ML20045D652
| ML20045D652 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 12/31/1993 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20045D647 | List: |
| References | |
| NUDOCS 9306290263 | |
| Download: ML20045D652 (26) | |
Text
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SUMMARY
REPORT REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST POINT BEACH NUCLEAR PLANT UNIT 1, 1993 TABLE OF CONTENTS 1.0 General Data 1 2.0 Technical Data 1 3.0 Test Data 1 4.0 Analysis and Interpretation 2 5.0 Type C Leakage Corrections 3 6.0 Type B Tests Performed Between Refuelings 4 i 7.0 Type C Tests Performed Between Refuelings 4 8.0 Type B and C Test Summary 5
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9.0 Comments on Valves with Excessive Leakage 12 9306290263 930618 ?I PDR ADOCK 05000266 R P PDR 8
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I REPORT OF REACTOR CONTAINMENT BUILDING INTEGRATED LEAKAGE RATE TEST FOR POINT BEACH UNIT 1 l
1 1.0 GENERAL DATA 1.1 Owner - Wisconsin Electric Power Company ,
1.2 Docket Number 266 !
1 1.3 Location - Two Rivers, Wisconsin l 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 - April 1, 1993 2.0 TECHNICAL DATA l l
2.1 Containment Net Free Volume - 1,000,000 cubic feet i 2.2 Design Pressure - 60 psig 2.3 Design Temperature - 286 F 1 1
2.4 Calculated Accident Peak Pressure (Pac) - 53 psig l 2.5 Calculated Accident Peak Temperature (Tac) - 278'F 3.0 TEST DATA Test Method - Absolute ata Analysis Technique - Total Time 3.3 Test Pressure - 31 psig .
1 3.4 Maximum Allowable Leakage Rate, L a- 0.400%/ Day 3.5 Reduced Pressure Allowable Leak Rate, Lt - 0.283%/ Day 3.6 Allowable Operational Leak Rate, .75 Lt -
0.212%/ Day 3.7 Integrated Leakage Rate Test Results 3.7.1 Total Time Leak Rate 0.753%/ Day 3.7.2 95% Upper Confidence Level 0.085%/ Day 1
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3.8 Verification Test Results l 3.8.1 Imposed Verification Leak Rate 0.268%/ Day 3.8.2 Total Time Analysis 0.297%/ Day 3.8.3 Verification Test Limits Lower Limit 0.250%/ Day Upper Limit 0.392%/ Day I 3.9 Penalties Containment Net Volume Changes 0.0060%/ Day Penetrations Not 'iligned 0.0002%/ Day Pressurized Component Additions 0.0025%/ Day Total 0.009%/ Day 3.10 As-Found Leak Rate 0.094%/ Day Corr 3cted for penalties at 95%
upper confidence level 4.0 ANALYSIS AND INTERPRETATION The seventh periodic Type A integrated leakage rate test (ILRT) of the Point Beach Nuclear Plant Unit 1 containment was l performed March 31 to April-1, 1993, 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" and procedure ORT-17,
" Containment Integrated Leak Rate Test."
Fourteen penetrations, listed in section 5.0 of this report, were not in a post-LOCA alignment during the ILRT. This required additions, based on minimum pathway leakage analysis, to the ILRT result of 0.0002%/ Day.
The pressurizer, reactor coolant drain tank, pressurizer relief tank, and containment sump A were all vented to the containment during the ILRT. Water level changes in these tanks resulted in a decrease in the containment net free volume of 2.6 i 12.12 cubic feet during the test. The correction to the ILRT result for this net volume change is 0.006%/ Day.
The accumulators for the inner purge supply and purge exhaust valve seals, and the safety injection accumulators, were ,
sources for pressurized component additions to the containment I during the ILRT. The total pressurized component additions to the containment were 0.24 lbm/ hour. The correction to hhe ILRT result for this air addition is 0.0025%/ Day.
The total leakage rate correction for penetrations not in post-LOCA alignment, net volume changes, and pressurized 2 !
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component additions is 0.009%/ Day.
The calculated leakage rate during the ILRT was 0.053%/ Day (total time). The calculated 95% upper confidence level was 0.085%/ Day (total time). Adding the total leakage rate l corrections for penetrations not in a post-LOCA alignment, i containment net volume changes, and pressurized component !
additions, yields the corrected leakage rates as.follows:
Total Time Leakage Rate, %/ Day Leakaae Rate UCL Calculated 0.053 0.085 l Corrections- 0.009 0.009
- As-Found/As-Left 0.062 0.094 l
No valve repairs were performed prior to the ILRT. Therefore, the as-found test is equivalent to the as-left test. Since the corrected 95% upper confidence level for the total time is l less than 0.75L e (0.212%/ Day), the test results demonstrated the leakage through the primary containment and systems and components penetrating primary containment does not exceed the allowable leakage rates specified in the Point Beach Nuclear Plant FSAR and Technical Specifications.
5.0 TYPE C LEAKAGE CORRECTIONS Due to the test configuration of the containment, fourteen penetrations were not subjected to the Type A test pressure. ;
These penetrations, justification, and as-found/as-left Type C test results are identified below:
Type C Results Eenetration Justification (Minimum Pathwavi I
CVCS Supply Line In use for reactor coolant 2 sccm
(#26) system purification CVCS Letdown Line In use for reactor coolant 20 sccm
(#10) system purification ]
RCP "A" Seal Injection Maintain flow of clean 1 sccm Line (#29A) water through RCP seals RCP "B" Seal Injection Maintain flow of clean 1 sccm Line (#29B) water through RCP seals Auxiliary Charging Proper venting of line is 1 sccm Line (#32C) not possible when seal injection lines are in use 3
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PACVS Supply Line Valve line-up modified to O sccm
(#31C) provide a flow verification path Sump A Drain Line was not vented in order 2 sccm
(#71) to maintain the ability to pump Sump A during the ILRT RCDT Pump Suction Line was not vented in order 3 sccm
(#9) to maintain the ability to pump the RCDT Excess Letdown HX Line was not vented during 55 scem
(#19,20) ILRT A RCP CCW Line was not vented during 0 sccm
(#15,17) ILRT B RCP CCW Line was not vented during 1 sccm
(#16,18) ILRT The fourteen penetrations not subjected to Type A test pressure were tested in the as-found condition following the Type A test at reduced pressure. All values are i2 sccm.
