ML20207E532

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Summary Rept:1986 Unit 2 Integrated Leakage Rate Test
ML20207E532
Person / Time
Site: Point Beach NextEra Energy icon.png
Issue date: 12/29/1986
From:
WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20207E460 List:
References
NUDOCS 8701020200
Download: ML20207E532 (17)
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SUMMARY

REPORT 1986 UNIT 2 ILRT TABLE OF CONTENTS p

1.0 General Data i 2.0 Technical Data

, 3.0 . Test Data O'

' 4.0 Analysis and Interpretation 5.0 Type C Leakage Valve Adjustments 6.0 Type B Tests Performed Between Refuelings 7.0 Type C Tests Performed Between Refuelings 8.0 Type B and C Test Summary 9.0 Comments on Valves With Excessive Leakage 8701020200 DR 861229 ADOCK 05000301 PDR

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' REPORT OF REACTOR CONTAINMENT BUILDING INTEGRATED

.. LEAKAGE RATE TEST FOR POINT BEACH UNIT 2

.1.0 GENERAL DATA 1.1' Ownerf- Wisconsin Electric Power Company ,

-1.2 Docket Number 50-301 1.3 Location - TVo Rivers, Wisconsin

-1.4 Containment Description - 3% foot pre-stressed post-tensioned p concrete cylinder with inch welded ASTM A-442 steel liner 1.5 Date Test Was Completed - October 2, 1986 2.0 TECHNICAL DATA 2.1 ' Containment Net Free Volume - 1,000,000 cubic feet e

2.2 Design' Pressure - 60 psig 2.3 Design Temperature - 286*F 2.4 Calculated Accident Peak Pressure (Pac) - 53 psig 2.5 Calculated Acc* dent Peak Temperature (Tac) - 286*F 3.0 TEST DATA 3.1 Test Method - Absolute 3.2 Data Analysis Technique - Total Time 3.3 Test Pressure 30.4 psig 3.4 Maximum Allowable Leak Rate, L, - 0.400%/ Day 3.5 Reduced Pressure Allowable Leak Rate, L - 0.268%/ Day t

3.6 Allowable Operational Leak Rate, 75% L t- 0.201%/ Day 3.7 Integrated Leakage Rate Test Results Total Time Leak Rate 0.026%/ Day 95% Upper Confidence Level 0.102%/ Day 3.8 Verification Test Results 3.8.1 Imposed Verification Leak Rate 0.268%/ Day (5.68 scfm) 3.8.2 Total Time Analysis 0.312%/ Day 3.8.3 Verification Test Limits Lower Limit 0.227%/ Day Upper Limit 0.361%/ Day

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, Containment' Volume-Changes ~ 0.003%/ Day

, Penetrations Not-Aligned 0.001%/ Day-l Nitrogen Additions - f' O.009%/ Day Total 0.013%/ Day

- :3.10 .As-found Leak Rate 0.115%/ Day

' Corrected for penalties at 95%

upper confidence. level e.

, .4.0 ANALYSIS AND INTERPRRTATION.

.. The fourth periodic. Type'A integrated leakage rate test (ILRT) of the Point

. . Beach Nuclear Plant Unit 2 containment was performed September 29 to 0ctober 2, 1986 with satisfactory results. The testing program was conducted in accordance with the' requirements of the Point Beach FSAR Chapter 15,L" Technical Specifications," Paragraph 4.4 containment tests.

During the ILRT, several~ penetrations were not in post-LOCA alignment. The

. correction to.the ILRT results is 0.001%/ day.

Containment water volume changes were 3*16.9 cubic feet. The correction to the ILRT-results is 0.003%/ day.

Nitrogen additions to_the containment were 14.17f26.27 lbm. The correction to the ILRT results'is 0.009%/ day.

The total leakage rate correction for penetrations not in post-LOCA alignment, water volume changes and nitrogen additions is 0.013%/ day.

The calculated leakage rate during the ILRT was 0.026%/ day (total time).

The calculated 95% upper confidence level was 0.102%/ day (total time).

