this' valve'in'the closed position'except when draining the<RCDT.: The total timerleakage rate dropped from 6.24. percent per day to 0.20191 percent per. day after operations: isolated 2-FCV-77-10.

Secondly,.the lower Essential. Raw Cooling Water (ERCW) penetration number X-59 was,found to be leaking'though the outboard vents'67-693A and' 67-693C. The. total. time leakage rate dropped lfrom 0.20191 percent.per day.to 0.0113261 percent per< day after operations closed'these outboard

. vents.

The'CILIT was then successfully completed on SON' unit 2.- The final reportable leakage rate.was .011326- percentage of containment. air mass per day as calculated by the TTLR method, an6 the observed 95' percent upper confidence limit.(UCL) was 0.0620 percent per day. The above

' mentioned 95 percent UCL includes leakage measured from type B&C tests for testable lines that were'in service during the. test. The reportable leak-rate was only 33 percent.of the allowable.0 1875 percent per. day c '(0.75L A )'. The March:18, 1989 "as-left" CILRT leakagerrate also'shows a

' vast' improvement over the previous leakages recorded'for' unit 2, proving the "as-left" condition of the reactor building primary containment;to be leak-tight'.

Appendix D shows a complete summary of the LLRT. performed on SQN unit 2' since'the cycle 2 CILRT performed in November 1984.

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1 ras' prescribed in Seguoyah Nuclear' Plant (SQN). unit'2 Technical.

Specification 4.6.1.2,:the leakage'of air from the' boundary forming.the 4

reactor' building primary. containment is limited to 0.25 percent by weight ,

of the containment air mass per day at.a pressure.of.P., 12.0 psig. In conformance with Title 10,. Code.of Federal Regulations, Part'50,-

p Appendix J, SQN Technical Specifications require that a reactor building CILRT be performed as part of the surveillance programs to demonstrate Js the. continuing leak-tight' integrity'of theireactor. building primary-

' containment.

.The second inservice' reactor building CILRT was successfully: completed on'. - *

. SON unit'2 by personnel'of the Tennessee' Valley Authority (TVA) on March 194.1989.- This test was conducted in'accordance with a plant-approved surveillance instruction (SI), SON SI-156, which is on ffile at the plant site; .This SI implements the requirements'of SQN unit:

'2 Technical Specifications and 10 CFR 50,'Appendiz J. .The.American National' Standard.for Containment Testing, ANSI 45.4-1972;'the proposed American Nuclear. Society for Containment Testing, ANS 56.8; and the 4 procedure outlined-in Bechtel's topical report, " Testing Criteria for-Integrated Leakage Rate Testing of Primary Containment Structures'for Nuclear Power Plants" (BN-TOP-1, Revision 1), provided guidance for the procedure implemented by the SI.

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SON unit 2 is'a 3,411-megawatt therarl, pressurized-water reactor employing an ice' condenser pressure suppression containment. 'The Final

Safety Analysis Report defines the calculated peak accident pressure, Pa , to be'12.0 psig. ...The reactor building containment is divided into four major _ compartments for the.CILRT analysis--the~ lower ice' condenser

' compartment which houses the, energy-absorbing ice beds,.the upper. ice condenser compartment which encloses'the support equipment for the ice-condenser; system,-the lower compartment which contains the reactor and the main piping'systessi and the upper' compartment which provides for a large work area within' containment and also can accommodate:the displaced air mass from the other compartments.In the unlikely event of a loss-of-coolant accident (LOCA).. These four compartments are connected by means of blowout panels located between the lower compartment and the lower ice condenser compartment and between the upper and upper ice condenser compartments. In the event of a LOCA, steam flows from the lower' compartment through the ice condenser. compartments and into' upper containment. The upper compartment is sealed from the lower compartment to' ensure that any steam released in'an accident will be forced through

' energy-absorbing ice beds. For the performance of the CILRT, the lower

(- and upper compartments were not sealed from each other to promote the free flow of air in co..tainment.

l' This report outlines tSe objectives, principal events, special equipment used, and analysis of the test results for the CILRT completed on March 19, 1989, on SON unit 2.

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.3.0 TEST PURPOSE j 1

The objective of the inservice CILRT was to demonstrate the leak-tight j integrity of the unit 2 reactor building containment for return-to-power .i operation.

For SON unit 2, the leak-tight integrity is defined in Technical {

Specification 4.6.1.2 to be that the leakage of air from containment is )

not to exceed 0.1875 percent per day (0.0078 percent per hour) at peak 1 accident pressure, P a*

4.0 CONDUCT OF TEST In compliance with Surveillance Instruction SNP SI-157, LLRTs were performed on containment closures (hatches and resilient seals), bellows, and electrical penetrations. LLETs were also performed on valves forming the boundary of the primary containment in accordance with surveillance instruction SNP SI-158.1. The above mentioned surveillance instructions were performed prior to the CILRT. All valves and penetrations satisfactorily met leakage requirements prior to the performance of the CILRT.

The initial pressurization of primary containment to 12.534 psig was completed at 08:19 on March 17, and the pressurization penetration (X-54) was isolated.

The stabilization period began at 08:20 on March 17, during which the primary containment boundary was tested for previously undetected leakage using a soap solution. The initial CILRT attempt after 23 samples taken at 12:04 March 17, 1989, measured a leakage rate of approximately 6.24 percentage of containment air mass per day (percent per dry) as calculated by the TTLR method procedure outlined in Bechtel's topical report, "Tese.ing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants" (BN-TOP-1, Revision 1).

Operations and Test personnel discovered two penetrations causing the excessive leakage problem and had operations personnel isolate them.

First, the Reactor Coolant Drain Tank (RCDT) outboard FCV, 2-77-10, on penetration number X-46 was found in the open position. The CILRT procedure listed this valve in the closed position except when draining the RCDT. The total time leakage rate dropped from 6.24 percent per day to 0.20191 percent per day after operations isolated 2-FCV-77-10.

Secondly, the lower Essential Raw Cooling Water (ERCW) penetration number X-59 was found to be leaking though the outboard vents 67-693A and 67-693C. The total time leaksge rate dropped from 0.20191 percent per day to 0.01132E percent per day after operations closed these outboard 4

vents.

i Reverific'ation of stabilization criteria was successfully completed at 08:15 on March 18. The temperature and pressure data taken during the

, stabilization period are shown graphically in figures 10 and 11.

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' c' ' .The CILRT compling p3ried bogtn ct 08:41 cud was conducted for 10 h2urs j and 40 minutes with'65 data samples collseted.' 'l v l Afterlthe completion of the CILRT, a. supplemental imposed' leakage- ]

} verification' test was' conducted to check.the results of the CILRT. The

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! imposed leakage was measured using a' mass flow meter technique, utilising. j a Hastings Mass' Flowmeter. ~A;1eakage rate (LR ) of.1.046 LA was

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^ 8 imposed on the, containment building. Agreement, as shown'in Appendix'B- l using TTLR, b6 tween the CILRT and tho' verification test was found to be.

l -0.03871 LA which is clearly within the 1 0.25 LA required by b 10.CFR 50, Appendix J.

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Figure 1" depicts the sequence of events for the CILRT and its verification conducted March 16-19,'1989. 'The following is an accounting

( of significant' events occurring during the test' program.

'03/10/89 17:45.- RCS pressurizer water level' sensing line connected to CILRT equipment.

03/15/89 04:00 Received ADMIN control of containment.

03/16/89 14:40 Lower. airlock door seals tested.

03/16/89 15:01 Upper door seals complete, tested airlocks configured.- ,

03/16/89 15:45 RTD location 14-channel 14 was reading erratic while channel 114 was reading good. Removed from data base and rebased.

DPE location 9-LPE for this location could not be located. Remoi,ed from data base and rebased.

03/16/89 20:50 Pressure in containment.is approximately 4 PSIG.

'03/10/89 21:15 Containment entry to check electrical connections.

03/17/89 01:41' Pressurizer water level verified and okay.

03/17/89 01:58 Compressors unloaded for 5 minutes and then brought back on.

03/17/89 01:54 Channel 234 jumped from 22.44 to 24.99 while channel 235 continued with steady rise - Started watching.

gauge closely for any additional abnormal jumps.

03/17/89- 02:29 No ch uge in pressure rate after cycling compressor.

