ML20148F713

Reactor Containment Bldg Local Leak Rate Test

ML20148F713
Person / Time
Site:	Beaver Valley
Issue date:	03/04/1988
From:	Patterson J, Sieber J, Zyra T DUQUESNE LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8803280264
Download: ML20148F713 (22)

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. ENCLOSURE 1 4

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DUQUESNE. LIGHT COMPANY i

Beaver Valley Power Station Unit No. l' l

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i REACTOR CONTAINMENT BUILDING l I

LOCAL LEAK RATE TEST Febritary 1988 (6th Refueling Outage) ]

TYPE 'B'. AND 'C' l

l PREPARED BY: 4 1 DATE:  % 2 P3B J. l Tes(tEngineer.patterson REVIEWED BY: as DATE: S/2bes T. G. 2yra Q l Director Testing & Plant Performance APPROVAL: C ce Y DATE: 3!Y h

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8803280264 880304 PDR p.

ADOCK 05000334 DCD

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DUQUESE LIGHT COMPANY Beaver Valley Power Station TABLE OF CONTENTS Page No.

Introduction 1 A. Type 'B' Test Results 2 B. Type 'C' Test Results 7 C. Total Type 'B' and 'C' Test Results 19

INTRODUCTION - Local Leak Rate Test 1987/1988 6th Refueling Outage This report contains a discussion of the Beaver Valley Power Station Unit No. 1 Type 'B' and Type 'C' Local Leak Rate Testing performed' during the 1987/1988 6th 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 1987/1988 6th Refueling Outage. Type 'A' Testing was last succesefully completed during the 1986 5th 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 i

leakage rate of containment) in order to meet plant Tcchnical 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 i

psia).

La equals 0.10 percent by weight of containment air volume (1,800,000 ft')

ct 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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A. TYPE 'B' TEST RESULTS Local Leakage Rate Testing for the Containment Electrical Penetrations (Type

'B' Testing) was performed during the months of December 1987, January 1988, and February 1988. The results were fou 4 to be acceptable.

The Local Leakage Rate Testit t the Containment Electrical Penetrations measures the leakage through the penetration 0-ring senis 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 Personnel Airleck, the Equipment Hatch Flanges, the Emergency Personnel Airlock, the Fuel Transfer Tube, and Penetrations #111 and #112. The results of these tests are also included on the summary for reference, i

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A. TYPE 'B' TEST RESULTS (continued) 6R Electrical Penetration Leakage Summarv (Sheet 1 of 2)

PENT LEAKAGE PENT LEAYAGE NO 0-RING SEAL / CANISTER NO 0-RING SEAL / CANISTER (SCCM) (SCCM) 1-B 2.0 / 2.0 7-E 2.0 / 2.0 1-D 2.0 / 2.0 7-F 2.0 / 2.0 1-F 2.0/2.0 * / N/A 7-G (NOTE 1) / 2.0 2-B 2.0 / 2.0 8A 2.0 / 2.0 2-D 2.0 / 2.0 8-B 2.0 / 2.0 2F 2.0 / 2.0 8-C 2.0 / 2.0 3A 2.0 / 2.0 8-D 2.0 / 2.0 3-B 2.3 / 2.0 8-E 2.0 / 2.0 3-C 2.0 / 2.3 8-F 2.0/2.0 * / N/A 3-D 2.0 / 2.0 8-G 2.0 / 2.0 3-E 2.0 / 2.0 9-A 2.0 / 2.0 3-F 2.0 / 2.0 9-B 2.0 / 2.0 3-G 2.0/2.0 * / N/A 9-C 2.0 / 2.0 4-A 2.0 / 2.0 9-D 2.0 / 2.0 4-B 2.0 / 2.0 9-E 2.0 / 2.0 4C 2.0 / 2.0 9-F 2.0 / 2.0 4-D 2.0 / 2.0 9-G 20 / 2.0 4-E 2.0 / 2.0 10-A 2.0 / 10.0 4-F 2.0 / 2.0 10-B 2.0 / 7.f 4-G 2.0 / 7.6 10-C 2.0 / 2.0 5-A 2.0 / 2.0 10-D 2.0 / 2.0 5-B 2.0 / 2.0 10-E 2.0 / 2.0 5C 2.0 / 2.0 10-F 2.0 / 2.0 5-D 2.0 / 2.0 10-G 2.0 / 5.8 5-E 2.0 / 2.0 11-A 2.0 / 4.2 5-F 2.0 / 2.0 11-B 2.0 / 2.0 5-G 2.0 / 2.0 11-C 2.0/2.0 * / N/A 6-A 2.0 / 2.0 11-D 2.0 / 2.0 6-B 2.0/2.0 * / N/A 11-E 2.0 / 9.3 6-C 2.0 / 2.0 11-F 2.0 / 2.0 6-D 2.0 / 2.0 11 G 2.0 / 2.0  !