Adding the total. leakage rate corrections for penetrations not in post-LOCA alignment and containment water level changes yields the corrected leakage rates as follows:

Leakage Rates, percent per day Total Time Leakage Rate UCL Calculated 0.026 0.102 Corrections 0.013 0.013 As-Found 0.039 0.115 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 r containment and systems and components penetrating primary prima,y containment does not exceed the allowable leakage rates specified in the Point. Beach Nuclear Plant Unit 2 FSAR and Technical. Specifications.

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, - 5.0. TYPE C LEAKAGE VALVE ADJUSTMENTS (Penalties) i,Due to the test'confdguration of the. containment, eight penetrations were not subjected to the 30 psig Type "A" test pressure. These penetrations,

justification, and Type "C" test results are identified below

Type "C" Results

Penetration Justification (thnimum Pathway)

, CVCS Supply Line In use to control primary 2 scem I

(#26). . system pressure CVCS Letdown Line In use to control primary 101 scem

(#10) system pressure

.RCP "A" Seal' Injection Maintain flow of clean 6 seem Line (#29A) water through RCP seals

'RCP "B" Seal Injection Maintain flow of clean 1 seem Line (#29B) water through RCP seals Service Air Line Modified to allow for 495 seem

(#33C) containment depressurization Containment Pressure Modified to provide a O scem Sensing Line (#31A) -pressure point for Type "A" test purposes Auxiliary Charging . Proper venting of line is 28 seem Line (#32C) not possible when seal injection lines are in use PACVS Supply Line Modified to provide a flow 0 seem

(#31C)- verification path NOTES 1. Type "C" leakage tests were performed prior to Type "A" test to assure "as-found" leakage.

2. PACVS sample line (31B) was used as a pressure point for the Type A test. The point of attachment for the ILRT pressure sensing line was the same point to which the local leak rate test rig is attached. For this reason the penetration was not leak tested prior to attaching the tubing to the ILRT instrumentation. No penalty was factored in for this penetration.

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1986 Unit 2 ILRT m Page 4 y

y 6.0i TYPE B' TESTS PERFORMED BETWEEN REFUELINGS Procedure Component Date Leak Rate TS Lower Personnel Hatch 8/24/82 343 seem TS-10 Upper Personnel Hatch 8/25/82 14 scem TS-10 Lower Personnel Hatch 11/8/82 1386 sccm TS-10 ~ Lower Personnel Hatch 11/10/82 '348 scem TS-10' Upper Personnel Hatch .11/11/82 875 seem TS-10 Lower Personnel Hatch 11/4/83 1240 seem TS-10 Upper Personnel Hatch 11/4/83 537 scem TS-10 Lower Personnel Hatch 5/2/84 1060 scem TS-10 Upper Personnel Hatch 5/2/84 160 scem TS-10 ~ Lower Personnel Hatch 5/1/85 842 scem TS-10 Upper Personnel Hatch 5/1/85 412 seem TS-10 Lower Personnel Hatch 4/29/86 439 scem TS-10 Upper Personnel Hatch 4/28/86 1837 sccm

'7.0 TYPE C TESTS PERFORMED BETWEEN REFUELINGS Procedure Penetration Date Valve (s) Tested Leak Rate TS-35 V1 9/30/82 Purge Exhaust 310 scem TS-35 V2 9/30/82 Purge Supply 190 seem TS-35 V1 1/21/84 Purge Exhaust 1995 scem TS-35 V2 1/21/84 Purge Supply 846 scem TS-35 VI 8/3/84 Purge Exhaust 25 seem TS-35 V2 8/3/84 Purge Supply 106 scem TS-35 V1 3/29/85 Purge Exhaust 153 seem TS-35 V2 3/29/85 Purge Supply 22000 scem TS-35 V1 5/25/86 Purge Exhaust 96 scem TS-35 V2 5/25/86 Purge Supply 251 scem ORT-61 71 6/15/82 Sump A to Aux 13 sccm Bldg Sump ORT-51 34C 1/24/86 2CV-2083 only 251 scem 3/11/86 2CV-2083 only 2 scem 3/11/86 A S/G Sample 14 scem Isolation 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 the 1982 and 1986 ILRT's.

