ML20126A101

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Reactor Containment Bldg Integrated Leak Rate Test,Point Beach Unit 2
ML20126A101
Person / Time
Site: Point Beach NextEra Energy icon.png
Issue date: 12/14/1992
From: Link B
WISCONSIN ELECTRIC POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CON-NRC-92-142 VPNPD-92-369, NUDOCS 9212170233
Download: ML20126A101 (16)


Text

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Wisconsin

' Elecinc

POMER COMPANY
P n umgn av % pus w,.cee wa;m mung, ;3e 1-VPNPD 36 9 NRC 14 2 December 14, 1992 10 CFR 50, Appendix J Document Control Desk U.S. NUCLEAR REGULATORY COMMISSION Mall Station P1-137 Washington, DC 20555 Gentlemen:

DOCKET 50-301 REAC1'.OR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST 4

POINT BEACH NUCLEAR PLANT, UNIT 2 In accordance with Section 15.4.4.I.D of the Point Beach Nuclear Plant Technical Specifications and Section V.B. of 10 CFR 50, Appendix J, this technical report is submitted summarizing the

! Type A containment integrated leakage rate test conducted during our 1992 Unit 2 refueling outage. Also included are summaries of the results from the Type B and C leak tests conducted subsequent to our 1989 Type A test. The Type B and C leak tests were performed during the refueling outages of September-November 1989, October-November 1990, and September-November 1991. The 1992 Type A test was performed by Wisconsin Electric with assistance from Bechtel Power Corporation. We have enclosed a summary report prepared in accordance with the format specified in ANSI /ANS 56.8 - 1987. The complete documentation (which includes all procedures, equipment calibrations, test data, and results) will be retained by Wisconsin Electric and is available for NRC review at Point Beach Nuclear Plant.

Our 1992 Unit 2 Type A integrated leak rate test was conducted in accordance with 10 CFR 50, Appendix J, Point Beach Nuclear Plant Operations Refueling Tests (ORT) -17, " Containment Integrated Leak Rate Test, Unit 2," and Bechtel Corporation Topical Report j

(BN-TOP-1), " Testing Criteria For Integrated Leakage Rate Testing of Containment Structures For Nuclear Power Plants." Our Type B and Type C penetration tests were conducted in accordance with 10 CFR 50, Appendix J and various Point Beach Nuclear Plant Operations Refueling Tests.

The overall as-found total time leakage rate measured for the 1992 Type A test was 0.158%/ day at the 95% upper confidence level. This is 79% of the operational leakage rate allowed by Point Beach Nuclear Plant Technical Specifications. The leakage rate reported 9212170233 921214 l KDR ADOCK 05000301 nn i

Document Control Desk December 14, 1992 Page 2 includes a 0.007%/ day penalty for non-standard valve alignments, containment net free volume changes, and pressurized component 1

additions to the containment.

The overall as-found leakage of the Type B and C tests conducted during the 1989 refueling outage was 18,261 standard cubic

, centimeters per minute (sccm) or 8% of 0.6L,. After repairs, the overall leakage rate was 17,553 scem or 8% of 0.6L, (0.6L, is 60% of the maximum allowable leakage as allowed by Point Beach Nuclear Plant Technical Specifications).

j The overall as-found leakage of the Type B and C tests conducted during the 1990 refueling outage was 26,512 sccm or 11% of 0.6L,.

After repairs, the overall leakage rate was 21,973 sccm or 10% of

O . 6 L, .

The overall as-found leakage of the Type B and C tests conducted during the 1991 refueling outage was 39,095 sccm or 17% of 0.6L,.

. After repairs, the-overall leakage rate was 21,088 scem or P% of 0 . 6 L, .

The results of all Type A, Type B, and Type C tests performed
subsequent to our 1989 Unit 2 outage, meet or exceed the

! requirements of Point Beach Nuclear Plant Technical Specifications and Section III of 10 CFR 50, Appendix J.

l If you have any questions concerning this report or require additional information, please feel free to contact us.

Sincerely, e

,f .

