ML20117M587
| ML20117M587 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 06/13/1996 |
| From: | Pearce L COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LWP-96-047, LWP-96-47, NUDOCS 9606180638 | |
| Download: ML20117M587 (5) | |
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Onnmonwrahh lilnon Company Quad Cities Generating Mation 22710 2(Mith Asenue North ontova. n. 612mmo Tri 30'HM22 il LWP-96-047 June 13, 1996 U.S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
Document Control Desk
SUBJECT:
Quad Cities Station Units 1 and 2 Secondary Containment Capability Test Summary Technical Report NRC Docket Nos. 50-254 and 50-265 l
Attached, in accordance with Section 6.6.B.4 and Table 6.6-1 of Appendix A to DPR-29 and DPR-30, is a summary of the Secondary Containment Leak Rate Tests performed for the Quad Cities Station Units 1 and 2 Reactor Buildings on May 18 and June 9, 1996.
These tests were performed in accordance with Section 4.7.C.1. of Quad Cities Units 1 and 2 Technical Specifications.
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. W. Pearce Station Manager Quad Cities Nuclear Power Station LWP/RR/mdh
Enclosure:
Secondary Containment Test Summary cc:
H. J. Miller, 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. Piet, Licensing, Downers Grove 9606180630 960613 PDR ADOCK 05000254 P
PDR 180059 Aol1 3 enrem Comranx
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l Quad Cities Nuclear Power Station Units 1 and 2 4
Secondary Containment Leak Rate Test Summary 4
i Introduction On May 10, 1996 a tornado hit the Quad Cities Reactor Building refuel floor siding, removing outer sheet metal and loosening some of the blowout panels on t'ie East side of the Reactor Building. Reactor Building to atmosphere D/P was j
verified negative after the tornado passed.
The immediate corrective actions were to initiate a shutdown of Unit 2 due to the unknown status of Secondary Containment.
Repairs were made to the blowout panel's. inner wall during the following week and 3 Secondary Containment Leak Rate Test was performed on the combined volume of the Reactor 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 the common Reactor Building simultaneously with a filter train flow rate of not more than 4000 cubic feet per minute (cfm).
The test was conducted with a local filter train flow rate of 3975 cfm.
On June 9,1996, the final repairs to the Reactor Building siding were completed. At this time another test was conducted to verify that the repairs did not effect secondary containment.
Secondary Containment Capability Tests I
The tests were initiated at 1803 hours0.0209 days <br />0.501 hours <br />0.00298 weeks <br />6.860415e-4 months <br /> on May 18, 1996 and 1741 hours0.0202 days <br />0.484 hours <br />0.00288 weeks <br />6.624505e-4 months <br /> on June 9, 1996.
By simulating a "HI" radiation signal in the Reactor Building Ventilation Monitors, with the 'B' SBGTS train selected as the primary. 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, 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 SBGTS flow rate of approximately 3975 cfm on May 18 and 3950 cfm on June 9.
See attached data sheets for each test.
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 performance of the Secondary Containment in a degraded condition. The leak was induced by opening a four inch fire header from outside to the Reactor Building.
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Quad Cities Nuclear Power Station Units 1 and 2 Secondary Containment Leak Rate Test Summary
. Test Results (cont'd)
Corrections for the Reactor Building to atmosphere differential temperatures were not performed, due to the very small differential temperatures of +3.4of on May 18 and -10.2 F on June 9.
These small differential temperatures correspond to +0.004" H,0 and -0.006 H)3 differential pressures respectively.
The temperature correction data is shownion the attached Summary of Test Data 4
sheets for reference only, a
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SUMMARY
OF TEST DATA May 18, 1996 Quad Cities 1 & 2 Reactor Building Leak Rate
'B' SBGTS Train Differential Wall Pressure (inches of water)
Flow (cfm)
North South East West Average 3975
-0.390
-0.420
-0.390
-0.390
-0.398 Differential Reactor Building to Atmosphere Temperature - +3.4 F Temperature Correction (inches of water) = +0.004 Temperature Corrected Average Differential Pressure (inches of water) - -0.394 Induced Leak Rate Results i
Differential Wall Pressure (inches of water)
Flow (cfm)
North South East West Average 3975
-0.360
-0.390
-0.380
-0.360
-0.373 Temperature Corrected Average Differential Pressure (inches of water) - -0.369 i
Summar_y of Wind and Temperature Conditions 4
Temperature (deg. F):
Indoor 81.6o F Outdoor 85.00 F Wind Velocity (MPH):
12.4 - 18.2 Wind Direction:
South (175.4 deg.)
Elevation Above Grade Level (feet):
196 The results of the test indicate that the SBGTS is capable of raintaining 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 -0.398 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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SUMMARY
OF TEST DATA l
June 9, 1996 Quad Cities 1 & 2 Reactor Building Leak Rate
'B' SBGTS Train Differential Wall Pressure (inches of water)
Flow (cfm)
North South East West Average 3950
-0.340
-0.290
-0.285
-0.270
-0.296 Differential Reactor Building to Atmosphere Temperature - -10.2F Temperature Correction (inches of water) - -0.006 Temperature Corrected Average
-Differential Pressure (inches of water) - -0.302 Induced Leak Rate Results Differential Wall Pressure (inches of water)
Flow (cfm)
North South East West Average 3950
-0.320
-0.290
-0.290
-0.280
-0.295 Temperature Corrected Average Differential Pressure (inches of water) - -0.301 Summary of Wind and Temperature Conditions Temperature (deg. F):
Indoor 73.8o F Outdoor 63.6 F Wind Velocity (MPH):
9.3 - 10.7 Wind Direction:
West (278.3 deg.)
Elevation Above Grade Level (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 -0.296 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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