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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20216E6111999-09-0707 September 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210H0731999-07-28028 July 1999 Proposed Tech Specs 3/4.7.5.1, Ultimate Heat Sink, Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4311999-07-27027 July 1999 Proposed Tech Specs,Changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G4801999-07-26026 July 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210G9161999-07-26026 July 1999 Proposed Tech Specs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrumentation - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5391999-07-26026 July 1999 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B for Type B & C Containment Leakage Rate Testing ML20195F9351999-06-10010 June 1999 Proposed Tech Specs,Revising TS 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.6.5.1, Crevs ML20207E7941999-05-21021 May 1999 Proposed Tech Specs Allowing Use of Expanded Spent Fuel Storage Capability ML20205E5031999-03-19019 March 1999 Proposed Tech Specs Withdrawing Proposed New Action B, Previously Submitted in 981027 Application ML20204F1821999-03-0909 March 1999 Proposed Tech Specs,Adopting Changes in Frequency & Scope of Volumetric & Surface Exams Justified by W TR WCAP-14535A ML20155E4971998-10-28028 October 1998 Proposed Tech Specs 4.0.2 Re Applicability of 25% Surveillance Interval Extension Allowance ML20197G5521998-10-28028 October 1998 Rev 8 to Dbnps,Unit 1 Technical Requirements Manual ML20155E3231998-10-28028 October 1998 Proposed Tech Specs Revising Various Sections of 6.0, Administrative Controls, Including Relocation of 6.11 Contents to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155D7791998-10-27027 October 1998 Proposed Tech Specs Relocating TS SR 4.6.5.1.d.4 Re Evs Negative Pressure Testing to TS 3/4.6.5.2,deleting TS Definition 1.24 & Making Related Changes Associated with Deletion of Subject Definition ML20155D8521998-10-27027 October 1998 Proposed Tech Specs Revising SRs 4.8.2.3.2.d,4.8.2.3.2.e, 4.8.2.3.2.f & Table 4.8-1 Re Testing of 125 Volt DC Station Batteries & Applicable TS Bases ML20155E0721998-10-27027 October 1998 Proposed Tech Specs Revising 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation,To Provide Potential Reduction in Spurious Trip Rate for Potential Cost Savings in Excess of $50,000 ML20151W3071998-09-0808 September 1998 Proposed Tech Specs Permitting Use of Framatome Cogema Fuels M5 Advanced Alloy for Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20151W2991998-09-0808 September 1998 Proposed Tech Specs Revising Section 3/4.7.6, Plant Systems - CREVS & Associated Bases ML20206D2721998-08-28028 August 1998 Rev 11,change 1 to Odcm ML20217P8351998-04-24024 April 1998 Proposed Tech Specs Clarifying Discussion of Margin Between RPS High Pressure Trip Setpoint & Lift Setting for Pressurizer Code Safety Valves ML20217P8811998-04-24024 April 1998 Proposed Tech Specs 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2 & Associated Bases Relocating Tables of Response Time Limits to Plant USAR Technical Requirements Manual ML20217C4881998-03-20020 March 1998 Proposed Tech Specs SR 4.4.5.3.c.1,providing Greater Specificity as to Location of Addl Insps in Unaffected SG ML20217N4471998-02-27027 February 1998 Proposed Tech Specs Pages Provided to Modify Proposed New Action 3.7.6.1.b to Make More Consistent w/NUREG-1431 ML20203L1111998-02-26026 February 1998 Proposed Tech Specs Pages Re Amend to License NPF-3 Involving Incorporation of New Repair Roll