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| TABLE I SECONDARY CONTAINMENT LEAK RATE TEST DATA TEST DATE: APRIL 23, 1980 TEST CONDITIONS Wind Direction North _ | | TABLE I SECONDARY CONTAINMENT LEAK RATE TEST DATA TEST DATE: APRIL 23, 1980 TEST CONDITIONS Wind Direction North _ |
| Wind Velocity 10 MPH , | | Wind Velocity 10 MPH , |
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| BASE READING (0 Flow) | | BASE READING (0 Flow) |
| Reactor Bldg. Atmosphere A P ("H O) 2 N. .75 E. .08 W. .80 S. .28 "A" SGTS PERFORMANCE System Flow Rate 2700 cfm Reactor Bldg. AtmosphereAP ("H O) 2 N. -1.16 E. .35 W. -1.12 S. .58 Secondary Containment Vacuum . 30" H20 "B" SGTS PERFORMANCE System Flow Rate 2800 cfm Reactor Bldg. Atmosphere AP ("H2 0) | | Reactor Bldg. Atmosphere A P ("H O) 2 N. .75 E. .08 W. .80 S. .28 "A" SGTS PERFORMANCE System Flow Rate 2700 cfm Reactor Bldg. AtmosphereAP ("H O) 2 N. -1.16 E. .35 W. -1.12 S. .58 Secondary Containment Vacuum . 30" H20 "B" SGTS PERFORMANCE System Flow Rate 2800 cfm Reactor Bldg. Atmosphere AP ("H2 0) |
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| N. -1.14 E. .38 W. -1.12 S. .58 Secondary Containment Vacuum .33"H20 80 07180M | | N. -1.14 E. .38 W. -1.12 S. .58 Secondary Containment Vacuum .33"H20 80 07180M |
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Latest revision as of 04:47, 1 February 2020
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20196D0241999-06-16016 June 1999
Proposed Tech Specs Re Reactivity Control Incorporating Operating Requirements That Are Consistent with NEDO-21231, Banked Position Withdrawal Sequence
ML20206R8161999-05-11011 May 1999
Proposed Tech Specs Re HPCI & RCIC Surveillance Testing
ML20206H9771999-05-0505 May 1999
Proposed Tech Specs Modifying Licensing Basis for EDG on- Site Diesel Fuel Storage Requirements & Corresponding TSs
ML20205A1451999-03-23023 March 1999
Core Shroud Insp Plan
ML20207F1171999-03-0303 March 1999
Proposed Tech Specs Page 3/4.6-13 Re Reactor Vessel Matl Surveillance Program Withdrawal Schedule
ML20151S3851998-08-31031 August 1998
Long-Term Program:Semi-Annual Rept
ML20237E0851998-08-24024 August 1998
Proposed Tech Specs Pages Supporting Proposed TS Amend Related to EDG AOT
ML20236X7191998-07-31031 July 1998
Proposed Tech Specs Page 3/4.9-5 Re Suppl to EDG for Allowed Outage Time
ML20249C7101998-06-26026 June 1998
Proposed Tech Specs Correcting Typos & Updating Bases
ML20249B3231998-06-15015 June 1998
Revised Complete Set of TS Pages Re Relocation of Radioactive Effluent TS & Radiological Environ Monitoring Program to ODCM
ML20217F9341998-03-26026 March 1998
Proposed Tech Specs Re EDG Allowed Outage Time
ML20217H2791998-03-25025 March 1998
Proposed Tech Specs 3.6.A.1 & 4.6.A.1,pertaining to Primary Sys Boundary,Thermal & Pressurizations Limitations & Surveillance Requirements & Basis 3/4.6.A
ML20203D4981998-02-20020 February 1998
Proposed Tech Specs Pages,Incorporating Ultimate Heat Sink Temperature of 75 F Into TS 3/4.5.B & Bases,As Required by Amend 173
ML20217K5691997-10-24024 October 1997
Proposed Tech Specs Page Adding Footnote Declaring One Containment Isolation valve,30-CK-432,operate for Limited Period Despite Not Being within IST Interval for Reverse Flow Testing
ML20211N6871997-09-16016 September 1997
Rev 9 to Procedure 8.I.1.1, Inservice Pump & Valve Testing Program
ML20211G2381997-09-15015 September 1997
Rev 8 to PNPS-ODCM, Pilgrim Nuclear Power Station Odcm
ML20211G2311997-09-12012 September 1997
Proposed Tech Specs Re Radiological Environ Monitoring Program Moved to ODCM
ML20216C0631997-08-29029 August 1997
Semi-Annual Long Term Program Schedule
ML20210K4381997-08-0808 August 1997
Revised TS Pages 3/4.5-7,B3/4.5-6 & B3/4/.5-7 Requiring Verification That SBO-DG Is Operable Prior to Voluntarily Entering LCO
ML20196J0041997-07-22022 July 1997
Proposed Revised TS Bases for Section 3.5.F,correcting Volume of Water Available in Refuel Cavity & Dryer/Separator Pool When Flooded to Elevation 114 Ft & Revising Torus Water Volume to Reflect Volume Above Min Pump NPSH
ML20210K3551997-07-0101 July 1997
Rev 16 to Procedure 7.8.1, Water Quality Limits
ML20136J5501997-03-0707 March 1997
Proposed Tech Specs Rev for Section 3.10, Core Alterations Allowing Removal of Suspect Fuel Bundles Out of Planned Sequence
ML20134C9671997-01-24024 January 1997
Proposed Tech Specs 2.0 Re Safety Limits
ML20133A6511996-12-23023 December 1996
