ML20005E235

Reactor Containment Bldg Integrated Leak Rate Test,Point Beach Nuclear Plant Unit 2, Summary Rept

ML20005E235
Person / Time
Site:	Point Beach
Issue date:	12/31/1989
From:	WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20005E231	List: ML20005E230 ML20005E235
References
NUDOCS 9001040139
Download: ML20005E235 (19)

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SUMMARY

! REPORT-4 ' REACTOR CO'NTAINMENT; BUILDING INTEGRATED: LEAK RATE TEST Nf"l p 4

POINTLBEACH NUCLEAR PLANT UNIT.2, 1989-

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. TABLE.OF-CONTENTS'

,  ; 4 11.0L GenerallData: 1 2.O. Technical Data 11 --

Ib 3. 0.- . Test 3 Data - l' 4.0 ; Analysis;andLInterpretation. -2 i-I 5.01. Type-:C Leakage Corrections -3 p ,

I, s.. '6'. 0. ' Type-:B Tests ; Performed Between Ref uelings - 4 1

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7. 01 LType' C.. Tests; Performed Between Refuelings- 4 L 8. 0 i Type 7B.-and C-Test Summary. 4-9.0 Comments on Valves with Excessive Leakage ,

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, REPORT OF REACTOR CONTAINMENT BUILDING INTEGRATED

,' LEAKAGE RATE TEST FOR POINT BEACH UNIT 2 1.0 GENERAL DATA (

-1.1 Owner - Wisconsin Electric Power Company 1.2 Docket Number 301

' 1. 3 Location - Two Rivers, Wisconsin 1.4 Containment Description - 3 foot pre-stressed post-tensioned concrete cylinder with inch welded ASTM A-442 steel' liner

1. 5 Date Test Was Completed - September 29, 1989 -

2.0- TECHNICAL DATA 2.1 Containment Net Free Volume - 1,000,000 cubic feet 2.2 Design Pressure - 60 psig i 2.3 Design Temperature - 286 F 2.4 Calculated Accident Peak Pressure (Pac) - 53 psig  :

2.5 Calculated Accident Peak Temperature (Tac) - 278 F

3. 0 TEST DATA-3.1- Test Method - Absolute-3.2 Data Analysis Technique - Total Time  :

3.3 Test Pressure 30.7 ps,ig 3.4 Maximum Allowable Leak Rate, L, - 0.400%/ Day 3.5 Reduced-Pressure Allowable Leak Rate, Lt - 0.268V Day f

3. 6 Allowable Operational Leak Rate, .75 L t- 0.201%/ Day 3.7 Integrated Leakage Rate Test-Results i Total Time Leak Rate 0.064%/ Day  !

95% Upper Confidence Level 0.115%/ Day 3.8 Verification Test Results 3.8.1 Imposed Verification Leak Rate 0.265%/ Day (5.66 scfm) 3.8.2 Total Time Analysis 0.299%/ Day 3.8.3 Verification Test Limits Lower Limit 0.262%/ Day Upper Limit 0.396%/ Day

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3.9 Penalties-

, Containment Volume Changes 0.0000%/ Day Penetrations Not Aligned 0.0003%/ Day.

Air. Additions 0.0006%/ Day Total' O.001%/ Day 3.10 >As-found Leak Rate 0.116%/ Day

~ Corrected for penalties at 95%

upper confidence livel 4.0. ANALYSIS AND INTERPRETATION 1

The fifth periodic-Type A integrated leakage rate test (ILRT) of the j Point Beach Nuclear Plant Unit 2' containment was performed September i 28 to September 29, 1989 with satisfactory results. The testing program was conducted in accordance with the requirements of the Point Beach Technical Specifications, Section 15.4,4, " Containment Tests."

During the ILRT, the ten penetrations listed in Section 5.0 of this report were not in a post-LOCA alignment. This requires us to add the results of their local leak rate tests to our ILRT result. The addition to the ILRT result for these local leak rate tests is 0.0003%/ day.