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1986 Unit 2;I'RT L

Page 5 REFUELING CONTAINMENT PENETRATION -

LEAKAGE RECORD Unit # 2 _

Refue)ing U2R8 Refueling U2R9 Date 1982-1983 TYPE "C" TESTS ' April - Nay 1982 March to. July 1983 AS-FOUND LEAKAGE AS-FOUND LEAKAGE LEAKAGE- AFTER LEAKAGE AFTER ORT seca REPAIR 'seca REPAIR NO. PENETRATION TITLE seca scen 25 9 RCDT Pump Suction Line 28 N/A 19 N/A (Enter highest test) 26 10 Letdown Line (6) 5 N/A 8 39 (Enter highest test) 27 11 RCP Seal Water Return Line (5) 22 N/A 20- 521 (Enter highest test) 28 12A DI Water Line 6 N/A 78 N/A 29 12B Test Connection 1 N/A 6 N/A 30 12C RCDT and PRT Vent 49 N/A 398 N/A (Add tests together) 31 14A Nitrogen Supply to PRT 0 N/A 0 N/A 32 14C Nitrogen Supply to the Accumulators 13 N/A- 202 N/A 33 25C PACVS Return Line 1 N/A 27 N/A 34 26 Charging Line Check Valve 46 N/A 2 N/A 35 28A Hot Leg Sample 7000 4000 8000 4 36 28B Pressurizer Liquid Space Sample 2000 70 1638 N/A 37 28C Pressurizer Steam Space Sample 139 N/A 1214 N/A 38 39 29A Seal Injection Supply RCP "A" 2 N/A 18 N/A 40 29B Seal Injection Supply RCP "B" 1 N/A 12 N/A 41 30A Test Connection 14 N/A 44 N/A F

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i'; Page 6 REFUELING CONTADRIENT PENETRATION

~ LEAKAGE RECORD q

Unit # 2 kefueling U2R10 Refueling U2R11 Date 1964-1985 TYPE "C" TESTS Sept to Dec 1984 Oct.to Nov 1985 AS-FOtBID LEAKAGE AS-FOtBID LEAKAGE LEAKAGE AFTER LEAKAGE AFTER ORT scca REPAIR scca REPAIR' NO. PENETRATION TITLE seca' seca 25 9 RCDT Pump Suction Line- 5 N/A 4 N/A j (Enter highest test) l 26 10 Letdown Line-(6) 22 860 -27 . N/A j (Enter highest test) l 27 11 RCP Seal W3ter Return Line (5) 685 59 308 N/A (Enter highest test)

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4 28 12A DI Water Line 20- N/A 10 N/A 29 12B Test Connection 10 N/A -N/A(8) N/A 30 12C RCDT and PRT Vent 2009 1335 971 N/A

! (Add tests together) 1 31 14A Nitrogen Supply to PRT 110 N/A 18 15 l 32 14C Nitrogen Supply to the Accumulators 39 N/A 132 N/A 33 25C PACVS Return Line 2 N/A 0 N/A 34 26 Charging Line check Valve 35 M/A 13 32 35 28A Hot Leg Sample 18 N/A 82 625 36 28B Pressurizer Liquid Space Sample 6 N/A 2000 N/A Pressurizer Steam Space Sample 37 28C 51 N/A 24 N/A 38 39 29A Seal Injection Supply RCP "A" 3 N/A 4 11

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40 29B Seal Injection Supply RCP "B" 7 N/A 4 10 41 30A Test Connection

  • 17 N/A N/A(8) N/A

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, LEAEAGE RECORD ,

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Date- 1982-1983 TYPE "C" TESTS 3 April.-'Nay 1982-- March.to(July]l983' AS-F0ERS LEAEAGE ,AS-F0g g smanne 4

LEAEAGE AFTER LEAEAGE AFTER

! ORT .sccm- REPAIR-  : secai . REPAIR-3 NO. PENETRATION TITLE- seca- - seca -

42 30C Reactor Nakeup Nater Supply. -0 N/A 1- .4= -N/A: .

