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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211Q4981999-09-10010 September 1999 Proposed Tech Specs Clarifying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits & Adding Ref to Caldon TR for LEFM ML20211G3221999-08-26026 August 1999 Proposed Tech Specs 4.0.6 Re SG Surveillance Requirements ML20212H0771999-08-20020 August 1999 Rev 6 to CPSES Glen Rose,Tx ASME Section XI ISI Program Plan for 1st Interval on 990820. Page 119 in Unit 1 ASME Section XI of Incoming Submittal Not Included ML20212G0821999-08-20020 August 1999 Rev 4 to Augmented Inservice Insp Plan for Cpses,Unit 1 ML20210R7091999-08-13013 August 1999 Revised Proposed Tech Specs for LAR 98-010,proposing Rev to TS Table 3.3.1-1, Rt Sys Instrumentation & TS Table B 3.3.1-1, Rt Sys Setpoints ML20211M0041999-08-0505 August 1999 Rev 31 to Technical Requirements Manual ML20211G7401999-07-27027 July 1999 Revs 29 & 30 to Technical Requirements Manual (TRM) for Cpses,Units 1 & 2 ML20209E1861999-07-0909 July 1999 Proposed Tech Specs,Adding Reactor Core Safety Limit Figures to Section 5.6.5 of Ts,Clarifying That Overpower N-16 Setpoint Remains in TS & Reflecting NRC Approval of TRs Used to Determine Core Operating Limits Presented in COLR ML20212J4251999-06-23023 June 1999 Proposed Tech Specs,Revising EDG Start Be Emergency Start Instead of Normal Start Following Loss of Offsite Power ML20195E5401999-06-0404 June 1999 Proposed Tech Specs Pages 3.2-6,3.4-24,3.4-25,3.7-23,3.7-30, 3.8-25,3.9-9,3.9-10 & 4.0-2,provided as Addl Aditorial Changes Supplementing LAR 99-001 ML20195B6461999-05-27027 May 1999 Marked-up TS Pages Re LAR 99-004,changing Plant Battery Surveillance ML20195B6771999-05-24024 May 1999 Proposed Tech Specs Relocating Parameter Limits Allows for Available Operating & Analytical Margins to Be Used in Most Efficient Manner ML20206G7111999-05-0404 May 1999 Proposed Tech Specs Revising Surveillances Associated with Plant Battery & EDGs & Miscellaneous Editorial Corrections ML20206Q0311999-04-16016 April 1999 Rev 28 to CPSES Technical Requirements Manual ML20205Q1681999-04-14014 April 1999 Rev 27 to CPSES Technical Requirements Manual ML20207F3511999-02-25025 February 1999 Fire Endurance Test to Qualify Protective Envelope for Class IE Electrical Circuits ML20203B0011999-01-25025 January 1999 Rev 10 to Security Training & Qualification Plan ML20211C1071999-01-15015 January 1999 Rev 3 to ASME Section XI ISI Program Plan,Unit 2 - 1st Interval ML20198J3171998-12-21021 December 1998 Proposed Tech Specs,Proposing Changes Administratively for Unit 1 & Increasing Licensed Power for Operation of Unit 2 to 3445 Mwt ML20198J2541998-12-18018 December 1998 Proposed Tech Specs Sections 1.0,3.1,3.3,3.4,3.6,3.7,3.9 & 5.0,converting to ITS ML20198J5211998-12-17017 December 1998 Corrected Tech Specs Pages for Section 3.8 to 971211 Submittal Re TS Conversion Application ML20197K0491998-12-11011 December 1998 Proposed Tech Specs Section 3.8, Electrical Power Systems, Converting to ITS ML20196C5361998-11-20020 November 1998 Proposed TS Converting to ITS Sections 4.0,3.4 & 3.6 ML20195F1751998-11-13013 November 1998 Proposed Tech Specs,Revising Administrative Controls Section to Include Configuration Risk