ML19305D259
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| ML19305D259 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 03/20/1980 |
| From: | BOSTON EDISON CO. |
| To: | |
| Shared Package | |
| ML19305D257 | List: |
| References | |
| NUDOCS 8004140311 | |
| Download: ML19305D259 (1) | |
Similar Documents at Pilgrim | |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
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[Table view]Startup Test Rept for Pilgrim Nuclear Power Station Cycle 11 ML20078N8421994-11-18018 November 1994 Rev 32 to Procedure 8.7.3, Secondary Containment Leak Rate Test ML20056E2221993-05-19019 May 1993 Final Pilgrim Nuclear Power Station Unit 1 Reactor Containment Bldg Integrated Leakage Rate Test Rept ML20045H5381993-01-29029 January 1993 Procedure 8.7.3,Secondary Containment Leak Rate Test. BECO-91-148, Reactor Containment Bldg Integrated Leakage Rate Test Rept1991-08-0505 August 1991 Reactor Containment Bldg Integrated Leakage Rate Test Rept ML20076D4891991-07-22022 July 1991 Procedure 8.7.3, Secondary Containment Leak Rate Test, Containment Results of Leak Rate Tests Performed on 910505 & 0620 ML20204H3501988-09-26026 September 1988 Restart Readiness Assessment Rept for Pilgrim Nuclear Power Station BECO-88-049, Reactor Containment Bldg Integrated Leakage Rate Test Types A,B & C Periodic Test1987-12-31031 December 1987 Reactor Containment Bldg Integrated Leakage Rate Test Types A,B & C Periodic Test ML20209D4721987-04-23023 April 1987 Secondary Containment Leak Rate Test Rept ML20236M1111987-03-0404 March 1987 Flooring Radiant Panel Test ML20236M1021987-03-0404 March 1987 Flooring Radiant Panel Test ML20236M1001987-03-0404 March 1987 Flooring Radiant Panel Test ML20236M0911987-03-0404 March 1987 Smoke Density Test (Nbs) ML20236M1211987-03-0404 March 1987 Flooring Radiant Panel Test ML20236M1281987-03-0404 March 1987 Flooring Radiant Panel Test ML20236M0811987-03-0404 March 1987 Smoke Density Test (Nbs) ML20112F8381985-01-0808 January 1985 Rev 15 to Secondary Containment Leak Rate Signoff ML20100F6031984-12-31031 December 1984 Reactor Containment Bldg Integrated Leakage Rate Test,Type A,B & C Periodic Test,Pilgrim Nuclear Power Station,Unit 1 ML20107A1861984-09-30030 September 1984 Rev 1 to Statistical Analysis of Boundary Strengths for Masonry Walls from Field Test Data ML20064B8921982-10-27027 October 1982 Mark I Containment Program:Plant-Unique Analysis Rept of Torus Suppression Chamber for Pilgrim Station - Unit 1 ML19331D1341980-08-18018 August 1980 Results of Startup Physics Testing Program Conducted for Cycle V Operation. ML19344B3271980-05-31031 May 1980 Primary Containment Integrated Leak Rate Test,Second Periodic Test & Local Leak Rate Tests Results,Jan-May,1980. ML19312E0011980-04-30030 April 1980 Test of Cable Penetration Fire Stops for Pilgrim 1 Nuclear Power Generating Station, Final Rept for 790907 Testing ML19320C9891980-04-23023 April 1980 Secondary Containment Leak Rate Test Data.Includes Test Conditions,Base Reading & Standby Gas Treatment Sys a & B Performance ML19312D9971980-03-31031 March 1980 Test of Cable Penetration Fire Stops for Pilgrim 1 Nuclear Generating Station, Final Rept for 790829 Testing ML19305D2591980-03-20020 March 1980 Secondary Containment Leak Rate Test Data. ML20126B3691980-03-0303 March 1980 Secondary Containment Leak Rate Test Data ML19312D9951980-01-31031 January 1980 Test of Cable Penetration Fire Stops for Pilgrim 1 Nuclear Power Generating Station, for 790531 Testing ML20236Q8821976-11-0505 November 1976 Friction Coefficients of Water-Lubricated Stainless Steels for Spent Fuel Rack Facility 1995-09-01 |
Text
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. TABLE I
- SECONDARY CONTAINMENT LEAK RATE TEST DATA TEST DATE: MARCH 20, 1980 TEST CONDITIONS Wind Direction . Southwest Wind Velocity A 8 MPH Barometric Pressure (outside Rx. Bldg.) 30.02" Hg Outside Temperature 48 F.
Inside Temperature 76 F.
BASE READING (0 Flow)
Reactor Bldg. Atmosphere d P ("H 2O)
N. .06 '
E. .05 W. .08 S. .15 "A" SGTS PERFORMANCE System Flow Rate - 4000 cfm Reactor Bldg. Atmosphere _OP ("H20)
N. .39 E. .38 W. .37 S. .40 Secondary Containment Vacuum - .32" H O 2 "B" SGTS PERFORPldiCE System Flow Rate 4000 cfm Reactor Bldg. Atmosphere 3 P ("H 2O)
N. .4 E. .34 W. .35 S. .40 Secondary Containment Vacuum - .27" H2O 80 0A 14 0 3/l
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