03/17/89 02:43 Compartment 3 pressure reading is lower than other compartment readings. Watched it closely.

03/17/89 02:43 Pressure is approximately 8.6 PSIG.

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03/17/89' LO3'27' Chtanel 234..is' ab:utl1.5 psi high3r-then rsdundant Q.: W .

channel.-

'RTD channel 201,; local RTD 002 is.. reading

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'03/17/89 LO3:55 erroneously.

03/17/89 04:23, Channel 234 is abou,t 0.9 psi higher,than redun6 ant ,i channel'235.

'03/17/89 -04:34 PressureInside containment = 10.16:psig.

'03/17/89: [05:27 504356 mensor temperature reading:is high. *

03/17/89 07:40 Failed. instrument ID local 2 due'to' erratic readings. Absolute pressure'atL26.87' psia.

03/17/89 08:19 . Reached test pressure at 27;023 psia.

W .03/17/89 08:20 RBegan stabilization phase'(sample No. 1).

03/17/89 11:00 Isolated 2-67-693A which is vent for 67-87/88.

03/17/89 12:00- Stabilization data indicates MLR of approximately-6 percent per day. . ERCN is suspect.

03/17/89 12:30- After 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of stabilization. data,.the temperature stabilization criteria was met with a value-of .1138 of/hr. . Made containment entry to isolate ERCN"

. valves so stabilization phase will continue. -

5 03/17/89I 13:30 Floor' drain backed up. -Identified water leaking from 62-637, isolated 62-637.

03/17/89 13:54 Point to point leak rate' dropped from 5.73 percent / day to 0.35' percent / day.

.03/17/89 14:35' 2-67-563A was closed.

03/17/89 14:50 Rebased backup computer to sample No. 34. MLR dropped to 0.30 percent per day after one hour and

,, five minutes of data.

'03/17/89. 15:04 Completed containment entry.

03/17/89 15:30 (Approximately). During containment entry, ASE detected flow through RCDT; had unit operator close-77-10.

.03/17/89 15:40 Changed sample f 9quency from 10 to 15 minute L intervals during otabilisation period.

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03/17/89 17:15 MLR ct 0.38 pere:nt per dry with 3.22 hrs. of d te.

2nd containment entry to let' operations pump sumps <

down to sero levels.

.03/17/89 18:00' Aligned non-essential control' air'to containment to drain sump.

L 03/17/89 18:10 Started draining sump.

03/17/89 18:40 Sump drained.

03/17/89 .19:30 Containment exit for crew that drained sump. , ,

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03/17/89' 20:00. CVCS seal return realigned for ILRT; individual block valves for RCPs isolated.

03/17/89 20:30 Fitters enter airlock to blank off 2A ERCW cooler.

03/17/89 20:57~ 2A lower containment vent cooler + 2A CRDM vent cooler blanked off.

03/17/89- 22:35 Cooler still gurgling after blanking outlet.

03/17/89 23:15 Ultrasonic leak detector taken inside to; help leak check.

03/18/89 01:18 Coolers isolated but still leak.

-03/18/89 01:30 Fitters exit containment.

~03/18/89 01:56 67-576A + 67-576C capped closed.

03/18/89 01:57 67-693A closed (had been reopened to prevent water.

p- leakage in annulus earlier.)

03/18/89 .02:01 67-693C closed.

03/18/89 03:08 Reverified pressurizer level is' tracking correctly.

03/18/89 03:41 Containment exit with ultrasonics. j 03/18/89 04:04 MLR at-1.07 percent per day when rebased data is sample No. 87-(taken at 02:15).

03/18/89 04:10 Rebased stabilization phase to 03:45.

C3/18/89 04:33 MLR at 0.228 percent per day.

03/18/89 04:44 MLR at 0.57 percent per day.

03/18/89 04: 58 Turning off lights inside.

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E 03/18/89; l05:07:, MLR ot 0.072 percant per dry.

,.4" <f03/18/891 .05:4 72 '

.. Containment' entry.to check 67-777.and'67-574C. . . No

, water.

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, ;03/18/89 06:02 -Lights-turned out-in No. l' fan room.-

03/18/89 06:203 Exited containment. ? Verified door. configurations are correct.

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, 03/18/89. '08:15: Rebased' stabilization.to look at last,6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of data.: Stabilization phase will contain sample Nos.. . .87-111. CILRT.Phase will begin.with sample No. 113 .

at 08:41 on:3/18/89. .The. temperature criteria was-

- encellent for the" stabilization period..~ Sample froguencies changed to 10 minute intervals' for: test phase.

Y 03/18/89 13:00 MLR at 0.0246 percent / day!with:4:13' hrs.' data.

4 A: 03/18/89 15:50 MLR'at-0.0182 percent / day with 7:11 hrs, data.

!! 03/18/89 16:50 Sample No. 159 showed an abnormal drop in pressure occurred for gauge No. 1, therefore, gauge,was deleted from data base and data recalculated.

'03/18/89 16:55 With sample No.-162;MLR at.0.0247 percent per day..

with gauge No. 1 removed, 8:17 hours of data.

Average pressure 'at 12.309 psig. -

03/18/89: 17:11.- Completed CILRT at sample'No.'164. Began taking verification sample No.:1.

$ l03/18/89 18:11' Waiting on operations 1 to resolve problem of-how-to-open verification flow path..

s 03/18/89 19:29 Established verification flow. Will rebase start of

'!. verification-to sample:No. 178 and include samples; 165-177 in the ILRT phase.

.03/18/89 19:35 - Verification flow established at 113267.4 SCCM.

.03/18/89 21:00 Rebased verification phase to sample No'. 181 (at 20:02).

03/19/89 01:25' Verification completed, samples 181-213.

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.03/19/89 '02:26 Began-depressurisation of. containment.

03/19/89 08:30 Depressurization complete. HP says o.k. to go 12.. .

1 03/19/89 09:00 Post-test calibration started.

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03/19/89 14:30 Post-test calibration complete.

03/19/89 16:00- Return ADMIN control of reactor building.

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l h3!CILRT and subsegu:nt' verification tosts waro c:mplotsd at 01:25 cn 4 T

' a March!19h 1989t and'adminletrative. control of_th> reactor building w.s:

. released at 16:00 hours. . Test personnel then immediately Degan investigation of:the: excessive leakage. problems' associated with

.-penetration numbers.X-46'and X-59.

The excessive leakage from penetration X-46'was( found to have occurred-

. because the RCDT-outboard FCV, 2-77-10, on penetration number X-46 was

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4 incorrectly 11ned up in'the open position. The-inboard FCV, 2-77-9, was N ;- correc'tly b)ocked open during the CILRT to allow draining of..the RCDT.

FCV-2-77-9 must be blocked open during'the CILRT because it is an air-operated valve which fails closed when control' air is isolated from'the

. containment. building. .Since both,the inboard FCV (2-77-9) and the.

outboard FCV'(2-77-10) were open,'a direct leakage path from containment-

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occurred,via the refuel canal drain lines, which are isolated during to . normal operation and usually. isolated during mode 5. xAfter FCV-2-77-10 was isolated during-the initial CILRT' attempt,:the leakage rate dropped- a from'6.24% per' day to 0.20191% per day.- CAQR SQP 890195 was initiated to L

investigate the.CILRT, valve line-up problem, and the results required a revisien to .the' CILRT procedure to add additional instructions for

~ tagging'the handswitch.for FCV-2-77-10.

The.' excessive. leakage from penetration X-59 was also-thoroughly

- investigated ^and showed the following results, e 1 i

Penetration X-59-had been tested per.SI-158.1 on'3/3/89, and based on test results, an "as-left" path leakage rate of 0.3266 SCFR was

. anticipated ( During the performance of SI-156 on 3/17/89, the path leakage rate appeared to be. considerably higher. -The 3/3/89 SI-158.1 local. leak rate data for penetration X-59'showed that 67-88 leaked 0.4338'

- SCFH and.67-87/575A leaked 0.3266 SCFE. A. unit action plan was initiated on 3/18/89: to measure post-CILRT leakage and, if different from the .