Mgt Program Into CPSES TS ML20195F5291998-11-11011 November 1998 Proposed Tech Specs Revising Core Safety Limit Curves & Overtemperature N-16 Reactor Trip Setpoints for Unit 2 Cycle 5 ML20196B8811998-10-30030 October 1998 Proposed Tech Specs Section 3.3 Re Instrumentation ML20154R7861998-10-21021 October 1998 Proposed Tech Specs Section 3.7, Plant Systems ML20154S2901998-10-14014 October 1998 Proposed Tech Specs Sections 3.1,3.2,3.4,3.5 & 5.0 Re Reactivity Control Sys,Power Distribution Sys,Rcs,Eccs & Administrative Control,Respectively ML20154C9101998-10-0202 October 1998 Proposed Tech Specs 4.0.6, SG SR, Adding Definitions Required for F* Alternate Plugging Criterion & Identifies Portion of Tube Subject to Criteria ML20153E2661998-09-24024 September 1998 Proposed Improved Tech Specs Sections 3.4, RCS & 5.0, Administrative Controls ML20237E8461998-08-28028 August 1998 Proposed Tech Specs Pages Re Sections 1.0,2.0 & 3.0 of Proposed TS Changes in 980707 & s,In Response to NRC RAI ML20154C4511998-07-20020 July 1998 Interim Change Request ISI-1R5-01, Unit 1 ISI Plan,Rev 5 ML20236T9931998-07-20020 July 1998 1RF06 ISI Summary Rept First Interval,Third Period,First Outage for CPSES Unit 1, Commerical Operating Date 900830 ML20236J3131998-07-0101 July 1998 Revised Proposed Tech Specs Pages Re Safety Injection Signal & Blackout Signal ML20249C6101998-06-22022 June 1998 Proposed Tech Specs Section 3.6 Re Conversion Application ML20216B2811998-04-24024 April 1998 Rev 13 to Cpses,Units 1 & 2,IST Plan for Pumps & Valves First Interval ML20216E6291998-04-0909 April 1998 Marked-up TS Pages,Reflecting Proposed Changes in Amends to Licenses NPF-87 & NPF-89 ML20216B1471998-04-0606 April 1998 Proposed Tech Specs,Allowing Plant to Continue to Operate W/O Having to Perform Portions of SRs ML20217A3901998-03-18018 March 1998 Proposed Tech Specs Surveillance Requirements 4.8.1.1.2f.4)a) & 4.8.1.1.2f.6)a) at Power Re Enforcement Discretion ML20216H1361998-03-13013 March 1998 Proposed Tech Specs Re Electrical Systems Surveillance Requirements ML20248L3191998-03-12012 March 1998 Proposed Tech Specs TS 4.8.1.1.2f.4)b) & TS 4.8.1.1.2f.6)b) Re Request for Enforcement Discretion ML20216D6021998-03-0909 March 1998 Proposed Tech Specs Temporarily Removing Requirement to Demonstrate Load Shedding Feature of MCC XEB4-3 as Part of SRs 4.8.1.1.2f.4)a) & 4.8.1.1.2f.6)a),for Unit 2 Only ML20203K8621998-02-27027 February 1998 Proposed Tech Specs,Increasing RWST low-low Level Setpoint ML20203J5211998-02-25025 February 1998 Proposed Tech Specs Page to Remove Requirement to Demonstrate Load Shedding Feature of MCC XEB4-3 as Part of Surveillance Requirements 4.8.1.1.2f.4(a) & 4.8.1.1.2f.7(a) Until Plant Startup Subsequent to Next Refueling Outage ML20203J6151998-02-24024 February 1998 Rev 26 to Technical Requirements Manual ML20217P1531998-02-12012 February 1998 Rev 2 to ISI-2R2-01, Unit 2 ISI Plan ML20202B1641998-02-0505 February 1998 Proposed Tech Specs Bases 3/4.7.1.5 Re Main Steam Line Isolation Valves ML20217P2961998-01-30030 January 1998 Rev 5 to Unit 1 ISI Program Plan ML20202E5981997-11-25025 November 1997 Rev 12 to CPSES Units 1 & 2 IST Testing Plan for Pumps & Valves,First Interval ML20212C3881997-10-24024 October 1997 Proposed Tech Specs Re Revised Core Safety Limit Curves & Revised Overtemperature N-16 Reactor Trip Setpoints 1999-09-10