(Enter.highestLtest)
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43 31B Contairueent Sample Line -33 -N/A 6e N/Ac

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44 31C PACVS Vent Line 1- N/A :22 N/A

!, (Add tests together) ,

i 45 46 32C Auxiliary Charging Line. O N/A- .640 .M/A 47 33A Instrtament Air Supply 3047 230 N/A- - 327 :- N/A-(Enter highest test) ,f 48 33B Instrument Air Supply 3048 41- N/A 76 N/A-(Enter highest test)

, t 49 33C Service Air Supply 125000 9 -0; N/A l 50 34A Sample Line PRT to Gas Analyzer 2 N/A 4' N/A (Add tests together) f 51 34C "A" SG Sample Line (1, 2, 4) N/A N/A .N/A N/A 52 34B "B" SG Sample Line (1, 2, 4) N/A N/A N/A N/A-53 34D Sample Line RCDT to Gas Analyzer 1 N/A .0 N/A (Enter highest test) -

i 54 50 "B" SG Blowdown (1, 2, 3, 4) N/A N/A 19 N/A ,

} 55 51 "A" SG Blowdown (1, 2, 3, 4) N/A N/A 8 N/A 5

56 52 Heating Steam Supply 272 N/A 178 N/A 57 53 Condensate Return from Containment 175 N/A 18000 .2 l 58 56 Contairunent Test Connection 25 N/A 38 N/A ,

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Date' 1984-1985 TYPE "C" TESTS  : Sept lto'Dec'1984i Oct to.Noril985,.,;

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'N AFTER ORT . seca . REPAIR' seca MPAIR ~

NO. PENETRATION TITLE a' !seca acca -

42 30C Reactor Nakeup Water Supply 2 N/A <17 N/A.

(Enter highest test). ~ -

43 31B- . Containment Sample Line, .5 .

N/A: N/A-(Enter highest test). _

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44 31C PACVS Vent Line. ..

.9 'N/A '

0- .N/A (Enter highest, test). -

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46 32C Auxiliary Charging Line. 22- N/A 157 N/A -

47 33A Instrument Air Supply 3047 1 N/A. 490 N/A (Enter highest test) 48 33B Instrument Air-Supply 3048 9 N/A. -353 , N/A' .

(Enter highest test) 49 33C Service Air Supply 1479 N/A 136000 528, 50 34A Sample Line PRT to. Gas Analyzer 28 N/A 12 N/A (Add tests together) 51 34C "A" SG Sample Line (1, 2, 4) N/A N/A -4 N/A 52 34B "B" SG Sample Line (1, 2, 4) N/A N/A 9  : N/A 53 34D Sample Line RCDT to Gas Analyzer .49 N/A 6 N/A-(Enter highest test) 54 50 "B" SG Blowdown (1, 2, 3, 4) 42 8 84 N/A 55 51 "A" SG Blowdown (1, 2, 3, 4) 151 N/As 172 N/A 56 52 Heating Steam Supply 3 98 .383 N/A-57 53 Condensate Return from Containment 58 110 (7) 172 58 56 Containment Test Connection 73 72 52 N/A

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.1986 Unit 2 ILRT @

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REFUELING CONTAIIGENT PENETRATION

  • LEAKAGE RECORD ~

l-Unit #- 2 Refueling U2R8 Refueling U2M9 Date '1982-1983 TYPE "C" TESTS- April - May 1982 .Narch to July 1983 AS-FO'JND LEAKAGE AS-FOtBID LEAKAGE LEAKAGE AFTER LEAKAGE AFTER ORT seca REPAIR secm - REPAIR NO. PENETRATION TITLE seca seca 59 54 P14A Spray Ptump Discharge Check 120 263 40. 1480 Valve 60 55 P14B Spray Pump Discharge Check 882 1340- 3000- 7 Valve 61 71 Sump "A" Drain to Auxiliary 2 N/A 12 N/A Building 62 V1 Purge Supply 420 N/A 511 N/A l 63 V2 Purge Exhaust 20 N/A 296 N/A