6.0 TYPE B TESTS PERFORMED BETWEEN REFUELINGS Procedure Component Date Leak Rate TS-10U Upper Personnel Hatch 11/11/90 1812 sccm TS-10L Lower Personnel Hatch 11/11/90 1604 sccm TS-35E Purge Exhaust 11/22/90 644 sccm TS-35S Purge Supply _ 11/22/90 7 sccm TS-10U Upper Personnel Hatch 11/21/91 1257 sccm TS-10L Lower Personnel Hatch 11/21/91 2040 sccm TS-35E Purge Exhaust 11/23/91 8 sccm TS-35S Purge Supply- 11/23/91 4 sccm TS-10U Upper Personnel Hatch 11/11/92 285 sccm TS-10L Lower Personnel Hatch 11/12/92 510 sccm TS-35E Purge Exhaust 11/21/92 17 sccm TS-35S Purge Supply 11/21/92 252 sccm 7.0 TYPE C TESTS PERFORMED BETWEEN REFUELINGS Procedure Penetration Date Valve (s) Tested Leak Rate
- ORT-61 71 7/22/90 1WL-1723 & 1728 3 sccm
- ORT-54 50 7/24/90 _1MS-5959 50 sccm
- ORT-61 71 1/10/91 1WL-1723 & 1728 4 sccm
- ORT-36 28b 1/29/91 ISC-966B & 953 550 sccm 4
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- ORT-61 was performed as a result of adding a new test line to penetration P-71, Sump 'A' Drain to Aux. Building. !
(Ref. MOD 87-039)
- ORT-54 was performed for post maintenance on 1MS-5959.
The packing was adjusted and cleaned to stop leaking. i (Ref. MWR 903198)
- ORT-36 was performed for post maintenance on SC-9668. The packing was adjusted to stop a shaft seal leak. ,
(Ref. MWR 910153) l l
8.0 TYPE B AND C TEST
SUMMARY
The following tables are the as-found and as-left leakage rates for the Type B and C tests conducted between 1990 and 1993 ILRT's.
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t I OPERATIONS REFUELIWG TEST REPORT Short List of Database, Index numbers (1-66) l Unit 1 l --------------------------- ......-- - .....---------------- ..---- ..---------------------
INDEX ORT NAME PRE-OUT AS FOUND POST-OUT POST-DATE 01 12 Fuel Transfer Tube Flange Seal 46 8 8 05/04/90 02 43H Containment Sampling Line 2 16 16 04/13/90 03 13 Equipment Hatch Flange Seals 2 2 2 05/04/90 l 04 44H PACVS Vent Line 37 0 0 04/03/90 05 TS-10U El. 66' Personnel Hatch Test 445 1422 370 05/10/90 l 06 SPARE O O O
! 07 TS-10L El. 26' Personnel Hatch Test 1723 1087 363 05/11/90
- 08 46H Auxiliary Charging Line 5 24 3 05/10/90 09 75 Mechanical Penetration 48 4 4 04/10/90 10 47H Instrument Air Supply 1808 3100 339 05/07/90 11 76 Mechanical Penetration 9 5 5 04/19/90 12 48H Instrument Air Supply 144 214 214 04/02/90 13 77 Mechanical Penetration 12 8 8 04/19/90 14 49 Service Air Supply 1 1282 728 05/12/90 15 78 Mechanical Penetration 10 41 41 04/22/90 16 50H PRT to Gas Anal. Sample Line 36 65 65 04/07/90 17 79 Mechanical Penetration (Xter Tube) 12 0 0 04/23/90 18 51 A Steam Generator Sample Isol Valve 18 25 25 04/07/90 19 80 Mechanical Penetration 0 8 8 04/20/90 l 20 52 B Steam Generator Sample Isol Valve 87 22 22 04/07/90 l 21 81 Mechanical Penetration 1 448 448 04/19/90 22 53H RCDT to Gas Anal. Sample Line 1 4 4 04/07/90 l 23 82 Mechanical Penetration 1 3 3 04/20/90 I 24 54 B Steam Generator Blowdown (5959) 1 3 2 05/06/90 25 83 Mechanical Penetration 33 4 4 04/20/90 26 55 A Steam Generator Blowdown (5958) 1055 2150 1280 04/25/90 27 84 Mechanical Penetration 0 2 2 04/21/90 28 56 Heating Steam to Containment 1703 2640 23 05/03/90 29 25H RCDT Pump Suction Line 12 6 12 04/26/90 30 57 Containment Condensate Return 16 1027 1027 04/11/90 31 26H Letdown Line l
1 2 2 05/04/90 l 32 58 Containment Test Connection 1 1 1 04/13/90 33 27H RCP Seal Return 1 25 25 04/07/90 34 59 862A Spray Discharge check 490 416 395 05/04/90 35 28 Demineralized Water Line 5 2 2 04/16/90 36 60 862B Spray Discharge Check 522 425 242 05/04/90 37 SPARE O O O 38 61 Sump 'A' Drain to Aux. Building 4 2 2 04/14/90 39 30H RCDT & PRT Vent 21 3 3 04/23/90 40 TS-35E Purge Exhaust 0 3 13 05/11/90 41 31 N"2 Supply to Prt 2180 465 465 04/10/90 ;
42 TS-35S Purge Supply 8 20 382 05/11/90 43 32 N"2 Supply to SI Accumulators 82 106 96 05/05/90 44 64H RE-211 & RE-212 Supply 9 9 9 04/11/90 45 33H PACVS Return Line 47 2 2 04/10/90 46 65H RE-211 & RE-212 Return 52 32 32 04/11/90 47 34 Charging Line Check Valve 6 1 3 04/28/90 48 66T Containment Pressure 5 10 10 04/19/90 49 35 Hot Leg Sample 9 6 6 04/07/90 Point Beach Nuclear Plant i
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- OPERATIONS REFUELING TEST REPORT Short List of Database, Index numbers (1-66) 1 Unit 1
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j INDEX ORT NAME PRE-OUT AS FOUND POST-OUT POST-DATE
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50 67T CCW to Excess Letdown HX 2 4 4 04/02/90 l 51 36 Press. Liquid Sample Line 365 355 355 04/13/90
- 52 67F CCW from Excess Letdown HX 1 2 2 04/02/90 53 37 Press. Steam Sample Line 9 47 8 05/10/90 54 68T CCW to P1A 220 344 344 04/02/90 1 55 SPARE O O O
! 56 68F CCW from P1A 39 12 12 04/02/90 57 39 No. 1 Seal Injection to P1A 1 2 2 04/14/90
- 58 69T CCW to PIB 860 218 218 04/02/90 59 40 No. 1 Seal Injection to PIB 1 1 1 04/13/90 ;
60 69F CCW from PIB 295 218 218 04/02/90 61 SPARE O O O l 62 72 Electrical Penetration 1 1 1 04/11/90 '
! 63 42H Reactor Makeup Water Supply 4 20 20 04/27/90' 64 SPARE O O O
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, 65 73 Electrical Penetration 1 2 2 04/22/90
! 66 71 Electrical Penetration 0 1 1 04/22/90
! Grand Total 12504 16383 7904 j ======= ======== ========
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Point Beach Nuclear Plant 7
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OPERATIONS REFUELING TEST REPORT Short List of Database, Index numbers (1-66)
Unit 1 4.
