ML20211A233

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Forwards Summary of Secondary Containment Leak Rate Test on 860918 Per Tech Spec Section 4.7.C.1.c
ML20211A233
Person / Time
Site: Quad Cities  
Issue date: 10/01/1986
From: Wojnarowski J
COMMONWEALTH EDISON CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
2192K, NUDOCS 8610150035
Download: ML20211A233 (3)


Text

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' Address Reply to: Post Office Box 767 PitIORITY ROUTING

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m-y October 1, 1986 L1T oL om gL_

Pt.0 FILE g Mr. James G. Keppler Regional Administrator U.S. Nuclear Regulatory Commission Ragion III 799 Roosevelt Road Glen Ellyn, IL 60137

Subject:

Quad Cities Station Units 1 and 2 secondaty Containment Capability Test Summary Technical Report NRC Docket Nos. 50-254 and 50-265

Dear Mr. Keppler:

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 Containment 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.l.c of the Quad Cities Units 1 and 2 Technical Specifications.

If you have any questions regarding this matter, please contact this office.

Very truly yours, F

7, J. R. Wojnarowski Nuclear Licensing Administrator la Attachment cc: NRC Resident Inspector - Quad Cities 0610150033 061001 2192K PDR ADOCK 00000254 g

P PDR OCT C 1986

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Quad-Cities Nuclear Power Station Units 1 and 2 Secondary Containment Leak Rate Test Summary Introduction Prior to the Unit Two Refueling Outage at the End of Cycle Eight 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.

7

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g e-Summary of Test Data September 18, 1986 Quad-Cities 1 & 2 Reactor Building Leak Rate-

'B' SBGT Train Wall Pressure (inches of water)

Flow (cfm)

North South East West Average 4000

-0.26

-0.275

-0.255

-0.24

-0.258 Summary of Wind and Temperature Conditions Temperature (F'):

Indoor 82'F Outdoor 62'F Elevation Above Grade Level (feet):

196 Wind Velocity (MPH):

4 Wind Direction:

South - 180'

-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 -0.258 inches of water, indicating adequate performance of the Secondary. Con-tainment and Standby Gas Treatment System.