N g-J -~~~)

, Bob Link l'

Vice President Nuclear Power Enclosures cc: NRC Resident Inspector NRC Regional Administrator, Region III DMC/jg i

SUMMARY

REPORT REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST POINT BEACH NUCLEAR PLANT UNIT 2, 1992 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 4 6.0 Type B Tests Performed Between Refuelings 5 7.0 Type C Tests Performed Between Refuelings 5 8.0 Type B and C Test Summary 6 9.0 Comments on valves with Excessive Leakage 13

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REPORT OF REACTOR CONTAINMENT BUILDING INTEGRATED

. LEAKAGE RATE TEST FOR POINT BEACil UNIT 2 i

i 1.0 GENERAL DATA

1.1 Owner

Wisconsin Electric Power Company i

1.2 Docket Number: 50-301 1

j 1.3 Location: Two Rivers, Wisconsin i

1.4 Containment

Description:

3\ foot pre-stressed

post-tensioned concrete cylinder with \ inch wolded ASTM A-442 steel liner

.] 1.5 Date Test Was Completed: October 1, 1992 4

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,' 2.0 TECHNICAL DATA 1

2.1 Containment Not Free Volume: 1,000,000 cubic feet 2.2 Design Pressure: 60 psig 1

q 2.3 Design Temperature: 286'F 2.4 Calculated Accident Peak Pressure (Pac): 53 psig 2.5 Calculated Accident Peak Temperature (Tac): 278'F l

! 3.0 TEST DATA 3.1 Test Method: Absolute 3.2 Data Analysis Technique: Total Time

{ 3.3 Test Pressure: 31 psig a

! 3.4 Maximum Allowable Leakage Rate, L: 0.400%/ day

, 3.5 Reduced Pressure Allowable Leak Rato, L,: 0.268%/ day 3.6 Allowable Operational Leak Rate, .75 L: g 0.201%/ day f 3.7 Integrated Leakage Rate Test Results I

3.7.1 Total Time Leak Rate 0.088%/ day 3.7.2 95% Upper Confidence Level 0.151%/ day i

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3.8 Verification Test Results 3.8.1 Imposed Verification Leak Rate 0.268%/ day 1

3.8.2 Total Time Analysis 0.319%/ day 3.8.3 Verification Test Limits l Lower Limit 0.289%/ day Upper Limit 0.423%/ day i

j 3.9 Penalties Containment Not Volume Changes 0.006%/ day 1 Penetrations Not Aligned 0.000%/ day l Pressurized Component Additions 0.001%/ day Total 0.007%/ day j 3.10 As-Found Leak Rate 0.158%/ day

Corrected for penalties at 95%
upper confidence level 4.0 ANALYSIS AND INTERPRETATION

[ The sixth periodic Type A integrated leakage rate test (ILRT)

, of the Point Beach Nuclear Plant Unit 2 containment was performed September 27 to October 1, 1992, 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."

e I

Eight penetrations, listed in Section 5.0 of this report, were

! not in a post-LOCA alignment during the ILRT. This required l' additions, based on minimum pathway leakage analysis, to the ILRT result of 0.0002%/ day.

The pressurizer, reactor coolant drain tank, pressurizer i relief tank, and containment Sump A were all vented to the l containment during the ILRT. Water level changes in these 4

tanks resulted in a decrease in the co.ntainment net free l volume of 6.52 i 13.70 cubic feet durilsg the test. The

correction to the ILRT result for this net volume change is

, 0.0060%/ 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 0.096 lbm/ hour. The correction to the

ILRT result for this air addition is 0.001%/ day.

The total leakage rate correction for penetrations not in l post-LOCA alignment, net volume changes, and pressurized component additions is 0.0072%/ day.

5 The calculated leakage rate during the ILRT was 0.088%/ day (total time). The calculated 95% upper confidence level was

, 0.151%/ day (total time) . Adding the total leakage rate j corrections for penetrations not in a post-LOCA alignment, containment not volume changes, and pressurized component ,

additions, yields the corrected leakage rates as follows: I

! Total Time Leakage Rate, %/ Day Leakace Rate MEL Calculated 0.088 0.151 I

Corrections 0.007 0.007

, As-Found/As-Left 0.095 0.158 I

t No valve repairs were performed prior to the ILRT. Therefore,

the as-found test is equivalent to the as-left test. Since i j the corrected 95% upper confidence level for the total time is j lecc than 0.75Lg (0.201%/ day), the test results demonstrated l the leakage through the primary containment and systems and

.i components penetrating primary containment does not exceed the

allowable leakage rates specified in the Point Beach Nuclear
Plant FSAR and Technical Specifications.