INDEX ORT NAME PRE-OUT AS FOUND POST-OUT POST-DATE
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01 12 Fuel Transfer Tube Flange Seal 8 28 28 04/29/91 02 43H Containment Sampling Line 16 4 4 04/17/91 j 03 13 Equipment Hatch riange Seals 2 190 190 05/08/91 4 04 44H PACVS Vent Line 0 20 20 04/10/91 4 05 TS-10U El. 66' Personnel Hatch Test 1812 230 230 05/10/91 06 SPARE O O O J 07 TS-10L El. 26' Personnel Hatch Test 1604 2480 2480 05/12/91 l 08 46H Auxiliary Charging Line 3 9 9 04/15/91 09 75 Mechanical Penetration 4 5 5 04/12/91 10 47H Instrument Air Supply 339 230 230 04/10/91 4 11 76 Mechanical Penetration 5 0 0 04/12/91 j 12 48H Instrument Air Sapply 214 254 254 04/10/91 13 77 Mechanical Fenetration 8 3 3 04/12/91 14 49 Service Air Supply 728 633 947 05/09/91 15 78 Mechanical Penetration 41 186 186 04/29/91 16 50H PRT to Gas Anal. Sample Line 65 43 43 04/10/91 17 79 Mechanical Penetration (Xfer Tube) 0 2 2 04/16/91 18 51 A Steam Generator Sample Isol Valve 25 54 54 04/15/91 19 80 Mechanical Penetration 8 1 1 04/10/91 20 52 B Steam Generator Sample Isol Valve 22 35 19 05/11/91 al 81 Mechanical Penetration 448 20 20 04/09/91 22 53H RCDT to Gas Anal. Sample Line 4 1 1 04/10/91 23 82 Mechanical Penetration 3 2 2 04/16/91 24 54 B Steam Generator Blowdown (5959) 50 3 100 05/08/91 25 83 Mechanical Penetration 4 2 2 04/17/91 26 55 A Steam Generator Blowdown (5958) 1280 5 5 04/16/91 27 84 Mechanical Penetration 2 12 12 04/19/91 28 56 Heating Steam to Containment 23 126 126 04/16/91 29 25H RCDT Pump Suction Line 12 4 4 05/01/91 30 57 Containment Condensate Return 1027 14 14 04/16/91 31 26H Letdown Line 2 224 224 04/27/91 32 58 Containment Test Connection 1 20 20 04/17/91 33 27H RCP Seal Return 25 1 1 04/12/91 34 59 862A Spray Discharge Check 395 13 960 04/28/91 35 28 Demineralized Water Line 2 20 20 04/17/91 36 60 862B Spray Discharge Check 242 13 482 04/28/91 37 SPARE O O O 38 61 Sump 'A' Drain to Aux. Building 4 7 7 05/03/91 39 30H RCDT & PRT Vent 3 1 1 04/17/91 40 TS-35E Purge Exhaust 0 8 8 11/23/91 41 31 N 2 Supply to Prq 465 1401 1401 04/16/91 42 TS-35S Purge Supply 0 2 4 05/11/91 43 32 N"2 Supply to SI Accumulators 96 105 105 04/17/91 44 64H RE-211 & RE-212 Supply 9 3 3 04/09/91 45 33H PACVS Return Line 2 7 7 04/09/91 46 65H RE-211 & RE-212 Return 32 52 52 04/09/91 47 34 Charging Line Check Valve 3 227000 32 05/03/91 48 66T Containment Pressure 10 143 1 3 04/17/91 49 35 Hot Leg Sample 6 2 7 04/29/91
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Point Beach Nuclear Plant 8
OPERAIIONS REFUELING TEST REPORT Short List of Database, Index numbers (1-66)
Unit 1
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INDEX ORT NAME PRE-OUT AS FOUND POST-OUT POST-DATE
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50 67T CCW to Excess Letdown HX 4 0 0 04/14/91 51 36 Press. Liquid Sample Line 550 165 368 04/30/91 52 67F CCW from Excess Letdown HX 2 1 1 04/14/91 53 37 Press. Steam Sample Line 8 6 14 04/30/91 54 68T CCW to P1A 344 0 0 04/13/91 55 SPARE O O O 56 68F CCW from P1A 12 0 0 04/13/91 57 39 No. 1 Seal Injection to P1A 2 1 1 04/15/91 58 69T CCW to PIB 218 2 2 04/13/91 59 40 No. 1 Seal Injection to PIB 1 2 2 04/15/91 60 69F CCW from PIB 218 111 111 04/13/91 61 SPARE O O O 62 72 Electrical Penetration 1 5 5 04/16/91 63 42H Reactor Makeup Water Supply 20 12 12 04/10/91 64 SPARE O O O 65 73 Electrical Penetration 5 1 1 04/17/91 66 71 Electrical Penetration 1 0 0 04/16/91 Grand Total 10440 233924 8985 l
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Point Beach Nuclear Plant 9
OPERATIONS REFUEL 8NG TEST REPORT i Short List of Database, Index numbers (1 - 66)
Unit 1 June 3, 1992
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INDEX ORT # NAME PRE-OUT AS FOUND POST-OUT POST-DATE
= ---- ==_ ----- .=- -------------------- -------------------