6-E 2.0 / 2.0 12 A 2.0 / 2.0 6-F 2.0 / 2.0 12-B 2.0 / 2.0 1 6-G 2.0 / 2.0 12-C 2.0 / 2.0 7-A 2.0/3.2 * / N/A 12-D 2.0 / 2.0 7B 2.0 / 2.0 12-E 2.0 / 4.2 l 7C 2.0 / 2.0 12-F 2.0 / 2.0 I 7-D 2.0 / 2.0 12-G 2.0 / 2.0 l TOTALS 85.2 73.9 78.0 101.0 SHT 1 l

• SPARE PENETRATION INSIDE/0U~ SIDE CONTAINMENT i

NOTE 1 -

CONAX ELECTRICAL PENETRATION INSTALLED AT 6R, 0-RINGS AND FEED !

THROUGHS TESTED SIKULTANEOULY l Page 3

A. TYPE-'B' TEST RESULTS (continusd) 6R Electrical Penetration Leakane Summary (Sheet 2 of 2)

PENT LEAKAGE PENT LEAKAGE NO .0-RING SEAL / CANISTF.R NO 0 RING SEAL / CANISTER (SCCM) (SCCM) 13-A 2.0/2.0 * / N/A 15-E 2.0 / 2.0 13-B (NOTE 1) / 2.0 15-F 2.0 / 2.0 13-C 2.0 / 2.0 15 G 2.0 / 2.0 13 D 2.0/2.0 * / N/A 16 A 2.0 / 2.0 13-E 2.0 / 2.0 16-B 2.0 / 2.0 13-F 2.0 / 5.9 16-C 2.0 / 2.0 13-G 2.0 / 2.0 16-D 2.0 / 2.0 14 A 2.0 / 2.0 16-E 2.0 / 2.0 2.0 2.0 2.0 14 -B / 16-F / 2.0 14-C 2,0 / 2.0 16-G 2.0/2.0 * / N/A 14-D 2.0 / 2.0 17-B 2.0 / 2.0 14-E 2.0 / 2.0 17-D 2.0/2.0 * / N/A 14-F 2.0 / 2.0 17-F 2.0/2.0 * / N/A 14 G 2.0 / 2.0 18-B 2.0 / 2.0 15-A 2.0 / 2.0 18-D 2.0 / 2.0 15-B 2.0 / 2.0 l 18-F 2.0/2.0 * / N/A 15-C 2.0 / 2.0 FB-1 2.0 / 2.0 15 D 2.0 / 2.0 TOTALS 38.0 35.9 42.0 26.0 SHT 2

• SPARE PENETRATION INSIDE/0UTSIDE CONTAINMENT NOTE 1 -

CONAX ELECTRICAL PENETRATION INSTALLED AT 6R, 0-RINGS AND FEED THROUGHS TESTED SIMULTANEOULY i

LEAKAGE TOTALS 0 RING SEAL / CANISTER SHEET 1 163.2 / 174.9

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(SCCM)

SHEET 2 80.0 / 61.9 (SSCM) l TOTAL 1.EARAGE 243.2 / 236.8 (SCcM) 1 TOTAL LEAKAGE 12.4 / 12.0 l (SCF/D) {

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A. TYPE 'B' TEST RESULTS (continued) 6R Type 'B' Leakage Summary l l

(Sheet 1 of 1) l Electrical Penetrations- 2-15-88 24.40 SCF/D I

Personnel Airlock 2-12-88 2.34 SCF/D Equipment Hatch Outer Flange 2-16-88 0.46 SCF/D 1 1

Equipment Hatch Inner Flange 2-17-88 0.48 SCF/D l l

l Emergency Personnel Airlock 2-17-88 0.47 SCF/D j Fuel Transfer Tube 2-10-88 0.46 SCP/D Penetration #111 12-30-87 1.11 SCF/D 1