Process for SG Tubes W/Defects in Upper Tube Sheet ML20197J2621997-12-23023 December 1997 Proposed Tech Specs Pages Re Changes to TS Definition 1.2, TS 3/4/9.5 & New TS 3.0.6 & Associated Bases.Ts Index Rev to Reflect Change to TS 3/4.9.5,included ML20197J5971997-12-23023 December 1997 Proposed Tech Specs Pages,Revising TS Surveillance Requirements for ISI Requirements of Internal Auxiliary Feedwater Header,Header to Shroud Attachment Welds & External Header Thermal Sleeves ML20217M5601997-09-0505 September 1997 Rev 11.0 to Davis-Besse Odcm ML20217R2821997-08-26026 August 1997 Proposed Tech Specs,Clarifying LCO 3.6.1.3.a & Revising Surveillance Requirement 4.6.1.3.c ML20217R2871997-08-26026 August 1997 Proposed Tech Specs,Modifying TS 3.2.5 Action Statement to Require Power Reduction to Less than 5% of Rated Thermal Power within Four Hrs If RCS Flow Rate Is Less than Specified Limit for Greater than Two Hrs ML20217G5981997-07-29029 July 1997 Proposed Tech Specs 3/4.4.3 Re Safety Valves & Pilot Operated Relief valve-operating ML20141F1101997-06-24024 June 1997 Proposed Tech Specs,Deleting Requirements for Safety Features Actuation Sys Containment High Radiation Monitors ML20138C3261997-04-18018 April 1997 Proposed Tech Specs 3/4.7.6 Revising Limiting Condition for Operation to Include New Required Actions in Event That One or Both Channels of Radiation Monitoring Instrumentation Becomes Inoperable ML20138A6891997-04-18018 April 1997 Proposed Tech Specs 3/4.5.3.2.1 & 3/4.5.2 Modifying Presently Specified 18-month Surveillance Frequencies to New Specified Frequencies of Once Each 24-months ML20140D9481997-04-0909 April 1997 ODCM, Rev 10 ML20138M1281997-02-14014 February 1997 Proposed Tech Specs 3.5.2 Re Emergency Core Cooling Systems & 4.5.2.f Re Surveillance Requirements ML20134L0561997-02-13013 February 1997 Proposed Tech Specs Re Changes Made Concerning Decay Heat Removal Sys Valve ML20134F1811997-01-30030 January 1997 Proposed Tech Specs Re Possession & Use of SNM as Reactor Fuel ML20134D7621997-01-30030 January 1997 Proposed Tech Specs Revising SR Intervals from 18 to 24 Months Based on Results of DBNPS Instrument Drift Study & TS 2.2, Limiting Safety Sys Settings, Based on Results of Revised Framatome RPS Instrument String Error ML20134B0591997-01-20020 January 1997 Proposed Tech Specs 3/4.5.3 Re ECCS Subsystems ML20132B7031996-12-11011 December 1996 Proposed Tech Specs Revising TS Definitions,Instrumentation TS & ECCS TS for Conversion to 24 Month Fuel Cycle for License NPF-3 ML20134F1891996-10-28028 October 1996 Proposed Tech Specs 3/4.8 Re Electrical Power Systems ML20117P5311996-09-17017 September 1996 Proposed Tech Specs,Supporting Conversion of DBNPS from 18 Month to 24 Month Fuel Cycle ML20117N8531996-09-12012 September 1996 Proposed Tech Specs Re Reactivity Control Systems & Emergency Core Cooling Systems ML20117M2201996-09-0404 September 1996 Proposed Tech Specs 6.2.3,removing Specific Overtime Limits & Working Hours ML20116K2631996-08-0707 August 1996 Proposed Tech Specs Re Definitions,Applicability Bases, Containment Spray Sys & Containment Isolation Valve for Conversion to 24 Month Fuel Cycle ML20117K1911996-05-28028 May 1996 Proposed Tech Specs 3/4.3.1.1 - RPS Instrumentation & TS 3/4.3.2.3 - Anticipatory RTS Instrumentation Increasing Trip Device Test Interval ML20101M1921996-03-29029 March 1996 Proposed Tech Specs 3/4.6.4.4 - HPS,3/4.6.5.1 - Shield Building Evs & 3.4.7.6.1 - CREVS Re Changing Surveillance Requirements for Charcoal Filter Lab Testing to Revise Methodology Used to Determine Operability in ESF AHUs ML20101C6961996-03-0606 March 1996 Proposed Tech Specs,Allowing Deferment of SR 4.5.2.b for ECCS Flowpath Containing HPI Pump 1-2 Until 10th Refueling Outage,Scheduled to Begin 960408 ML20100E0101996-02-0505 February 1996 Proposed TS 3/4.3.2.1,Table 3.3-3,safety Features Actuation Sys Instrumentation,Reflecting Design & Actuation Logic of Plant Sequencers & Essential Bus Undervoltage Relays ML20107C3101995-12-21021 December 1995 Rev 9 to Odcm 1999-09-07