01 12 Fuel Transfer Tube Flange Seal 28 18 18 05/10/92 02 43H Containment Sampling Line 4 14 14 04/18/92 03 13 Equipment Hatch Flange Seals 190 38 38 04/18/92 04 44H PACVS Vent Line 20 0 0 04/14/92 05 TS-10U El. 66' Personnel Hatch Test 1257 472 472 05/19/92 06 SPARE 07 TS-10L El. 26' Personnel Hatch Test 2040 3100 441 05/25/92 08 46H Auxiliary Charging Line 9 2 5 06/02/92 09 75 Hechanical Penetration 5 11 11 04/15/92 10 47H Instrument Air Supply 230 302 302 04/20/92 11 76 Mechanical Penetration 0 34 34 04/16/92 12 48H Instrument Air Supply 254 261 261 04/20/92 13 77 Mechanical Penetration 3 4 4 04/16/92 14 49 Service Air Supply 947 102 102 05/18/92 15 78 Mechanical Penetration 186 6 6 04/15/92 16 50H PRT to Gas Anal. Sample Line 43 32 32 04/18/92 17 79 Mechanical Penetration (Xfer Tube) 2 14 14 04/16/92 18 51 A Steam Generator Sample Isol valve 54 94 94 04/21/92 19 80 Mechanical Penitration 1 6 6 04/16/92 20 52 B Steam Generator Sample Isol Valve 19 90 90 04/21/92 21 81 Mechanical Penetration 20 0 0 04/16/92 22 53H RCDT to Gas Anal. Sample Line 1 10 10 04/18/92 23 82 Mechanical Penetration 2 15 15 04/17/92 24 54 B Steam Generator Blowdown (5959) 100 6 6 04/18/92 25 83 Mechanical Penetration 2 4 4 04/17/92 26 55 A Steam Generator Blowdown (5958) 5 13 70 05/19/92 27 84 Mechanical Penetration 12 9 9 04/17/92 28 56 Heating Steam to containment 126 4 4 04/22/92 29 25H RCDT Pump Suction Line 4 1 1 05/12/92 '
30 57 Containment Condensate Return 14 17 17 04/22/92 ]
31 26H Letdown Line 224 367 357 04/28/92 32 58 Containnent Test connection 20 3 3 04/30/92 j 33 27H RCP Seal Return 1 10 10 04/21/92 34 59 862A Spray Discharge Check 960 666 666 05/10/92 35 28 Demineralized Water Line 20 18 18 05/16/92 ,
36 60 862B Spray Discharge check 482 647 647 05/11/92 )
37 SPARE 38 61 Sump 'A' Drain to Aux. Building 7 2 2 05/01/92 l 39 30H RCDT & PRT Vent 1 0 0 04/20/92 l 40 TS-35E Purge Exhaust 8 1 0 05/20/92 l 41 31 N"2 Supply to Prt 1401 1660 247 05/17/92 ;
42 TS-35S Purge Supply 4 43 358 05/20/92 43 32 N"2 Supply to SI Accumulators 105 121 121 04/20/92 44 64H RE-211 & RE-212 Supply 3 9 9 04/28/92 45 33H PACVS Return Line 7 11 11 04/14/92 46 65H RE-211 & RE-212 Return 52 65 65 04/28/92 47 34 Charging Line Check Valve 32 1 139 05/24/92 48 66T Containment Pressure 143 18 18 04/14/92 POINT BEACH NUCLEAR POWER 10
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4 OPERATIONS REFUELIWG TEST REPORT j Short List of Database, Index numbers (1 - 66)
Unit 1 June 3, 1992 4
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ZNDEX ORT # NAME P:tE-OUT AS FOUND POST-OUT POST-DATE
- 49 35 Hot Leg Sample 7 2 9 05/06/92
- 51 36 Press. Liquid Sample Line 368 740 261 05/07/92 j 52 67F CCW from Excess Letdown HX 1 4 4 04/29/92 53 37 Press. Steam Sample Line 14 54 54 04/16/92 54 68T CCW to P1A 0 20 20 04/15/92 55 SPARE 56 68F CCW f *on P1A 0 5 5 04/15/92 57 39 No. 1 Seal Injection to P1A 1 3 3 04/15/92 58 69T CCW to PIB 2 0 0 04/14/92
- 59 40 No. 1 Seal Injection to PIB 2 3 3 04/15/92 4
60 69F CCW from PIB 111 3 3 04/14/92 61 SPARE j 62 72 Electrical Penetration 5 8 8 04/15/92 3
63 42H Reactor Makeup Water Supply 12 27 27 04/28/92 64 71 Electrical Penetration 0 1 1 04/15/92 65 73 Electrical Penetration 1 2 2 04/15/92 66 Calibration correction Grand Total 9572 9197 5165 mummman saammmes naamasam 5
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POINT BEACH NUCLEAR POWER 11
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- 9.0 COMMENTS ON VALVES WITH LEAKAGE APPROACHING OR EXCEEDING 0.6La AT STANDARD TEMPERATURE AND PRESSURE 4
- OPT 34 (1991)
Check valve, 1CV-370, charging system regenerative heat exchanger supply, would not close during the initial Type C
- test. The leakage past the valve was in excess of the leak
! rate limit of 0.6La, the maximum leakage allowed by-Technical i
Specification 15.4.4.II.B and 15.4.4.III.B. The root cause analysis results indicated the disc arm bushing steps had worn during the course of normal _ operation. The wear allowed 2 binding at the hinge connection which prevented disc arm movement and caused the disc to remain open. Corrective action consisted of cladding the worn disc arm bushing steps and hand filing the steps to their design contour. Post maintenance leakage was found to be 32 sccm.
