ML20112A564
| ML20112A564 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/31/1984 |
| From: | Lacey W DUQUESNE LIGHT CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| ND1SS1:2381, NUDOCS 8503180365 | |
| Download: ML20112A564 (21) | |
Text
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DUQUESNE LIGHT COMPANY Beaver Valley Unit No.1 LOCAL LEAK RATE TEST December 1984 TYPE ' B' AND ' C '
8503180365 841221 PDR ADOCK 05000334 p PM o
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DUQUESNE LIGHT COMPANY Beaver Valley Power Station TABLE OF CONTENTS Pege No.
Introduction I A. Type 'B' Test Results 2 B. Type 'C'-
Test.Results 8 9
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, INTRODUCTION. - Local Leak Rate Test 1984 This report containe a discussion of the Beaver Valley Power Station Unit No. 1 Type 'B' and Type 'C' Local Leak Rate Testing performed during the 1984 Refueling Outage. It has been prepared in accordance with the requirements of 10 CFR 50, Appendix J, Section V, Paragraph B.3. Part A summarizes the results of the Type 'B' Testing, and Part B summarizes the results of the Type 'C' Testing. It should be noted that Type 'A' Leak Testing was not performed during the 1984 Refueling Outage. Type 'A' Testing was last successfully completed during the 1982 Refueling Outage.
The combined leakage rate for all penetrations and valves subject to Type 'B' and 'C' Tests must be less than 60 percent of La (the maximum
- allowable leakage rate of containment) in order to meet plant Technical
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Specifications. La is 0.10 percent by weight of the Containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at Pa (53 psia).
La equals 0.10 percent by weight of Containment air volume (1,800,000 Ft') at 53 psia (0.001 x 1,800,000 x 53/14.7) = 6489.80 SCF/D 60 percent of La equals 3893.88 SCF/D.
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4 A. TYPE 'B' TEST RESULTS
.s Local Leak' age Rate Testing for the Containment Electrical Penetrations (Type 'B' Testing) was performed during the months of November and December, 1984. The results were found to be acceptable.
The Local Leakage Rate Testing for the Containment Electrical Penetra-tions measures the leakage through the penetration 0-ring seals on the bolt-on ,
flanges and the leakage from the penetration canister. A summary sheet is included listing the electrical penetration leakage rates.
Other Type 'B' Leakage Rate Tests measure the leakage through the Per-sonnel Airlock, the Emergency Personnel Airlock Flanges, the Fuel Transfer Tube, and Penetrations #111 and #112. The results of these tests are also included on the summary for reference.
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A. TYPE 'B' TEST RESULTS (Cr.ntinuad)
Leakage Leakage Penetration 0-Ring Seal / Canister Penetration 0-Ring Seal / Canister Number (SCCM) Number (SCCM)
- 1-B 2.0 / .01 5-B 2.0 / 2.0
- 1-D 2.0 / .01 5-C 2.0 / 2.0 1-F 2.0/2.0* / N/A 5-D 2. 0- / 2.0
- 2-B 2.0 / .01 5-E. 2.0 / 2.0 82-D 2.0 /' .01 5-F 2.0 / 2.2
- 2-F 2.0 / .01 5-G 2.0 / 29.0 3-A 2.0 / 2.0 6-A 2.0 / 2.0 3-B 2.0 / 2.0 6-B 2.0/2.0* / N/A 3-C 2.0 / 2.0 6-C 2.0 / 2.0 3-D 2.0 / 2.0 6-D 2.0 / 2.0 3-E 2.0 / 2.0 6-E 2.0 / 2.0 3-F 2.0 / 2.0 6-F 2.0 / 2.0 3-G 2.0/2.0* / N/A 6-G 2.0 / 2.0 4.A 2.0 / 3.0 7-A 2.0/3 S* / N/A 4-B 2.0 / 2.4 7-B 2.0 / 5. 0 4-C 2.0 / 33.0 7-C 2.0 / 3. 2 4-D 2.0 -
/ 36.0 7-D 2.0 / 2.0 4-E 2.0 / 2.0 7-E 2.0 / 2.0 4-F 2.0 / 2.0 7-F 2.0 / 2.0 4-G 2.0 / 10.0 7-G 2.0/2.0* / N/A 5-A 2.0 / 2.6 8-A 2.0 / 4.2 i
Totals 46.0 / 103.05 49.5 / 69.6 Page 3
- Inside/Outside of Containment
- Pressure Decay Test Used to Determine Leak Rate Page 3
_. _ . _ _ _ ~_ __. _ __ . - . . . _ _ _ . _ . _ _ . _ , _ _ . . _ .