Penetration #112 12-30-87 0.46 SCF/D I l

TOTAL Type 'B' Leakage 30.18 SCF/D l

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A. TYPE 'B' TEST RESULTS (continued) 6R Type 'B' Corrective Action Summary The following electrical penetrations required maintenance due to high leak rates, or physical damage:

PENT NO FNR NO INITIAL LEAKAGE FINAL IIAKAGE (SCCM) (SCCM) 4-D CANISTER 875278 65.0 2.0 10-B CANISTER 875281 37.5 7.5 10-C CANISTER 875282 11.2 2.0 10-G CNAISTER 875283 18.5 5.8 12-E CANISTER 875277 2.0 4.2 13-F CANISTER 875276 8.1 5.9 15-E CANISTER 875275 8.3 2.0 The high leak rate on the 4-D penetration was due to a leaking canister pressure gauge. The gauge was replaced, and the canister was satisfactorily retested.

The high leak rate on the 10-B penetration was due to a tubing leak near the canister test isolation valve. The tubing was repaired with high shear strength adhesive, and the canister was satisfactorily retested.

The high leak rate on the 10-C penetration was due to a tubing leak near the canister test isolation valve. The tubing was repaired with high shear strength adhesive, and the canister was satisfactorily retested.

The high leak rate on the 10-G penetration was due to a tubing leak where it connects to the caniter test isolation valve. The connection was repaired with high shear strength adhesive, and the canister was satisfactorily rotested.

The canister pressure gauge and test isolation valve assembly for 12-E penetration was accidently broken off during work in the penetration area. The assembly was rewelded onto the penetration canister, and was satisfactorily retested.

The high leak rate on the 13-F penetration was due to a tubing leak where it connects to the canister test connection. The connection was repaired with high shear strength adhesive, and the canister was satisf actorily retested.

The high leak rate on the 15-E penetration was due to a tubing leak where it connects to the canister test isolation valve. The connection was repaired with high shear strength adhesive, and the canister was satisfactorily retested.

Two new electrical penetrations were installed per DCP 900 during 6R at locations 7-G and 13-B replacing the existing blank flanges. Both new electrical penetrations were satisfactorily tested.

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1 B. TYPE 'C' TEST RESULTS The purpose of Type 'C' Testing is to demonstrate 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' Tests together with the appropriate Type 'B' Tests were performed during the period of December 14, 1987 through February 8, 1988. The results of these tests met tha applicable acceptance criteria and are '

reviewed on the accompanying tables. '

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B. TYPE 'C' TEST RESULTS (continued) 6R Tvoe C Leakaaf Summarv (Sheet 1 of 7)

CONTAINMENT AS FOUND AS LEFT ASSIGNED petit VALVE DATE VALVE VALVE PENETRATION NO. MARK NO. TESTED LEAKAGE LEAKAGE LEAKAGE IN OUT (SCF/D) (SCF/D) (SCF/D)

MOV-CC-112A2 X 01-23-88 0.46 0.47 1 0.56 CCR-247 X 01-11-88 0.56 0.56 MOV CC-112B3 X 01-26-88 0.56 0.47 2 0.56 CCR-252 X 01-08-88 561.3 0.56 MOV-CC-112A3 X 01-25-88 3.10 8.37 4 179.8 CCR-251 X 01-11-88 179.8 179.8 MOV-CC-112B2 X 01-26-88 0.46 9.33 5 9.33 CCR-248 X 01 06-88 7.87 7.87 TV-CC-107D1 X 0.46 0.46 8 12-23-87 0.56 TV-CC-107D2 X 0.56 0.56 TV CC-111D1 X 8.75 8.75

, 9 12-16-87 8.75 TV-CC-111D2 X 3.46 3.46 TV-CC-110D X 0.46 0.46 11 TV CC-110F1 X 01-11-88 0.49 0.49 0.49 TV-CC-110F2 X FP 827 X 01-07-88 0.46 0.46 13 0.47 TV-FP 107 X 01-23-88 230.4 0.47 TV-CC 110E3 X 0.46 0.46 14 01-08-88 0.46 TV-CC-110E2 X 0.46 0.46  !