The pressurizer, safety injection accumulators, reactor coolant drain tank,. pressurizer relief tank and containment sump A were all vented

toLthe containment during the ILRT. Water level changes in these

' tanks resulted in an increase in the containment net free volume of 18.819.9 cubic feet during the test. The correction to the ILRT  ;

result for this volume change is 0.0000%/ day. i Air additions to the containment from accumulators for the inner purge supply and purge exhaust valve seals were 0.058 lbm/ hour. The correction to the ILRT result for this air addition is 0.0006%/ day.

i The total leakage rate correction for penetrations not in post-LOCA  ;

alignment, water volume changes and air additions is 0.001%/ day.

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The calculated leakage rate during the ILRT was 0.064%/ day (total time). The relculated 95% upper confidence level was 0.115%/ day

-(total time). Adding the total leakage rate corrections for

, penetrations not in post-LOCA alignment, containment water level changes and air additions, yields the corrected leakage rates as follows:

1. Total Time Leakage Rates, %/ day L Leakage Rate UCL I Calculated 0.064 0.115 Corrections 0.001 0.001 l- As-Found 0.065 0.116 Since the corrected 95% upper confidence level for total time is less than 0.75L, (0.201%/ day), the test results demonstrate the leakage through the primarf containment and systems and components penetrating primary i

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i 1989 Unit 2 ILRT

, ;. .. Page 3 containment does not exceed the allowable leakage rates specified in the Point Beach Nuclear Plant Unit 2 FSAR and Technical Specifications.

L 5. 0 TYPE C LEAKAGE CORRECTIONS

( Due to the test configuration of the containment, ten penetrations were not subjected to the Type A test pressure. These penetrations, justification, and as-found Type C test results are identified below:

L I Type C Results Penetration Justification (Minimum Pathway)

L CVCS Supply Line In use for reactor coolant 51 scem

(#26) system purification CVCS Letdown Line In use for reactor coolant 0 scem

(#10) system purification RCP "A" Seal Injection Maintain flow of clean 34 sccm Line (#29A) water through RCP seals RCP "B" Seal Injection Maintain flow of clean 5 seem Line (#298) water through RCP seals Service Air Line Modified to allow for 1 scem

(#33C) containment depressurization l Containment Pressure Modified to provide a 1 secm Sensing Line (#31A) pressure sensing point for Type A test purposes Auxiliary Charging Proper venting of-line is I sccm Line (#32C) not possible when seal ,

injectionlinesareinuse  !

PACVS Supply Line Modified to provide a flow 18 scem

(#310) verification patch Sump A Drain Line was not vented in order 25 seem

(#71) to maintain the ability to pump Sump A during the ILRT RCDT Pump Suction Line was not vented in order to 3 seem i

(#9) maintain the ability to pump the RCDT Penetrations 31A, 310 and 33C were modified as part of the Type A test line-up. Type C leakage tests were performed on these penetrations prior to modification to ensure an as-found condition. The remainder, which were not disturbed by the line-up, were tested in the as-found condition following the Type A test. All values are 12 secm.

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'y 1989 Unit 2 ILRT 4

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6.0 TYPE B TESTS PERFORMED BETWEEN REFUELINGS' Procedure Component Date Leak Rate TS-10 Lower Personnel Hatch 5/1/87 578 seem TS-10 Upper Personnel Hatch 5/1/87 1787 seem TS-35 Purge Exhaust (VI) 5/15/87 0 sccm i

TS-35 Purge Supply (V2) 5/15/87 12000 seem Upper Personnel Hatch TS-10 5/3/88 138 seem TS-10 Lower Personnel Hatch 5/4/88 39 seem

• TS-36 Purge Exhaust (VI) 5/27/88' 3 seem

• TS-36 Purge Supply (V2)- 5/27/88 991 seem ORT-71 Electrical Penetration E58 1/12/89 5 seem (Pre-maintenance)

ORT-71 Electrical Penetration E58 1/12/89 1 seem (Post maintenance)

TS-10 Lower Personnel Hatch 5/2/89 1660 seem TS-10 Upper Personnel Hatch 5/2/89 591 seem TS-36 Purge Exhaust (VI) 5/19/89 34 seem TS-36 Purge Supply (V2) 5/19/89 1940 seem

• TS-36, a Unit 2 specific procedure was implemented in late 1987 to test VI and V2. TS-35 is still used for Point Beach Unit 1.