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5.0 TYPE C LEAKAGE CORRECTIONS ,

1 Due to the test configuration of the containment, 8 penetra-tions were not subjected to the Type A test pressure. These  !

penetrations, justification, and as-found/as-left Type C test results are identified below: l Type C Results Penetration Justifigation (Minimum Pathway)

CVCS Supply Line In use for reactor coolant 27 seca

(#26) system purification CVCS Letdown Line In use for reactor coolant 70 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 cican 1 sccm Line (#29B) water through RCP seals Auxiliary Charging Proper venting of line is O sccm Line (#32C) not possible when seal injection lines are in use 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 1 sccm

(#71) to maintain the ability to pump Sump A during the ILRT RCDT Pump Suction Line was not vented in order 0 sccm

(#9) to maintain the ability to pump the RCDT The 8 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 12 sccm.

6.0 TYPE B TESTS PERFORMED BETWEEN REFUELINGS Procedure Component Date Leak Rate TS-10 Upper Personnel Hatch 5/5/90 330 sccm TS-10 Lower Personnel Hatch 5/5/90 965 sccm TS-36 Purge Exhaust (V1) 5/20/90 403 sccm TS-36* Purgo Supply (V2) 5/20/90 2240 sccm TS-36 Purgo Supply (V2) 5/29/90 1836 sccm TS-10 Upper Personnel Hatch 5/1/91 360 sccm TS-10 Lower Personnel Hatch 5/1/91 312 sccm TS-36 Purge Exhaust (V1) 5/24/91 177 sccm TS-36 Purge Supply (V2) 5/24/91 183 sccm TS-10 Upper Personnel Hatch 4/29/92 1233 sccm TS-10 Lower Personnel Hatch 4/29/92 1857 sccm TS-36 Purge Exhaust (V1) 6/13/92 77 sccm TS-36 Purge supply (V2) 6/13/92 863 sccm

  • IA-876, check valve to boot seal for purge supply valve (V2), was sticking and not permitting sufficient air flow to boot seal. The leakage rate of 2240 sccm for the purge supply valva (V2) is in excess of adminis-trative limits, but less than the limits specified in Technical Specifications section 15.4.4.III.B. IA-876 was replaced during the following refueling outage (U2R16).

7.0 TYPE C TESTS PERFORMED BETWEEN REFUELINGS Procedure Penetration Date Valvefs) Tested Leak Rate

  • ORT-61 71 1/10/91 2WL-1723 & 1728 6 sccm
    • ORT-36 28b 1/26/91 2SC-966B & 953 2500 sccm
  • ORT-61 was performed as a result of adding a new test line to Penetration P-71, Sump 'A' Drain to Aux. Building.
    • ORT-36 was performed for post maintenance on SC-966B. The leakage rate of 2500 seem is in excess of administrative limits, but less than the limits specified in Technical Specifications section 15.4.4.III.B. SC-966B was replaced during the following outage (U2R17).

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3 8.0 TYPE B AND C TEST

SUMMARY

I The following tables are the as-found and as-left leakage

rates for the Type B and C tests conducted between 1989 and i 1992 ILRT's.

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1 j OPERATIONS REFUELING TEST REPORT Short List of Database, Indsx numbcre (1-66)

Unit 2

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! INDEX ORT NAME PRE-OUT AS FOUND POST-OUT POST-DATE

) .......................__.........____...... .._______.....___.. ...___............ ........

01 12 Fuel Transfer Tube Flange Seal 113 17 17 11/12/89 02 43H Containment sampling Line 3 39 39 10/17/89

  • 03 13 Equitunent Hatch F'ange Seals 61 79 79 11/10/89

) 04 44H PACVS Vent Line 11 19 19 09/25/89 I 05 TS-10U El. 66' Personnel Hatch Test 591 6 6 11/19/89 06 SPARE O O O l

. 07 TS-10L El. 26' Personnel Hatch Test 1660 1 1 11/18/89 l 08 46H Auxiliary Charging Line 2 62 62 10/17/89 j 09 75 Mechanical Penetration 316 608 608 10/12/89 i 10 47H Instrument Air Supply 1001 1070 1070 09/24/89 l 11 76 Mechanical Penetration 8 2 2 10/12/89 12 48H Instrument Air Supply 493 435 435 09/24/89 13 77 Hect.anical Penetration 5 7 7 10/12/89 14 49 Service Air Supply 55 61 2090 11/20/89