Proposed Revised Tech Specs 1.0 Re definitions,3.4 Re Standby Liquid Control sys,3.5 Re Core & Containment Cooling systems,3.7 Re Containment Systems & 3.9 Re Auxiliary Electrical Sys
ML20132E5491996-12-10010 December 1996
Proposed Tech Specs Table 3.2.C.1 Re Instrumentation That Initiates Rod Blocks,Table 3.2.C.2 Re Control Rod Block Instrumentation Setpoints & Table 4.2.C Re Minimum Test & Calibr Frequency for Control Rod Blocks Actuation
ML20135C1461996-11-26026 November 1996
Proposed Tech Specs,Modifying Definition 1.M, Primary Containment Integrity, to Include All Instrument Line Flow Check Valves to Make Definition Consisten W/Lco 3/4.7.A.2.a.4
ML20134K4361996-11-0707 November 1996
Proposed Tech Specs Re Installation of BWROG Enhanced Option 1A
ML20117K6551996-09-0505 September 1996
Proposed Tech Specs,Providing Revised TS Pages 3/4.5-7 & 3/4.5-6
ML20116M1561996-08-12012 August 1996
Proposed Tech Specs to Plant TS Section 6.0,Administrative Controls & Sections 6.5.B.10.C & 6.14 of Util Quality Assurance Manual
ML20117K6611996-07-17017 July 1996
Rev 15 to PNPS Procedure 1.2.2 Administrative OPS Requirements
ML20108C0581996-05-0101 May 1996
Proposed Tech Specs Re Core Alteration to LCO & Surveillance Conditions Associated W/Secondary Containment
ML20111B4201996-05-0101 May 1996
Proposed Tech Specs,Reflecting Implementation of 10CFR50 App J,Option B
ML20111C2761996-05-0101 May 1996
Proposed Tech Specs 3.1.1 Re Reactor Protection Sys (Scram) instrumentation,3.2.C.1 Re Instrumentation That Initiates Rod Blocks & 3/4.4 Re Standby Liquid Control
ML20108C1071996-05-0101 May 1996
Proposed Tech Specs,Relocating Administrative Controls Re QA Review & Audit Requirements of Section 6 from Plant TS to Boston Edison QA Manual
ML20108A6561996-04-25025 April 1996
Proposed Tech Specs Re Part of Overall Effort to Improve Outage Performance at Plant
ML20095E0771995-12-0808 December 1995
Proposed Tech Specs Bases Page B2-2,including GE11 GEXL Correlation Axial Power Profile & R-factor Ranges & Correcting Error in GE11 GEXL Correlation Mass Flux Range in GE Design ref,NEDE-31152-P, GE Fuel Bundle Designs
ML20100J2521995-11-22022 November 1995
Rev 7 to Pilgrim Nuclear Power Station Odcm
ML20092B5861995-09-0101 September 1995
Rev 0 to Third Ten-Yr Interval ISI Plan for Pilgrim Nuclear Power Station
ML20092C4331995-09-0101 September 1995
Startup Test Rept for Pilgrim Nuclear Power Station Cycle 11
ML20092A4421995-08-31031 August 1995
Corrected Tech Spec Page Re Reactor High Pressure Trip Setting
ML20086K2661995-07-14014 July 1995
Proposed Tech Specs Re Section 2.1,Bases:Safety Limits; Section 3.3.C,scram Insertion Times & Section 4.11.C, Minimum Critical Power Ratio to Reflect Use of Advanced GE-11 Fuel Design in Cycle 11
ML20078R6221995-02-15015 February 1995
Proposed Tech Specs Substituting for Pages Contained in Proposed TS Amends Submitted Prior to 950130 Authorization
ML20078N4861995-02-0909 February 1995
Proposed Tech Specs,Increasing Reactor High Water Level Isolation Trip Level Setting
ML20077Q1181995-01-13013 January 1995
Owner'S Specification for Reactor Shroud Repair
ML20077M6921995-01-0909 January 1995
Proposed Reformatted Tech Specs & Bases
ML20077A8991994-11-22022 November 1994
Proposed Tech Specs Re Suppression Chamber Water Level
ML20077B1861994-11-22022 November 1994
Proposed Tech Specs 3.5.F,4.5.F.1 & 3.9.B.1 & 2 Re EDG Allowed out-of-svc Time
ML20078K7961994-11-22022 November 1994
Proposed Tech Specs Re Changes to MSIV Leakage Requirement
ML20078K8151994-11-22022 November 1994
Proposed TS Pages 3/4.2-20 & 3/4.2-35 Re Tables 3.2.C-1 & 4.2.C
ML20078N8421994-11-18018 November 1994
Rev 32 to Procedure 8.7.3, Secondary Containment Leak Rate Test
1999-06-16
[Table view]
Category:TEST REPORT
MONTHYEARML20092C4331995-09-0101 September 1995
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
[Table view] |
Text
e ~ _.
TABLE I SECONDARY CONTAINMENT LEAK RATE TEST DATA TEST DATE: APRIL 23, 1980 TEST CONDITIONS Wind Direction North _
Wind Velocity 10 MPH ,
Barometric Pressure (outside Rx. Bldg.) 29.27" Hg Outside Temperature 430 F.
Inside Temperature 750 F.
BASE READING (0 Flow)
Reactor Bldg. Atmosphere A P ("H O) 2 N. .75 E. .08 W. .80 S. .28 "A" SGTS PERFORMANCE System Flow Rate 2700 cfm Reactor Bldg. AtmosphereAP ("H O) 2 N. -1.16 E. .35 W. -1.12 S. .58 Secondary Containment Vacuum . 30" H20 "B" SGTS PERFORMANCE System Flow Rate 2800 cfm Reactor Bldg. Atmosphere AP ("H2 0)
N. -1.14 E. .38 W. -1.12 S. .58 Secondary Containment Vacuum .33"H20 80 07180M
-