(Ref. LER 91-003, PBNP Unit 1) l I
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SUMMARY
REPORT j REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RA*E TEST
!- POINT BEACH NUCLEAR PLANT UNIT 1, 1993 TABLE OF CONTENTS 1.0 General Data 1 5
2.0 Technical Data 1 3.0 Test Data 1 !
4.0 Analysis and Interpretation 2 5.0 Type C Leakage Corrections 3 6.0 Type B Tests Performed Between Refuelings 4 7.0 Type C Tests Performed Between Refuelings 4 8.0 Type B and C Test Summary 5 9.0 Comments on Valves with Excessive Leakage 12 i
e REPORT OF REACTOR CONTAINMENT BUILDING INTEGRATED LEAKAGE RATE TEST FOR POINT BEACH UNIT 1 1.0 GENERAL DATA 1.1 Owner - Wisconsin Electric Power Company 1.2 Docket Number 266 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 - April 1, 1993 2.0 TECHNICAL DATA 2.1 Containment Net Free Volume - 1,000,000 cubic feet 2.2 Design Pressure - 60 psig 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 - 31 psig 3.4 Maximum Allowable Leakage Rate, La - 0.400%/ Day 3.5 Reduced Pressure Allowable Leak Rate, Lt- 0.283%/ Day 3.6 Allowable Operational Leak Rate, .75 L t -
0.212%/ Day 3.7 Integrated Leakage Rate Test Results 3.7.1 Total Time Leak Rate 0.053%/ Day 3.7.2 95% Upper Confidence Level 0.085%/ Day 1
4 5 3.8 Verification Test Results 3.8.1 Imposed Verification Leak Rate 0.268%/ Day 3.8.2 Total Time Analysis 0.297%/ Day l
3.8.3 Verification Test Limits Lower Limit 0.250%/ Day
]! Upper Limit 0.392%/ Day 3.9 Penalties
! Containment Net Volume Changes 0.0060%/ Day l
Penetrations Not Aligned 0.0002%/ Day Pressurized Component Additions 0.0025%/ Day Total 0.009%/ Day 3.10 As-Found Leak Rate 0.094%/ Day Corrected for penalties at 95%
upper confidence level 4.0 ANALYSIS AND INTERPRETATION The seventh periodic Type A integrated leakage rate test (ILRT) of the Point Beach Nuclear Plant Unit 1 containment was performed March 31 to April 1, 1993, 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" and procedure ORT-17,
" Containment Integrated Leak Rate Test."
Fourteen penetrations, listed in section 5.0 of this report, were not in a post-LOCA alignment'during the ILRT. This l required additions, based on minimum pathway leakage analysis, i to the ILRT result of 0.0002%/ Day.
The pressurizer, reactor ccolant drain tank, pressurizer relief tank, and containment sump A were all vented to the containment during the ILRT. Water level changes in these tanks resulted in a decrease in the containment net free volume of 2.6 12.12 cubic feet during the test. The correction to the ILRT result for this net volume change is 0.006%/ Day.
The accumulators for the inner purge supply and purge exhaust valve seals, and the safety injection accumulators, were sources for pressurized component additions to the containment during the ILRT. The total pressurized component additions to the containment were 0.24 lbm/ hour. The correction to the ILRT result for this air addition is 0.0025%/ Day.
The total leakage rate correction for penetrations not in post-LOCA alignment, net volume changes, and pressurized 2
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4 component additions is 0.009%/ Day.
I The calculated leakage rate during the ILRT was 0.053%/ Day.
(total time). The calculated 95% upper confidence level was 0.085%/ Day (total time). ' Adding ~the. total leakage rate corrections for penetrations not in a post-LOCA alignment, l containment net volume changes, and pressurized component-additions, yields the corrected leakage rates as follows:
Total Time Leakage Rate, %/ Day Leakace Rate. UCL Calculated 0.053 0.085 Corrections 0.009 0.009 As-Found/As-Left 0.062 0.094 No Valve repairs were performed prior _to the ILRT. Therefore, the as-found test is equivalent to-the as-left test. Since the corrected ~95% upper confidence level for the total time is less than 0.75Lt (0.212%/ Day), the test results demonstrated the leakage through the primary containment and systems _and components penetrating primary containment does not exceed the allowable leakage rates specified in the Point Beach Nuclear Plant FSAR and Technical' Specifications.
. 5.0 TYPE C LEAKAGE CORRECTIONS Due to the test configuration of the containment, fourteen penetrations were not subjected to the Type A' test pressure.
These penetrations, justification, and as-found/as-left Type C test results are identified below:
Type C Results Penetration Justification (Minimum Pathway)
CVCS Supply Line In use for reactor coolant 2 sccm
(#26) system purification CVCS Letdown Line In use for reactor coolant 20 sccm l
(#10) system purification ,
l RCP "A" Seal Injection Maintain _ flow of clean 1 sccm Line (#29A) water through RCP seals RCP "B" Seal Injection Maintain flow of clean 1 sccm Line (#29B) water through RCP seals Auxiliary Charging Proper venting of line is 1 sccm Line (#32C) not possible when seal injection lines are in use 3
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l PACVS Supply Line Valve line-up modified to O sccm
(#31C) provide a flow verification path l Sump A Drain Line was not vented in order 2 sccm
(#71) to maintnin the ability to pump Sump A during the ILRT RCDT Pump Suction Line was not vented in order 3 sccm
(#9) to maintain the ability to pump the RCDT Excess Letdown HX Line was not vented during 55 sccm
(#19,20) ILRT A RCP CCW Line was not vented during 0 sccm
(#15,17) ILRT B RCP CCW Line was not vented during 1 secm
(#16,18) ILRT The fourteen penetrations not subjected to Type A test pressure were tested in the as-found condition following the Type A test at reduced pressure. All values are 2 secm.