7.0 TYPE C TESTS PERFORMED BETWEEN REFUELINGS Procedure Penetration Date Valve (s) Tested Leak Rate

• 0RT-25 9 4/6/88 2-1698 80 seem

• 0RT-25 9 4/7/88 2-1698- 135 sccm

• 0RT-25 was modified to perform a pre- and post-maintenance test on valve ,

2-1698 only.

8.0 TYPE B AND C TEST

SUMMARY

The following tables are the as-found and as-left leakage rates for r the Type 8 and C tests conducted between.the 1986 and 1989 ILRT's.  !

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1989 Unit 2 ILRT --

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ne REFUELING CONTAINMENT PENETRATION ~

LEAKAGE RECORD Unit # 2 Refueling U2R12 Refueling UZR13 Date 1986-1987 TYPE B TESTS Sept to Nov 1986 Oct to Nov 1987 AS-FOUND LEAKAGE AS-FOUND LEAKAGE LEAKAGE AFTER LEAKAGE AFTER ORT scca REPAIR scca REPAIR NO. PENETRATION TITLE scca sccm 12 No Number Fuel Transfer Tube Flange 65 N/A 81 N/A 13 No Number Equipment Hatch Flange 20 . M/A S N/A 71 E58 Electrical Penetration 1 N/A 42 N/A 72 E20, 22 Electrical Penetration 10 -N/A 46 N/A 73 El Electrical Penetration 4 N/A S 1 75 P-50, 51 Mechanical Penetration Test 898 N/A 788 . M/A P-52 & 53 76 P-58 Mechanical Penetration Test 1 N/A 6 NJA 77 P-57 Mechanical Penetration Test 2 N/A 8 N/A 78 P-69, 70 MPT (Sump "A" & "B" Drain Lines) 4 N/A 219 N/A

& 71 79 No Number MPT (Fuel Transfer Tube Penetration) 11 N/A 9 N/A 80 P-13, 27 Mechanical Penetration Test 1 N/A 2 N/A

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REFUELING CONTAIMMENT PENETRATION LEAKAGE RECORD Unit # 2 RefueIing U2R12 Refue1ing U2R13.

Date 1986-1987 . TYPE B TESTS Sept to Nov 1986 Oct to Nov 1967 AS-FOUND LEAKAGE AS-FOUND LEAKAGE LEAKAGE AFTER LEAKAGE AFTER ORT scca REPAIR sccm' REPAIR NO. PENETRATION TITLE sccm seca 81 P-3/, 38 P-36, 40 Mechanical Penetration Test 14 N/A 36 N/A P-48, 45 P-44, 46 82 P-5 & 6 P-47, 43 Mechanical Penetration Test 34 N/A 16 N/A P-39, 35 P-55, 54 83 P-15, 16 17, 18 Mechanical Penetration Test 12 N/A 5 N/A 10, 11 84 P-7, 3, Mechanical Penetratien Test 76 N/A 27 N/A 9 & 22

TS-10 Upper Personnel Hatch 1787 N/A 225 N/A IS-10 Lower Personnel Hatch 578 N/A 5510 N/A 15-36 V-1 Purge Exhaust 132 88 131 508 IS-36 V-2 Purge Supply 365 49 %1 197 END OF TYPE B IESTS "l

1989 Unit-2 ILRT. ~'

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REFUELING CONTAINMENT PENETRATION J^

LEAKAGE RECORD Unit # 2 Refueling U2R12 Refueling U2R13 D:.ta 1986-1987 TYPE C TESTS Sept to Nov 1986 Oct.to Nov 1987 AS-FOUND LEAKAGE. AS-FOUND LEAKAGE LEAKAGE AFTER LEAKAGE AFTER ORT scca REPAIR scca REPAIR NO. PENETRATION TITLE sccm sccm 25 9 RCDI Pump Suction Line 5 N/A 16 N/A (Enter highest test) 26 10 Letdown Line 283 N/A 32 N/A (Enter highest test) 27 11 RCP Seal Water Return Line 254 -N/A 138 M/A

((Enter highest test) 28 12A DI Water Line 7 17 0 N/A 30 12C RCDI and PRI Vent (Note 1) 7250 316 20 12 (Add tests together) 31 14A Nitrogen Supply to PRI 299 N/A 22 N/A 32 14C Nitrogen Supply to the Accumulator 635 N/A 488 N/A 33 42 PACVS Return Line 1 N/A 0 N/A 34 26 Charging Line Check Valve 2 169 189 N/A 35 28A Hot Leg Sample 51 3 48 N/A 36 288 Pressurizer Liquid Space Sample 2720 35 69 N/A