A. TYPE 'B TEST RESULTS (Centinusd) .
Leakage Leakage Penetration 0-Ring Seal / Canister Penetration 0-Ring Seal / Canister Number (SCCM) Number (SCCM)
. s-B 2.0 / 2.0 11-B 2.0 / 2.0 s-C 2.0 / 2.0 11-C 2.0/2.0* / N/A
.s-D 2.0 / 2.0 11-D 4.0 / 2.0 s-E 2.0 / 2.0 11-E - 2.0 / 6.8 a-F 2.0/2.0* / _N/A 11-F 2.0 / 2.0 s-c 2.0 / 2.0 11-c 2.0 / 2.0 9-A 2.0 / 2.0
- 12-A 2.0 / 2.0 9-5, 2.0 / 2.0 12-B 2.0 / 6.5 9-C 2.0 / 5.0 12-C 2.0 / 2.0 9-D 2.0 / '2 . 0 12-D 2.0 / 12.0 9-E 2.0 / 2.0 12-E 2.0 / 2.0 9-F 2.0 / 2.0 12-F 2.0 / 2.0 9-c 2.0 / 16.0 12-c 2.0 / 2.0 10-A 2.0 / 12.4 13-A 2.0/2.0* / N/A 10-B 2.0 / 34.0 13-B 2.0/2.0* / N/A 10-C 2.0 / 17.7 13-C 2.0 / 2.0 10-D 2.0 / 2.0 13-D 2.0/2.0* / N/A f
10-E 2.0 / 2.0 13-E 2.0 / 10.3 5
10-F 2.0 / 2.0 13-F 2.0 / 5.0 10-c 2.0 / 31.0 13-c 2.0 - / 2.0 11-A 2.0 / 3.8 14-A 2.0 / 2.0 44.0 / 145.9 50.0 / 64.6 I
- Inside/Outside of Containment
! e Pressure Decay Test Used to Determine Leak Rate Page 4
-A. TYPE 'B' TEST RESULTS (Continusd).
6 Leakage Leakage 0-Ring Seal / Canister Penetration 0-Ring Seal / Canister Penetration (SCCM) Number (SCCM)
Number 14-B 2.0 / 2.0 16-A 2.0 / 2.0 14-C 2.0 / 2.0 16-3 2.0 / 2.0 14-D 2.0 -
/ 2.0 16-C ' 2.0 / 2.0 14-E 2.0 / 2.0 16-D 2.0 / 2.0 14-F 2.0 / 2.0 16-E 2.0 / 2.0 14-c 2.0 / 10.0 16-F 2.0 / 2.0 15-A 2.0 / 2.0 16-c 2.0/2.0* / N/A 15-n 2.0 / 2.0 *17-5 2.0 / .01 15-C 2.0 / 2.0 17-D 2.0 /2.0* / N/A 15-D 2.0 / 3.8 17-F 2.0/2.0* / N/A 15-E 2.0 / 4.5
- 18-5 2.0 / .01 15-F 2.0 / 2.0
- 18-D 2.0 / .01 15-c 2.0 / 2.0 18-F 2.0/2.0* / N/A 111 2.0 / 2.0 26.0 / 38.3 36.0 / 14.03
- Inside/Outside of Containment
- Pressure Decay Test Used to Determine Leak Rate 4-Page 5
. = _ . ... . . .. - . . - - - _ . - - . - - . . . .
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, A. TYPE 'B' TEST RESULTS (Continued) ,
l Leakage
. Totals 0-Ring Seal / Canister (SCCM)
Page 3 95.5 / 172.65 4 Page 4 94.0 / 210.5 4 .