[Table view] Category:TEST REPORT
MONTHYEARML20138E6191995-01-17017 January 1995 ASTM E136-94 Behavior of Matls in Vertical Tube Furnace. W/Rept Summarizing Results of Preliminary Tests Under Project 82NK21937,dtd 830926 & Ltr Forwarding Test Results Re Caulking Matl ML20209B5111987-04-22022 April 1987 Summary Rept for Davis-Besse Motor-Operated Valve Reliability Program ML20212M8171986-08-26026 August 1986 Test of Integrated Control Sys at Davis-Besse Nuclear Power Station to Determine Integrated Control Sys Response When Power Lost & Subsequently Restored, on 860317 ML20107B3061985-01-31031 January 1985 Rev 1 to Calculation M-8, Pressurizer Surge Line - Class 1 Piping Analysis ML20099H1181984-12-31031 December 1984 Reactor Containment Bldg Integrated Leak Rate Test ML20128N8361982-09-30030 September 1982 Performance Test Program for Increased Blowdown on Crosby 4M16 HB-BP-86 Pressurizer Safety Valve ML20063E2911982-03-22022 March 1982 Environ Qualification Rept 3394-2,Anticipatory Reactor Trip Sys ML20063E2351982-03-0101 March 1982 Seismic Qualification Rept 3394-1 Anticipatory Reactor Trip Sys ML20063E2731982-02-11011 February 1982 Seismic Simulation Test Program on Anticipatory Reactor Trip Sys (Arts) ML20039E6801981-12-18018 December 1981 Rept on 811209 Ottawa County/Toledo Edison Siren Test. ML20010G8621981-06-0909 June 1981 B&W Post-Test Analysis for Semiscale Test S-07-10D. ML20004C0871981-05-20020 May 1981 Suppl to Post-Refueling Physics Testing,Davis-Besse Unit 1, Cycle 2 Power Escalation Testing. ML19350A4291981-03-0505 March 1981 Cycle 2 Startup Rept for Facility ML20062J9351980-10-14014 October 1980 Analog & Digital Isolation Device Qualification, & Addendum a ML19337B6311980-08-29029 August 1980 Primary Reactor Containment Integrated Leakage Rate Test Rept. ML19260A2031979-10-0505 October 1979 Revised Pages to Initial Startup Rept, Suppl 6,covering 790706-1005 ML19259C7061979-08-0808 August 1979 Revised Pages to Chapter 1 of Initial Startup Rept,As Revised by Suppl 5 for Period 79046-0705 ML19319B8261978-05-26026 May 1978 Fire Confirmation Testing of Cable Tray Penetration Seals in Concrete Walls Utilizing Silicone Elastomers. Prepared for Util ML19329A9281978-05-0808 May 1978 Initial Startup Rept. ML19317F6341977-09-30030 September 1977 Confirmatory Testing of Fire Retardant Seals for Electrical Penetrations Through Fire Barriers Installed at Facility. ML19329A9051977-05-25025 May 1977 Fire Equivalency Test for Silicone Foam. ML19329A8101977-03-30030 March 1977 Conduit Separation Test Program, Final Program ML19329A9801976-12-22022 December 1976 Containment Vessel Integrated Leak Rate Test. ML19319B8241976-12-16016 December 1976 Isolation Circuit Test Rept. ML19329B1861976-12-16016 December 1976 Reactor Protection Sys Noise Testing Summary. ML19319B8251976-12-16016 December 1976 Cleveland Illuminating Co East Lake Tests. ML19319B8271976-12-16016 December 1976 Lynchburg Research Ctr Tests. ML19329C2141976-12-15015 December 1976 ECCS Emergency Sump & Pump Suction Line Testing, Final Rept ML19329C2991976-12-14014 December 1976 Hose Stream Testing of Bisco SF-20 Silicone Foam,Bisco SF-150L High Density Silicone & Bisco Flexible Boot Penetration Seals. ML19329C2051976-10-15015 October 1976 ECCS Emergency Sump Model Testing to Investigate Vortexing Potential, Interim Rept ML19319B8301971-01-21021 January 1971 Bailey Meter Co 880 Sys Count Rate Channel Noise Testing, 710104-21. 1995-01-17