15 76 Hochanical Penetration 141 2 2 10/21/89 j 16 50H PRT to Cas Anal. Sample Line 2 4 4 10/10/89 j 17 79 Mechanical Penetration (Xfer Tube) 0 8 8 10/19/89 j 18 51 A Steam Generator Sample Isol Valve 68 937 937 10/16/89 l

19 80 Hechanical Penetration 4 1 1 10/20/89

20 52 B Steam Generator Sample Isol Valve 15 17 17 10/16/89 j 21 83 Hechanical Penetration 30 0 0 10/11/89

{ 22 53H RCDT to Gas Anal. Sample Line 3 3 3 10/10/89 j 23 82 Mechanical Penetration 31 2 2 10/12/89 j 24 54 B Steam Generator Blowdown (5958) 1087 744 744 10/02/89

25 83 Hechanical Penetration 23 2 2 10/20/89 26 55 A Steam Generator Blowdown (5959) 90 635 635 10/02/69 27 84 Mechanical Penetration 16 1 1 10/19/89 28 56 Heating Steam to Containment 83 25 191 11/09/89 4

29 25H RCDT Pump Suction Line 4 4 4 11/14/89 i 30 57 Containment condensate Return 3270 2040 31 11/09/89 j 31 26H Letdown Line 98 513 513 10/17/89 j 32 58 Containment 7est Connection 87 35 35 10/12/89 l

33 27H RCP Seal Return 121 202 202 10/06/89 i 34 59 862A Spray Discharge Check 21 301 11 10/10/89 l 35 28 Demineralized Water Line 0 1 1 10/12/89 j 36 60 862B Spray Discharge Check 1 67 16 10/10/89 j 37 SPARE O O O g 38 61 Sump 'A' Drain to Aux. Building 5 49 49 10/21/89

}- 39 30H RCDT & PRT Vent 2 2 2 10/06/89 j 40 TS-36E Purge Exhaust 34 280 391 11/19/89

41 31 N"2 Supply to Prt 15 12 12 10/05/89 ,

i 42 TS-36S Purge Supply 2840 480 4920 11/21/89

43 32 N*2 Supply to SI Accumulators 480 730 487 10/01/89 ,

j 44 64H RE-211 & RE-212 Supply 205 305 305 10/15/89

. 45 33H PACVS Return Line 0 35 35 10/02/89 y -- 46 65H RE-211 & RE-212-Return 319 358 358 10/15/89 47 34 Charging Line Check Valve 525 51 51 10/17/89

48- 66T Containment Pressure 2 10 10 10/17/89
j 49 35 Hot Leg Sample 136 4 47 10/13/89 POINT BEACH NUCLEAR POWER j I i

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l OPERATIONS REFUELING TEST REPORT short Lict of Detebaco, Index numboro (1-66)

Unit 2 4

INDEX ORT NAME PRE-OUT AS FOUND POST-OUT POST-DATE 50 67T CCW to Excess Letdown HX 214 11 11 10/01/89 51 36 Press. Liquid sample Line 2 3330 131 11/17/89 52 67F CCW from Excess Letdown HX 14 25 25 10/01/89 53 37 Press. Steam sample Line 70 230 49 10/07/89 54 68T CCW to P1A 88 620 620 09/30/89 55 SPARE O O O 56 68F CCW from P1A 288 620 620 10/02/89 57 39 No. 1 Seal Injection to P1A 128 34 34 10/01/89 58 69T CCW to PIB 49 2450 926 10/12/89 59 40 No. 1 seal Injection to PIB 2 5 5 10/01/89 60 69F CCW from PIB 33 535 535 09/30/89 61 SPARE O O O 62 72 Electrical Penetration 6 1 1 10/19/89 63 42H Reactor Makeup Water Supply 1 122 122 10/12/89 64 85 Eddy Current Cables 0 1 1 11/06/89 65 73 Electrical Penetration 2 11 11 10/21/89 66 71 Electrical Penetration 2 0 0 10/12/89 Grand Total 14976 18261 17553

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POINT BEACH NUCLEAR POWER

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CPERATIONS REFUELING TEST REPORT Short List of Datebeco, Indsx numbero (1-66)

