Main Steam Line Break Qualification Test on Okozel Insulation, Final ReptML20050D009 |
Person / Time |
---|
Site: |
Sequoyah |
---|
Issue date: |
04/16/1981 |
---|
From: |
OKONITE CO. |
---|
To: |
|
---|
Shared Package |
---|
ML20050C841 |
List: |
---|
References |
---|
RTR-NUREG-0588, RTR-NUREG-588 344, 344-R01, 344-R1, IEB-79-01B, IEB-79-1B, NUDOCS 8204090475 |
Download: ML20050D009 (7) |
|
|
---|
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 ML20211K1201999-08-30030 August 1999 Proposed Tech Specs,Adding New Specification That Addresses Use of Interim Provisions Upon Discovery of Unintended TS Action 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 ML20207F7631999-03-0202 March 1999 Proposed Tech Specs Pages Re Application for Amends to Licenses DPR-77 & DPR-79,deleting Iseg from License Conditions ML20207D6011999-02-26026 February 1999 Proposed Tech Specs Relocating TS 3.7.6, Flood Protection Plan & Associated Bases from TS to Plant TRM ML20207D6331999-02-26026 February 1999 Proposed Tech Specs Providing for Consistency When Exiting Action Statements Associated with EDG Sets 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 ML20206S0131999-01-15015 January 1999 Proposed Tech Specs 3.3.3.3, Seismic Instrumentation & Associated Bases,Relocated to Plant Technical Requirements Manual 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 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 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 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 ML20202J7141998-02-13013 February 1998 Proposed Tech Specs Adding New LCO That Addresses Requirements for Main Feedwater Isolation,Regulating & Bypass Valves ML20202J7651998-02-13013 February 1998 Technical Requirements Manual 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 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 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 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 ML20195J8031987-08-31031 August 1987 Impact Testing of Rockbestos & Anaconda Cables 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 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 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 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 ML20195J7721987-07-22022 July 1987 Impact Testing of Aiw Cable ML20236T5931987-07-21021 July 1987 Rev 0 to Special Test Instruction STI-32, 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 ML20236T5691987-07-21021 July 1987 Rev 0 to Special Test Instruction STI-30, Functional 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 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 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 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 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 ML20003F0931981-04-13013 April 1981 Startup Test Revisions. ML20008F8721981-04-13013 April 1981 Table 14.1-2a to Revised Startup Test Program 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] |
Text
n j av 1 !
- THE OKONIT"1 COMPANY r m.w w.w.w crx.4e
~
A pril 16, 1981 Ii ENGINEERING REPORT NO. 344, REV.1 f
D 8
f(
b N"$)e 0
I s-MAIN STEAM LINE BREAK OUALIFICATION TEST
>I2 ON OKOZEL INSUIATION Oj El
- I!
N h FINAL REPORT IQ t 3 f i lliii Introduction t, i.
8 A postulated design basis event - main steam line break (MSLB) test was per-formed on Okozel (Tefzel 280) insulated wire. The test was performed to determine if Okozel would remain operational in the event of such an accident.
The test program was designed to incorporate the requirements of IEEE Standards 323-1974 and 383-1974 as well as TVA contract number 79K6-825902 The MSLB profile was taken from Figure 2 of the TVA specification. Margins in accordance with IEEE 323, section 6. 3.1. 5 were added to the profile.
Th'ermal aging was performed at the Okonite Passaic Laboratory. Isome dix, Incorporated was contracted for irradiation aging. A copy of the irradiation certification is attached as Appendix 1.
The main steam line break profile was performed by Approved Engineering Test Laboratories. A copy of their final report is attached as Appendix 2 The AETL report also includes other materials tested in conjunction with the Tefzel 280.
Summary Two sets of thermally aged and irradiated and unaged sampics of Okozel in-sulated wire were exposed to the MSLB temperature-pressure profile as given in Figure 1 All samples maintained their electrical load throughout the entire profile. The two unaged samples and one of the aged sampics passed the final IEEE 383 " Post-LOCA Simulation Test".
