ML20235U179
| ML20235U179 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 09/22/1987 |
| From: | Johnson I COMMONWEALTH EDISON CO. |
| To: | Davis A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 3608K, NUDOCS 8710130400 | |
| Download: ML20235U179 (3) | |
Text
-_ -
G
/
s Commonwealth Edison
("
) Oro First Nrional Plaz9., Chicaro. Illinoi).
7 A~daTesifisj2i16?'F6EM5FEibD6F
'n j]'
<1 Chicago, lilinois 60690 - 0767 J
' ?RIORITY R0!!TtNB September 22, 1987 gnt gg
%A hF
~
LW@
- vi id' vET DFA Mr. A. Bert Davis Th M Regional Administrator U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137
Subject:
Quad Cities Station Units 1 and 2 Secondary Containment Capability Test Summary Technical Report NRC Docket Nos. 50-254 and 50-265
Dear Mr. Davis:
Attached, in accordance with Section 6.6.C.4 and Table 6.6-1 of Appendix A to DPR-29 and DPR-30, is a summary of the Secondary Contaiment
(
Leak Rate Test performed for the Quad cities Station Units 1 and 2 Reactor Buildings on September 18, 1986. This test was performed in accordance with Section 4.7.C.I.c of the Quad Cities Units 1 and 2 Technical Specifications.
If you have any questions regarding this matter, please contact this office.
3 Very truly yo'rs, j
l
/
h I y v vr I. M. John Nuclear Licensing Administrator i
1m Attachment cc: NRC Resident Inspector - Quad Cities
)
h K
EP 2 8 1987 4
3608K P
1
~~C.E O l I
3 Quad-Cities Nuclear Power Station Units 1 and 2 Secondary Containment Leak Rate Test Summary Introduction Prior to the Unit One Refueling Outage at the End of Cycle Nine operations, a Secondary Containment Leak Rate Test was performed on the combined volume of Unit One and Two Secondary Containment Building. The test was performed to demonstrate the ability of the Standby Gas Treatment System (SBGTS) to maintain a quarter of an inch of water vacuum in both Reactor Buildings simultaneously with a filter train flow rate of not more than 4000 cfm. The test was conducted with a local flow indication of 4000 cfm.
Secondary Containment Capability Test The test was initiated with 'B' SBGTS train in primary by simulating a "HI" radiation signal in the Unit One and Unit Two Reactor Building Ventilation Monitors.
This action isolated Reactor Building Ventilation Systems, stopping all supply and exhaust fans, and started the 'B' SBGTS train. When equilibrium conditions were reached, differential pressure readings were taken.
Test Results Data on wind speed, wind direction, building inside and outside temperatures, and differential building pressures were obtained for a SBGTS flow rate of approximately 4000 cfm on the 'B' filter train.
l
NL 4'
Summary of Test Data September 10, 1987 Quad-Cities 1 & 2 Reactor Building Leak Rate
-j
'B' SBGT Train 1
i Wall Pressure'(inches of water)
Flow (cfm)
North South East West Average
]
4000
-0.250
-0.285
-0.260
-0.275
-0.2675 Summary of Wind and Temperature Conditions Temperature ( F):
Indoor 92 F Outdoor 72 F
}
Elevation Above Grade Level (feet):
196 Wind Velocity (MPH):
10 Wind Direction:
From North to South l
The results of the test indicate that the SBGTS is capable of maintaining a quarter of an inch of water vacuum under the calm wind conditions with a filter train flow rate of no more than 4000 cfm.
Average building differential pressure for the train results in -0.2675 inches of water, indicating adequate performance of the Secondary Con-tainment and Standby Gas Treatment System.
I l
}
a
.________-___m