Unit 2 July 21, 1992 INDEX ORT NAME PRE-OUT AS FOUND POST-OUT POST-DATE 01 12 Fuel Transfer Tube Flange Seal 17 34 34 10/28/90 1 02 43H Containment Sampling Line 39 4 4 10/12/90 I 03 13 Equipment Hatch Flange Seals 79 5 5 10/25/90 a 04 44H PACVS Vent Line 19 4 4 10/11/90

) 05 TS-10U El. 66' Personnel Hatch Test 330 1960 1960 11/11/90 l

06 SPARE O O O 07 TS-10L El. 26' Personnel Hatch Test 965 492 492 11/09/90 08 46H Auxiliary Charging Line 62 4 4 10/18/90 09 75 Mechanical Penetration 608 1148 1148 10/16/90 10 47H Instrument Air supply 1070 1823 1823 10/12/90 11 76 Hechanical Penetration 2 0 0 10/17/90

< 12 4BH Instrument Air Supply 435 505 505 10/12/90 j 13 77 Mechanical Penetration 7 0 0 10/17/90 1 14 49 Service Air Sup;.y 2090 2290 580 11/12/90

15 78 Mechanical Penetration 2 12 12 10/18/90 j 16 50H PRT to Cas Anal. Sample Line 4 4 4 10/19/90 17 79 Hechanical Penetration (Xfer Tube) 8 70 70 10/27/90 18 51 A Steam Generator Sample Isol Valve 937 933 933 10/11/90 19 80 Mechanical Penetration 1 9 9 10/17/90

+

20 52 B Steam Generator Sample Isol Valve 17 8 8 10/11/90 21 81 Hechanical Penetration 0 33 33 10/11/90 22 53H RCDT to Gas Anal. Sample Line 3 1 1 10/24/90 23 82 Mechanical Penetration 2 1 1 10/13/90 24 54 B Steam Generator Blowdown (5958) 744 1706 1706 10/31/90 1 25 83 Hechanical Penetration 2 1 1 10/17/90

{ 26 55 A Steam Generator Blowdown (5959) 635 217 217 10/30/90

! 27 84 Hechanical Penetration 1 2 2 10/17/90 28 56 Hoating Steam to containment 191 311 311 10/13/90 I

29 25H RCDT Pump Suction Line 4 312 312 10/31/90 30 57 Containment Condensate Return 31 55 55 11/07/90 31 26H Letdown Line 513 57 57 10/18/90 32 58 Containment Test connection 35 34 34 10/19/90 33 27H RCP Seal Return 202 150 150 10/21/90 34 59 862A spray Discharge check 11 1207 1785 11/07/90 l 35 28 Demineralized Water Liie 1 76 76 10/21/90 36 60 862B Spray Discharge C3eck 16 489 534 10/10/90

37 SPARE O O O 38 61 Sump 'A' Drain to Aux. Building 49 4 4 11/02/90 39 30H RCDT & PRT Vent 2 1 1 10/22/90 l 40 TS-36E Purge Exhaust 403 310 648 11/11/90 41 31 N 2 Supply to Prt 12 32 32 10/19/90 42 TS-36S Purge Supply 1836 1360 2440 11/11/90 43 32 N'2 Supply to SI Accumulators 487 257 257 10/12/90 44 64H RE-211 & RE-212 Supply 305 612 612 10/12/90 45 33H PACVS Return Line 35 4 4 10/11/90 46 65H RE-211 & RE-212 Return 358 400 403 10/12/90 47 34 Charging Line check Valve 51 34 11 11/04/90 48 66T Containment Pressure 10 -35 35 10/12/90 49 35 Hot Leg Sample 47 126 4 11/07/90 POINT LEACH NUCLEAR POWER

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I 1 3 OPERATIONS REFUELINO TEST REPORT I .

