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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217F9701999-10-14014 October 1999 Proposed Tech Specs,Incorporating ARC for Axial Primary Water Stress Corrosion Cracking at Dented Tube Support Plate Intersections ML20217E4301999-10-12012 October 1999 Proposed Tech Specs,Revising Requirements for Containment Penetrations During Refueling Operations ML20211M7341999-08-30030 August 1999 Marked-up & Revised TS Pages,Providing Alternative to Requirement of Actually Measuring Response Times ML20211K1721999-08-30030 August 1999 Proposed Tech Specs,Providing Clarification to Current TS Requirements for Containment Isolation Valves ML20209B7731999-06-30030 June 1999 Proposed Tech Specs Updating Requirmements for RCS Leakage Detection & RCS Operational Leakage Specifications to Be Consistent with NUREG-1431 ML20196F2211999-06-24024 June 1999 Proposed Tech Specs Pages for Amend to Licenses DPR-77 & DPR-79,allowing Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20196G4701999-06-24024 June 1999 Proposed Tech Specs Pages Re Amends to Licenses DPR-77 & DPR-79,revising TS to Be Consistent with Rev to ISTS Presently Submitted to NEI TSTF for Submittal as Rev to NUREG-1431 ML20196G7961999-06-22022 June 1999 Proposed Tech Specs Bases,Clarifying Proper Application of TS Requirements for Power Distribution Systems & Functions That Inverters Provide to Maintain Operability & Providing Updated Info on Cold Leg Injection Accumulators ML20196G8071999-06-22022 June 1999 Revs to Technical Requirements Manual ML20195E9841999-06-0707 June 1999 Proposed Tech Specs,Increasing Max Allowed Specific Activity of Primary Coolant from 0.35 Microcuries/Gram Dose Equivalent I-131 to 1.0 Microcuries/Gram Dose Equivalent I-131 for Plant Cycle 10 (U2C10) Core ML20206E1611999-04-29029 April 1999 Proposed Tech Spec Change 99-04, Auxiliary Suction Pressure Low Surveillance Frequency Rev. Change Deletes Surveillance ML20206E1391999-04-29029 April 1999 Proposed Tech Spec Change 99-03, Main Control Room Emergency Ventilation Sys Versus Radiation Monitors. Changes Add LCOs 3.3.3.1 & 3.7.7 to Address Inoperability of Radiation Monitoring CREVS & NUREG-1431 Recommendations ML20204E8501999-03-21021 March 1999 Plant,Four Yr Simulator Test Rept for Period Ending 990321 ML20204H4081999-03-19019 March 1999 Proposed Tech Specs,Relocating TS 3.8.3.1,3.8.3.2,3.8.3.3 & Associated Bases Associated with Electrical Equipment Protective Devices to Technical Requirements Manual ML20207D6331999-02-26026 February 1999 Proposed Tech Specs Providing for Consistency When Exiting Action Statements Associated with EDG Sets ML20207D6011999-02-26026 February 1999 Proposed Tech Specs Relocating TS 3.7.6, Flood Protection Plan & Associated Bases from TS to Plant TRM ML20206S0131999-01-15015 January 1999 Proposed Tech Specs 3.3.3.3, Seismic Instrumentation & Associated Bases,Relocated to Plant Technical Requirements Manual ML20199K6001999-01-15015 January 1999 Proposed Tech Specs Adding New Action Statement to 3.1.3.2 That Would Eliminate Need to Enter TS 3.0.3 Whenever Two or More Individual RPIs Per Bank May Be Inoperable,While Maintaining Appropriate Overall Level of Protection ML20195H6111998-11-16016 November 1998 Proposed Tech Specs Revising EDG SRs by Adding Note That Allows SR to Be Performed in Modes 1,2,3 or 4 If Associated Components Are Already OOS for Testing or Maint & Removing SR Verifying Certain Lockout Features Prevent EDG Starting ML20154H7251998-10-0808 October 1998 Proposed Tech Specs Pages,Supplementing Proposed TS Change 96-08,rev 1 to Add CRMP to Administrative Controls Section & Bases of TS ML20238F1091998-08-27027 August 1998 Proposed Tech Specs Providing for Insertion of Limited Number of Lead Test Assemblies,Beginning W/Unit 2 Operating Cycle 10 Core ML20238F3001998-08-27027 