[Table view] Category:TEST REPORT
MONTHYEARML20207F3511999-02-25025 February 1999 Fire Endurance Test to Qualify Protective Envelope for Class IE Electrical Circuits ML20112G4061996-05-30030 May 1996 CPSES Unit 2 Cycle 3 Startup Rept ML20067D2151994-01-14014 January 1994 First Periodic Reactor Containment Bldg Integrated Leakage Rate Test Final Rept, for Comanche Peak Ses Unit 1 ML20059F5341993-10-0404 October 1993 Fire Endurance Test of Thermo-Lag 330-1 Fire Protective Envelope (Flex-Blanket Wrapped Cables Laid in 36 Inch Cable Tray Assembly) ML20059F5281993-10-0404 October 1993 Fire Endurance Test of Thermo-Lag 330-1 Fire Protective Envelope (Box Design Air Drop from Two Nested 24 Inch Cable Tray Assemblies) TXX-9332, Cycle 1 Startup Rept1993-09-15015 September 1993 Cycle 1 Startup Rept ML20059F5231993-08-27027 August 1993 Fire Endurance Test of Thermo-Lag 330-1 Fire Protective Envelope (24 Inch Cable Tray Assembly W/2 Inch Diameter & 1-1/2 Inch Diameter Air Drop) ML20059F5041993-08-27027 August 1993 Fire Endurance Test of Thermo-Lag 330-1 Fire Protective Envelope (Three 24 Inch Cable Tray Assemblies) ML20059F5111993-08-23023 August 1993 Fire Endurance Test of Thermo-Lag 330-1 Fire Protective Envelope (12 Inch Cable Tray & 2 Inch Conduit) ML20128H1191993-01-14014 January 1993 Fire Endurance Test of Thermo-Lag 330-1 Fire Protective Envelope (24 Inch Tray W/Air Drops) ML20128G9981993-01-13013 January 1993 Fire Endurance Test of Thermo-Lag 330-1 Fire Protective Envelope (12 Inch Tray) ML20128H0181993-01-13013 January 1993 Fire Endurance Test of Thermo-Lag 330-1 Fire Protective Envelope (30 Inch Tray W/Tee) ML20128H0521993-01-13013 January 1993 Fire Endurance Test of Thermo-Lag 330-1 Fire Protective Envelope (3/4 Inch,1-1/2 Inch & 2 Inch Conduits) ML20128H0771993-01-13013 January 1993 Fire Endurance Test of Thermo-Lag 330-1 Fire Protective Envelope (30 Inch Tray) ML20128H1121993-01-13013 January 1993 Fire Endurance Test of Thermo-Lag 330-1 Fire Protective Envelope (24 Inch Tray W/Tee) ML20128H0311993-01-11011 January 1993 Fire Endurance Test of Thermo-Lag 330-1 Fire Protective Envelope (Two 3 Inch Conduits W/Junction Boxes) ML20128H1021993-01-0707 January 1993 Fire Endurance Test of Thermo-Lag 330-1 Fire Protective Envelope (Two 3 Inch Conduits W/Junction Boxes) ML20128H0921993-01-0505 January 1993 Fire Endurance Test of Thermo-Lag 330-1 Fire Protective Envelope (3/4 Inch,3 Inch & 5 Inch Conduits W/Radial Bends) ML20128H0681992-11-0404 November 1992 Fire Endurance Test of Thermolag 330-1 Fire Protective Envelope (36 Inch Tray W/Tee) ML20126C8361992-09-30030 September 1992 Reactor Containment Building Integrated Leakage Rate Test for Comanche Peak Steam Electric Station,Unit 2 Final Rept ML20044B5591992-04-29029 April 1992 Toxicological Evaluation of Combustion Products from Thermal Barrier Matl Decomposed Under Flaming & Nonflaming Conditions, Rept of Test Fr 3987 ML20062D8951990-11-12012 November 1990 Cycle 1 Startup Rept ML20012E1941990-03-23023 March 1990 Cycle 1 Startup Physics Tests Control Rod Worth Predictions Utilizing TU Electric Control Rod Swap Methodology. ML19327A9401989-07-31031 July 