6.0 TYPE B TESTS PERFORMED BETWEEN REFUELINGS Procedure Component Date Leak Rate TS-10U Upper Personnel Hatch 11/11/90 1812 sccm
~
TS-10L Lower Personnel Hatch 11/11/90 1604 sccm TS-35E Purge Exhaust 11/22/90 644 sccm l
TS-35S Purge Supply 11/22/90 7 sccm TS-10U Upper Personnel Hatch 11/21/91 1257 sccm TS-10L Lower Personnel Hatch 11/21/91 2040 sccm
! TS-35E Purge Exhaust 11/23/91 8 sccm 4 TS-35S Purge Supply 11/23/91 4 sccm j TS-10U Upper Personnel Hatch 11/11/92 285 sccm TS-10L Lower Personnel Hatch 11/12/92 510 sccm i TS-35F Purge Exhaust 11/21/92 17 sccm
- TS-35S Purge Supply 11/21/92 252 sccm l
7.0 TYPE C TESTS PERFORMED BETWEEN REFUELINGS Procedure Penetration Date Valve (s) Tested Leak Rate d
l
- ORT-61 71 7/22/90 1WL-1723 & 1728 3 sccm
- ORT-54 50 7/24/90 1MS-5959 50 sccm d
- ORT-61 71 1/10/91 1WL-1723 & 1728 4 sccm
- *** ORT-36 28b 1/29/91 1SC-966B & 953 550 sccm J
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- ORT-61 was performed as a result of adding a new test line to penetration P-71, Sump 'A' Drain to Aux. Building.
(Ref. MOD 87-039)
- ORT-54 was performed for post maintenance on 1MS-5959.
The packing was adjusted and cleaned to stop leaking.
(Ref. MWR 903198)
- ORT-36 was performed for post maintenance on SC-966B. The packing was adjusted to stop a shaft seal leak.
(Ref. MWR 910153) 8.0 TYPE B AND C TEST
SUMMARY
The following tables are the as-found.and as-left leakage rates for the Type B and C tests conducted between 1990 and 1993 ILRT's.
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l OPERATIONS REFUEL 8NG TEST REPORT l ,
Short List of Database, Index numbers (1-66) i Unit 1
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l ZNDEX ORT NAME PRE-OUT AS FOUND POST-OUT POST-DATE l
i 01 12 Fuel Transfer Tube Flange Seal 46 8 8 05/04/90 02 43H Containment Sampling Line 2 16 16 04/13/90
- 03 13 Equipment Hatch Flange Seals 2 2 2 05/04/90 1 04 44H PACVS Vent Line 37 0 0 04/03/90 1 05 TS-10U El. 66' Personnel Hatch Test 445 1422 370 05/10/90 06 SPARE O O O l
j 07 TS-10L El. 26' Personnel Hatch Test 1723 1087 363 05/11/90 j 08 46H Auxiliary Charging Line 5 24 3 05/10/90 l 09 75 Mechanical Penetration 48 4 4 04/10/90 i 10 47H Instrument Air Supply 180P 3100 339 05/07/90 i 11 76 Mechanical Penetration 9 5 5 04/19/90 l 12 48H Instrument Air Supply .144 214 214 04/02/90 j 13 77 Mechanical Penetration 12 8 8 04/19/90
{ 14 49 Service Air Supply 1 1282 728 05/12/90 l 15 78 Mechanical Penetration 10 41 41 04/22/90 1 16 50H PRT to Gas Anal. Sample Line 36 65 65 04/07/90 1 17 79 Mechanical Penetration (Xfer Tube) 12 0 0 04/23/90
. 18 51 A Steam Generator Sample Isol Valve 18 25 25 04/07/90
, 19 80 Mechanical Penetration 0 8 8 04/20/90 i 30 52 B Steam Generator Sample Isol valve 87 22 22 04/07/90 1 21 81 Mechanical Penetration 1 448 448 04/19/90
! D 53H RCDT to Gas Anal. Sample Line 1 4 4 04/07/90 1 23 82 Mechanical Penetration 1 3 3 04/20/90 l 24 54 B Steam Generator Blowdown (5959) 1 3 2 05/06/90 l 35 83 Mechanical Penetration 33 4 4 04/20/90 l 26 55 A Steam Generator Blowdown (5958) 1055 2150 1280 04/25/90 j 37 84 Mechanical Penetration 0 2 2 04/21/90
{ 28 56 Heating Steam to containment 1703 2640 23 05/03/90 4
29 25H RCDT Pump Suction Line 6 12 12 04/26/90 30 57 Containment condensate Return 16 1027 1027 04/11/90
- 31 26H Letdown Line 1 2 2 05/04/90
. 32 58 Containment Test Connection 1 1 1 04/13/90 j 33 27H RCP Seal Return 1 25 25 04/07/90 i 34 59 862A Spray Discharge check 490 416 395 05/04/90 1 35 28 Demineralized Water Line 5 2 2 04/16/90
! 36 60 862B Spray Discharge check 522 425 242 05/04/90
- 37 SPARE O O O 38 61 Sump 'A' Drain to Aux. Building 4 2 2 04/14/90 1 39 30H RCDT & PRT Vent' 21 3 3 04/23/90 l 40 TS-35E Purge Exhaust 0 3 13 05/11/90 j 41 31 N"2' Supply to Prt 2180 465 465 04/10/90 42 TS-35S Purge Supply 8 20 382 05/11/90
- 43 32 N"2 Supply to SI Accumulators 82 106 -96 05/05/90