TV-CC 111A2 X 45.32 45.32 16 01-07-88 45.32

• TV-CC-111A1 X 1.40 1.40 TV-CC-103B1 X 0.46 0.46 l 17 01-11-88 11.18 TV-CC 103B X 11.18 11.18 TOTAL PENETRATION LEAKAGE SHEET 1 (SCF/D) 257.48 Page 8

B. TYPE 'C' TEST RESULTS (continued) 6R Tvoe C Leakane Summarv (Sheet 2 of 7)

CONTAINMENT AS FOUND AS LEFT ASSIGNED PENT VALVE DATE VALVE VALVE PENETRATION NO. MARK NO. TESTED LEAKAGE LEAKAGE LEAKAGE IN OUT (SCP/D) (SCP/D) (SCP/D)

TV-CC-103C1 X 7.46 7.46 18 01 20 88 62.21 TV-CC-103C X 62.21 62.21 MOV-CH-378 X 24.09 24.09 19 CH-369 X 12-22-87 24.09 MOV-CH-381 X 0.46 0.46 SI-42 X 0.61 0.61 20 02 02-88 0.61 SI-41 X 0.46 0.46 RH-14 X 0.53 0.53 24 RH 16 X 01-14-88 0.47 0.47 1.00 RH 15 X 0.47 0.47 TV-CC-105D1 X 11.95 11.95 25 12 16-87 11.95 TV CC-105D2 X 6.69 6.69 TV CC-107El X 69.57 69.57 26 12 24-87 69.57 TV-CC-107E2 X 0.56 0.56 TV-CC-105El X 01-21-88 193.5 31.69 27 31.69 TV-CC 105E2 X 01 11-88 15.66 15.66 l TV-CH-200A X l

TV-CH-200B X 0.75 0.75 TV-CH-200C X 28 01 05 88 RV-CH-203 X 2.38 2.38 54.43 MOV-CH-142 X 51.30 51.30 TV-CH-204 X 1.91 1,91 TOTAL PENETPATION LEAKAGE SHEET 2 (SCP/D) 235.55 Page 9

B. TYPE 'C' TEST RESULTS (continued) 6R Tvoe C Leakage Summarv (Sheet 3 of 7)

CONTAINMENT AS FOUND AS LEFT ASSIGNED PENT VALVE DATE VALVE VALVE PENETRATION NO. MARK NO. TESTED LEAKAGE LEAKAGE LEAKAGE IN OUT (SCF/D) (SCF/D) (SCF/D)

TV-DG-108A X 11.67 11.67 29 01-16-88 11.67 TV-DG-108B X 9.80 9.80 FP-304 X 0.46 0.46 31 12-21-87 4.39 TV-FP-105 X 4.39 4.39 FP-800 X 12-19-87 0.46 0.46 32 19,91 TV-FP-106 X 12-21-87 19.91 19.91 TV-DA-100A X 168.9 83.88 38 01-23-88 83.88 TV-DA-100B X 304.9 24.23 SA-15 X 1.87 1.87 42 12-16 87 1.87 SA-14 X 1.12 1.12 TV CV-102-1 X 02-01-88 238.1 6.03 43 6.03 TV-CV-102 X 12 15 87 0.46 0.46 TV-CV-101A X 69.63 6.94 44 12 17-87 6.94 TV-CV-101B X 64.99 3.89 RC-72 X 10,64 10.64 45 12-18-87 10.64 TV-RC-519 X 1.25 1.25 IA-91 X 28.41 28.41 47 12-15-87 28.41 IA-90 X 11.90 11.90 TV-DG-109A2 X 0.46 0.46 48 12-22 87 2.78 TV-DG-109Al X 2.78 2.78 RC 68 X 41.01 41.01 49 12-18-87 41.01 TV-RC-101 X 3.59 3.59 TOTAL PENETRATION LEAKAGE SHEET 3 (SCP/D) 217.53 Page 10

B. TYPE 'C' TEST RESULTS (continued) 6R Type C Leakane Summarv (Sheet 4 of 7)

CONTAINMENT AS FOUND AS LEFT ASSIGNED PENT VALVE DATE VALVE VALVE PENETRATION NO. MARK NO. TESTED LEAYAGE LEAKAGE LEAKAGE IN OUT (SCF/D) (SCF/D) (SCF/D)