. 64 X1 R11/R12 Suction Stipply 159 N/A 147 190 l (Enter highest test) 1 I 65 X2 R11/R12 Discharge Return 6000 304 60000 5 4 (Enter highest test) i 66A 31A Pressure Test of PT-945 and 946 3 N/A 0 N/A i 66B 14B Pressure Test of PT-947 and 948 0 N/A 0 N/A

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66C 32A Pressure Test of PT-949, 950 and 969 8 0 0 N/A 67 19 & 20 CCW to and from Excess Letdown HEX 158 N/A 14 N/A l (Add tests together) 68 15 & 17 CCW to and from "A" RCP 6 N/A 5 190 (Add tests together)

! 69 16 & 18 CCW to and from "B" RCP 377 N/A 337 N/A (Add tests together) ..

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. REFUELING CONTAllGIENT PENETRATIONi .

LEAKAGE RECORD , . '7" a

Unit # 2' Refueling U2R10. Refueling U2E11 Date 1984-1985 TYPE "C" TESTS Sept to Dec 1984. _Oct to Nov 1985:

AS-FOUND LEAKAGE AS-FOUND LEAKAGE ,

tEAx4GE ArrER LEAxAGE AFTER o.-

ORT scem - REPAIR scca E REPAIR 2 NO. PENETRATION TITLE seca scca , - +,

59 54 P14A Spray Pump Discharge Check 3000 .42 3000 1712 Valve . ,j .

60 55 P14B Spray Pump Discharge Check .4900 2300_ 24000_ 6-Valve 61 71 Sump "A" Drain to Auxiliary- 3 N/A 0 N/A Building .

62 V1 Purge Supply 790 .N/A 246 968 -

63 V2 Purge Exhaust .518 N/A 21000- 298 64 XI R11/R12 Suction Supply 1350 N/A 405 N/A (Enter highest test) -

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65 X2 R11/R12 Discharge Return 448 N/A 432 N/A.

(Enter highest test) 66A 31A Pressure Test of PT-945 and 946 0 N/A 7 N/A 66B 14B Pressure Test of PT-947 and 948 0 N/A 6 N/A 66C 32A Pressure Test of PT-949, 950 and 969 0 N/A 7 N/A 67 19 & 20 CCW to and from Excess Letdown HEX 308 N/A- 218 N/A (Add tests together) 68 15 & 17 CCW to and from "A" RCP (7) 601 (7) 2010 (Add tests together) 69 16 & 18 CCW to and from "B" RCP 59 N/A 10091 1811 (Add tests together)

END OF TYPE "C" TESTS

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' REFUELING CONTAIIRIENT PEIETRATION.

LEARAGE RECORD -

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Unit'#' 2 .

Refueling U2R8  ; Refueling U2R9 'H Date- -1982-1983 TYPE "B" TESTS- _

' April: May 1982! March to July.1983.

4 AS-y0guo r.raram . AS-y0tBID LEARAGE LEARAGE AFTER- r.raram AFTER .

ORT seca ' REPAIR seca : ' REPAIR-NO. PENETRATION TITLE ' seem - '

scce 12 No Number Fuel Transfer Tube Flange .0 N/A c238: N/A -

13 No. Number- Equipment. Hatch Flange; 3 N/A: -13 :N/A ,

70 71 E56 Electrical Penetration 1- .0: 7 N/A 72 E20, 22 Electrical Penetraton- 0 2 1 N/A, 73 El Electrical Penetration 0 N/A 2 N/A 74 75 P-50, 51 Mechanical Penetration Test 1120 N/A- '1278- N/A-P-52 & 53 ,

76 P-58 Mechanical-Penetration Test 2 N/A. 1- N/A 77 P-57 Mechanical Penetration Test 6 N/A1 0 N/A-78 P-69 & 70 NPT (Sump "A" & "B" Drain Lines) 5 N/A ,

44 :N/A:

l 79 No Number MPT (Fuel Transfer Tube Penetration) 0 N/A- 0 N/A i 80 P-13, 27 Mechanical Penetration Test 4 N/A, 7 N/A

! & 29 1

81 P-37, 38,

, P-36, 40 Mechanical Penetration Test 258 3 0 N/A l P-48, 45

P-44, 46 82 P-S & 6 i P-47, 43 Mechanical Penetration Test 10 N/A 0 N/A l P-39, 35 P-55, 54

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y 1986, Unit! 2 ILRT ."