Page 5 62.0 / 52.33
.j Total Leakage
'(SCCM) 251.5 / 435.48 l'
Total Leakage 12.78 / 22.14 (SCF/D)
Electrical Penetrations (12/7/84 ) 34.92 SCF/D Personnel Airlock (12/14/84) .461 SCF/D Equipment Hatch Outer Flange (12/16/84) .459 ' SCF/D Equipment Hatch Inner Flange (12/16/84) .468 SCF/D Emergency Personnel airlock (12/18/84) .479 SCF/D Fuel Transfer Tube (12/7/84) .471 SCF/D Penetration #111' (11/26/84) .465 SCF/D Penetration #112 (11/27/84) .465 SCF/D TOTAL Type 'B' Leakage. 38.188 SCF/D Page 6
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- A. TYPE 'B' TEST RESULTS (Continued)
CORRECTIVE ACTIONS RIMMARY The following electrical penetration required maintenance due to a high leak rate:
Per.etration No. MWR-No.- Initical Leakage Final Leakage 6-G Canister 848317 160.SCCM 2.0 SCCM The high leak rate on the 6-G Canister was due to a leaking section of tubing used to pressure check the canister. The tubing was repaired with a High Shear strength adhesive and the canister was then successfully leak tested.
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. B. . TYPE 'C ' TEST RESULTS The purpose of Type 'C ' Testing is to demons trate the integrity of Containment Isolation Valves in accordance with Appendix J of the
. Title 10 Code of Federal Regulations Part 50 and BVPS Technical Specification 3.6.1.2.
A complete series of Type 'C ' Tes ts together with the appropriate
' Type 'B' Tests were performed during the period of October 16, 1984 through December 16, 1984. The results of these tests met the applicable acceptance criteria and are reviewed on- the accompanying tables.
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. Typ2 C Tcat Reculto 1984 Pcrfor::::nca l
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"As Found" "As Lef t" Pene- Valve Valve tration- Valve Date Leakage Leakage Penetration Number Tested Tested (SCF/D)- (SCF/D) Leakage
-1 MOV-CC-112A2 11-12-84 0.465 0.465 CCR-247 3.95 3.95 3.95
- 2 MOV-CC-11283 11-13-84 0.466 0.466 CCR-252 '22.6 22.6 22.6 4 MOV-CC-112A3 11-12-84 7.44 7.44 CCR-251 124.2 124.2 124.2 5 MOV-CC-112B2 11-12-84 0.466 0.466 CCR-248 0.566 0.566 0.566 8 TV-CC-107D1 11-5-84 3.16 3.16 TV-CC-107D2 1.24 1.24 3.16 9 TV-CC-111D1 11-5-84 0.465 .0.465
-TV-CC-111D2 11.28 11.28 11.28 -
11 TV-CC-110D 12-5-84 5.62 5.62 TV-CC-110F1 &
TV-CC-110F2 2.46 2.46 5.62 13 FP-827 10-23-84 0.465 0.465 TV-FP-107 0.465 0.465 0.465 14 TV-CC-110E3 12-6-84 0.469 0.469 TV-CC-110E2 0.469 0.469 0.469 16- TV-CC-111A1 12-14-84 2.28 2.28 TV-CC-111A2 704.366 253.54 253.54 17 TV-CC-103B1 12-4-84 70.23 70.23 TV-CC-1038 136.37 136.37 136.37 18 TV-CC-103C1 12-5-84 23.86 23.86 TV-CC-103C 130.6 130.6 130.6 19 MOV-CH-378 & 34.8 34.8 CH-369 11-13-84 0.465 0.465 34.8 MOV-CH-381 20 SI-42 11-15-84 1.39 1.39 SI-41 0.465 0.465 1.39 Pace 9
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. Typo C: Test Resulto. 1984 Performanco "As Found" "As Left"
- - Valve Valve
.Pene . .