TV-SI-101-2 X 11.37 11.37 53 01-18-88 11.37 TV-SI 101-1 X 6.64 6.64 TV-SS-109Al X 0.46 0.46 55-1 12-22-87 0.46 TV-SS-109A2 X 0.46 0.46 TV-LM-100A1 X 0.46 0.46 55-2 12-14 87 0.46 NOTE 1 TV-LM-100A2 X 0.46 0.46 TV-SS 111A1 X 0.46 0.46 55-4 12-22-87 0.46 TV-SS-111A2 X 0.46 0.46 TV-SS-100A1 X 0.46 0.46 56-1 12-22 87 0.46 TV-SS-100A2 X 0.46 0.46 TV-SS 102A1 X 0.47 0.47 56 2 01-27 88 0.47 TV-SS-102A2 X 0.47 0.47 TV-SS-105A1 X 0.47 0.47 56-3 01-27-88 0.47 TV-SS-105A2 X 0.47 0.47 TV-LM 101A X 9.72 9.72 57-3 12 18-87 9.72 CV-35 X 9.72 9.72 TV-LM 101B X 4.07 4.07 57-4 12-18-87 4.07 CV-36 X 3.94 3.94 TV-CC-103Al X 0.47 0.47 58 01 15 88 1.82 TV-CC-103A X 1.82 1.82 QS-4 X 0.47 0.47 63 01-13-88 0.47 MOV-QS-101B X 0.47 0.47 TOTAL PENETRATION LEAKAGE SHEEI 4 (SCF/D) 30.23 NOTE 1 - INCLUDES PENETRATIONS 57-1,57-2, AND 97-3 WHICH ALSO SHARE THESE CNMT ISOLATION VALVES THROUGH A COMMON 4-WAY VALVE.

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B. TYPE 'C' TEST RESULTS (continued) 6R Tvoe C Leakane Summarv (Sheet 5 of 7)

CONTAINMENT AS FOUND AS LEFT ASSIGNED PENT VALVE DATE VALVE VALVE PENETRATION NO. MARK NO. TESTED LEAKAGE LEAKAGE LEAKAGE IN OUT (SCF/D) (SCF/D) (SCF/D)

QS-3 X 32.59 32.59 64 01-13-88 42.49 MOV-QS-101A X 42.49 42.49 70 RS-101 X 01-21-88 18.66 18.66 18.66 71 RS-100 X 12-23-87 5.57 5.57 5.57 HY-197 X 1.27 1.27 87 01-15-88 1.64 HY-lli X 1.64 1,64 HY-196 X 17.14 8.44 88 01 15-88 8.44 HY-110 X 0.47 1.64 AS-278 X 10.16 10.16 89 12-19-87 10.16 TV-SV-100A X 4.16 4.16 VS-D-5-3B X 90 02-08 88 370.7 0.46 0.46 VS-D-5-3A X VS-D-5-5B X i 91 VS-D-5-5A X 01-27-88 176.1 1.25 1.25 VS-D-5 6 X TV-CV-150C

& X 6.56 6.56 l HY-102 92 01-14-88 17.81 TV-CV-150D

& X 17.81 17.81 HY-104 TV-CV 150B

& X 0.47 0.47 HY-101 93 01-14-88 1.88 TV-CV-150A

& X 1.88 1.88 HY-103 TOTAL PENETRATION LEAKAGE SHEET 5 (SCF/D) 108.36 Page 12

B. TYPE 'C' TEST RESULTS (continued) 6R Type C Leakane Summarv (Sheet 6 of 7)

CONTAINMENT AS FOUND AS LEFT ASSIGNED PENT VALVE DATE VALVE VALVE PENETRATION NO. MARK NO. TESTED LEAKAGE LEAKAGE LEAKAGE IN OUT (SCF/D) (SCF/D) (SCF/D)

HCV-CV-151 X 13.89 1.58 94 01-04 88 1,58 HCV-CV-151-1 X 0.46 0.46 SOV-HY-102B1 X 0.46 0.46 l 95-64 12-19-87 0.46 bOV-HY-102B2 X 0.46 0.46 SOV HY-103B1 X C.46 0.46 95-69 12-19-87 0.46 SOV-HY-103B2 X 0.46 0.46 SOV-HY-104B1 X 0.46 0.46 l 95-72 12-19-87 0.46 l SOV HY-104B2 X 0.46 0.46 TV SS-104A1 X 0.47 0.47 97-1 01 15-88 0.47 TV SS-104A2 X 0.47 0.47 TV-SS-103Al X 0.47 0.47 97-2 01-15-88 0.47 TV SS-103A2 X 0.47 0.47