1989 Final Rept, Reactor Containment Bldg Integrated Leakage Rate Test. ML20235J4461989-01-11011 January 1989 Rev 1 to Test Rept Demonstration of IE to Non-IE Isolation for RS-232C Serial Data Port ML20151E4691988-07-13013 July 1988 Civil/Structural Tests Re Hilti Expansion Anchors Installed in Coredrilled Holes & Richmond Inserts W/Partial Bolt Engagements ML20155J8071988-03-31031 March 1988 Final Summary Rept Comanche Peak Conduit Tests, Technical Rept ML20235F9041987-09-11011 September 1987 Rev 3 to M-28, Justification of Clip Modelling Procedure ML20235F8551987-07-27027 July 1987 Rev 2 to M-38, Siderail Extension Study ML20235F7881987-07-23023 July 1987 Rev 3 to M-12, Qualification Procedures for Cable Tray Support Evaluation ML20235F8201987-05-0505 May 1987 Rev 2 to M-27, Thermal Load Evaluation ML20210C8031987-02-28028 February 1987 Rev 0 to Comanche Peak Steam Electric Station Cable Tray Sys Analysis/Test Correlation ML20210C8911987-02-25025 February 1987 Rev 1 to Thermal Load Evaluation ML20210D2441987-02-24024 February 1987 Vol 1 to Book 25, Reduced Section Properties for Channels ML20210D1351987-02-17017 February 1987 Vol 1 of Book 24 to Cth Post-Test Analysis Correlation ML20210D1651987-01-31031 January 1987 Rev 0 to Comanche Peak Cable Tray Tests, Final Summary Rept ML20236N4161986-10-0909 October 1986 Rev 3 to LIS-100C, Min Required Gap Between Bldgs ML20236N4681986-10-0909 October 1986 LIS-501C, Turbine Bldg Seismic Displacement ML20236N4331986-10-0101 October 1986 Rev 4 to LIS-100C, Min Required Gap Between Secondary Walls & Floors Above ML20211K1801986-09-19019 September 1986 Rev 1 to Calculation/Problem ROTC-06, Multimode Factor Evaluation Train C ML20236N4611986-09-0505 September 1986 Rev 0 to LIS-100C, Min Required Gap Between Rcb & Auxiliary Bldg at Approx 900 Ft & Above ML20236N4861986-09-0505 September 1986 LIS-520C, Relative Displacement Between Reactor & Auxiliary Bldgs at Elevation 916 Ft ML20212D6211986-09-0404 September 1986 Test Rept 48422-1, Cable Separation Test Program ML20211K1871986-07-10010 July 1986 Test Rept for Static Testing of Train C Beam Clamps & Unistrut Hangers for Comanche Peak Steam Electric Station (Cpses) ML20211K2151986-05-27027 May 1986 Rev 0 to Calculation/Problem ROTC-02, Procedure to Calculate Anchor Bolt Loads,Train C Conduit 2 Inches & Under ML20212D7021986-05-0101 May 1986 Test Rept 48037-02, Electrical Raceway Separation Verification Testing ML20236N4501985-11-11011 November 1985 LIS-100C, Min Required Gap Between Containment Wall & Internal Structure A07596, Torsiograph Test of Emergency Diesel Generator 1DG2 at Comanche Peak Steam Electric Station1985-02-28028 February 1985 Torsiograph Test of Emergency Diesel Generator 1DG2 at Comanche Peak Steam Electric Station ML20107A9731984-12-31031 December 1984 Reactor Containment Bldg Unit 1 Preoperational Type B & C Local Leak Rate Test ML20094N6791984-08-10010 August 1984 Radiation Analysis of Barton Model 288A Differential Pressure Indicating Switch for Texas Utils Generating Co 1999-02-25
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EQ/IES(84)-164 L
TEST REPORT l
Radiation Ana l ysis of the -Barton Mode l 288A Differential Pressure Indicating Switch for the Texas Utilities Generating Company.