- SI-158.1 "as-Icft" data, to determine the cause._ The valves were tested

- in' place after conclusion of the CILRT. The-post-CILRT leakage rate data

' showed:that 67-88 leaked 570.4995.SCFR and 67-87/575A leaked 171.6762 SCFE. ;CAQR 890169 was initiated'3/19/89 to determine the cause for the excessive leakage ~through penetration X-59. , Maintenance was performed to inspect and repair these valves. The results showed that,the valve' disc on 67-88 was traveling past the normal seating position and a.0.016" clearance between'the disc and' seat had opened. . Next, it was.found that the valve disc on 67-87 was traveling just slightly into the seating area. Maintenace personnel removed the check valve bonnet and found that 67-575A had dirty seats from residue after evaporation of ERCW. All valves were inspected in the closed position. .Each valve was cleaned or adjusted: and . reassembled for final "as-left" local leak rate ' testing per SI-158.1. The final "as-left" SI-158.1 leak rate data taken-3/22/89 showed that 67-88 leaked 0.0000 SCFH and 67-87/575A. leaked 0.0000 SCFH.

The CACR investigation evaluated the historical record of these valves for generic implications per SON AI-12 Part'III paragraph 2.9.4.B.7 to avoid . re:rring CAQRs. .The "as-found" SI-158.1 leak rate data showed that eleven of the seventeen lower ERCW tests had 0.0000 SCFH leakage.

Four more of these ERCW inboard isolation valves showed a leakage of 0.0000 SCFH following maintenance on the associated inboard check 0243C/COC3 M

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. valves. 'During the; performance of SI-156,}only penetration-X-59;showed!

' leakage;in' excess of?the expected. amount. Therefore, the~ excessive leakage associated with penetration X-59.certainly: appears to be an:

. isolated. incident and'not:a recurring problem or a programmatic deficie'ncy.-

The~ investigation researched thefcause for penetration X-59 to exhibit a- ,

pathfleakage rate higher.than what was espected following the 3/3/89 "as - -l

- left":SI-158.1 test.- Pertinent event records were reviewed to gather information on a'11 maintenance, modifications inspections; 'and testing

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activities: conducted onitheriower ERCW system'from 3/1/89 to 3/17/89. , ,.

This included:. operations configuration control logs;. work control group

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records; MOVAT maintenancerrecords; mechanical maintenance 1 records; modifications work plans; SI-158.1 chronological log sheets; and.the SI-156 log book. -The local leak rate: procedure SI-158.1 used to. perform-the 3/3/89."as-left" leak rate tests was thoroughly reviewed and' personnel interviews were' conducted'with the: leak rate testers involved.-

, ~ MOVATS= records 1for the 2/15/89 testing of'67-87.'showed an open to close stroke time of157.45 seconds and a close to'open stroke time of 57.25 seconds. The 3/20/89 post-CILRT MOVAT test was made withou*. adjustments and showed an open to close stroke time of'57.5-seconds along with a close to open stroke. time of 57.54 seconds. However, the factLthat the 2/15/89 and 3/20/89 MOVAT. tests are-virtually identical only indicatt.s.

that- the valvei operator was ; performing as espected.. The MOVAT stroke

' time test does not indicate valve position because there are no internal travel stops inside;this. type of butterfly' valve. The travel stop 11mits for.this type of valve are set in the valve; operator itself. -The

- operator limits were adjusted 3/22/89, and the subsequent MOVAT test data, showed an open'to close. time of'59.96 seconds:and a close to open' time of-59.92 seconds.; The final "as-left" SI-158.1 leak, rate test on 3/22/89-showed.that 67-87/575ALleaked 0.0000 SCFE.

Mechanical Maintenance used WEB 753972 to remove 67-88 from the X-59 line on 2/4/89 for inspection and repairs. The valve body and the operator were physically separated during the maintenance process.

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The' valve seating surfaces were inspected and cleaned,:and on 2/5/89, 67-88 was-reinstalled in the'line. Then the valve operator'was' attached to the

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valve body. This sequence of installing the valve body without the operator attached precludes the visual confirmationof' valve' disc

. position when setting the travel stop limits. The MOVAT' records-for the-3/1/89. testing'of 67-88 showed an optn to close-stroke time'of 29.5-

- seconds and aiclose to open stroke time of 29.46 seconds. The'3/29/89 post-CILRT MOVAT tests were made'without adjustments and showed an open to close= stroke time of 29.5 seconds,and.a close to open stroke time of.

29.44 seconds. However, the fact that the 3/1/89 and 3/20/89 MOVAT. tests are virtu' ally Identical only indicates that the valve operator,was performing as espected. The MOVAT stroke time test does not indicate valve position'because there are no internal' travel stops inside this type of butterfly valve. The travel stop limits for this type of valve are set in the valve operator itself. The operator limits were adjusted 3/21/89 and the subsequent MOVAT test data showed an open to close stroke time of 27.85 seconds and a close to open stroke time of 27.77 seconds.

The final "as-left" leak rate test on 3/22/89 showed that 67-88 leaked 0.000 SCFH.

0243C/COC3 y ,

4: '

i TharoLwas na cvid:ncs thzt'eny undscumentsd maintentncs or modifications was. performed on these valves that could have accounted for.their.

unerpected failure during SI-156.. Similarly, there was no evidence that any non-documented' maintenance or. modification activities were performed on the;. lower ERL*W system.1 The test' personnel.. involved with tbs 3/3/89

'.SI-158.1(leak rate test.were qualified per1ASNT-TC-1A. The apparent cause for'the incorrect'SI-158.1. leak. rate tests recorded 3/3/89-for

. valves 67-88 and 67-87/575A hasfneen determined to be personnel error during the conduct of the local leak rate tests. .The root cause-apparent 1y' stems from inattention to detail in properly connecting the:

. hose from test equipment to the test connection for the valves being tested.- The test hose passed.over,a sharp edge.which probably crimped .

the hoseLflat enough to hinder the flow rate.. *he. pre-test'" free-flow"-

~ ~

verification step was performed with enough pressure to overcome this flow restriction in the hose and indicate that a clear flow path existed. However, when the relatively low. test pressure and flow rate was applied, the hose restriction masked the' correct. leakage rate.

CAQR 890169 recommended that the local leak rate procedure be revised to Juclude additional instructions to check the routing of the test hose as part of properly connecting the test equipment. It also recommends that the Maintenance Department investigate setting the trave 1~stop limits for these type of butterfly valves while the valve is removed from the line prior to reinstallation.

5.0 TEST RESULTS The "as-found" condition of the reactor building primary containment (the condition of the containment at the end of the o7erating' cycle) demonstrated the leak-tight integrity of unit 2. For Sequoyah. unit 2, the leak-tight integrity is defined in Technical Specification 4.6.1.2 to-be that the leakage.of air from containment is not to exceed 0.1875 percent par day.(0.0078 percent per hour) at' peak accident pressure, j P. The "as-found" reportable 95% UCL, including the addition of the a

local leak rate test " leakage savings", was.only 0.079 percent / day, and shows a. vast improvement over the previous leakages recorded for unit 2.

This' improvement is attributed to improved maintenance,~erpansion of the

. local leak rate test program, .and the replacement.of 5 isolation valves with' chronic leakage histories.

.The CILRT sampling period began at 08:41 after stabilization-was reached at 08:15 on the 18th.

The CILRT was conducted for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months and 40 minutes and 65 data samples

. wore collected. The' calculated leak rate reported by.tho' total time leak

. rate method (TTLR) was 0.011326 percentage of containment air mass per day (0.00047 percent per hour), and'is shown graphically in figure 12.

The observed 95 percent upper coniidence limit for the measured mass leak rate was 0.06194 percent per day (0.0026 percent per hour). This reportable leak rate represents 33 percent of the allowed 0.18750 percentage of containment air mass per day (0.75L A) as described in Technical Specification 4.6.1.23 The mass leak rate (MLR) was 0.02785 percent per day and is shown graphically in figure 13, with a 95 percent upper confidence limit of 0.03158 percent per day. The higher TTLR i confidence limit is due primarily to the different calculation technique used to determine confidence limits in the total time analysis as defined in BN-TOP-1, Revision 1.