- Short List of Databaco, Indsx numboro (1-66)

{ Unit 2 July 21, 1992 i 't j

j INDEX ORT NAME PRE-OUT AS TOUND POST-OUT POST-DATE j 50 67T CCW to Excess Letdown HK 11 1 1 10/13/90 i 51 36 Press. Liquid Sample Line 131 224 1402 11/06/90 l 52 67F CCW from Excess Letdown HX 25 1 1 10/13/90 l

{' 53 37 Press. Steam Sample Line 49 3140 588 11/07/90 )

54 68T CCW to P1A 620 103 103 10/09/90 l 55 SPARE O O O l i 56 60F CCW from P1A 620 1330 1330 10/09/90 j 57 39H No. 1 Seal Injection to PIA 34 1 1 10/17/90 j 58 69T CCW to PIB 926 2360 470 11/04/90 1 59 40H No. 1 Seal Injection to PIB 5 2 2 10/17/90 l 60 69F CCW from PIB 535 2200 470 11/04/90 1 61 SPARE O O O j 62 72 Electrical Penetration 1 0 0 10/13/90 ,

63 42H Reactor Hakeup Water Supply 122 14 14 10/14/90 l l 64 85 Eddy Current cables 1 1 270 11/06/90 65 73 Electrical Penetration 11 1 1 10/18/90  !

1 66 71 Electrical Penetration 0 2 2 10/18/90 I Grand Total 15769 26512 21973 j ....... ........ ........

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OPERATIONS REFUELING TEST REPORT j

Snort LiGt of Databaco, Ind3x numbers (1-66)

Unit 2 July 21, 1992 1-INDEX ORT # NAME PRE-OUT ONE-TEST POST-OUT POST-DATE

! 01 12 Fuel Transfer Tube Flange Seal 34 276 276 10/31/91 02 43H Containment Sampling Line 4 5 5 10/01/91 03 13- Equipment Hatch Flange Seals 5 10 10 10/30/91 1 04 44H PACVS Vent Line 4 12 12 10/01/91 i 05 Td-20U El. 66' Personnel Hatch Test 360 657 657 11/07/91 06 SPARE O O O

! 07 TS-10L El. 26' Personnel Hatch Test 312 4200 4200 11/07/91 l 08 46H Auxiliary Charging Line 4 1 1 10/14/91 09 75 Mechanical Penetration 1148 47 47 10/19/91-

, 10 47H Instrument Air Supply 1823 1624 1624 10/11/91 11 76 Mechanical Penetration 0 0 0 10/19/91 l

12 48H Instrument Air Supply 505 484 317 10/11/91

! 13 77 Mechanical Penetration 0 13 13 10/19/91 l 14 49 Service Air Supply 580 80 80 50/28/91 l 15 78 Mechanical Penetration 12 0 0 10/21/91 .

j 16 50H PRT to Gas Anal. Sample Line 4 3 3 10/18/91 l 17 79 Mechanical Penetration (Xfer Tube) 70 0 0 10/31/91 18 51 A Steam Generator Sample Isol Valve 933 1627 1627 10/10/91 ,

19 80 Mechanical Penetration 9 2 2 10/08/51 +

20 52 B Steam Generator Sample Isol Valve 8 27 77 11/08/91 21 81 Mechanical Penetration 13 3 3 10/01/91 22 53H RCDT to Gas Anal. Sample LLne 1 8 8 10/18/91  ;

i 23 82 Mechanical Penetration 1 4 4 10/22/91 l 24 54 B Steam Generator Blowdow- (5958) 1706 1940 1940 10/19/91

! 25 83 Mechanical Penetration 1 1 l'10/23/91 26 55 A Steam Generator Blovidowa (5YS9) 217 1013 1813 10/19/91 l l 27 84 Mechanical Penetration 2 5 5 10/23/91 1 l

28 56 Heating Steam to Containment 311 3 3 10/01/91.

29 25H RCDT Pump Suction Line 312 27 27 11/01/91 30 57 Containment Condensato Return 55 84 84 10/09/91 31 26H Letdown Line *; 2C9 2/9 J 10/12/91 '

32 58 -Containment Test Connection 31 22 22 10/22/9?,

33 27H RCP Seal Ra. urn 1f 0 - 161 -181 10/09/91 34 59 862A Sprav Discharge Check -1785 1222 1222 11/04/91 j 35 28 Dominera7.ced Water Line 76 5 5 11/04/91 36 60 862B Spray Discharge check 534 138 138 11/04/91 37 SPARE O O O 38 61 Sump 'A' Drain to' Aux. Building 6 I 1 11/03/91

! 39 30H RCDT &'PRT Vent 1 4 4 10/13/f1

! 40 TS-36E Purge Exhaust 177 917 5i7.11/07/93 ,

41 31 N'2 Supply to Prt 32 9730 0 10/08/91 42 TS-36S Purge Supply. 183' 2610 2610 11/07/91  !