August 1998 Proposed Tech Specs Replacing 72 H AOT of TS 3.8.1.1,Action b,w/7 Day AOT Requirement for Inoperability of One EDG or One Train of EDGs ML20209J1631998-08-0707 August 1998 Rev 41 to Sequoyah Nuclear Plant Odcm ML20236G5961998-06-29029 June 1998 Proposed Tech Specs Typed Pages for TS Change 95-19, Section 6 - Administrative Controls Deletions ML20249C6371998-06-26026 June 1998 Proposed Tech Specs Lowering Specific Activity of Primary Coolant from 1.0 Uci/G Dose Equivalent I-131 to 0.35 Uci/G Dose Equivalent I-131,as Provided in GL 95-05 ML20248F0051998-05-28028 May 1998 Proposed Tech Specs for Section 6, Administrative Controls Deletions ML20217N3511998-04-30030 April 1998 Proposed Tech Specs Pages,Modifying Surveillance Requirement 4.4.3.2.1.b to Change Mode Requirement to Allow PORV Stroke Testing in Modes 3,4 & 5 W/Steam Bubble in Pressurizer Rather than Only in Mode 4 ML20203J1681998-02-25025 February 1998 Proposed Tech Specs Pages,Revising EDG Surveillance Requirements to Delete Requirement for 18-month Insp IAW Procedures Prepared in Conjunction W/Vendor Recommendations & Modify SRs Associated W/Verifying Capability of DGs ML20202J7651998-02-13013 February 1998 Technical Requirements Manual ML20202J7141998-02-13013 February 1998 Proposed Tech Specs Adding New LCO That Addresses Requirements for Main Feedwater Isolation,Regulating & Bypass Valves ML20202J6961998-02-13013 February 1998 Proposed Tech Specs Incorporating MSIV Requirements to Be Consistent W/Std TS (NUREG-1431) ML20202J7601998-02-13013 February 1998 Proposed Tech Specs Section 3.7.9 Re Relocation of Snubber Requirements ML20198T4311998-01-21021 January 1998 Proposed Tech Specs Re New Position Title & Update of Description of Nuclear Organization ML20199F8231997-11-30030 November 1997 Cycle 9 Restart Physics Test Summary, for 971011-971130 ML20199K4571997-11-21021 November 1997 Proposed Tech Specs Adding one-time Allowance Through Operating Cycle 9 to Surveillance Requirement 4.4.3.2.1.b to Perform Stroke Testing of PORVs in Mode 5 Rather than Mode 4,as Currently Required ML20211A3191997-09-17017 September 1997 Proposed Tech Specs Re Pressure Differential Surveillance Requirements for Containment Spray Pumps ML20203B9731997-08-0505 August 1997 Rev 1 to RD-466, Test & Calculated Results Pressure Locking ML20217J5581997-07-31031 July 1997 Cycle Restart Physics Test Summary, for Jul 1997 ML20210J1671997-04-30030 April 1997 Snp Unit 1 Cycle 8 Refueling Outage Mar-Apr 1997,Results of SG Tube ISI as Required by TS Section 4.4.5.5.b & Results of Alternate Plugging Criteria Implementation as Required by Commitment from TS License Condition 2C(9)(d) ML20137T0871997-04-0909 April 1997 Proposed Tech Specs Re Elimination of Cycle 8 Limitation for SG Alternate Plugging Criteria ML20137M8581997-04-0101 April 1997 Proposed Tech Specs 2.1 Re Safety Limits & TS 3/4.2 Re Power Distribution Limits ML20137C8421997-03-19019 March 1997 Proposed Tech Specs Re Conversion from Westinghouse Electric Corp Fuel to Framatome Cogema Fuel ML20136J0381997-03-13013 March 1997 Proposed Tech Specs Section 5.6.1.2,revising Enrichment of Fuel for New Fuel Pit Storage Racks ML20134P8631997-02-14014 February 1997 Proposed Tech Specs Requesting Discretionary Enforcement for 48 Hours Which Is in Addition to 72 Hours Allowed Outage Time Provided by TS Action 3.8.1.1.b ML20134K9981997-02-0707 February 1997 Proposed Tech Specs Revising TS Change Request 96-01, Conversion from W Electric Corp Fuel to Framatome Cogema Fuel (MARK-BW-17), to Ensure That Core Analysis Computer Code Output Actions Are Consistent W/Hot Channel Factor SRs ML20138F2581997-01-17017 January 1997 Rev 39 to Sequoyah Nuclear Plant Odcm ML20134L9261996-11-0808 November 1996 Proposed Tech Specs Re Placing of Channel in Trip for Reactor Trip & Engineered Safety Feature Instrumentation Sys Solely to Perform Testing as Not Requiring Channel to Be Declared Inoperable ML20129D2661996-10-18018 October 1996 Proposed Tech Specs,Removing Existing Footnotes That Limit Application of Apc for Plant S/G Tubes to Cycle 8 Operation for Both Units ML20129G7301996-09-26026 September 1996 Proposed Tech Specs 3/4.3.3 Re Fire Detection instrumentation,3/4.7.11 Re Fire Suppression Systems & 3/4.7.12 Re Fire Protection Penetrations ML20134J9991996-09-23023 September 1996 Fuel Assembly Insp Program 1999-08-30