'tration Valve Date Leakage Leakage Penetration Tested Tested Number (SCF/D) (SCF/D) Leakage 24 'RE-14 & RH-16 10-31-84 3.077 3.077 RH-15 4.21 4.21 '4.21 25 TV-CC-105D1 12-4-84 176.24 65.55 TV-CC-105D2 -
34.9 34.9 65.55 26 TV-CC-107El '
12-10-84 177.92 75.2 TV-CC-107E2- 6.25 6.25 75.2 5
27' TV-CC-105El 1 1 84 33.9 33.9 TV-CC-105E2 .564 .564 33.9 28 TV-CH-200A,B Ca 12-14-84 25123 214.28 214.28 HOV-CH-142 &
RV-CH-203 -
TV-CH-204 0.465 0.465 29~ TV-DG-108A 12-2-84 18.98 18.98 TV-DG-108B 10.92 10.92 18.98 31 TV-FP-105 10-20-84 0.462 0.462 FP-804 0.694 0.694 0.694 32 TV-FF-106 10-20-84 3.24 3.24 FP-800 0.462 0.462 3.24 38 TV-DA-100A 11-15-84 97.12 97.12 TV-DA-1005 ,
78.62 78.62 97.12 42 SA-15 1 2 84 .1.91 1.91 SA-14 3.17 3.17 3.17 43 TV-CV-102-1 10-23-84 195.3 195.3 TV-CV-102 1.72 1.72 195.3 44 TV-CV-101A 12-8-84 69.63 5.11 TV-CV-101B
- 2.23 5.11 45 RC-72 12 84 120.76 .470 TV-RC-519 .466 39.3 39.3 47 IA-90 1 2 84 26.58 26.58 IA-91 12.59 ,
12.59 26.58
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- Could Not Pressurise (cee IR 84-05) n w
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. -Typ3 C TOct R=ults 1984 P0rformanco b "As Found" "As Lef t" Pene- Valve Valve tration Valve Date Leakage Leakage Penetration Number Tested Tested (SCF/D) (SCF/D)- Leakage 48 TV-DG-109Al 10-25-84 0.464 0.464 TV-DG-109A2 0.464 0.464 0.464 49 RC-68 10-29-84
- 23.03 TV-RC-101 7.41 7.41 23.03 53 TV-SI-101-1 10-24-84 24.09 24.09 TV-SI-101-2 24.56 24.56 24.56 55-1 TV-SS-109Al 10-30-84 0.463 0.463 TV-SS-109A2 0.463 0.463 0.463 55-2 57-1 TV-LM-100A1 10-17-84 0.462 0.442 0.462 57-2 TV-LM-100A2 0.462 0.462 97-3 l ... .
55-4 TV-SS-111A1 10-30-84 0.463 0.463
, TV-SS-111A2 0.463 0.463 0.463 56-1 TV-SS-100A1 10-27-84 0.463 0.463 TV-SS-100A2 0.741 -
0.741 0.741 56-2 TV-SS-102A1 10-26-84 0.463 0.463 TV-SS-102A2 0.463 0.463 0.463 56-3 TV-SS-105A1 12-11-84 93.20 93.20 TV-SS-105A2 46.60 46.60 93.20 57-3 CV-35 10-17-84 10.62 10.62 TV-LM-101A 10.62 10.62 10.62 l 57-4 CV-36 10-17-84 3.32 3.32
. TV-LM-101B 4.06 4.06 4.06 l
58 TV-CC-103A 12-4-84 4.26 4.26
( TV-CC-103Al 0.468 0.468 4.26 i
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- Coeld Not Pressurize (see IR 84-85)
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_Typ3 C Test Results 1984 Parformanco "As Found" "As Left" Pene- . Valve Valve tration Valve Date Leakage Leakage Penetration Number' Tested Tested (SCF/D) (SCF/D) Leakage 63 QS-4 11-4-84 46.29 46.29 MOV-QS-1015 171.3 171.3 171.3 64 QS-3 1 1 84 0.464 0.464 MDV-QS-101A 0.464 0.464 0.464 70 RS-101 10-22-84 17.62 17.62 17.62 71 RS-100 10-22-84 0.464 0.464 0.464 87 NY-111 12-7-84 1.71 1.71 HY-120 0.829 0.896 1.71 88 NY-110 12-12-84 17.95 0.464 NY-119- 0.552 0.464 0.464 89 AS-278 10-20-84 34.22 34.22 TV-SV-100A 7.86 7. 86 34.22 90 VS-D-5-3A &
VS-D-5-38 1 1 84 233.22 18.56 18.56 VS-D-5-5A &
91 VS-D-5-55 &
VS-D-5-6 10-27-84
- 8.83 8.83 92 NY-102 &
10-17-84 9.68 9.68 TV-CV-150C NY-104 &