Prepared by: Approved by:
/ b- (() Nih h 62 >(
T. J. Riedl C. G.. Morris, Manager Class 1E Systems Class 1E Systems I
8408160340 840810 PDR ADOCK 05000445 1 A. PDR
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D TABLE QE CONTENTS EECU QM TITLE P A GE 1.0 SCOPE 3 2.0
SUMMARY
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3.0 CONCLUSION
5 2
1.0 SCOPE
-This report summarizes available information concerning the effects of gamma radiation on the material mechanical properties of the Barton Mode l 288A D/P Indicating Switch and jusii f les that f or a gamma dose of 1.61x106 rads there are no observable radiation effects which impact the materials' mechanical properties.
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2.0 -
SUMMARY
An evaluation was performed on the effects of gamma radiation on materia ! mechan ica l properties of the Barton Model 288A D/P Indicating Switch.
The organic materials of the Switch were Identified and evaluated for radiation Induced degradation of the mater ia l s' mechan ica l properties when expose j to a TID of 1.61x106 rads. The higher level of radiation (> 104 rads) for this unit, which is located outside containment, is caused by the recirculation of reactor coolant through nearby piping following an accident.
The Inorganics and meta l l ics of the Switch were considered to be little affected by the radiation environment and are more radiation resistant than the organic materials. A list of the organic materials and corresponding part numbers for the Barton 288A D/P Switch is shown in Table 1.
The radiation resistance characteristics of these materials is shown in Table 2.
AlI materia l s show a higher l eve l of radiation to l erance than the required 1.61 x 106 rad s. Buna-N, f or wh ich damage begins at 7x105 reds, is used as a gasket for the bezel assembly and is considered not to effect the performance of the Switch. Based on this inf ormation, degradation of the per f ormance of these materia l s wou Id not be expected as a result of an exposure to a total Integrated dose of 1.61 x 106 rads.
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a 3.0- CONCLUSION-In summary it can be conc l uded that the Barton Mode l 288A
~D/P Indicating Switch is quallfled to a radiation environment of 1.61 x 10 6 rads for the Comanche Peak Steam Electric Station.
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TABLE I EM L DESCRIPTION MATERIAL-0228.0025B Hi ALARM PHENOLIC 0228.0024B LO ALARM PHENOLIC 0038.0033T TERMINAL BLOCK PHENOLIC 0226.0028C STOP, SNUBBER 30 SHORE NEOPRENE 0277.0026C BEZEL GASKET 60 SHORE BUNA-N 0001.0039R 0-RING FLANGE GASKET VITON INSULATION, WIRE VINYL (TEFZEL) i 6
j
IABLE. Z Ebenotics Un f i l l ed pheno l ics exh ib it exce l l ent phys ica l and electrical tolerance to radiation. Fillers have great influence, both positi ve and negati ve, on the composite materia l s. Cellulose fillers are among the most sensitive materials. Two studies concur that cellulose filled phenolics wilI suffer a 20-25%
decrease in e longation, tensile strength and impact strength at a dose of 5x106 rads. Electrical measurements made in another study Indicate that electrical properties are not significantly changed to 2x107 rads. Mineral filled pheno l ics show exce l l ent radiation stability, and are among the more radiation resistant plastics. They are unaffected by a radiation exposure of 3.9x108 reds. Mineral and f lock f i l led pheno l ics wi l I have radiation resistance between the l imits of ce l l u lose f i l led and minera l fiIled phenolics.
Enaa _H (Nitrile Rubber)
Nitrile, as in the case of most rubbers, exhibits good to exce l lent radiation tolerance. Damage begins at 7x105 rads. The 50% demage level for tensile strength, elongation, set at break, ,
compression set and shore hardness is reached between doses of 1x107 reds and 3x108 rads.
Vitoa Fluoropolymers are safely used to a dose of 1x106 rads for dynamic stress and 1x107 rads for static stress applications.
.V i n y t. (TEFZEL)
Tefzel Insulation exhibits a decrease in elongation of approximately 25% at 2x107 rads and 50% at 3x107 rads.
ERQar_ Rag (Gasket)
Neoprene has been extensi ve l y examined in irradiation studies.
The resuits indicate that damage begins at around 2x106 rads.
The 50% damage leveI f or tensi l e strength, e longation, set at break, compression set and shore hardness is reached between doses of 1x107 rads and 1x108 rads.
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