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37 28C Pressurizer Steam Space Sample 16 18 140 N/A 1

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REFUELING CONTAINMENT PENETRATION '

LEAKAGE RECORD Unit #~ 2 Refueling U2R12 Refueling U2R13 D:ta .1986-1987 TYPE C TESTS Sept to Nov 1986 Oct to Nov 1987' AS-FOUND LEAKAGE AS-FOUND LEAKAGE LEAKAGE AFTER LEAKAGE AFTER ORT scca REPAIR 'scca REPAIR NO. PENETRATION TITLE sccm sccm 39 29A Seal Injection Supply RCP "A" 6 N/A 22 N/A 40 29B Seal Injection Supply RCP "B" 1 N/A 21 N/A 42 30C Reactor Makeup Water Supply 5- 4 16 N/A (Enter highest test) 43 31B Containment Sample Line 11 N/A 0 N/A (Enter highest test) 44 31C PACVS Vent Line O N/A 0 N/A (Enter highest test) 46 -

32C Auxiliary Charging Line 1467 N/A 85 N/A 47 33A Instrument Air Supply 3047 5 N/A 365 N/A (Enter highest test) 48 33B Instrument Air Supply 3048 78 N/A 60 N/A (Enter highest test) 49 33C Service Air Supply 145000 1 12 75.

50 34A Sample Line PRI to Gas Analyzer 4 N/A 3 N/A (Add tests together) 51 34C "A" SG Sample Line 29 N/A 31 N/A

1989 Unit 2 ILRT  :-

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REFUELING CONTAINNENT-PENETRATION  ;

LEAKAGE RECORD Unit # 2 Refue1ing U2R12 Refue1ing U2R13 D:te 1986-1987 TYPE C TESTS Sept to Nov 1986 Oct to Nov 1987 AS-FOUND LEAKAGE AS-FOUND LEAKAGE LEAKAGE AFTER LEAKAGE AFTER ORT scca REPAIR ~scca REPAIR NO. PENETRATION TITLE sccm scca

~52 34B "B" SG Sample Line 29 N/A 15 N/A 53 34D Sample Line RCDI to Gas Analyzer 5 .N/A 4 N/A (Enter highest test) 54 50 "B" SG Blowdown 705: N/A 24 N/A SS 51 "A" SG Blowdown 317 N/A 84 N/A 56 S2 Heating Steam Supply 683 N/A 218 N/A 57 53 Condensate Return from Containment 15430 1135 0 116 58 56 Containment Iest Connection 43 N/A 0 N/A 59 54 P14A Spray Pump Discharge Check 4000 112 753 N/A Valve 60 SS P148 Spray Pump Discharge Check 879 1220 2039 67 Valve 61 71 Sump "A" Drain to Auxiliary 8 N/A 33 N/A Building 64 X1 R11/R12 Suction Supply 184 N/A 185 N/A (Enter highest test)

1989' Unit 2 ILRT' *:

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REFUELING CONTAINMENT PENETRATION '

LEAKAGE RECORD Unit # 2 Refueling U2R12 Refueling U2R13 Date 1986-1987 TYPE C TESTS Sept to Nov 1986 Oct to Nov 1987 AS-FOUND LEAKAGE- AS-FOUND LEAKAGE LEAKAGE AFTER LEAKAGE AFTER ORT scca REPAIR scca. REPAIR NO. PENETRATION TITLE sccm sccm 65 X2 R11/R12 Discharge Return 323 N/A 253 N/A (Enter highest test) 66A 31A Pressure Test of PT-945 and 946 17 N/A 0 N/A 668 14B Pressure Test of PT-947 and 948 7 N/A 0 N/A 66C 32A Pressure Test of PI-949, 950 and %9 -3 N/A 0 N/A 67 19 & 20 CCW to and from Excess Letdown HEX (Note 2) 860 4006 87 (Add tests together) 68 15 & 17 CCW to and from "A" RCP (Note 2) 498 31/2 192 (Add tests together) 69 16 & 18 CCW to and from "B" RCP 13225 1383 11868 520 (Add tests together)