! PC-38 X 18.52 18.52 103 12-17-87 18.52 PC-37 X 10.18 10.18 PC-9 X 0.46 0.46 104 12-17-87 0.46 PC-10 X 0.46 0.46

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TV-SS 112A1 X 13.90  ! 0.47 105-2 01-15 88 4.69 TV-SS-112A2 X 4.64 4.69 MOV-SI-842 X 0.46 0.46 106 12-19 87 --

0.46 TV-SI-889 X 0.46 0.46 S0V-HY-102A1 X 0.46 0.46 109 44 12-19-87 0.46 SOV-HY-102A2 X 0.46 0.46 TOTAL PENEIRATION LEAKAGE SHEET 6 (SCF/D) 28.49 I

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. l B. TYPd 'C' TEST RESULTS (continued) 6R Tyne C Leakage Summary (Sheet 7 of 7)

CONTAINMENT AS FOUND AS 1. EFT ASSIGNED PENT VALVE DATE VALVE VALVE PENETRATION NO. MARK NO. TESTED LEAKAGE LEAKAGE LEAKAGE IN OUT (SCF/D) (SCF/D) (SCF/D)

SOV-HY-103Al X 0.46 0.46 109 49 12-19 87 0.46 SOV-HY-103A2 X 0.46 0.46 S0V-HY-104A1 X 0.46 0.46 109-52 12-19-87 0.46 S0V-HY-104A2 X 0.46 0.46 RC-277 X 0.46 0.46 110-1 01-15-88 0.46 RC-278 X 0.46 0.46 VS-169 X 0.46 0.46 VS-170 X 0.46 0.46 P.A.L. 01 15-88 (NOTE 2)

VS-167 X 0.46 0.46 VS-168 X 0.46 0.46 TOTAL PENETRATION LEAKAGE SHEET 7 (SCF/D) 1.38 NOTE 2 - THE ASSIGNED PENETRATION LEAKAGE FOR THESE VALVES IS ADDED WITH THE PERSONNEL AIRLOCK OVERALL TYPE B LEAKAGE, AND NOT INCLUDED IN THE TYPE C TOTAL, P.A.L. - PERSONNEL AIRLOCK TOTAL PENETRATION LEAKAGE SHEET 1 (SCF/D) 257.48 TOTAL PENETRATION LEAKAGE SHEET 2 (SCF/D) 255.55 TOTAL PENETRATION LEAKAGE SHEET 3 (SCF/D) 217.53 TOTAL PENETRATION LEAKAGE SHEET 4 (SCF/D) 30.23 TOTAL PENETRATION LEAKAGE SHEET 5 (SCF/D) 108.36 TOTAL PENETRATION LEAKAGE SHEET 6 (SCF/D) 28.49 TOTAL PENETRATION LEAKAGE SHEET 7 (SCF/D) 1.38 TOTAL CONTAINMENT TYPE C LEAKAGE - SUM OF SHEETS 1 THRU 7 (SCF/D) 899.02 Page 14

B. TYPE 'C' TEST RESULTS (continued) 6R Type 'C' Corrective Action Summary (Sheet 1 of 4)

Penetration No. 1 The initial leak test was performed January 11, 1988. Due to EQ Requirements, the limit switch and torque switch for valve MOV-CC-112A2 were replaced per Maintenance Work Request 882052. Following the replacement, the Type C retest was performed on January 23, 1988, with a leakage of 0.47 SCF/D.

Penetration No. 2 The initial leak test was performed January 7, 1988. Valve CCR-252 leaked ,

at 561.3 SCF/D. The high leakage rate was due to the valve being closed (

beyond its optimum seating position (butterfly valve). The valve was )

recycled and the retest performed on January 8, 1988, with a leakage of 0.56 SCF/D. The valve stop was adjusted to ensure the valve would not over travel its optimum seating position.

Due to EQ Requirements, the limit switch and torque switch for valve MOV-CC-112B3 were replaced per Maintenance Work Request 882055. Following the replacement, the Type C retest was performed on January 26, 1988, with a leakage of 0.47 SCF/D.