0243C/COC3

= - _- - - - . - - - -

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'. t v Aft 3r tha comp 1Gtion of th$ CILRT,Ja, supplemental imposed logkig3

verification' test.was. conducted tolcheck the results of the,CILRT. 'The-Limposed leakage was. measured'using~a' mass flow meter. technique, utilisingj

a Hastings Mass Flowmeter. JA leakage rate (L )ROf'1.046 LA - was .

limposed~on theEcontainment' building. '

.The calculated TTLR during the-5 hours and 20 minutes verification test-was 0.26575; percentage of containment' air mass per' day and is'shown graphically in' figure 19. Agreement, as shown in Appendix 8 using TTLRr between the CILRT and the verificationitest was'found to be -0.03871.LA which is clearly within the 1 0.25 LA required by 10'CFR 50, Appendix J.

The calculated containment mass leak rateT(LRM);during:the~5 hours and .

-20 minutes verificationitest was 0.27232 percentage of! containment airr mass per dayLshown graphically'in figurej20. Agreement, as shown-in Appendix!B;using MLR, between the CILRT and theJverification test was also achieved and was-found to'be -0.07819 L .A The CILRT.and subsequent verification test were completed at 01:25 on March 19, 1989.. The final reportable leakage rate was .011326 percentage of containment e.ir mass'per day as calculated by the TTLR method, and'the-observed'95 percent upper confidence limit (UCL) was 0.0620 percent.per day. The.above mentioned 95 percent UCL includes leakage measured from type B&C tests ~for testable' lines that' wore in service ~during the test.

'The. reportable leak rate we.r.(only 33, percent of therallowable 0.1875 pereent.per day-(0.75L A). .The : March.18, 1989 "as-loft" CILRT_ leakage rate also sh,ws'a.. vast < improvement'over-the previouscloakages recorded; for unit 2r proving the "as-left" condition of the reactor building

~

primary containment to be leak-tight.

- 6 '. 0 L MEASUREMENTS AND CALIBRATIONS g 6.1 Test Eguipment

' Table 1' lists'the. range, accuracy, and repeatability of the-special test, equipment used in the unit.2, cycle 3'CILRT. Prior to the start of the CILRT, all testLequipment was calibrated by.the TVA 3 Central Laboratories or other facilities with standards traceable to the National Bureau of.. Standards. After installation of all special

. test equipment inside containment, each sensor was checked for functional operation. The special test instrumentation interfaces

-with a portable minicomputer which produces highly accurate remote scanning of' temperature, pressure, and dewpoint sensors. Upon test-completion and.depressurization each sensor was again functionally checked to ensure adherence to calibration. ,

Pressurization for the CILRT was achieved using portable-high'-capacity air compressors. The compressors were rated at 3,500-SCFM of dry, oil-free air, and brought containment to test pressure in approximately 17 hours1.967593e-4 days 0.00472 hours 2.810847e-5 weeks 6.4685e-6 months , including final " topping off" stages of pressurization.

0243C/COC3 l

r s pl I E D' a Thilcak-tight intcgrity of: S:guayah Nuc10cr Plant unit 2 was :

ce accurately, measured- and recorded by computer-based instrumentation. .)

< LThe computer-based data acquisition. system provided reliable,. j

'l 1

=

,immediate calculations of test datar which allowed test engineers to-more easily monitor important test parameters.:

il;

,6.2 Sensor Location .

Table 2 lists the final volumetric weighing factor for'each temperature and dowpoint sensor based on the 4-compartment model.

L , . Figures 3 through 8 indicate sensor locations., The pressure' sensors

. Lwere divided so that; initially;two sensors measured each~of the four' ~ *

, compartments through penetrations X-27C, X-87Di X-87A, And X-98.

lUtilising two pressure sensors per compartment' allows'the removal of any one malfunctioning pressure gauge during the_ test and continue to accurately monitor containment pressure.. An. additional pressure gauge measured barometric pressure at the test station.-

6.3 comenter-named Data Aeaufsition and Data nediction f

The-raw test data measured'by the special. test instrumentation during the Sequoyah Nuclear Plant unit 2 CILRT was scanned and collected by.a new microprocessor based data' acquisition system. '

This raw test data was automatically presented to a portable'aulti-tasking minicomputer system for correction to calibration: curves and-reduction to containment leak rate. The minicomputer produced-y immediate statistical and graphical results of the containment test.

parameters,,incicaing. temperature, pressure, vapor pressure, mass, mass leak rate,,and total time'1eak rate plots.

These calculated results were reported automatically to the test director as the data was collected. Figure 2 depicts the functional-relationship _between the special test instrumentation and the data acquisition and analysis system.

All calculations performed by the minicomputer system were in conformance with the procedures outlined in ANS 56.8, ANSI 45.4 and Bechtel-Topical Report (BN-TOP-1, Revision'1).

Source listings for all computer programs are on file with tho' Computer Engineering Group, in Chattanooga, Tennessee.

6.4 Reactor Buildino Containment Model An ice condenser pressure suppression containment presents special problems not normally' encountered in the leak testing of dry containment. structures. The pressure suppression design feature s requires the reactor building containment to ha divided into t distinct compartments, where vastly different temperatures and-vapor pressures may exist.- While each compartment is vented to the containment atmosphere during the performance of the CILRT, the direct circulation of air is limited.

0243C/COC3

e -------- - ,,

24 l

(l{7 '

, < Sinca en icafc:nd:naar es ttinment typically cxhibits"o 40'F g" ,,

. temperature differential'between the' ice compartmentseand others, it;

.- 'is>necessary(to compensate by? compartmentalization so the leak' rate: j

~ 1s[ accurately measured.'-For Sequoyah unit 2.CILRT, a four-compartment containment model was used to measure the leak rate.

The free ' air- mass is calculated individually for each compartment,- y and containment' leak. rate is' calculated for the sum of the- I compartmental masses. Each sensor within a compartment is' volume 4 weighted for'the calculation'of compartment average temperature and.

~

vapor pressure.- Figure'9 depicts.the four compartments used in the -1

. Sequoyah unit 2 reactor. building containment model.

~

i The Reactor Coolant: System (RCS)' Pressurizer water level.was-i, continuously monitored by the1CILRT data acquisition system throughoutlthe CILRT period so.that adjustments ~could be: accurately

. h made to the containment'" free-air" volume" calculations... Other component levels in'the RCS were monitored'via plant instrumentation by plant personnel during the CILRT to account for other " free-air" volume changes not reflected by.the pressurizer. With the exception-of the RCS, all other components exposed to CILRT pressure were at H 100 percent level for the duration of the CILRT and subsequent.

verification test. Thus,'no additional " free-air"' volume adjustments were necessary. Test sayineers requested that

= operations control the water level-in the primary system so that no abrupt level changes.would occur.

7.0 ~ ANALYSIS OF TEST DATA ,

-The previous. sections of:this report have discussed the general. test conduct, calibration methods, and test equipment. In this section events and problems: that-influenced the test results are ' discussed and are used to formulate conclusions on the performance of the Sequoyah unit 2, cycle

.3 CILRT.-

'7.1 Instrument Check The data presented in this section reflects the test results-following recalibration and deletion' , if necessary, of the;special test equipment uced during the test.

Temperature sensor at location three (shown:in Figure 3)-was found to be out of tolerance at the 120*Forange~only. Tais.did not' affect the outcome of the CILRT because the range of temperature for-location three was between 72*F and-77*F during the' entire test.-

The corrections made to the final CILRT:and verification test data did not effect the success of the CILRT perfo,rmed on unit 2. In additional, all final ~ test results and reported data in this report reflect the above mentioned corrections.

The instrumentation error analysis of Appendix A indicates that the instrumentation used in the unit 2, cycle 3 CILRT was accurate to 0.0130 LA in determining the containment leak rate for unit 2, far t arpassing the recommendations of ANS 56.8 which states that the ecasuring system be capable of detecting 0.25 L A.

0243C/COC3

y a

'7;2I Discussion of Graohical and Tabular Results' .

e nThe March 18-19, 1989 CILRT that was1 performed.on' unit 2 at:Sequoyah. g Nuclear Plant was concluded. af ter' 65 samples were taken in 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months 7 and. forty minutes'of testing._ Figure'12'is a graphical represen-tation of the TTLR and figure.13 is a graphical representation'of the MLR,1 expressed as a percentage of containment air mass l'er day,-

during the CILRT. Tabulated data accumulated during the CILRT Jis shown in Table 3.