[Table view] Category:TEST REPORT
MONTHYEARML20204E8501999-03-21021 March 1999 Plant,Four Yr Simulator Test Rept for Period Ending 990321 ML20199F8231997-11-30030 November 1997 Cycle 9 Restart Physics Test Summary, for 971011-971130 ML20203B9731997-08-0505 August 1997 Rev 1 to RD-466, Test & Calculated Results Pressure Locking ML20217J5581997-07-31031 July 1997 Cycle Restart Physics Test Summary, for Jul 1997 ML20210J1671997-04-30030 April 1997 Snp Unit 1 Cycle 8 Refueling Outage Mar-Apr 1997,Results of SG Tube ISI as Required by TS Section 4.4.5.5.b & Results of Alternate Plugging Criteria Implementation as Required by Commitment from TS License Condition 2C(9)(d) ML20064M0881994-03-0707 March 1994 Reactor Containment Bldg Integrated Leak Rate Test Sequoyah Nuclear Plant Unit 1 Conducted 931217-20 ML20099B8841992-07-0909 July 1992 Reactor Containment Bldg Intergrated Leak Rate Test Sequoyah Nuclear Plant Unit 2, Conducted on 920427-29 ML20029A3091991-01-31031 January 1991 Nonproprietary Sequoyah Nuclear Plant Unit 2 Cycle 5 Restart Physics Test Summary. ML20059H1881990-08-31031 August 1990 Nonproprietary Sequoyah Nuclear Plant Unit 1,Cycle 5 Restart Physics Test Summary ML20056A5321990-08-0606 August 1990 Reactor Bldg Containment Integrated Leak Rate Test, Sequoyah Nuclear Plant Unit 1 Conducted on 900504-06 ML20044B2191990-07-13013 July 1990 Eagle 21 Start-Up Rept for 900522- 0616. W/900713 Ltr ML20245B3631989-03-18018 March 1989 Reactor Bldg Containment Integrated Leak Rate Test ML20195J8251987-11-23023 November 1987 Insulation Wall Thickness Measurement of Silicone-Rubber Cables at Identified Failure Points ML20236V5171987-11-19019 November 1987 Qualification Test Program for Silicone Rubber Cables W/ Reduced Insulation Thicknesses for Use in TVA Sequoyah Nuclear Plant,Unit 2 ML20236T5381987-11-13013 November 1987 Rev 1 to DC High Voltage Cable Test Rept ML20236Q1871987-10-13013 October 1987 Elevated Temp Test Rept & Mechanical Pull Test Rept for Littelfuse Flas 5,5 AMP Fuses Lot 2,3,4 & 6 ML20236T9461987-09-0303 September 1987 Rev 0 to Special Test Instruction STI-23, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage Conduit MC1730B, Incorporating Instruction Change Icf 87-1616 ML20236T6421987-09-0101 September 1987 Rev 0 to Special Test Instruction STI-34, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage - Conduit Mc 1497B, Incorporating Temporary Change 87-1520 ML20195J8031987-08-31031 August 1987 Impact Testing of Rockbestos & Anaconda Cables ML20236T9891987-08-31031 August 1987 Rev 0 to Special Test Instruction STI-29, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage - Conduit MC1606A, Incorporating Temporary Change TCF 87-1623 ML20236T8481987-08-25025 August 1987 Rev 2 to Special Test Instruction STI-17, DC High Voltage Test for Selected Unit 2 1E Cables in Vertical Drop Configuration ML20236T6141987-08-17017 August 1987 Rev 0 to Special Test Instruction STI-33, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage ML20236T9781987-08-0303 August 1987 Rev 1 to Special Test Instruction STI-28, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage - Conduit MC1605A ML20236T8641987-07-29029 July 1987 Rev 1 to Special Test Instruction STI-19, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Jamming, Incorporating Change 87-1251 