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-TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT 1 t
l Ji FIRE EQUIVALENCY TEST l
l EUR l SILICONE FOAM (SF-20 vs Dow Corning 3-6548)
May 25, 1977 H
800'1150 [C 2
. .' q y Introduction The purpose of this report is to describe the circumstances leading up to the need for a substitute naterial for BISCO SF-20 silicone foam, the se-1ection and testing of Dow Ccrning Corporation 3-6548 silicone foam, and our evaluation of the suitability of DC 3-6548 for use at Davis Besse Nuclear Power Station Unit 1.
Discontinuation of BISCO SF-20 The BISCO SF-20 silicone foam is a four-part mixture of Dow Corning material.
The formulation of this four-part mixture is a proprietary process with BISCO.
Subsequer.t to the BISCO development of their formulation, Dow Corning pro-caeded to develop a two-part mixture which was proprietary to Dow Corning and which is available to any applicator and is marketed under the name of Dow Corning 3-6548 Silicone RIV Foac. The BISCO SF-20 material had been fully qualified by testing for application at Davis-Besse and was approved by NEL-PIA for fire barriers on the project.
On April- 6,1977 bisco informed us that some components of the SF-20 formula-tion were no longer being manufactured by Dow Corning and would not be available to comp.ete the BISCO work. Immediate action was required as the project was preparing to load fuel that month.
As a result of this disclosure, BISCO was requested to be at the Davis-Besse site on April 7 to review this situation. We contacted Dow Corning and were informed that there was no possibility that additional production of the com-ponents for the BISCO SF-20 material would be undertaken.
Efforts were made to review i 's in the country that might have a stock of- this material, including General Electric and TVA, but no material could be found.
On April 8 discussions at the Davis-Besse site between Bechtel, BISCO and TECo led to the decision to attempt to qualify the DC 3-6548 material for use on the Davis-Besse project. NEL-PIA indicated titat they would approve this ma-terial based upon an equivalency fire exposure test performed in accordance with the requirements of ASTM E 119-73 " Standard for Fire Tests of the Building Construction and Materials".
Testing A three-hour fire exposure test was performed at the Fire Research Laboratory of the Portland Cement Association in Skokie, Illinois on April 12, 1977. A 12-inch thick concrete slab was prepared containing four one-foot square blockouts. Two of the one cubic foot blockouts were filled with SF-20 ma-terial, and the other two of the one cubic foot blockouts were filled with Dow Corning 3-6548 silicone foam. Each blockout was filled to the full depth L of.12 inches, which is the minimum depth .used as a fire barrier at Davis Besse Unit'l.
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The fire endurance test was conducted in accordance with ASTM E 119-73.
The test slab was placed horizontally on the furnace such that the heat would impinge. upwards against the material. The foam materials were exposed to heat in accordance with Section 2, Time-Temperature Curve, of ASTM E 119-73.
The temperatures within each seal were measured during the fire exposure.