~

The temperature trends in the upper-ice compartment were cyclic in nature.(see Figure 14)'.- The reason for;the trends is directly-related to.the defrost cycles of thel i ce condenser air handling; units. .These' temperature trends resulted in corresponding mass trends in the upper-ice compartment as shown in figure 15.

Figures 15 through 18.show graphical representations of average temperatures,. pressures, and masses during the 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months and 40 minutes CILRT. Table 3 is a tabular listing of important measured parameters and corresponding results for.the unit 2 CILRT.

Final results indicate a TTLR of 0.011326 percent per. day and a MLR of 0.027854 percent per day. The associated 95' percent upper con-

-fidence limits.for the Sequoyah unit'2, cycle 3 CILRT were 0.062008 percent per day,for TTLR and 0.031579 percent per day for MLR.

After instrumentation received post-test calibrations, the.

calibration reports indicated that all instrumentation used in.the unit 2 CILRT and subsequent verification test was in proper tolerance, with the exception of items already mentioned.-

7.3 Discussion of Aare===nt (verification Test)

Appendix J to.10 CFR 50 specifies the technique for.the calculation of. agreement between the CILRT and its subsequent verification.

Appendix J requires the absolute value of the diffwrence between the measured containment leak rate with a superimposed. leak and the sum of the. imposed leak and the measured containment leak rate be less' than 0.25 L A.

The' verification test was concluded at 01:25 on March' 19, 1989.

After collecting 32 samples in approximately 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months and 20 minutes, agreement, as prescribed by Appendix J of 10 CFR 50, between the CILRT (LAM) and the imposed leak rate (LR ) was reached at

-0.03871 LA using TTLR, which is well within.the r 0.25 LA allowable limit.

Agreement was also reached using MLR and was found to be -0.07819 l A ~ Appendix B details the methods of agreement r, calculations.

I L.

Tabulated data collected during the 5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months and 20 minute verification test is shown in Table 4.

F3gures 19 and 20 show the mass and total time leak rate plots during the 5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months and.'20 minute hour verification test, while Figares 21 through 23 show graphical representations of average temperature and pressure and mass.

0243C/C0C3

- _ _ - = _ _ - _ _ - - - _ _ _ - - _ _ _ - _ _ _ .i

n .

8.0 CONCLUSION

S The reactor building containment integrated. leak rate test performed;on-p Sequoyah Nuclear Plant unit:2, cycle 3, was successfully completed on March 18-19, 1989.. The final reportable leakage rate was .011326-

percentagefof containment air mass per day.as: calculated by.the TTLR u method, and the observed 95% upperfconfidence limit (UCL) was 0.06194%

/per day. This 95% UCL includes leakage measured from. Type B&C tests for testable lines that were in service during the test. The reportable leak' rate was only 33% of the allowable 0.1875% per day (0.75LA),.

demonstrating that'the "as-left" condition of the unit 2 reactor building ~

primary containment was leak-tight. Therefore, the leak-tight integrity ofithe unit 2 containment:was in conformance at the end of cycle 3 and" continues-for the beginning of cycle 4.

As mentioned earlier, the local leak rate procedure will be revised to include additional instructions to check the routing of the test-hose as part of: properly connecting the test equipment. Also, the ERCW valves are rubber ifned butterfly valves which do not have internal travel stops.- The travel Ftops are set in the operator, usually with the valve installed'in-line and, therefore, the valve position cannot be guaranteed.. Therefore, whenever maintenance has removed one of'these type of valves from the line, it would be best to reinstall it with the operator attached and the limits adjusted. It has been recommended that the Maintenance department investigate. setting the travel stop limits for" these type of butterfly valves while the valve'is removed from theilinee prior to reinstallation.

Modes'1, 2, 3 and 4 require ihat containment leakage rates shall be determined to-be in conformance with the. criteria specified-in Appendix J

'of"10CFR50 and SON L.C.O. 3.6.1.2. The allowable leakage-(La) for Sequoyah Nuclear Plant. unit 2 is-currently defined.in the Technical:

Specifications as 0.254 per day'of'the containment free air volume at a calculated peak accident pressure (Pa) of 12.0 psig, or 225.2 SCFH.

~

Technical Specifications also define the acceptance criteria for the Containment Integrated Leak Rate Test (CILRT) as.75% La, or 0.1875 percent per day. The condition of the Sequoyah Nuclear Plant unit 2 containment at the end of the operating cycle proved to be leak-tight, with the "as-found" leakage rate less than half of the allowable limit (0.1875 percent per day). The excessive leakage encountered during the initial CILRT attempt resulted from isolated incidents occurring only during the cycle 3 maintenance outage, and were not a reoccurring containment problem or programmatic deficiency. Subsequent to operations personnel isolating FC7-2-77-10, the. leakage rate was initially measured

~

at 0.20191 percent per day. While this initially measured Teakage rate exceeded the SQN unit-2 technical specification limit of 0.1875 percentage of containment air mass per day, it was still below the La allowable' limit of 0.25 percent per day. The draft version of Appendix J to 10 CFR 50 dated October 29, 1986, under section III.A.7.b states that

-the "as-found" leakage rate must not exceed La. The unit 2 "as-found" CILRT leakage rate would have been acceptable under this philosophy. The "as-left" reportable 95% UCL leak rate measured 0.0620 percent per day, which is only 33 percent of the allowable limit (0.1875 percent per day). Therefore, the leak-tight integrity of the unit 2 containment was in conformance at the end of cycle 3 and continues for the beginnning of cycle 4, with the excessive leakage occuring only during the cycle 3 maintenance outage.

0243C/COC3

\,

D

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TABLES t

0243C/COC3

The technigu3L ef cultic:aptrtment mod 311:tg .ctupled with a c:mputor-bns:d d*to ccquiciticn cystem yield:d immedicto rscults th t accurctoly measured and displayed the' unit 2 containment' leak rate.

In summaryi the ~ "as-found" and "as-lef t" condition of the unit 2:reac+.or building primary containment has improved dramatically, probler valves have been replaced, LLRT and CILRT procedures'have been expandeo and improved, and past CILRT leakage problems have been specifically identified and positive corrective actions have been taken to prevent recurrence. ~The specific cause of the excess leakage during the cycle 2-and cycle 3 CILRTs have been directly addressed through the-local leak rate test program. Test results and problem identification have . .

demonstrated that a general, containment leakage problem 6oes not exist.

We conclude that the conditions which-caused the leakage to exceed the

-leakage limit set forth in the technical specifications can best be addressed;through. local' leak rate ^ testing.

I i

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TABLE 2 n .

VOLUMETRIC WEIGHTING GROUPS Volumetric Weight Number of Segment Per Sensor.by' Temperature Transducers Volume Compartment (Percent)

I.' Upper compartment 13 651,000 7.6923 II. Lower compartment 25- 383,720 '4.0000' III. -Ice-upper compartment 6 47,000 16.6666 IV.- Ice-lower compartment _,1 110,500 25.0000 '

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I. Upper compartment 3 651,000 33.3333 II. Lower. compartment 3 383,720 33.3333 III. Ice-upper compartment '4 47,000 25.0000 IV. . Ice-lower compartment _,2. 110,500 50.0000 12 6

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e e e APPENDICES 4

4 0243C/COC3

l APPENDIX A 4

iSSUMED CONDITIONS AT THE TIME DE TEST: PA = 26.6960 PSIA T = 66.2800 DEG F RESULTS USING 065 SAMPLES (SAMPLES I-113 - T-177) ELAPSED TIME 010:40

1. TOTAL ABSOLUTE PRESSURE METHOD: NUMBER OF SENSORS:-07 RANGE: 0- 30.0 PSIA ERROR IN PRESSURE = 0.5786920E-04 PSIA (USING REPEATABILITY)~

ERROR IN PRESSURE = 0.1513786E-02 PSIA (USING ACCURACY) 2... WATER VAPOR PRESSURE: NUMBER OF SENSORS: 12 ERROR IN VAPOR PRESSURE = 0.2655944E-03 PSIA (USING REPEATABILITY)

ERROR IN VAPOR PRESSURE =. 0.2655811E-02 PSIA (USING ACCURACY) 3.' TEMPERATURE : NUMBER OF SENSORS: 48 ERROR IN TEMPERATURE = 0.2041242E-03 DEG R (USING REPEATABILITY)