43 32 N'2 Supply to SY acewmulatora 357 271 271 09/30/91 44 64H RE-211 & RI-112. Supply 612 850 850 10/14/91 45 33H PACVS Return sine 4 7 '7 09/30/91 46 65H 'RE-211_& RE-212 Return 400 447 447 10/14/91 47 34 Charging Line Check Valve 11 '11 11 10/14/91 48 66T Containment Presoura 35- $51 551 10/01/91

49 35 Hot Leg Sanple 4 224 224 10/16/91 l  !

I i POINT BEACH NUCLEAR PLANT ,

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it-t* OPERATIONS REFUELING TEST REPORT I

Short List of Database, Index numbers (1-66) i Unit 2 July 21, 1992 i

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i ENDEX ORT # .M AME PRE-OUT ONE-TEST POST-OUT POST-DATE j _________ _________.__________.....__._____________________....__________.....__..____...__

50 677 CCW to 3xcess Letdown HX 1 4 12 11/02/91 j 51 36 Press. Liquid Sample Line 2500 2522 15 11/09/91-l 52 67F CCW froir Excecs Letdown HX 1 4 4 10/01/91 i 53 37 . Press. Steam Sample Line 588 1420 50 11/03/91

! 54 68T CCW to P1A 103 106 177 10/27/91

! 55 SPARE O O O j 56 68F CCW from PIA 1330 57 57 10/04/91

57 39H No. 1 Seal Injection te P1A 1 2 2 10/03/91 i 58 69T CCW to PIB 470 3003 397 11/02/91 l

59 40H No. 1 Seal Injection to PIB 2 6 6 10/03/91 4 60 69F CCW from P1B 470 3 87 11/02/91 l 61 SPARE O O O i 62 72 Electrical Penetration 0 1 1 10/01/91 j 63 42H Reactor Makeup Water Supply 14 30 30 10/22/91 l 64 85 Eddy current cables 270 1972 132 11/05/91 l

65 73 Electrical Penetration 1 1 1.10/01/91 j

66 71 Electrical Penetration 2 8 8 10/08/91 f Grand Total 18565 39095 21088 t

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POINT BEACH NUCLEAR PLANT 12 -

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9.0 COMMENTS ON VALVES WITH LEAKAGE APPROACHING OR EXCEEDING 0.6L.

- AT STANDARD TEMPERATURE AND PRESSURE l TS 36 (1990)

IA-876, check valve to boot seal for purge supply valve (V2),

i was sticking and not permitting sufficient air flow to boct seal. The leakage rate of 2240 scem for the purge supply i valve (V2) is in excess of administrative limits, but less than the limits specified in Technical Specifications

, Section 15.4.4.III.B. IA-876 was replaced during the following refueling outage (U2R16).

ORT 67 (1991)

! Check valve, 2CC-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 qualification of the leakage rate. A second test with a higher volume test rig was performed and the check valve seated with a resulting leakage rate of 4 sccm. Maintenance was then performed on the valve to determine the cause for not seating the first time. The valve seat was cleaned and a new O-ring installed. Post-maintenance testing was completed

satisfactorily with a leakage rate of 12 secm. (Licensee Event Report No. 91-004-00, 11/15/91)

ORT 31 (1991)

, Diaphragm valve, 2RC-595, nitragen s.gply to the pressurizer l relief tank, had an as-found *.eakage rate of 9730 sccm. This leakage rate is in excess of administrative limits, but less than the limits specified in Technical Specifications Section 15.4.4.III.B. The cause of the excess leakage was the result of the stem travel jack nut on the valve being too tight and thus preventing the valve from fully closing. The

stem lock nut was adjusted and post-maintenance testing was competed satisfactorily with a leakage rate of 0 sccm.

(Not reportable, but covered in Licensee Event Report i No. 91-004-00, 11/1S/91) l ORT 36 (1991)

Globe valve, 2SC-966B, pressurizer liquid sample line, had an as-found leakage. rate of 2520 sccm. This leakage rate is in excest. of administrative limits, but less than the limits specified in Technical Specifications Section 15.4.4.III.B.

Investigation revealed a crack in the valve body starting below the valve seat and extending to the inlet side of tha valve. The valve body was replaced and post-maintenance testing was completed sahisfac torily with a leakage rate of i 15 sccm. (Not reportable, but. covered in Licensee Event Report No. 91-004-00, 11/15/91)

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