ML20236T9101987-07-29029 July 1987 Rev 0 to Special Test Instruction STI-23, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage - Conduit MC1748A, Incorporating Change 87-1176 ML20195J7721987-07-22022 July 1987 Impact Testing of Aiw Cable ML20236S0511987-07-22022 July 1987 Rev 0 to Special Test Instruction STI-31, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage Conduit MC1732B ML20236T8971987-07-21021 July 1987 Rev 0 to Special Test Instrustion STI-22, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage Conduit MC1728B, Incorporating Instruction Change Icf 87-1619 ML20236T9641987-07-21021 July 1987 Rev 0 to Special Test Instruction STI-27, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage, Incorporating Change ICF-87-1283 ML20236T9261987-07-21021 July 1987 Rev 0 to Special Test Instruction STI-25, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage Conduit MC1754A, Incorporating Change 87-1252 ML20236T9181987-07-21021 July 1987 Rev 1 to Special Test Instruction STI-24, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage, Incorporating Instruction Change ICF-87-1253 ML20236T8801987-07-21021 July 1987 Rev 0 to Special Test Instruction STI-21, Cables ML20236T6521987-07-21021 July 1987 Rev 0 to Special Test Instruction STI-35, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage ML20236T5931987-07-21021 July 1987 Rev 0 to Special Test Instruction STI-32, Cables ML20236T5691987-07-21021 July 1987 Rev 0 to Special Test Instruction STI-30, Functional ML20195J7581987-07-20020 July 1987 Tests on Silicone Rubber Insulated Control Cables ML20236A2541987-06-10010 June 1987 Rev 1 to Lab Tests of Air Entrapment in Slightly Sloped Sensing Lines & Consequent Pressure Transmission Error ML20215C5691986-05-30030 May 1986 Cable Sidewall Bearing Pressure Tests ML20154K7711986-02-14014 February 1986 Reactor Bldg Containment Integrated Leak Rate Test,Sequoyah Nuclear Plant Unit 1,Conducted 851203-05 ML20107F6541985-02-19019 February 1985 Reactor Bldg Containment Integrated Leak Rate Test, Conducted on 841120-21 ML20071B3981983-02-17017 February 1983 Reactor Bldg Containment Integrated Leak Rate Test, Conducted on 821208-09 ML18025B8521982-03-18018 March 1982 Revision a to Qualification Test Rept for Model 1801104-05 PSA 1/4 Shock. ML20039A7801981-12-10010 December 1981 Summary Auxiliary Feedwater Pump Endurance Test,Sequoyah Nuclear Plant Unit 2. ML20010H7341981-08-31031 August 1981 Catalytic Combustion Hydrogen in Presence of Methyl Iodide, Final Rept ML20004A9741981-05-19019 May 1981 Reactor Bldg Containment Integrated Leak Rate Test, Conducted 810214-15 ML20050D0091981-04-16016 April 1981 Main Steam Line Break Qualification Test on Okozel Insulation, Final Rept ML20008F8721981-04-13013 April 1981 Table 14.1-2a to Revised Startup Test Program ML20003F0931981-04-13013 April 1981 Startup Test Revisions. ML20050D0111981-04-0808 April 1981 Qualification Tests of Electric Cables Under Simulated Steam Line Break (Slb) by Sequential Environ Exposure to Environs of Thermal Aging,Radiation,Steam & Chemical Spray. ML20008E5551981-02-27027 February 1981 Insp Device in Lieu of Insp Ports. Photographs Encl 1999-03-21
[Table view] |
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ESSEX GROUP, INC. .
POWER CONDUCTOR DIVISION PROJECT REPORT I Report Number : PE-53 i
' ' ^ 0 ED Date: May 7, 1980 n i , , ,', ,', ,", , [, , , , ,,, , , ,, .
Centracter f re's esy eart of his resseeslJ tility for the correctness el destte. detaf's os. . .es.ies.
IEMMESSEE V ALLEY AUTHOR 6TT sa SEP 2 31980
' ~ ' y.w. in An otre TITLE: I ,
MAIN STEAM LINE BREAK (MSLB)
Test On Aged And Irradiated Cable Specimens PROCEDURE: -
Manufacture and prepare samples of Class 1E cable for aging and subsequent submittal to Isomedix, Inc. for irradiation and simula-tion of Main Steam Line Break Temperature and Pressure Profile.