END OF TYPE C TESTS

1989 Unit'2'ILRT.

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REFUELING CONTAINMENT PENETRATION [~

LEAKAGE RECORD' Unit # 2 Refueling U2R14 Date 1988 TYPE B TESTS Oct to Nov 1988 AS-FOUND LEAKAGE LEAKAGE AFTER ORT scca - REPAIR NO. PENETRATION TITLE sccm 12 No Number Fuel Transfer Tube Flange 101 N/A 13 No Number Equipment Hatch Flange 60 N/A 71 ES8 Electrical Penetration 2 N/A 1

72 E20, 22 Electrical Penetration 4 N/A 73 El Electrical Penetration 1 M/A 75 P-SO, 51 Mechanical Penetration Test- 310 N/A P-52 & 53 76 P-58 Mechanical Penetration Test 1 N/A 77 P-57 Mechanical Penetration Test 4 N/A 78 P-69 & 70 MPT (Sump "A" & "B" Drain Lines) 8 N/A 79 No Number MPI (Fuel Transfer Tube Penetration) 0 N/A 80 P-13, 27 Mechanical Penetration Test 4 N/A

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REFUELING CONTAINMENT. PENETRATION .l' LEAKAGE RECORD Unit # 2 Refueling 02R14 ~

Dste 1988 TYPE B TESTS Oct to Nov 1988

.AS-FOUND LEAKAGE LEAKAGE AFTER ORT scca REPAIR-NO. PENETRATION TITLE sccm 81 P-37, 38 ~

P-36, 40- Mechanical Penetration Test 27 N/A P-48, 45 P-44, 46 82 P-5 & 6 P-47, 43 Mechanical Penetration Test 29 N/A P-39, 35 P-55, 54 83 P-15, 16 17, 18 Mechanical Penetration Test '

23 N/A 10, 11 84 P-7, 8, Mechanical Penetration Test 12 N/A-9 & 22 IS-10 Upper Personnal Hatch 3450 N/A IS-10 Lower Personnel Hatch 2450 N/A TS-36 V-1 Purge Exhaust 155 5/1 TS-36 V-2 Purge Supply 364 494 END OF TYPE B TESTS

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1989 Unit 2 ILRT. - -

Page 13 [~'3 REFUELING CONTAINMENT.PEMETRATION  ;

LEAKAGE RECORD' Unit # 2 Refueling U2R14 Date 1988 TYPE C TESTS Oct to Nov 1988' AS-FOUND LEAKAGE

-LEAKAGE AFTER ORT scca REPAIR NO. PENETRATION TITLE sccm 25 9 RCDT Pump Suction Line 3 N/A (Enter highest test)

! 26 10 Letdown Line 94 N/A (Enter highest test) 27 11 RCP Seal Water Return Line 120 N/A

((Enter highest test)

J 28 12A DI Water Line O N/A 30 12C RCDI and PRI Vent. 1 N/A (Add tests together) 31 14A Nitrogen Supply to PRI 14 N/A 32 14C Nitrogen Supply to the Accumulator 480 33 42 PACVS Return Line O N/A 34 26 Charging Line Check Valve 523 N/A 35 28A Hot Leg Sample 135 N/A 36 288 Pressurizer Liquid Space Sample 4630 1 37 28C Pressurizer Steam Space Sample 68 N/A

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. ,1 REFUELING CONTAINMENT PENETRATION .

LEAKAGE RECORD Unit # 2 .

Refueling U2R14 D:te 1988 TYPE C TESTS Oct to Nov 1988-AS-FOUND LEAKAGE LEAKAGE AFTER ORT scca REPAIR NO. PENETRATION TITLE- sccm 39 29A Seal Injection Supply RCP "A" 123 N/A 40 29B Seal Injection Supply RCP "B" 1 N/A-47 30C Reactor Makeup Water Supply 1. M/A (Enter highest test) 43 318 Containment Sample Line 3 N/A (Enter highest test) 44 31C PACVS Vent Line 20 13 (Enter highest-test) 46 32C Auxiliary Charging Line 2- N/A 47 33A Instrument Air Supply 3647 365 1001 (Enter highest test) 48 33B Instrument Air Supply 304B 98 492 (Enter highest test) 49 33C Service Air Supply 1 32.