The second aged sample also passed the final withstand test after two localized areas of physical dam-age were isolated. Evidence of physical damage is given in the body of this report.
Procedure D
Four twenty foot sampics of 1/C #16 AWG 7 X tinned coated 0. 015" Okozel (Tefzel 280) were prepared at Okonite for testing by marking the center fifteen fe et. Two samples were placed in a circulating air oven for thermal aging at 180 C for one week. Upon completion of thermal aging SIC, % PF and insula-tion resistance (IR) measurements were made.
ygy yg UCLEAk LANT*
b
~
\\
__ DOCK 0_5000327 DR A PDR
. (2)
KYS Representatives 4
Switzer Phone Junod Phone Norman Phone Teams will consist of players in age groups (a) under 12 (born in 1970 and 1978), (b) under 14 (born in 196) and 1970), and (c) under 16-(born in 1967 and 1968).
Regular league play will include competition with Chattanooga teams and those from Kingsport on an away and home basis.
Tryouts will be held on
,1982 at Bearden Jr. High School (under 12 age level) and at Christian Acadeg of Knoxville (under 14 and under 16, from 15 00 - 3:30 pm.
Call for additional information.
~!
4 n---,
, - - -g an,,
April 16,1981 Engineering Report No. 344, Rev.1 Page 2 The thermally aged Okozel sampics along with other thermally aged samples were delivered to Isomedix for irradiation. The sampics were exposed to a minimum 55 megarads of gamma radiation from a Cobalt 60 source.
The 55 megarads simulates the expected tohlinstalled life exposure with margin added. (See attached radiation certification, Appendix 1. )
After irradiation all samples were sent to Approved Engineering Test Labs, for the MSLB test. The AETL report is included as Appendix 2 to this report.
Discussion of Results All samples successfully maintained rated voltage and current throughout the MSLB event. The unaged Okozel samples and one of the aged and irradiated Okozel samples met the Post-LOCA simulation test requirements. The re-maining aged and irradiated sample failed to withstand the 1200 volts at two localized areas. With these areas isolated the remainder of the sample passed the required withstand test.
The first failure occurred on the rise at 900 volts. The fault was found and is olated. The withstand voltage was reapplied and the sample held voltage for three minutes before failing again. No further work on this sample was attempted at AETL. Further, investigation was performed at the Okonite laboratory. With both damaged areas isolated the remainder of the length passed the requireli withstand test.
If the damaged sites are examined it can be observed that the morphology of the damaged areas are identical with respect to the regions extending fa'r enough from the sites to preclude cause and affect. The surface " condition" existed before the failure. Photographs on file at Okonite magnified 7. 5 X show how the failure sites are identical to several other sites of apparent dam-age. These damaged areas have a reduced wall of insulation and the curvature of the dielectric is absent.
Upon further investigation, cross-sectional views were examined within 40 mils of both faults. The reduced wall at the first fault was approximately 2 mils. The wall thickness at the second fault was approximately 2. 5 mils.
Again photographs of these cross-sections were taken. The measurements were taken far enough from the fault so that the wall thickness was not affected by the dielectric puncture. Visual examination at 30 X magnification indicated that the damaged area wall thickness increased as the distance from the fault increased. Therefore, the wall thickness at the fault was probably as thin as or possibly thinner than those thicknesses measured.
If the measured thicknesses are used as the fault thicknesses, the dielectric failure of the first fault occurred at 900 volts through a 2 mil wall or 450 volts per mil. The second fault occurred at 1200 volts through a 2. 5 mil wall or 480 volts / mil.
6 l
4 A ril 16,1981 P
Engineering Report No. 344, Rev.1 Page 3 With these two faults cleared, the remainder of the sample passed the 5 minute 80 volts / mil ac withstand test requirement. A four foot effective length was then subjected to an ac rapid rise breakdown. Breakdown occured at 8. 5 kV in an area similar in damage to the first two except to a lesser extent. The wall thickness was 12 mils which meant a 708 volt / mil average breakdown strength.