, 44 64H RE-211 & RE-212 Supply 9 9 9 04/11/90 4 45 33H PACVS Return Line 47 2 2 04/10/90 q 46 65H RE-211 & RE-212 Return 52 32 32 04/11/90 47 34 Charging Line check Valve 6 1 3 04/28/90 l 48 66T Containment Pressure 5 10 10 04/19/90 49 35 Hot Leg Sample 9 6 6 04/07/90
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} Point Beach Nuclear Plant 6
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- o. j OPERAT20NS REFUELING TEST REPORT short List of Database, Index numbers (1-66)
Unit 1 INDEX ORT NAME PRE-OUT AS FOUND POST-OUT POST-DATE 50 67T CCW to Excess Letdown HX 2 4 4 04/02/90 j 51 36 Press. Liquid Sample Line 365 355 355 04/13/90 i 52 67F CCW from Excess Letdown HX 1 2 2 04/02/90 1 53 37 Press. Steam sample Line 9 47 8 05/10/90 I 54 68T CCW to P1A 220 344 344 04/02/90 l 55 SPARE O O O 56 68F CCW from PIA 39 12 12 04/02/90 57 39 No. 1 Seal Injection to P1A 1 2 2 04/14/90 l 58 69T CCW to PIB 860 218 218 04/02/90 l 59 40 No. 1 Seal Injection to PIB 1 1 1 04/13/90 60 69F CCW from PIB 295 218 218 04/02/90 61 SPARE O O O 62 72 Electrical Penetration 1 1 1 04/11/90 63 42H Reactor Makeup Water Supply 4 20 20 04/27/90 64 SPARE O O O 65 73 Electrical Penetration 1 2 2 04/22/90 66 71 Electrical Penetration 0 1 1 04/22/90 Grand Total 12504 16383 7904
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Point Beach Nuclear Plant 7
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OPERATIONS REFUELING TEST REPORT Short List of Database, Index numbers (1-66)
Unit 1 INDEX ORT NAME PRE-OUT AS FOUND POST-OUT POST-DATE
__------------_-_------_-------___--_-__--____- - _= -------_______-_-------_----_--_--___ ,
01 12 Fuel Transfer Tube Flange Seal 8 28 28 04/29/91 02 43H Containment Sampling Line 16 4 4 04/17/91 I 03 13 Equipment Hatch Flange Seals 2 190 190 05/08/91 04 44H PACVS Vent Line 0 20 20 04/10/91 05 TS-100 El. 66' Personnel Hatch Test 1812 230 230 05/10/91 l 06 SPARE O O O 07 TS-10L El. 26' Personnel Hatch Test 1604 2480 2480 05/12/91 08 46H Auxiliary Charging Line 3 9 9 04/15/91 09 75 Mechanical Penetration 4 5 5 04/12/91 10 47H Instrument Air supply 339 230 230 04/10/91 81 76 Mechanical Penetration 5 0 0 04/12/91 12 48H Instrument Air Supply 214 254 254 04/10/91 13 77 Mechanical Penetration 8 3 3 04/12/91 14 49 Service Air Supply 728 633 947 05/09/91 15 78 Mechanical Penetration 41 186 186 04/29/91 16 50H PRT to Gas Anal. Sample Line 65 43 43 04/10/91 17 79 Mechanical Penetration (Xfer Tube) 0 2 2 04/16/91 18 51 A Steam Generator Sample Isol Valve 25 54 54 04/15/91 19 80 Mechanical Penetration 8 1 1 04/10/91 20 52 B Steam Generator Sample Isol valve 22 35 19 05/11/91 31 81 Mechanical Penetration 448 20 20 04/09/91 22 53H RCDT to Gas Anal. Sample Line 4 1 1 04/10/91 23 82 Mechanical Penetration 3 2 2 04/16/91 24 54 B Steam Generator Blowdown (5959) 50 3 100 05/08/91 25 83 Mechanical Penetration 4 2 2 04/17/91 26 55 A Steam Generator Blowdown (5958) 1280 5 5 04/16/91 27 84 Mechanical Penetration 2 12 12 04/19/91 28 56 Heating Steam to containment 23 126 126 04/16/91 29 25H RCDT Pump Suction Line 12 4 4 05/01/91 30 57 Containment Condensate Return 1027 14 14 04/16/91 31 26H Letdown Line 2 224 224 04/27/91 32 58 Containment Test Connection 1 20 20 04/17/91 33 27H RCP Seal Return 25 1 1 04/12/91 34 59 862A Spray Discharge Check 395 13 960 04/28/91 35 28 Domineralized Water Line 2 20 20 04/17/91 36 60 862B Spray Discharge Check 242 13 482 04/28/91 37 SPARE O O O 38 61 Sump 'A' Drain to Aux. Building 4 7 7 05/03/91 !
39 30H RCDT & PRT Vent 3 1 1 04/17/91 40 TS-35E Purge Exhaust 0 8 8 11/23/91 41 31 N"2 Supply to Prt 465 1401 1401 04/16/91 42 TS-35S Purge Supply 0 2 4 05/11/91 43 32 N*2 Supply to SI Accumulators 96 105 105 04/17/91 44 64H RE-211 & RE-212 Supply 9 3 3 04/09/91 45 33H PACVS Return Line 2 7 7 04/09/91 46 65H RE-211 & RE-212 Return 32 52 52 04/09/91 47 34 Charging Line check Valve 3 227000 32 05/03/91 48 66T Containment Pressure 10 143 143 C4/17/91 , !