TV-CV-150D 18.45 18.45 18.45 93 HY-101 &
TV-CV-1505 10-17-84 4.61 4.61 NY-103 &
TV-CV-150A 5.53 5.53 5.53 94 HCV-CV-151 10-19-84 0.463 0.463 HCV-CV-151-1 6.02 6.02 6.02 95-64 SOV-HY-102B1 10-16-84 0.461 0.461 SOV-HY-102B2 0.461 0.461 0.461
- Could Not Pressurise (see IR 84-05)
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. Typ3 C Tcst Re:ults 1984 Pcrfernnca "As Left" "As Found" Fane- ,
Valve Valve tration Valve Date Leakage Leakage Penetration Number Tested Tested (SCF/D) (SCF/D) Leakage 95-69 SOV-HY-103B1 10-16-84 0.461 0.461 SOV-HY-103B2 0.461 0.461 0.461 95-72 SOV-HY-104B1 10-16-84 0.461 0.461 SOV-HY-104B2 0.461 0.461 0.461 97-1 TV-SS-104A1 11-3-84 0.464 0.464 TV-SS-104A2 0.464 0.464 0.464 97-2 TV-SS-103Al 11-3-84 0.464 0.464 TV-SS-103A2 0.464 0.464 0.464 103 PC-37 10-18-84 5.54 5.54 PC-38 0.462 0.462 5.54 104 PC-9 10-19-84 0.463 0.463 PC-10 0.463 0.463 0.463
- 105-2 TV-SS-112A1 10-30-84 0.463 0.463 TV-SS-112A2 0.463 0.463 0.463 106 MOV-SI-842 12-7-84 0.467 0.472 TV-SI-889 0.467 0.467 0.472 109-44 SOV-HY-102A1 10-16-84 0.461 -
0.461 SOV-HY-102A2 0.461 0.461 0.461 109-49 SOV-HY-103Al 10-16-84 0.461 0.461 SOV-HY-103A- 0.461 0.461 0.461 109-52 SOV-HY-104A1 10-16-84 0.461 0.461 SOV-HY-104A2 0.461 0.461 0.461 110 RC-277 10-16-84 0.463 0.463 RC-278 0.463 0.463 0.463 Page g3
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f .5 i TYPE 'C ' TEST RESUI.TS (Continued) 1984 Performance p
I Total Imak Rate Total Type B Tests 38.188 SCF/D Total Type C Tests 1969.157 SCF/D '
TOTAL tocal Imakage Rate Tests 2007.345 SCF/D
't Acceptance Criteria: Total f.eak Rate (Type 'B ' and 'C' ) < 3893.88 SCF/D e
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Type C Test R::ults (Continued) 1984 P:rfsrm:nco CORRECTIVE ACTIONS SU.PfARY Penetration No. 16 The initial leak test was performed November 30, 1984. Valve [W-CC-111A2] leaked at 704.37 SCF/D. Maintenance Work Request 848751 was initiated. The plus was cleaned and the valve repacked. The valve was retested on December 9, 1984, with a leak rate of 942.80 SCF/D.
WR 848758 was initiated and the seat, stem, and plug were replaced.
The retest was performed on December II., 1984, with a leak rate of 253.54 SCF/D.
Penetration No. 25 The initial leak test was performed on November 3, 1984. Valve [TV-CC-105D1] leaked at a rate of 176.24 SCF/D. WR 848316 was initiated and the seat and plus were cleaned. The bonnet gasket and packing were replaced. The retest was performed on December 4, 1984 with a leakage of 65.55 SCF/D.
Penetration No. 26 The initial leak test was performed on December 4, 1984. Valve [TV-
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CC-107E1] leaked at a rate of 177.92 SCF/D. WR 848756 was initiated and the plug and seat were cleaned. The bonnet gasket, seat ring gasket, and packing were replaced. The retest was performed on December 12, 1984 with a leak rate of 75.2 SCF/D.