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REFUELING CONTAINMENT PENETRATION .

LEAKAGE RECORD Unit # 2 . Refueling U2R10 . Refueling U2R11 Date -1984-1985 TYPE "B" TESTS ~ Sept to Dec 1984 Oct to Nov 1985

.AS-FOUND LEAKAGE AS-FOUND LEAKAGE LEAKAGE AFTER LEAKAGE AFTER ORT scem- REPAIR scca REPAIR NO. PENETRATION TITLE scem seem 12 No Number Fuel Transfer Tube Flange 5 N/A 198 N/A 13 No Number Equipment Hatch Flange 6 4 1 N/A-J 70 71 E58 Electrical Penetration 0 N/A 10. N/A 72 E20, 22 Electrical Penetraton 16 N/A 0 N/A 73 El Electrical Penetration 1 N/A 1- N/A-74 75 P-50, 51 Mechanical Penetration Test 775 N/A 535 N/A, P-52 & 53 76 P-58 Mechanical Penetration Test 7 N/A 11 N/A 77 P-57 Mechanical Penetration Test 4 N/A 11 N/A 78 P-69 & 70 MPT (Sump "A" & "B" Drain Lines) 4 N/A :10 N/A 79 No Number MPT (Fuel Tranafer Tube Penetration) 0 N/A 48 N/A 80 P-13, 27 Mechanical Penetration Test 0 N/A 10 N/A

& 29

, 81 P-37, 38, P-36, 40 Mechanical Penetration Test 0 N/A 38 N/A P-48, 45

! P-44, 46 1

, 82 P-5 & 6 .

] P-47, 43 Hechanical Penetration Test 0 N/A 45 N/A

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'1986 Uni'p 2 ILRT : E.

LPage;13 ~' _ q REFUELING CONTAINNENT. PENETRATION- -,

LEAKAGE RECORD

' Unit # 2 Refueling U2R8 Refueling U2R9 '

Date 1982-1983 TYPE "B" TESTS April - May.1982 March to July 1983 AS-FOUND LEAKAGE AS-FOUND LEAKAGE .,

.. LEAKAGE - AFTER. LEAKAGE AFTER ORT sccm REPAIR sccm REPAIR.

-NO. PENETRATION TITLE seca - seca i

.83 P-15, 16 17, 18 Mechanical Penetration Test 19 N/A 2 N/A .

10, 11 84 P-7, 8, Mechanical Penetration Test 24 N/A 0 N/A 9 & 22 ,

TS-10 Upper Personnel Hatch 55 N/A 1566 N/A TS-10 Lower Personnel Hatch 975 N/A 861 N/A 9

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1986 Unit 2 ILRT .

Page 14 REFUELING CONTAINMENT PENETRATION -

LEAKAGE RECORD Unit # 2 Refueling U2R10 Refueling U2R11 Date 1984-1985 TYPE "B" TESTS Sept to Dec 1984 Oct to Nov 1985 AS-FOUND LEAKAGE AS-FOUND LEAKAGE LEAKAGE AFTER LEAKAGE AFTER ORT sccm REPAIR scem REPAIR NO. PENETRATION TITLE scem seem 83 P-15, 16 17, 18 Mechanical Penetration Test 26 N/A 17 N/A 10, 11 84 P-7, 8, Mechanical Penetration Test 6 N/A 9 N/A' 9 & 22 TS-10 Upper Personnel Hatch 1250 N/A 18 N/A TS-10 Lower Personnel Hatch 1530 N/A 1099 N/A END OF TYPE "B" TESTS

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I Notes for Type B & C Test Summary Tables B

$ 1. Modification E-168, completed April 6, 1978, removed the containment

[ isolation signal from the steam generator blowdown and sample valves.

[ Following this modification, leak testing of these valves was no longer

[ required.