49 35 Hot Leg' Sample 6' 2 7 04/29/91 l
-_-_____--_-_-_-_------_.-____-_---____---------______-____--__-___--------__-----__-__j l
Point Beach Nuclear Plant 0
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OPERATIONS REFUELING TEST REPORT l
. Short List of Database, Index numbers (1-66) I Unit 1 INDEX ORT NAME PRE-OUT AS FOUND POST-OUT POST-DATE ]
30 67T CCW to Excess Letdown HX 4 0 0 04/14/91 j 51 36 Press. Liquid Sample Line 550 165 368 04/30/91 i 52 67F CCW from Excess Letdown HX 2 1 1 04/14/91 53 37 Press. Steam sample Line 8 6 14 04/30/91 54 68T CCW to P1A 344 0 0 04/13/91 55 SPARE O O O 56 68F CCW from P1A 12 0 0 04/13/91 57 39. No. 1 Seal Injection to P1A 2 1 1 04/15/91 58 69T CCW to PIB 218 2 2 04/13/91 59 40 No. 1 Seal Injection to PIB 1 2 2 04/15/91 60 69F CCW from PIB 218 111 111 04/13/91 61 SPARE O O O 62 72 Electrical Penetration 1 5 5 04/16/91 63 42H Reactor Makeup Water Supply 20 12 12 04/10/91 64 SPARE O O O 65 73 Electrical Penetration 5 1 1 04/17/91 66 71 Electrical Penetration 1 0 0 04/16/91 Grand Total 10440 233924 8985 r
_= .. .__ ___-_______________________________ ___
Paint Beach Nuclear Plant 9
OPERATIONS REFUELING TEST REPORT Short List of Database, Index numbers (1 - 66)
Unit 1 June 3, 1992 X 4$b J- 3-f L
____________________________ ___________________________________=- _____________________
INDEX ORT # NANZ PRE-OUT AS FOUND POST-OUT IOST-DATE 01 12 Fuel Transfer Tube Flange Seal 28 18 18 05/10/92 02 43H Containment Sampling Line 4 14 14 04/18/92
, 03 13 Equipment Hatch Flange Seals 190 38 38 04/18/92 04 44H PACVS Vent Line 20 0 0 04/14/92 05 TS-10U El. 66' Personnel Hatch Test 1257 472 472 05/19/92 06 SPARE 07 TS-10L El. 26' Personnel Hatch Test 2040 3100 441 05/25/92 08 46H Auxiliary Charging Line 9 2 5 06/02/92
< 09 75 Mechanical Penetration 5 11 11 04/15/92 10 47H Instrument Air Supply 230 302 302 04/20/92
. 11 76 Mechanical Penetration 0 34 34 04/16/92 12 48H Instrument Air Supply 254 261 261 04/20/92 13 77 Mechanical Penetration 3 4 4 04/16/92 14 49 Service Air supply 947 102 102 05/18/92 15 78 Mechanical Penetration 186 6 6 04/15/92 16 50H PRT to Gas Anal. Sample Line 43 32 32 04/18/92 17 79 Mechanical Penetration (Xfer Tube) 2 14 14 04/16/92 18 51 A Steam Generator Sample Isol Valve 54 94 94 04/21/92 19 80 Mechanical Penetration 1 6 6 04/16/92 20 52 B Steam Generator Sample Isol Valve 19 90 90 04/22/92 21 81 Mechanical Penetration 20 0 0 04/16/92 22 53H RCDT to Gas Anal. Sample Line 1 10 10 04/18/92 23 82 Mechanical Penetration 2 15 15 04/17/92 24 54 B Steam Generator Blowdown (5959) 100 6 6 04/18/92 25 '83 Mechanical Penetration 2 4 4 04/17/92 26 55 A Steam Generator Blowdown (5958) 5 13 70 05/19/92 27 84 Mechanical Penetration 12 9 9 04/17/92
- 28 56 Heating Steam to Containment 126 4 4 04/22/92 29 25H RCDT Pump Suction Line 4 1 1 05/12/92 30 57 Containment Condensate Return 14 17 17 04/22/92 31 26H Letdown Line 224 367 367 04/28/92 32 5E Containment Test connection 20 3 3 04/30/92 33 27H RCP Seal Return 1 10 10 04/21/92 34 59 862A Spray Discharge Check 960 666 666 05/10/92 35 28 Demineralized Water Line 20 18 18 05/16/92 36 60 862B Spray Discharge Check 482 647 647 05/11/92 37 SPARE 38 61 Sump 'A' Drain to Aux. Building 7 2 2 05/01/92 39 30H RCDT & PRT Vent 1 0 0 04/20/92 40 TS-35E Purge Exhaust 8 1 0 05/20/92 41 31 N"2 Supply to Prt 1401 1660 247 05/17/92 42 TS-35S Purge Supply 4 43 358 05/20/92 43 32 N'2 Supply to SI Accumulators 105 121 121 04/20/92 44 64H RE-211 & RE-212 Supply 3 9 9 04/28/92 45 33H PACVS Return Line 7 11 11 04/14/92 46 65H RE-211 & RE-212 Return 52 65 65 04/28/92 47 34 Charging Line Check valve 32 1 139 05/24/92 48 66T Containment Pressure 143 18 18 04/14/92 POINT BEACH KUCLEAR POWER 10
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j OPERATIONS REFUELING TEST REPORT
! . Short List of Database, Index numbers (1 - 66) l Unit 1 June 3, 1992 1
4 INDEX ORT # NAME PRE-OUT AS FOUND POST-OUT POST-DATE l 49 35 Hot Leg Sample 7 2 9 05/06/92 5 50 67T CCW to Excess Letdown HX 0 4 4 04/29/92 j 51 36 Press. Liquid Sample Line 368 740 261 05/07/92 3
52 67F CCW from Excess Letdown HX 1 4 4 04/29/92 a 53 37 Press. Steam Sample Line 14 54 54 04/16/92-l 54 68T CCW to P1A 0 20 20 04/15/92 I 55 SPARE 56 68F CCW from P1A 0 5 5 04/15/92 1
! 57 39 No. 1 Seal Injection to P1A 1 3 3 04/15/92 58 69T CCW to PIB 2 0 0 04/14/92
- 59 40 No. 1 Seal Injection to PIB 2 3 3 04/15/92 j 60 69F CCW from PIB 111 3 3 04/14/92 '
- 61 SPARE
) 62 72 Electrical Penetration 5 8 8 04/15/92
! 63 42H Reactor Makeup Water supply 12 27 27 04/28/92
[ 64 71 Electrical Penetration 0 1 1 04/15/92 1 65 73 Electrical Penetration 1 2 2 04/15/92 66 Calibration Correction 1
- Grand Total 9572 9197 5165 i
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i POINT BEACH NUCLEAR POWER 4- 11 1
9.0 COMMENTS ON VALVES WITH LEAKAGE APPROACHING OR EXCEEDING 0.6L, AT STANDARD TEMPERATURE AND PRESSURE-ORT 34 (1991)
Check valve, 1CV-370, charging system regenerative heat exchanger supply, would not close during the initial-Type C test. The leakage past the valve was in excess of the leak rate limit of 0.6La, the maximum leakage allowed by-Technical Specification 15.4.4.II.B and.15.4.4.III.B. The root cause analysis results indicated the disc arm bushing steps had worn during the course of normal operation. The wear allowed binding at the hinge connection which prevented disc arm movement and caused the disc to remain open. Corrective action consisted of cladding the worn disc arm bushing steps and hand filing the steps to their design contour. Post maintenance leakage was found to be 32 secm.
(Ref. LER 91-003, PBNP Unit 1)
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