Penetration No. 28
- The initial leak test was performed on November 16, 1984. The valves
[W-CH-200A, B, & C] leaked at a rate of 196.84 SCF/D, [RV-CH-203] and
[MOV-CH-142] leaked at a combined rate of 56.39 SCF/D. WR 842485 had i been initiated prior to the initial testing to repair a suspected leak in [TV-CH-2005). The following WR's were also initiated at the same l times WR 842491 - to replace valve [RV-CH-203] due to a crack in the valve body.
WR 848407 - to replace the diaphrass on the operator of valve
[TV-CH-200A] as a preventive maintenance measure.
WR 848408 - to replace the diaphragm on the operator of valve
[TV-CH-200B] as a preventive maintenance measure.
WR 848409 - to replace the diaphragm on the operator of valve
[TV-CH-200Cl as a preventive maintenance measure.
l The first retest was performed on November 28, 1984. Valve [RV-CH-203] leaked at a rate of 1.31 SCF/D. Valves [TV-CH-200A, B, & C]
would not hold the applied pressure. The operator limits on the trip Page 15
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. Typs C Tost R:sults (Continu:d) 1984 Pcrforranco i l
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CORRECTIVE ACTIONS
SUMMARY
- valves were adjusted to allow the plugs to seat properly. The second retest of [TV-CH-200A, B, & C] was done on December 2, 1984. The valves leaked at a combined rate of 194.47 SCF/D.
After the initial leak test, the motor on valve [MOV-CH-142] burned out. NWR 848453 was written and the motor and overload relays were replaced. MWR 848455 was initiated to clean the limit switches and
' adjust the Limitorque modutronic unit. The valve was ratested on December 11, 1984 with a leakage of 9.38 SCF/D.
When closing the motor operator cover after cleaning the limit switch contacts, a wire was inadvertently pinched. This caused a short in the control circuit, which again caused the motor to burn out. NWR 848456 was initiated to replace the motor and the modutronic unit.
The final retest was performed on December 14, 1984, with a leakage of 18.50 SCF/D.
Penetration No. 44-The initial leak test was performed on October 31, 1984. Valve [TV-CV-101A] leaked at a rate of 69.63 SCF/D while valve [TV-CV-101B]
would not hold the applied pressure. NWR 848315 was initiated to repair [TV-CV-101A] and MWR 848314 was initiated to repair (TV-CV-1018]. The seat ring gasket, body to bonnet gasket, packing, and plus insert were replaced on both valves. The retest was performed on December 8, 1984. Valve (TV-CV-101A] leaked at a rate of 5.11 SCF/D and (TV-CV-101B] leakage was 2.23 SCF/D. -
Penetration No. 45 The initial- leak test was performed.on October 25, 1984. Valve [RC-72] leaked at a rate of 120.76 SCF/D. Valve [TV-RC-519] leaked at a rate of 0.466 SCF/D. MWR 647241 was initiated to repair valve [RC-72]. Subsequent to the initial test, valve [TV-RC-519] developed a body to bonnet leak and NWR 848347 was initiated for its repair. The lower valve diaphragm was replaced and the studs torqued. [TV-RC-519]
was ratested on November 29, 1984 with a leakage of 39.3 SCF/D.
The body / bonnet gasket on [RC-72] was replaced and the valve was ratested on December 9, 1984. The valve leaked at a rate of 0.470 SCF/D.
Penetration No. 49 The initial leak test was performed on October 29, 1984. Valve [RC-
. 68] would not hold the applied pressure. MWR 848305 was initiated and the disc, spring, and bonnet gasket were replaced. The seating surfaces were polished with lapping compound. The retest was performed on November 30, 1984, with a leak rate of 23.03 SCF/D.
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Typ3 C Test Roaults (Ccntinutd) ~ 1984 Performanco !
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a CORRECTIVE ACTIONS SLTfARY Penetration No. 87 The initial leak test was performed on October 20, 1984. Valve [HY-120] leaked at a rate of 0.829 SCF/D; however, the valve lifted before the allowable 1.2 paid when tested under BYT 1.1-1. 47 .' 3. Valve [HY-111) was therefore not leak tested at this time. ,
WR 847239 was initiated for the repair of valve [HY-120]. The valve ;
was disassembled, the seat and gate were cleaned, and the disc and !
bonnet gasket were replaced. The retest was performed on October 29, 1984. Valve [HY-111] leaked at a rate of 1.71 SCF/D. Valve [HY-120]
again' failed the lift test.