ERROR IN TEMPERATURE = 0.1443448E-01 DEG R (USING ACCURACY)

4. ISG (USING REPEATABILITY)

ISG =2400'TMASQRT(2A(CEPR/P)AA2)+2A((ERVR/P)AA2)+2A((ETR/T)AA2))

ISG = 0.3242329E-02 PERCENT / DAY = 0.1303015E-01 LA

5. ISG (USING ACCURACY)

ISG =2400/TMASQRT(2A((EPA /P)AA2)+2A((ERVA/P)AA2)+2A((ETA /T)AA2))

ISG = 0.3746853E-01 PERCENT / DAY = 0.1505771 LA

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J 4

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APPENDIX B ;

l 1

CALCULATION OF AGREEMENT (USING TTLR) 4

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l f 4 Where _LRM - LR-LAM i 1 25 j LA l

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. . ~l Wher6: LRM;" containment leak rate measured during verification LR

imposed' leak rate for thrification Lga A containment leak rate measured during CILRT LA = full pressure design basis leakage

('

ll/ LRM

113847.4 SCCM LR = 113181.2 SCCM LAg = 4854.258 SCCM LA = 108188.19 SCCM LRM - LR-LAM = 113847.4 - 113181.2 - 4854.258 = -0.03871' LA 108188.19 Agreement: -0.03871 LA c 2 0.25 LA Therefore, compliance with Appendix J using the TTLR, has easily been met.

4 0243C/COC3 C__ _ _ _.

'~f'

v. 'APPENDIZ B CALCULATION OF AGREEMENT FUSING MLRI Agreements; Law - Ln - L Ag 1 .25 LA Where Lgg m containment' leak rate measured during verification LR." 1* Posed leak rate for verification

l. '

LAg = containment leak rate measured during..CILRT

LA_= full, pressure design basis leakage LRM = 110659.3 SCCM

.LR:= 113181.2 SCCM LAg =-11937.61 SCCM LA = 108188.19 SCCM

.LRM - LR-LAM'"'116659.3 - 113131.2'- 11937.61 = -0.07819 LA 108'188.19

. Agreement -0.07819=LA < z 0.25-LA Therefore, compliance-with Appendix J using the MLR, has also'been met.

9 9

0243C/COC3 a___u____________ _ _ . . _ _ . . ._ _ _ _ _ _ _ _ _ - .- _ .- . _ _ . _ _ _ _ _ _ _ _ .

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APPENDIX C r

SPECIAL TEST INSTRUMENTATION I. Pressure Measurements (8-total)

Two Mansor Quartz Manometers Per Compartment II.. Temperature Measure (48 total)

Upper Compartment (13 total) V = 651,000 cubic feet RTD -1 RTD -9 - -

RTD -2 RTD -10 RTD -3. RTD -11 RTD -4 RTD -12 RTD RTD -13 RTD -6 RTD -7 RTD -8 Lower Compartment (25 total) V = 383,720 cubic' feet RTD -25 RTn -38 RTD -2C RTD -39 RTD -27 RTD -40 RTD -28 RTD -41 RTD -29 RTD -42 RTD -30 RTD -43 RTD -31 RTD -43 RTD -32 RTD -44 RTD -34. RTD -45 RTD -35 RTD -46 RTD -36 RTD -47 RTD -37 RTD -48 RTD -38 RTD -49 Ice' Condenser (10 total)

Unoer Volume LREer Volume V = 47,000 cubic feet V = 110,500 cubic feet RTD -15 RTD ~21 RTD -16 RTD -22 RTD -17 RTD -23 RTD -18 RTD -24 !

RTD -19 i RTD -20, 0243C/COC3 l_ _ _ _ __ -

f( 72 ppgggy * .

1.; ,

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(: SPECIAL TEST leis rxUrENTATION - .

h. (Continued) .

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- III.- Vapor Pressure Measurement: (11 total)

Upper Compartment (3 total)

DPE --I {

DPE -2

'DPE -3 Lower Compartment.(3 total)

DPE -4.

DPE -5 DPE -6

. Ice Condenser (6 total)

Uoner Volume Lower Volume DPE -10 DPE -7 DPE -11 DPE -8 DPE -12 DPE -13 IV. Test Station Equipment Temperature 1 RTD Barometric Pressures 1 Pressure Gauge 0243C/COC3

= - _ - -.

.s. -

9 p4 .O APPENDIX D b , LOCAL LEAK RATE TEST

SUMMARY

.)

j

.A; 1Tvoe'B Tests-f U Two methods were used.to perform the type B tests - the absolute' method (pressure decay) and theivolumetrics mass flowmeter. method. Both methods =

~

.use air or nitrogen as the test medium, with,the testable l volume pres -

surised to a' designated test pressure., The absolute method' determines:

the leakage' rate by a measured pressure. drop'during a' set time specified L a in Sequoyah's surveillance instruction, SNP SI-157, for testable' ~

penetrations,and SNP SI-159_for the.. personnel. air lock test. The: . ,.. i L volumetrics' mass flowmoter makes a direct mass flow measurement with' e readings given in standar.i; cubic centimeters per minute-(SCCM).

-All testable penetrations were tested prior to the performance of.;the

.CILRT.

g, Any penetrations or hatch covers opened after the completion of the CILRT will be tested prior to-unit startup under the applicable plant-approved surveillance instructions.

A summary of all type B test data since the unit 2 cycle 2 CILRT conducted in November 1984 is included in this appendiz (see Table D-2).

B. Tvom C Testa ,

Three methods were used to perform the type.C tests -- an airflow method, a water displacement method, and the volumetrics mass'flowmotor method.

The airflow method consists of a rotameter-flow facility in'line with the.

' testable valve through a. test connection.. An air supply is connected to the rotameter facility, which measures tho' flow of air necessary to replace the air-leakage past the valve being tested. From this, a leakage rate is determined.

The water displacement method consists of a calibrated water test tank equipped.with a sight. glass. A timed water level. drop is measured to calculate the' leakage past the valve (s) being tested. A separate air

' source is used to' maintain the water pressure at the ptescribed test pressure. A special " water inventory test".is conducted on containment spray, applicable only to valves FCV-72-2'and FCV-72-39 and the rearsinder of test utilising the water displacement method are the ERCW discharge isolation valves.

.The'volumetrics mass flowmeter is also used to conduct type C. tests.

- All testable' containment isolation valves were tested prior to the performance of the CILRT. The results of these tests are noted in the summary of type C data in this appendix (see Table D-1).

0243C/COC3

y <

- r .. 7,;

' , i APPENDIX D .*

E '" T *

, , f(Contiturd).

ji Any.;maintenancelaction or repairs'on containment isolation valve subject"

~

i .

to type'C tests which would.affoct~ leakage from primary containment ~will

' be retestod'under.the applicablez plant-approved-surveillance instruction-

. before unit startup.,

- A summary of'the=. data for.all type C tests since the unit 2' cycle 2' CILRT is includedLin'this appendix. . Penetrations in water-sealed' systems; subject to inventory restrictions'and penetrations-whose leakage might bypassLthe shield building emergency gas treatment system are-identified in' Table D-1 of this. appendix. . -

E f

1 a

9 J

k 4

1 i-t 02(3C/C0C3-

---.___.____E___

W-i

)

I APPENDIX D -

'l

SUMMARY

OF LOCAL LEAKAGE RATES Unit 2, Cycle 3 J L .i Type B Leakage As Left 'I A.- Penetration Leakage 1 2389 1 B. ' Air Lock Doors 2.6061 Total Ty,pe B Leakage 3.815 q Total C Leakage- 1.6987 As Left Maximum Allowable Total (Types B and C): 5.5137 141.9 SCFH Penetrations defined as potential bypass leakage i paths 4.3048 59.1250 SCFH Penetrations water sealed to at least 1.1 Pa subject to inventory restrictions:

Containment Spray 0.06 CFH 0.08 CFH RHR Spray 0.02 CFH 0.11 CFB 6

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_ _ ___ ____.___ d

[ .g. :6 TABLE D-2 TYPE B TEST

SUMMARY

CYCLE 3 UNIT 2

'I. Airlock Door Test (overail)

Penetration Date Testgd ]mak Rate (SCFH)

X-2A 04/09/85 AF/AL 1.4047.