Penetration No. 4 The initial leak test was performed January 11, 1988. Due to EQ Requirements, the limit switch and torque switch for valve MOV-CC-112A3 were replaced per Maintenance Work Request 882053. Following the replacement, the Type C retest was performed on January 25, 1988, with a leakage of 8.37 SCF/D.

Penetration No. 5 l

( The initial leak test was performed January 6, 1988. Due to EQ l Requirements, the limit switch and torque switch for valve MOV-CC-112B2 were replaced per Maintenance Work Request 882054. Following the replacement, the Type C retest was performed on January 26, 1938, with a leakage of 9.33 SCF/D.

l Penetration No. 13 The initial leak test was performed January 7, 1988. Valve TV-FP-107 leaked at 230.4 SCF/D. The valve was rebuilt per Maintenance Work Request 878106 and Design Change Package 833. The valve trim was replaced with a later design, soft seat trim. The Type C retest was performed on January 23, 1988, with a leakage of 0.47 SCF/D.

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l B. TYPE 'C' TEST RESULTS (continued)  !

6R Type 'C' Corrective Action Summary (Sheet 2 of 4)

Penetration No. 27 The initial leak test was performed January 11, 1988. Valve TV-CC-105El leaked at 193.5 SCF/D. Maintenance Work Request 882502 was initiated. The valve plug was machined to remove indications. The valve seat was machined to remove raised metal. The Type C retest was performed on January 21, 1988, with a leakage of 31.69 SCF/D.

Penetration No. 38 The initial leak test was performed January 15, 1988. Valve TV-DA-100A leaked at 168.9 SCF/D and valve TV-DA-100B leaked at 304.9 SCF/D.

Maintenance Work Requests 882509 for TV-DA-100A and 882510 for TV-DA-100B were initiated.

The seat ring and seat were replaced on valve TV-DA-100A and the plug lapped. The Type C retest was performed on January 23, 1988, with a leakage of 83.88 SCF/D.

The seat and plug of valve TV-DA-100B were cleaned of debris and the valve re-assembled. The Type C retest was performed on January 23, 1988, with a leakage of 24.23 SCP/D.

Penetration No. 43 The initial leak test was performed December 15, 1987. Valve TV-CV-102-1 leaked at 238.1 SCF/D. The valve was rotated in the system per Design Change Package 666 to permit leak testing the valve on top of the valve seat, rather than from under the valve seat. The Type C retest was  !

performed on February 1, 1988, with a leakage of 6.03 SCF/D.

Penetration No. 44 The initial leak test was performed December 14, 1987. Valve TV-CV-101A l 1eaked at 69.63 SCF/D and valve TV CV-101B leaked at 64.99 SCF/D. Since no air leakage was detected at the downstream vent for either valve, Maintenance Work Request 879156 was initiated for the inboard penetratien boundary valve CV-14. Corrosion was removed from the seat and disc of valve CV-14. The Type C retest was performed on December 17, 1987, with a leakage of 6.94 SCF/D for TV-CV-101A and 3.89 SCF/D for TV-CV-101B.

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4 B. TYPE 'C' TEST RESULTS (continued) 6R Type 'C' Corrective Action Summary (Sheet 3 of 4)

Penetration No. 63 The leak test was performed on Je.nuary 13, 1988. Valve QS-4 leaked at 0.47 SCF/D. Maintenance Work Request 882506 was initiated due to binding when QS-4 was cycled. The valve shaft was lubricated to eliminate the binding.

A Type C retest was not performad, since the seating surfaces of the valve were not affected.

Penetration No. 70 The initial leak test was performed December 23, 1987. Valve RS-101 leaked at 0.46 SCF/D. Maintenance Work Request 879160 was initiated due to binding when RS-101 was cycled. The valve shaft was lubricated to eliminate the binding. A Type C retest was not going to be performed, since the seating surf aces of the valve were not affected; however, it was discovered that the downstream piping was not properly vented during the initial leak test, due to water in Recire. Spray Pump RS-P-2B casing. The Type C retest was performed on January 21, 1988, with a leakage of 18.66 SCF/D.

Penetration No. 71 The leak test was performed on December 23, 1987. Valve RS-100 leaked at 5.57 SCF/D. Maintenance Work Request 879161 was initiated due to binding when RS-100 was cycled. The valve shaft was lubricated to eliminate the binding. A Type C retest was not performed, since the seating surfaces of the valve were not affected.

