NRC 2010-0012, License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Lnformation

License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Lnformation

ML100630133
Person / Time
Site:	Point Beach
Issue date:	03/03/2010
From:	Meyer L Point Beach
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC 2010-0012, TAC ME1081, TAC ME1082
Download: ML100630133 (52)

Text

March 3,2010 NRC 201 0-0012 10 CFR 50.90 U.S. Nuclear Regulatory Commission AlTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 License Amendment Reauest 261 Extended Power Uprate Response to Reauest for Additional lnformation

References:

(1)

FPL Energy Point Beach, LLC letter to NRC, dated April 7,2009, License Amendment Request 261, Extended Power Uprate (ML091250564)

(2)

NRC letter to NextEra Energy Point Beach, LLC, dated February I, 2010, Point Beach Nuclear Plant, Units 1 and 2 - Request For Additional lnformation From Electrical Engineering Branch Re:

Auxiliary Feedwater - Round 2 (TAC NOS. ME1081 and ME1082)

(ML100120331)

NextEra Energy Point Beach, LLC (NextEra) submitted License Amendment Request (LAR) 261 (Reference 1) to the NRC pursuant to 10 CFR 50.90. The proposed amendment would increase each unit's licensed thermal power level from 1540 megawatts thermal (MWt) to 1800 MWt, and revise the Technical Specifications to support operation at the increased thermal power level.

Via Reference (2), the NRC staff determined that additional information is required to enable the staff's continue the review of LAR 261. Enclosure 1 provides the NextEra response to the NRC staff's request for additional information. Enclosure 2 provides the manufacturer's engineering report for the new auxiliary feedwater pump (AFW) motor power cables. Enclosure 3 provides the manufacturer's test report for the new AFW motor power cables.

Summarv of Reaulatorv Commitments The following new Regulatory Commitment is proposed:

NextEra will provide final responses to Question 1 and Question 6 of the NRC letter dated February 1,2010 (ML100120331) by March 26,2010.

NextEra Energy Point Beach, LLC, 661 0 Nuclear Road, Two Rivers, WI 54241

Document Control Desk Page 2 The information contained in this letter does not alter the no significant hazards consideration contained in Reference (1) and continues to satisfy the criteria of 10 CFR 51.22 for categorical exclusion from the requirements of an environmental assessment.

In accordance with 10 CFR 50.91, a copy of this letter is being provided to the designated Wisconsin Official.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on March 3,2010.

Very truly yours, NextEra Energy Point Beach, LLC

,.I.'

-.carry Meyer Site Vice President Enclosures cc:

Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW

ENCLOSURE 1 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 LICENSE AMENDMENT REQUEST 261 EXTENDED POWER UPRATE RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION The NRC staff determined that additional information was required (Reference I ) to enable the Electrical Engineering Branch continue review of the auxiliary feedwater (AFW) portion of License Amendment Request (LAR) 261, Extended Power Uprate (EPU) (Reference 2). The following information is provided by NextEra Energy Point Beach, LLC (NextEra) in response to the NRC staff's request for additional information (RAI).

Question I In response to staff's request for additional information (RAI) dated August 26,2009, regarding the emergency diesel generator (EDG) voltage dip below the acceptance limit of 75 percent nominal voltage during motor start, the licensee stated that the EDGs are capable of starting safeguard loads, and the voltage recovers quickly to the acceptable level. Based on staff's review of the dynamic loading calculations, the staff notes that under certain loading conditions for Train "A" EDG, the frequency is outside 2 percent margin, the worst-case voltage dip is 45-48 percent and the voltage overshoot is 129.5 percent. Train "A" voltage and frequency variations are outside the industry accepted standards and guidance. Provide detailed analyses regarding the downstream effects on components such as contactors, control fuses, inverters, battery chargers, solenoids, motor-operated valves, solid state devices, etc., and the basis to show that all required loads will start and continue to run with sufficient margins after accounting for any uncertainties. Provide justification for the performance capabilities of the EDG "A" regulator and excitation systems to support shutdown equipment within design-basis requirements during a design-basis accident. The staff notes that Train "B" EDG bus voltages remain above 75 percent of nominal voltage, consistent with NRC Regulatory Guide (RG) 1.9, throughout the motor starting sequence in all postulated loading conditions. Provide a summary of all bus voltages for the 'B' train distribution system.

NextEra Response NextEra is currently evaluating options to improve the emergency diesel generator (EDG) dynamic response under certain loading conditions. As a result, additional time is required to complete the supporting engineering analyses and calculations. Accordingly, a response to this question will be provided by March 26,2010. This schedule was discussed with the NRC during a telephone conference on February 25,2010.

Page 1 of 6

Question 2 The cables for new auxiliary feedwater (AFW) pump motors are planned to be routed through the existing duct banks and manholes which are susceptible to moisture, wet or flooding conditions. The stars review of Point Beach's operating experience indicates that, since 1997, numerous corrective action documents were generated to capture concerns associated with cable submergence and water ingress through underground cableways and manholes. Provide cable design specifications and manufacturer's certification to provide assurance that these cables are designed for the environment they will be subjected to. Also, provide details of the proposed initial tests and periodic tests for these cables including the type of tests and the frequency.

