ML20134M579
| ML20134M579 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 02/07/1997 |
| From: | Pearce L COMMONWEALTH EDISON CO. |
| To: | Pearce L NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LWP-97-012, LWP-97-12, NUDOCS 9702200297 | |
| Download: ML20134M579 (3) | |
Text
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Commonwcalth Idm>n Company Quad Cities Generating Station j
^
22710 206th Asenue Nonh
- Conlova, 11.61212 9740 Tcl.409M i-22 iI LWP-97-012 i
Febmary 7,1997 U.S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
Document Control Desk
SUBJECT:
Quad Cities Station Units 1 and 2 I
Secondary Containment Capability Test Summary Technical Report NRC Docket Nos. 50-254 and 50-265 i
Attached, in accorci ace v,ith Sxtion 6.6.B.4 and Table 6.6-1 of Appendix A t
to DPR-29 and DPA-20, is a summary of the Secondary ContainmGit Ieak Rate Test performed for the Quad Cities Station Units 1 and 2 Reactor Buildings on i
Febmary 2,1997. This test was performed in accordance with Section 4.7.N.3. of Quad Cities Units 1 and 2 Technical Specifications.
i Very !mly yours, O
L V0A U-I. W. Peatre Station Manager f
Quad Cities Nuclear Power Station LWP/RR/kdm j.-f{f
Enclosure:
Secondary Containment Test Summary cc:
A. B. Beach, Regional Administrator, Region III C. G. Miller, Senior Resident Inspector, Quad Cities R. M. Pulsifer, Project Manager, NRR D. C. Tubbs, Mid American Energy Company R. J. Singer, Mid American Energy Company P. L. Piet, Licensing, Downers Grove
.?00034 DCD - License (both electronic and hard copy) 9702200297 970207
~
PDR ADOCK 05000254 P
PDR A l'nicum company
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Quad Cities Nuclear Power Station Units 1 and 2 Secondary Containment Izak Rate Test Summary I
Introduction i
t Prior to the Unit Two Refueling Outage at the End of Cycle Fourteen operations, a Secondary Containment Izak Rate Test was performed on the combined volume of the Unit One and Unit 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 3
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 filter train flow rate of 4000 cfm.
Secondary Containment Canability Tests The test was initiated at 0921 hours0.0107 days <br />0.256 hours <br />0.00152 weeks <br />3.504405e-4 months <br /> on February 2,1997 with the 'B' SBGTS train in primary by simulating a "HI" radiation signal in the Reactor Building Ventilation Monitors.
This action isolated the Reactor Building Ventilation systems, stopping all operating supply and exhaust fans, and starting 'B' SBGTS train. When equilibrium conditions were reached, j
differential pressure readings were taken.
i Test Results Data on wind speed, wind direction, building inside and outside temperatures, and i
differential building pressures were obtained for SBGTS flow rate of approximately 4000 cfm on the 'B' filter train. The test data represents the "as-found" condition of the Secondary Containment Building.
A 4 inch hole (leak) in the Secondary Containment was induced during the test. The purpose was to obtain data in order to quantify the perfonnance of the Secondary Containment in a h
degraded condition. The leak was induced by opening a four inch fire header from outside i
to the Reactor Building.
l Corrections for the reactor building to atmosphere differential temperatures were not performed. The temperature correction data is shown on the attached Summary of Test Data sheet for reference only.
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SUMMARY
OF TEST DATA j
February 2,1997
]
Ouad Cities 1 & 2 Reactor Building f eak Rate
'B' SBGTS Train Differential Wall Pressure (inches of water) i Elow (cfm)
North South Fast West Average j
4000
-0.38
-0.38
-0.40 -0.38
-0.385 Differential Reactor Building to Atmosphere Temperature = 43.4 F i
Temperature Correction (inches of water) = -0.038 I
Temperature Corrected Average Differential Pressure (inches of water) = -0.423 Induced 12ak Rate Results Differential Wall Pressure (inches of water)
Flow (cfm)
North South East West Average i
4000
-0.36
-0.34
-0.36 -0.33
-0.348
[
l Temperature Corrected Average Differential Pressure (inches of water) = -0.386 Summary of Wind and Temoerature Conditions Temperature (deg. F):
Indoor 75.6* F
)
Outdoor 32.2' F f
Wind Velocity (MPH):
13.0 - 4.7 (Beginning to End of Test) i Wind Direction:
NW (343 deg.)
i Elevation Above Grade 12 vel (feet):
196 The results of the test indicate that the SBGTS is capable of maintaining a quarter of an inch of water vacuum under calm wind conditions with a filter train flow rate of no more than 4000 cfm. Average reactor building differential pressure for the train results in -0.385 inches of water (without correction for building to atmosphere differential temperature),
indicating adequate performance of the Secondary Containment and Standby Gas Treatment System.
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