Penetration No. 88 The initial leak test was performed January 12, 1988. Valve HY-196 leaked at 17.14 SCF/D and valve HY-110 leaked at 0.47 SCF/D. Maintenance Work Request 882511 was initiated for penetration boundary valve HY-119 shaft leakage. The internals of valve HY-119 had been removed during the 5th Refueling Outage. The valve shaft was removed and the opening temporarily plugged. The Type C retest was performed on January 15, 1983, with a leakage of 8.44 SCF/D for valve HY-196 and 1.64 SCF/D for valve HY-110.

Penetration No. 90 The initial leak test was performed January 18, 1988. Valves VS-D-5-3A and V3-D-5-3B leaked at 370.7 SCF/D (pressurized between CIV's). Maintenance Work Request 882319 was initiated for a packing leak on valve VS-D-5-3A and Maintenance Work Request 882513 was initiated for a packing leak on valve VS-D-5-3B. The old packing was removed and both valves repacked. The Type C retest was performed on February 8, 1988, with a leakage of 0.46 SCF/D.

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1 B. TYPE 'C' TEST RESULTS (continued) 4 i

6R Type 'C' Corrective Action Summary (Sheet 4 of 4) t Penetration No. 91 The initial leak test was performed January 18, 1988. Valves VS-D-5-5A, VS-D-5-5B, and VS-D-5-6 leaked at 176.1 SCF/D (pressurized between CIV's).

Maintenance Work Request 875577 was initiated to inspect the_ seat and repack valve VS-D-5-5A. Maintenance Work Request 857439 was initiated for a crack ons the Motor Operator of VS-D-5-5A. The seat was inspected satisfactorily, the valve repacked, and the motor operator replaced on valve VS-D-5-5A. The

'vpe C retest was performed on January 27, 1988, with a leakage of 1.25 SCF/D.

Penetration No. 94 The initial leak test was performed December 21,. 1987. Valve HCV-CV-151 leaked at 13.89 SCF/D. Maintenance Work Request 679158 was initiated. l Prior to any work being performed by Maintenance, it was discovered that l valve HCV-CV-151 had not gone fully closed to tho mechanical stop (chain operated valve). The Type C retest was performed on January 4, 1988, with a i leakage of 1.58 SCF/D. Maintenance Work Request 87?158 was voided.

1 Penetration No. 105-2 ,

I l

The initial leak test was performed December 22, 1987. Valve TV-SS-112A1 l leaked at 13.90 SCP/D. Since no air leakage was detected at the downstream i l

vent Maintenance Work Request 879162 was initiated for inboard penetration boundary valve TV-SS-110. The packing for valve TV-SS-110 was adjusted.

The Type C retest was performed on January 15, 1988, with a leakage of 0.47 SCP/D.

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C. TOTAL TYPE 'B' and 'C' TEST RESULTS 6R Total Type 'B' and 'C Leakage Summary (Sheet 1 of 1)

Total Type 'B' Leakage 30.18 SCF/D Total Type 'C' Leakage 899.02 SCF/D Total Type 'B' *nd 'C' Leakage 929.20 SCF/D (All ble 3,893.88 SCF/D [0.6 La])

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p 'r at!4GL

~7pf Telephone (412) 393 6000 Nuclear Group P.O. Oox 4 Shippingport, PA 15077 0004 U. S. Nuclear Regulatory Commission Attn: Document Control Desk

/ Washington ,

DC 20555

Reference:

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR Reactor Containment Building Integrated Leak Rate Test l Gentlemen:

)

Leak Attached as Enclosure 1 is the Reactor Containment Building Local Rate Test for Beaver Valley Powar Station, Unit No. 1. This report documents the results of the Type B and Type C testing conducted during our sixth refueling outage which ended March 2, 1988. This report is being submitted in accordance with 10 CFR 50, Appendix J, Section V, paragraph B.3.

If you have any questions, please call me or members of my staff, i

Sincerely, l

0 M---- ..

. D. Sieber Vice President Nuclear Group cc: Mr. J. Beall, Resident Inspector Mr. W. T. Russell, NRC Region I Administrator Mr. P. Tam, Project Mancger Director, Safety Evaluation & Control (VEPCO)

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