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2. In the C. W. Fay to H.R. Denton letter dated May 2, 1980, WE committed to -

g restore the containment isolation signals back to the steam gener ator jg blowdown and sample valves but not test them per Appendix J.

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gg 3. Modification M-731, completed June 1983, installed an additional automatic -

E containment isolation valve in each blowdown line. These new valves are E located inside containment in series with the existing valves. Periodic leak testing of the new isolation valves as well as the original isolation *

[

5 valves commenced following installation during the 1983 refueling outage.

4. The pump and valve test program submitted to the NRC on March 28 1985 E L
g called for resumption in leak testing of the blowdown sample valves and commencement in leak testing of the new blowdown valves inside l

l- containment. Although the blowdown line isolation valves outside g containment receive a containment isolation signal, they cannot be relied t upon for isolation purposes since they are not seismically installed.

g These valves were not included in the test program although they will > ..

jg continue to be leak tested until the containment isolation signal is g removed.

i j 5. Modification M-682, completed July 1983 installed an additional automatic  ;

E containment isolation valves in the reactor coolant pump seal return line.

E The new valve is ' cated inside containment and in series with the existing isolation valve. Periodic leak testing of the new isolation valve commenced following installation during the 1983 refueling outage.

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6. Modification M-684, completed July 2983, installed an additional automatic 5 containn ent isolation valve in the letdown line. The new valve i s located l inside cantainment and in series with the existing isolation valve.

7 Periodic leak testing of the nev valve commenced following installation i during the 1983 refueling outage.

7. Valve leakrate could not be determined. Test volume could not be pressurized due to excessive leakage.

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8. Based on a review of containment penetrations, done by WE, documented in . .

the Moylan to Zach memo, dated February 2, 1984, it was determined that g these penetrations were not required to be Type C tested.

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I 1986 Unit 2 ILRT Page 16 9.0 COMMENTS ON VALVES WITH LEAKAGE APPROACHING OR EXCEEDING 0.6L_ AT STANDARD TEMPERATURE AND PRESSURE l

Ort 49 (1982)

Check valve SA-2C, service air supply to unit 2 containment, was discovered leaking at 125,000 sec per minute. Upon investigation it was discovered that the clapper arm bracket was out of alignment preventing the disc from seating properly. The clapper arm bracket was adjusted and the valve was retested. The after repair leak rate was 9 sec per minute. This item was not reportable.

Ort 68 (1984)

Check valve 2-755A, "A" RCP component cooling water supply check valve, appeared to stick open during the initial Type C test. The required test pressure could not be achieved, precluding quantification of the leakage rate. Upon disassembly it was discovered that one of the discs hinge pin bushings had migrated toward the disc's swing arm resulting in the valve

-disc intermittently sticking. The valve was repaired and satisfactorily

. retested. After repair leak rate was 601 sec per minute. (Licensee Event Report No. 84-008/00,12/11/84.)

Ort 68 (1985) .

Check valve 2-755A, "A" RCP component cooling water supply, appeared to stick open during the initial Type C test. The required test pressure could not be achieved, precluding quantification of the leakage rate.

Followup maintenance could not find any prchlem with the valve. The valve was lapped and returned to service. The after repair leak rate was 1,680 sec per minute. (Licensee Event Report No. 85-002/00, 12/18/85.)

ORT 49 (1985)

Check valve SA-2C, service air supply, was discovered leaking at 136,000 sec per minute. Up on disassembly it was discovered that rust and scale had built up on the seat and disc surfaces. The valve was cleaned and reassembled. The after test leak rate was 528 sec per minute. (Licensee Event Report 85-002/00, 12/18/85.)

ORT 57 (1985)

Manual valve, HV-287, heating condensate return from Unit 2 containment was discovered to be leaking in excess of 20,000 sec per minute. (Limit of leak tester.) The required test pressure could not be achieved precluding quantification of the leak rate. The valve seating surfaces were lapped, valve internals were cleaned and the stem packing was replaced. The after repair leak rate was 172 sec per minute. (Licensee Event Report 85-002/00, 12/18/85.)

A

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