X-2B 04/10/85 AF/AL 0.6956 *

X-2B 10/17/85 AF/AL 2.6800 X-2A 10/16/85 AF/AL 3.3663 X-2A 09/23/87 AF 474.6750 X-2B 09/23/87 AF/AL 0.3731 X-2A 10/38/87 AL 4.5500 X-2B 03/08/88 AF/AL 2.0044 X-2A 03/10/88 AF/AL 2.6314 X-2B 02/11/89 AF/AL 2.3837 X-2A 03/14/89 AF 23.4420 X-2A 03/15/89 AL 0.2224 II. Bellows Penetration Date Tested Leak Rate (SCFH)

X-12A Inboard 08/07/87 AF/AL 0.0000 01/22/89 AF/AL O.0000 X-12A Outboard 08/07/87 AF/AL 0.0000 01/22/89 AF/AL 0.0000 X-12B I 08/14/87 AF/AL 0.0011 01/22/89 AF/AL 0.0000 X-12B O 08/14/87 AF/AL 0.0000 01/22/89 AF/AL 0.0000 X-12C I 08/14/87 AF/AL 0.0000 01/22/89 AF/AL 0.0000 X-12C O 08/14/87 AF/AL 0.0000 01/21/89 AF/AL 0.0000 X-12D I 06/06/87 AF/AL 0.0000 01/22/89 AF/AL 0.0000 X-12D 0 08/06/87 AF/AL 0.0000 01/22/89 AF/AL 0.0000 X-13A I 08/07/87 AF/AL 0.0000 l 01/28/89 AF/AL 0.0000 X-13A O 08/07/87 AF/AL 0.0000 01/28/89 AF/AL 0.0000 X-13B I 08/14/87 AF/AL 0.0110 01/28/89 AF/AL 0.0000 I-13B O 08/14/87 AF/AL 0.0000 01/28/89 AF/AL 0.0000 X-13C I 08/14/87 AF/AL 0.0000 01/28/89 AF/AL 0.0000 1

0243C/COC3 1

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ d

p R' TABLE D-2

~

1 *

-(C:ctinuad)

II.: Bellows;(Contiauad)

-)

Penetration Date Tested Leak Rate (SCTH) 1 X-13C 0 ,

'08/14/87 AF/AL- 0.v000 01/28/89 AF/AL 0.0000 l

- X-13D I- 08/06/87 AF/AL .0.0000 01/28/89 AF/AL 0.0000 X-13D 0 08/06/87 AF/AL 0.0000 01/28/89 AF/AL' O.0000 - -

- X-14A- 08/07/87: AF/AL . 0.0000 01/21/89 AF/AL 0.0000-X-14B' 08/06/87 AF/AL 0.00001 01/21/89 AF/AL 0.0000'

! X-14C 08/07/87 AF/AL 0.0000 01/21/89 AF/AL 0.0000

. X-14D 08/06/87 AF/AL 'O.0000

01/21/89 AF/AL 0.0000 ,

- X-15 08/10/87 AF/AL 0.0000 01/21/89 AF/AL 0.0000 X 08/15/87 AF/AL 0.0000 01/21/89 AF/AL 0.0000 X-20A- 08/10/87 AF/AL -0.0000 01/21/89-AF/AL 0.0'000 X-20B 08/15/87 AF/AL 0.0000 01/21/89 AF/AL 0.0000-D X-21 08/10/87-AF/AL 0.0000-01/21/89 AF/AL 0.0000-X-22; 08/10/87 AF/AL .0.0000-01/21/89 AF/AL 0.0000 X 08/10/87 AF/AL 0.0000' 01/21/89 AF/AL 0.0000 X-30 08/15/87LAF/AL' O.0000 01/22/89 AF/AL 0.0000 X-32 08/16/87 AF/AL 0.0000'

, 01/22/89 AF/AL 0.0000--

X-33 08/16/87 AF/AL 0.0000 01/22/89 AF/AL 0.0000 X-45 08/16/87 AF/AL 0.0000-01/22/89 AF/AL 0.0000 X 08/16/87 AF/AL 0.0000-01/22/89 AT/AL 0.0000 X-47A I' 08/17/87 AF/AL 0.0000 01/28/89 AF/AL 0.0000 X-47A O 08/17/87 AF/AL 0.0000 01/28/89 AF/AL 0.0000 X-47B I 08/17/87 AF/AL 0.0000 01/28/89 AF/AL 0.0000 0243C/COC3

r . . TABLE D-2 L (CaStinued)

II. Bellows (Continued)~

Penetration Date Tested Leak Rate-(SCFH)

X-47B O 08/17/87 AF/AL 0.0000 01/28/89 AF/AL 0.0000-X-81 08/15/87 AF/AL 0.0000 01/22/89 AF/AL 0.0000 X-107 08/16/87 AF/AL 0.0008 01/22/89 AF/AL 0.0000 X-108 08/17/87 AF/AL 0.0000 01/28/89 AF/AL 0.0000 X-109- 08/17/87 AF/AL 0.0000 01/28/89 AF/AL 0.0000 III. Electrical Penetration Date Tested Leak Rate (SCFH)

X-120E 07/25/87 AF/AL 0.0000 01/22/89 AF/AL 0.5536 X-121E 07/12/87 AF/AL 0.0000 01/22/89 AF/AL 0.0000 X-122E 07/17/87 AF/AL 0.0000 01/22/89 AF/AL 0.0000 X-123E 07/22/87 AF/AL 0.0000 01/23/89 AF/AL 0.0000 X-124E 07/25/87 AF/AL 0.0000 01/21/89 AF/AL 0.0000 X-126E 07/12/87 AF/AL 0.0000 01/22/89 AF/AL 0.0000 X-127E 07/21/87 AF/AL 0.0000 01/22/89 AF/AL 0.0000 X-128E 07/21/87 AF/AL 0.0000 01/22/89 AF/AL 0.0000 X-129E 07/23/87 AF/AL 0.0013 01/22/89 AF/AL 0.0000 X-131E 07/25/87 AF/AL 0.0006 01/23/89 AF/AL 0.0000 X-132E 07/22/87 AF/AL 0.0000 01/23/89 AF/AL 0.0000 X-133E 07/22/87 AF/AL 0.0206 01/23/89 AT/AL 0.0000 X-134E 07/17/87 AF/AL 0.0000 01/22/89 AF/AL 0.0000 X-135E -

07/17/87 AF/AL 0.0000 01/22/89 AF/AL 0.0000

)

OI43C/COC3

(C:ntitued)

III.- Electrical (Continued)

Penetratista Date Tested- Leak Rate'(SCFH) i r-136E 07/17/87 AF/AL 0.0000 01/22/89.AF/AL 0.0000 X-137E 07/17/87 AF/AL~ 0.0030 01/23/89 AF/AL 0.0000 X-138E .07/17/87 AF/AL 0.0000 01/22/89 AF/AL 0.0000 X-139E 07/12/87 AF/AL 0.0000 -

01/22/89 AF/AL 0.0000 X-140E' 07/17/87 AF/AL 0.0000 01/22/89 AF/AL 0.0000 X-141E 07/22/87 AF/AL 0.0000 01/23/89 AF/AL- 0.0000

- X-142E 07/17/87 AF/AL 0.0000-01/23/89 AF/AL 0.0000 X-143E 07/22/87 AF/AL 0.0000 01/23/89 AF/AL 0.0000 X-144E 07/22/87 AF/AL 0.0000 01/23/89 AF/AL 0.0000 X-145E 07/25/87 AF/AL 0.0008 01/23/89 AF/AL 0.0000 X-146E 07/25/87 AF/AL 0.0019 01/23/89 AF/AL 0.0000-X-147E- 07/12/87 AF/AL 0.0000 01/22/89 AF/AL 0.0000 X-148E 07/12/87 AF/AL 0.0000 01/22/89 AF/AL 0.0000 X-149E 07/12/87 AF/AL 0.0000 01/22/89 AF/AL- 0.0000-X-150E 07/11/87 AF/AL 0.0000 07/12/87'AF/AL 0.0000 01/22/89 AF/AL 0.0000 X-151E 07/11/87 AF/AL 0.0000 07/12/87 AF/AL 0.0000 01/22/89 AF/AL 0.0507 X-152E 07/11/87 AF/AL 0.0000 07/12/87 AF/AL 0.0011 01/22/89 AF/AL 0.0486 X-153E 07/21/87 AF/AL. 0.0000 01/23/89 AF/AL 0.0000 X-154E. 07/21/87 AF/AL 0.0000 01/23/89 AF/AL 0.0000 X-156E 07/21/87'AF/AL 0.0000 01/23/89 AF/AL 0.0000 i

