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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
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Text
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TEST NUMBER _g-8279 Independent / Textile (4a5 Service,lnc.
P.O. Box 1948 /1503 Murray Avenue Dalton, Georgia 30722-1948 / Phone 404-278-3013 REPORT CUSTOMER: BOSTON EDISON MARCH 4, 1987
)
SUBJECT:
Specimens of the submitted samples were prepared and tested in accordance with l ASTM E-648 and/or Federal Test Method 372, NFPA 253 i FLOORING RADIANT PANEL TEST Sample Description Style: PATTERN: L8203 Color: 354 Roll No.: DYE LOT e 17472 Fiber:
Pile:
Secondary Backing:
Test Assembly Burlington's pressure sensitive adhesive was used to give the carpet, described above, directly to 1/4 inch asbestos / cement board for testing.
Test Results Specimen No.1 Specimen No. 2 Specimen No.3 Critical Radiant Flux: .79 watts /cm2 .86 watts /cm2 .84 watts /cm2 Total Burn Length: 25.0 cm. 21.0 cm. 22.0 cm.
Flame Front Out: 24.0 minutes 18.0 minutes 22.0 minutes Average Critical Radiant Flux: ,g3 watts /cm2 n Estimated Standard Deviation .04 watts /cm2
,$$ 5% coefficient of variation N00 ge Some separation of primary backing from secondary occured during testing due to w melt.ing of precoat Laminate CD O OQ i}h 04 Authorized Signa u 'e
$ INDEPENDENT TEXTIL ' TESTI SERVICE, INC.
OCc our letters and reports are for the exclusive use of the customer to wnom they are addressed. and ineir communication to any others of the use of the I' Q name of Independent Textile Testing service. Inc., must receive our prior wotten approval our let'ers and reports appiy only to the sample tested and (D O.o- are not necessarily indicative of the quahties of apparently identical or simiiar products The reports and lettera and the name of the indep indent Textde Testing service. inc , are not to be used under any circumstances in as<ertising to the general public 1 400
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