- A weight was installed on the counterweight arm of the check valve and the valve was rotested. [HY-120] leaked at a rate of 0.896 SCF/D with i the weight installed. The valve passed the lift test and the weight ;
was left on the arm.
Penetration No. 88 -
The initial leak test was performed on October 13, 1984. Valve [HY- "
' ' ~
110] leaked at a rate of 17.95 SCF/D. Valve [HY-119] leaked at a rate of 0.552 SCF/D, but failed the check valve lift test.-
WR 847238 was initiated'for the repair of [HY-119). The valve was disassembled, the seat and gate were cleaned, and the disc and bonnet-gasket were replaced.
The retest was performed on October'29, 1984.- Valve [HY-110] leaked at a rate of 50.97 SCF/D, while valve [HY-119) leaked at rate of 5.07 SCF/D and failed the lift test. WR 848311 was initiated for the ;
repair of valve [HY-110]. The following is a summary of the corrective action taken on valves [HY-110) and (NY-119] after October .
30, 1984: -
[HY-110] - valve was disassembled, all parts were cleaned, the ball, stem, seats, 0-ring, and seals were replaced.
[HY-119) - the valve was disassembled, all parts were cleaned, the l 0-ring, rock shaft gland flex-gasket, and Woodrift key were replaced.
l A second retest was performed on December 7, 1984, before work had been started on [HY-110). Valve [HY-119] passed the check valve lift ,
i test with a weight installed on the weight arm. The measured leak rate was 2.45 SCF/D. Valve [HY-110] leaked at.a rate of 122.56 SCF/D.
After work was completed on [HY-110), both valves were retested. The
, "as left" leak rate for both valves was 0.464 SCF/D. a i
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,Typa C Test:R:sults (Centinuid) 1984 Parfcreanco CORRECTIVE ACTIONS
SUMMARY
Penetration No. 90
.The initial leak test was performed on October 25,. 1984. The penetration leaked at' a rate of 233.22 SCF/D. MWR 847242 was initiated to have the -limits of the Limitorque motor on [VS-D-5-3A]
adjusted to allow the valve to fully close. After the adjustment, the
- penetration was retested on November 1, 1984. The leak rate was 18.56
.SCF/D.
Penetration No. 91 The initial' ' leak test was performed on October 25, 1984. The penetration would not hold the applied pressure. MWR 848301 was initiated to adjust the limits of the Limitorque motor on (VS-D-5-5A]
to allow the valve to fully close. -After the adjustment, 'the valve was retested on October 27, 1984. The leak rate was 8.83 SCF/D.
Penetration No. 106 .
The initial leak test was performed on November 11, 1984. Valves (HOV-SI-842] and (TV-SI-889] both leaked at.a rate of 0.467 SCF/D.
Following this test, the motor operator on (M0V-SI-842] was replaced under DCP 351 with an environmentally qualified motor operator. The retest was performed on December 7,1984 with a measured leak rate of 0.472 SCF/D.
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'Af Telephone (412) 393 6000 Nuclear Group P.O. Box 4 Shippingport, PA 15077-0004 March 12, 1985 NDISS1:2381 United States Nuclear Regulatory Commission Director of Nuclear Reactor Regulation ATTN: Mr. Steven A. Varga Operating Reactors Branch No.1 Division of Licensing Washington, D.C. 20555
Reference:
Beaver Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66 Local Leak Rate Test Report Centlemen:
Enclosed is the 1984 Beaver Valley Local Leak Rate Test Report, submitted in accordance with Appendix J of 10 CFR Part 50. The report provides a summary of the results of the local leak rate testing conducted at BVPS Unit No. I during the Fourth Refueling Outage.
Very truly yours, N
IN.bP Station Supe it endent Attachment cci Mr. W. M. Troskoski, Resident Inspe ctor U.S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U. S. Nuclear Regulatory Commission c/o Document Management Branch Washington, D.C. 20555 Director, Safety Evaluation & Control Virginia Electric & Power Company P. O. Box 26666 One James River Plaza Richmond, VA 23261 q
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