50 34A Sample Line PRT to Gas Analyzer 2 N/A (Add tests together) 51 34C "A" SG Sample Line 67 N/A

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1989 Unit 2 ILRT ..

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REFUELING CONTAINNENT PENETRATION LEAKAGE RECORD

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, Unit # 2 Refueling U2R14 Date 1988- TYPE C TESTS Oct to Nov 1988 AS-FOUNO LEAKAGE LEAKAGE' AFTER ORT sccm REPAIR NO. PENETRATION TITLE scca 52 348 "B" SG Saiaple Line 14 N/A S3 340 Sample Line RCDT to Gas Analyzer ..., 2 N/A (Enter highest test) 54 50 "B" SG Blowdown 1085 N/A 55 51 "A" SG Blowdown 89 N/A 56 52 Heating Steam Supply 82 N/A i 57 S3 Condensate Return from Cont.ainment 3270 432 58 56 Containment Test Connection 84 N/A 59 54 P14A Spray Pump Discharge Check 155 20 Valve 60 55 P148 Spray Pump Discharge Check 90 0 Valve 61 71 Sump "A" Drain to Auxiliary 4 N/A Building 64 X1 R11/R12 Suction Supply 202 N/A (Enter higtest test)

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REFUELING CONTAINMENT PENETRATION LEAKAGE RECORD Unit # 2 Refueling U2R14 09te 1988 TYPE C TESTS Oct to flov 1988 AS-FOUND LEAFAGE LEAKAGE AFTER ORT sccm REPAIR NO. PENETRATION TITLE scca 65 X2 R11/R12 Discharge Return 317 N/A (Enter highest test) 66A 31A Pressure Test of PT-945 and 946 0 N/A 66B 14B Pressure Test of PT-947 and 948 0 N/A 66C 32A Pressure Test of .PT-949, 950 and %9 0 N/A 67 19 & 20 CCW to and from Excess Letdown HEX 225 N/A.

(Add tests together) 68 15 & 17 CCW to and from "A" RCP 99 376 (Add tests together) 69 16 & 18 CCW to and from "B" RCP 3894 81 (Add tests together)

END OF TYPE C TESTS

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'.. 1989 Unit 2 ILRT-l

. . P.ge 17 Notes for Type B and C Test Summary Tables f

1. . Modification 87-143, completed October 1987, cut and capped the -

nitrogen supply to the Reactor Coolant Drain Tank (RCDT). The .

., . isolation valve in this line, check valve 2-1713, had a poor leakage  !

test history and other means were available to supply nitrogen to the

.RCDT, so a section of the line was removed and caps were welded in its  ;

., place.

2. Valve leak rate was not determined. The test volume could not be ,

pressurized due to excessive leakage. '

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i 9.0 COMMENTS ON VALVES WITH LEAKAGE APPROACHING OR EXCEEDING t 0.6La AT STANDARD TEMPERATURE AND PRESSURE

! ORT 49 (1986)

Check valve, SA-20, service air supply to Unit 2 containment, was discovered leaking at 145,000 secm. Investigation revealed that the clapper arm bracket was out of alignment preventing the disc from seating properly. The clapper was adjusted and shimmed to allow proper closing. The bracket was pinned to hold the clapper in the proper position. Post-repair leakage was 1 scem. This item was not reportable.

ORT 67 (1986)

Check valve, 2-767, excess letdown heat exchanger supply, would not seat properly during the initial Type C test. The required test pressure could not be achieved which precluded quantification of the leakage rate. The valve was disassembled and the disk 0-ring and spring were replaced. Post-repair leakage was 2 secm. (Licensee Event Report No. 86-005-01, 2/9/87)

ORT 68 (1986)

Check valve, 2-755A, "A" RCP component cooling water supply would not seat properly during the initial Type C test. The required test pressure could not be achieved which precluded quantification of the leakage rate. An investigation revealed that the valve disc did not contact the valve seat evenly due to wear which had caused excessive clearance in the disc-to-hanger arm joint. The valve was replaced and the post-repair leakage was 30 secm. (Licensee Event Report Nos.

86-005-00, 10/31/86 and 86-005-01, 2/9/87) l l

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