The reason for physical damage could be attributed to two causes. First, the integrity of the insulation was violated during the manipulation necessary to remove the samples from the mandrel. Some minor difficulty was experienced when separating the turns from each other. They were stuck anywhere from a fraction of an inch to several inches.
This occurrence was also observed to a lesser extent on the duplicate sample. Second, as situated on the mandrel, support is limited to seven half-inch steel brackets around the circumference. These supports are areas of greatest pressure which must be accounted for.
The nature of this failure would not be seen on a multiconductor cable where the mode of support would be along each components entire length.
In summary, the two faults occurred at predictable locations where physical damage was observed. With the two faults isolated, the remainder of the sample, as well as its duplicate sampic and the unaged sample, passed all requirements.of this rigorous test and demonstrate a margin of assurance.
j b 7ait) w/
Uper:u:
R. F. DeMair mi! -
l J. R. Cancelosi
.t JRC/ row L..:.
n.
G
[I APPENDIX 1, pg.1 C 7
~
tla M
y.;
Ud sw w ISDMEDIX February 25, 1981 s.
Mr. George Dobrowolski j
Okonite Corporation Canal and Jefferson Street Passaic, New Jersey 07055
Dear Mr. Dobrowolski:
l I
This will summarize parameters pertinent to the irradiation of one (1) mandrel wrapped with cable and five (5) metal screens with cable samples,.as per your Purchase Order No. 9-80-721.
See attached sheet for specimen description.
The mandrel was placed in a Cobalt-60 gamma field and exposed j
at each of 4 quadrants, as marked on the mandrel.
By integrating the dose rate at any point.on the mandrel during its 4 position exposure, an average dose rate was obtained which, when multi-plied by the total exposure time, yields total dose.
The specimen was exposed for'a period of 118 hours0.00137 days <br />0.0328 hours <br />1.951058e-4 weeks <br />4.4899e-5 months <br /> at an average dose rate of 0.48 megarads per hour.
The calculated dose based on dosimetry is 56 megarads.
Incorporating the i 3% accuracy of the dosimetry system, therefore, the reported minimum dose is 55 megarads.
The metal screens were exposed for a period of 240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br /> at a nominal dose rate of 0.86 megarads.per hour.
The calculated dose I
based on dosimetry was 206 megarads.
Incorporating the i 3%
accuracy of the dosimetry system, therefore, the reported minimum dose is 200 megarads.
Halfway through the exposure, the specimens were rotated 180 degrees to give a more uniform' dose distribution.
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 November 11, 1980. A copy of the i
dosimetry cor-relation report is available upon request.
q l
s isomedix inc.
- 25 Eastmans Road, Parsippany. New Jersey 07054. (201) 887-2666
APPEN N Okonite Corporation February 25, 1981 Irradiation was conducted in air at ambient temperature and Radiant heat from the source heated the samples pressure.
somewhat, but the temperature did not exceed 100 degrees F, as indicated by previous measurements on an oil solution in the same relative position.
Iriadiation for the mandrel was initiated on December 6, 1980 and was completed on December 13, 1980.
Irradiation for the five metal screens was initiated on December 7, 1980 and was completed on December 27, 1980.
Very truly yours, ISOMEDIX, INC.
David P. Constantine Production Manager DC:ns Attachment cc:
Mr. G. Dietz e
N Isomodix inc. = 25 Eastmans Road. Parsippany. New Jersey 07054. (201) 887-266G
LAP &L@QfLG'G3, pg.E SPECIMEN DESCRIPTION to 50 Mrads l
Mandrel Samples 03 - 99315 A-3 & A-4 03 - 99315 B-3 & B-4 TVA SLB A-3 & A-4 TVA SLB B-3 &,B-4 to 200 Mrads Screens Samples 01 - 96656
~30' samples A - 1, 2, 5, 6& 9 B - 1, 2, 3, 5, 6&9 C - 1, 2, 3, 5, 6 & 10 2'
samples A-1, 5, 7 & 9 B-1, 3, 5, 7 & 9 C - 1, 3, 5, 7 & 9 i
N
' isomedix inc.
- 25 Eastmans Road. Par:,ippany. New Jersey 07054. (>01) 887-2GGG