-)

0243C/COC3 l

1 i

m____..___

,. I&EEE._D-2

.catinu2d)

.l III. Electrical (Continued)

Penetration Date Tested Leak Rate (SCFH)

X-157E 07/21/87 AF/AL 0.0000 , j 01/23/89 AF/AL 0.0000 1 i

X-158E 07/21/87 AF/AL 0.0000 01/23/89 AF/AL 0.0000 X-159E' 07/22/87 AF/AL 0.0000 01/23/89 AF/AL .0.0000 f

' ~

Z-160E 07/22/87 AF/AL 0.0000'

.01/23/89 AF/AL 0.0000 X-161E 07/22/87 AF/AL 0.0000 01/23/89 AF/AL 0.0000 X-163E 07/22/87 AF/AL 0.0112 01/23/89 AF/AL 0.3760 X-164E 07/22/87 AF/AL 0.0000 01/23/89 AF/AL 0,0000 X-165E 07/21/87 AF/AL 0.0102 01/23/89 AF/AL 0.0000 X-166E 07/21/87 AF/AL 0.0000 01/23/89 AF/AL 0.0000 X-167E 07/23/87 AF/AL 0.0000 01/22/89 AF/AL 0.0000

-X-168E 07/23/S7 AF/AL 0.0000 01/22/89 AF/AL 0.0000 X-169E 07/23/87 AF/AL 0.0000 01/22/89 AF/AL 0.0000 X-170E 07/23/87 AF/AL 0.0000 01/22/89 AF/AL 0.0000 IV. Hg Annivrers Penetration Date Tested Leak Rate (SCFH)

H2 Train A 08/28/87 AF 0.4583 H2 Train A 10/29/87 AF 0.2807 H2 Train B 10/29/87 AF/AL 0.0000 H2 Train A 11/15/87 AL 0.0000 H2 Train B 01/18/88 AF/AL 0.0000 H2 Train A 01/18/88 AF/AL 0.0000

, H2 Train A 02/22/88 AF 2.1112 H2 Train B 02/22/88 AF 0.0000 H2 Train A 02/26/88 AL 0.0000 H2 Train B '

02/26/88 AL 0.0000 H2 Train A 03/16/89 AF 4.4812 H2 Train B 03/16/89 AF 1.7777 H2 Train A 03/22/89 AL 0.0000 H2 Train A 03/22/89 AL 0.0000 l

l i

0243C/COC3 l

l

.1

TABLE D-2 -

(C:ntinu d) *

.V. Pressure Differential Tr3nsmitters Penetration Date Testgi Leak Rate (SCFH)

'PDT-30-42 02/03/86 AF/AL 0.0000 PDT-30-43 02/03/86 AF/AL 0.0000-

'PDT-30-44 02/03/86 AF/AL 0.0000 PDT-30-45 02/03/86 AF/AL 0.0000 PDT-30-43 02/19/86 AF/AL 0.0000 PS-30-46A 10/18/87'AF/AL 1.0000 '

PS-30-46B 10/18/87-AF/AL 0.0000 PS-30-47A 10/18/87 AF/AL, 0.0000-PS-30-47B 10/18/87'AF/AL 0.0000 ;

PS-30-48A- 10/18/87 AF/AL 0.0000 j PS-30-48B- 10/18/87 AF/AL. 0.0000 i

PT-30-30C 10/18/87 AF/AL 0;0000 PT-30-310 10/18/87 AF/AL 0.0000 PT-30-311 10/18/87 AF/AL 0.0000 :

PDT-30-42 .11/05/87 AF/AL 0.0000 j

.PDT-30-43 11/05/87 AF/AL 0.0000 l PDT-30-44 11/05/87 AF/AL 0.0000 j PDT-30-45 11/05/87 AF/AL 0.0000 1 PS-30-46A 03/15/89 AF/AL 0.0000 I PS-30-46B 03/15/89 AF/AL 0.0000 PS-30-47A 03/15/89 AF/AL 0.0000 PS-30-47B 03/15/89 AF/AL 0.0000 i PS-30-4BA. 03/15/89 AF/AL 0.0000 {

PS-30-48B 0A/15/89 AF/AL 0.0000 1 PDT-30-30C 'J3/15/89 AF/AL 0.0000 PT-30-310 03/15/89 AF/AL 0.0000 PT ~40-311 03/15/89 AF/AL 0.0000 PDT-30-42 03/15/89 AF/AL 0.0000 PDT-30-43 03/15/89 AF/AL. 0.0000 PDT-30-44 03/15/89 AF/AL 0.0000 PDT-30-45 03/15/89 AF/AL 0.0000 VI. Resilient Seals Penetration Date Tested Leak Rate (SCFH)

X-1 10/30/87 AF/AL 0.0000 04/08/88 AF 0.0000 05/02/88 AL 0.0000 01/19/89 AF 0.0000 03/16/89 AF 0.0000 0.0000 03/24/89 AL 024'3C/COC3

N v )

TABLE D-2 (Ccntinuid)

.VI. Resilient Seals (Continued)

Penetration Date Tested Leak Rate (SCFH)

X-3 10/01/87 AF/AL 0.0008 01/22/89 AF 0.0000 03/12/89 AL 0.0000 X-40D 07/27/87 AF/AL 0.0000 01/21/89 AF/AL 0.0000 X-54 07/27/87 AF/AL 0.0000 ~ ~

04/08/88-AF 0.0000 04/26/88 AL 0.0000 01/19/89 AF 0.0000

'03/23/89 AL -

0.0000 X-79A 10/14/87 AF 2.4536-10/16/87 AL 0.0015' 01/21/89 AF 0.0000 03/12/89 AL 0.0000 X-79B 10/14/87 AF/AL 0.0000 01/21/89 AF 0.0000 03/12/89 AL 0.0000 X-111 07/26/87 AF/AL 0.0672 01/30/89 AF/AL 0.0000 X-112 07/26/87 AF/AL 0.0000 01/30/89 AF/AL 0.0000 X-113 07/26/87 AF/AL 0.0000 01/30/89 AF/AL 0.0000 X-88 07/27/87 AF/AL 0.0000 01/21/89 AF/AL 0.0000 X-117 07/26/87 AF/AL 0.0000 01/21/89 AF/AL 0.0000 X-118 07/27/87 AF/AL 0.0000 01/22/89 AF/AL 0.0000 03/23/89 AF/AL 0.0000 l

l 0243C/COC3

E- ,

M f TABLE D-3 h-;

1.

1- Tvoe B and C Tests Cvele 3 - Unit 2

. Path Leakage Tabulation'.

l Summarv-As Found As Left A. Type B Leakage

' ~

I. Penetrations 0.1331 SCFH 1.2089 SCFH

'I. Air Lock Doors 1.5779 SCFH 2.6061 SCFB-A. Type.C Leakage 5.5099 SCFH 1.6987 SCFH 0243C/COC3 l

1 j

., APPENDIX E I'

References

1. 10 CFR 50, Appendix J. " Reactor Containment Leakage Testing for Water-

-Cooled Power Reactors"

2. ANSI N45.4-1972, American National Standard,' " Leakage Rate Testing of Containment Structures of Nuclear Service"

3. ANS 56.8, American Nuclear Society, " Containment System Leakage Testing Requirements"

~ ~

4. Sequoyah Nuclear Plant FSAR Chapters 6.2 and 6.3

5. Sequoyah Nuclear Plant Technical Specification 4.6.1.2

6. Bechtel Topical Report, " Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants" -

BN-TOP-1, Revision 1

)

l 0243C/COC3 1

ML20245B363

Text

SUMMARY

2.0 INTRODUCTION

SUMMARY

8.0 CONCLUSION

SUMMARY

SUMMARY

.

SUMMARY

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