The actual temperature data taken during this test is attached in Tables I, II, III and IV. During the test the temperatures at the unexposed surface did not exceed the ASid Heat Transmission End Point Criteria. The temper-ature 3 inches beneath the unexposed surface (as close as less than 2 inches from the charring surface) did not exceed 160'F. The temperatures at the surf aces of each seal, and the temperatures at similar depths within each seal correspond with slight exceptions.
Following the three-hour fire exposure it was noted that no smoke or flame had oenetrated or bypassed the unexposed seal surface. When the test slab was removed from the furnace it was placed charred-face downward on a re-fractory blanket and allowed to cool. During this cooling period the ma-terial was allowed to smolder, thus continuing to degrade the sealing material. Af ter approximately 30 minutes the slab was raised, and the charred material was scraped away so that depth measurements could be made. The SF-20 material was charred to a maximum depth of 6 inches in both blockouts.
The Dow Corning 3-6548 material was charred to a maximum depth of 7 3/8 inches in one blockout and 71/2 inches in the other blockout.
Evaluation The fire equivalency test satisfied the requirements of ASTM E 119-73 and NEL-PIA and is consistent with testing pcrformed to qualify the SF-20 ma-terial for use at Davis-Besse Unit 1.
The arrangement of the test apparatus provided conservatism in that by being placed above the flame, much of the charred material fell from the blo< kout during the test. This caused the remaining material to be exposed to rore direct furnace heat, thus increasing the rate of cut arial degeneration Additional conservatism was provided when the material was allowed to amolder for 30 minutes following the fire exposure test. This caused the mate rials to char to a greater depth than had occurred daring the test.
The differences in the depth of charring betwaen the two materials is not con-sidered to be significant as compared with the total depth of the penotration seal. More importantly, in no case did the seal permit the transmission of flame or smoke, the unexposed surface of the seal remained near ambiest temperature, and even seal material within 2 inches of the charring eurface remained cool with respect to the furnace temperature.
Conclesions The results of the fire equivalency test provide complete confidence that the Dow Corning 3-6548 silicone foam will perform as a suitable fire barrier.
The testing, which was observed by representatives of Toledo Edison Company, Bechtel Company, BISCO and NEL-PIA, met the conditions of acceptance of ASTM E 119-73. By virtue of this test and receipt of NEL-PIA approval of the material, all established criteria had been satisfied to qualify Dow Corning 3-6548 silicone - foam as a three-hour fire barrier.
2
3 HOUR FIRE EXPOSURE EQUIVALENCY TEST of-
. BISCO SF-20 POUR COMPONENT SILIC0dc FOAM -
and DOW CORNING CORP. 3-6548 SILICONE FOAM TABLE I Surface Temperature OF 1
Minutes A B C D 0 90 90 90 90 30 85 80 85 85 60 80 80 80 80 90 85 85 80 85 120 85 85 85 85 150 85 85 85 85 180 90 90 85 90 TABLE II Temperature immediately below skin OF Minutes A B C D 0 80 80 90 90 30 80 80 85 85 60 80 85 80 ed 90 80 85 85 90 120 80 85 90 90 UO 85 80 90 90 180- 85 85 95 100 Note: Seals A & B - BISQ SF-20 Seals C & D - Dow Corning 3-6548 3
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3 HOUR FIRE EXPOSURE EQUIVALENCi TEST of
. BISm SF-20 NUR COMPONENT SILICONE POAM and DOW (DRNING CORP. 3-6548 SILICDNE MAM TABLE III Temperatures 3" from surface OF Minutes A B C D 0 80 80 80 90 30 80 85 85 90 60 80 85 90 90 90 85 85 100 100 120 90 85 110 120 150 115 90 125 140 180 150 105 150 160 TABLE IV Temperatures 6" from surface OF Minutes A B C D 0 80 . 80 90 90 30 85 85 100 100 60 85 95 130 125 90 90 110 190 170 120 125 130 270 245 150 330 200 350 330 180 495 340 460 450 Note: Seals A & B - BISCO SF-20 Seals C & D - Dow Corni. g 3-6548 4
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