CONCLUSION: ..
Specimens of Class 1E EP insulated conductor having successfully withstoodtheeffectsogheatagingto40yearsat90C, irradiation to a level of 2.05 x 10 Rads (C 60) and a MSLB temperature and pressure profile according to the requirements of the TVA Specifi-cation are judged to be fully qualified for service according to the referenced specifications. .
REFERENCE:
TVA Specification 25.016 Item 93 Contract 6-825722
- Isomedix Radiation Certification Essex Arrhenius Plot (Class 1E EP)
Respectfully submitted, SEOUOYAH ^ 'w J. L. Steiner .
C204090461 B20407 Chief Engineer DR ADOCK 05000
,,a...
d Page 2 PE-52 Mai d tcam Line Break JLS J'[.jMay8,1980 ,
QUALIFICATION CRITERIA:
- Specimens submitted shall withstand the following exposure.
All specimens shall withstand all tests with the exception that both thermally aged and unaged cables shall be submitted.
t 1- Heat aging - where applicable - for 140 hours at
'162C. Arrhennius Plot available. .
2- Exposure to Co60 source to a total exposed dose
- of 200 Megarad at a rate of exposure not to exceed 1 Megarad per hour.
3- Temperature and pressure specified for the' time specified by the TVA contract 6-825722. .
4- Withstand application of 80 volts / mil of insulation for 5 minutes.
DISCUSSION:
Three specimens of single conductorsr(#12 AWG, .030" wall Class 1E EP insulation) were aged in a circulating air oven for 149 hours at 162C and two (2) were not. Specimens were-subjected to the radiation from a . Cobalt 60 source to a total dose of 205 Megarads. The specimens were then coiled onto a mandrel and inserted into a pressure vessel.. At this point the vessel was flooded and the insulation resistance (IR) was measured. One specimen gave a comparatively low reading but the decision was made to test. Steam. was admitted to the vessel to simulate the pressure, temperature and time of the postulated MSLB event according to the profile attached. Steam was readmitted to the levels shown
> in the profile to provide test margin. Specimens had IR measurements taken at the two ensuing 346F plateaus. The vessel was cooled, the specimens removed and subjected to 2400 volts AC (60Hz) while submersed in tap water. End of i Test.
1-s
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/ .*[d ~PE-52 Ma Steam Line Break
( r * {, 'l May 8, 1980 - l
. p i DATA:
IR3 IR4 HiPot SPECIMEN # AGED IR1 IR2 14T .28T 2.5M 39M OK l 1 YES 8.2T 35M 35M 1.1M OK 2 . YES ,
YES 11T 1.3M 1.1M 1.3M OK 3
2.8T . 4T' 18M 19M OK 4 NO 17T .4T 26M 6.4M OK 5 NO
- NOTES: IR1 After aging (if applicable) before irradiation IR2 After irradiation IR3 First 346F plateau Second 346F plateau .
IR4
/
T 1012 ohms M 106 ohms
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ISOMEQlX December 20, 1979 To: Richard Prins Component Testing i From: - David P. Constantine -
Production Manager
Subject:
Irradiation for Essex International This will summarize parameters pertinent to the irradiation of one (1) double mandrel wrapped with 31 cable samples as per your SRR No. 0047, dated Octob.er 29, 1979.
The mandrel was placed in a Cobalt-60 gamma field and exposed at each of 4 quadrants, as marked on the mandrel. . Ey integrating ~
the dose rate at any point on the mandrel during its 4-position ~
exposure, an average dose rate was obtained which, when multiplied by the total exposure time, yields total dose. i The mandrel was exposed for 289 hour.s at an average dose rate of f 0.71 megarads per hour. The calculated dose based on dosimetry N is 205 megarads. In'corporating the 13% accuracy of the dosimetry system, therefore, the reported minimum dose is 200 megarads.
Dosimetry was performed using Harwell Red 4034 Perspex dosimeters, utilizing a Bausch and Lomb Model 710 spectrophotometer as the readout instrument. This system,is calibrated directly with NBS, with the last calibration being May 30, 1979. A copy of the dosimetry correlation report is available upon request.
Irradiation was conduct'ed in air at ambient temperature and pressure.
Radiant heat from the source heated the samples somewhat, but the temperature did not exceed 900F, as indicated by previous measure-ments on an oil solution in the same relative position. .
Irradiation was initiated on November 9, 1979, and was completed ,
on December 29, 1979. ,
hw David P. Constantine w
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