NextEra Response Power to the new motor-driven auxiliary feedwater (MDAFW) pump 1 P-53 motor from Train B EDGs will be routed through the existing duct banks. Power to the new MDAFW pump 2P-53 motor from Train A EDGs will be routed through the control building and primary auxiliary building (PAB) and will not be routed through existing duct banks and manholes.

The new MDAFW pump power cables are Okonite Okoguard Okoseal, Type MV-I05 518 kV Shielded Power Cable. Enclosure 2 provides the engineering report from the manufacturer for this cable. Enclosure 3 provides the cable test report. As noted in Section 6 of the manufacturer's engineering report and in the cable test report, periodic wetting of the cables has been evaluated and results of the testing have shown acceptable results.

Post-installation testing of the MDAFW pump power cables will consist of wiring continuity testing and insulation resistance (megger) testing to meet the following acceptance criteria:

Documented verification of continuity for wiring.

Insulation resistance tests will be conducted for each conductor to all other conductors of the same cable tied together and grounded. Tests will be conducted at 1000 V for power cables. The test duration will be at least 60 seconds. The minimum acceptance measured value in meg-ohms shall be the rated cable insulation voltage, in kilovolts, plus I.

High potential test of 8000 V rated cables will be performed at 35,000 V for 15 minutes.

Leakage will be recorded at one-minute intervals. If leakage current decreases or remains steady after leveling off, the test is considered satisfactory.

Baseline Tan Delta testing will be performed on the power cable routed in the cable vault from the Train B switchgear to MDAFW pump 1 P-53 motor.

A preventive maintenance activity will be initiated to Tan Delta test the new MDAFW pump I

P-53 motor cable at a 6-year interval after installation. The frequency may be adjusted based on observed conditions and operating experience.

The new MDAFW pump motor cables will be included in the cable condition monitoring program. The cable condition monitoring program manages aging of conductor insulation materials on cables and connectors, and other electrical insulation materials that are installed in adverse localized environments caused by heat, radiation or moisture.

Page 2 of 6

Question 3 In response to the staff's RAI dated August 26, 2009, regarding EDG/loss of voltage relay time delays, the licensee stated that the EDG output breaker closure within 14 seconds is consistent with accident analysis. The staff notes that this is inconsistent with the designAicensing basis for the EDGs. Specifically, Final Safety Analysis Report Section 8.8.1, Design-Basis, states that the EDGs are required to start and be ready for loading within 10 seconds after receiving a start signal. In addition, Section 8.8.3 states that the time from receipt of start signal to EDG ready to accept load shall not exceed 10 seconds (reaches its rated speed and voltage and the associated breaker closes automatically to reenergize the safeguard buses). The staff notes that the existing EDG design (time delays for output breaker closure is 14 seconds) is inconsistent with chapter 8 design-basis requirements. Explain the inconsistency and identify all the loads that are started on the safety bus at 10 seconds in accordance with Chapter 8 design-basis.

Final Safety Analysis Report (FSAR) Section 8.8.1, Diesel Generator System Design Basis, states the EDGs are required to start and be ready for loading within 10 seconds after receiving a start signal. This is a criterion for the EDG and is not affected by the EPU. The EDGs remain capable of starting and being ready to load within 10 seconds of a start signal, which is within the FSAR 8.8.1 requirement. There are no loads assumed to start on the safety related buses at 10 seconds.

The accident analysis time delays are based on the EDGs powering the buses within 14 seconds to support the timing requirements for safety-related loads. The 14 seconds is included within the total time requirements of the accident analysis for low head safety injection (LHSI), high head safety injection (HHSI), containment spray and containment fan coolers when a loss of offsite power (LOOP) is considered. The acceptance criteria take into consideration the degraded voltage logic, loss of voltage logic, and EDG ready to load logic.

The accident analysis described in PBNP FSAR Chapter 14 assumes delay times to account for delays associated with the processing of the accident signal, degraded voltage protection scheme to close EDG output breaker, and the start of the ESF equipment and components to attain design performance. The total delay time assumed for each accident also accounts for appropriate delays for instrumentation logic and signal transport. For the FSAR Chapter 14 accident analyses, the EDG is assumed to start and be ready to load within 10 seconds of receiving a start signal. Delays for instrumentation logic and signal transport account for the difference between the 10 second EDG ready to load time listed in the FSAR Section 8.8.1 and the assumed time of 14 seconds in the FSAR Chapter 14 accident analysis. Since the EDGs are required to start and be ready to load within 10 seconds, the EDG is capable of supplying power to the safeguards buses within 14 seconds and bounds the accident analyses.

Question 4 Explain how the EDG fuel oil consumption and volume calculation accounted for additional fuel oil requirements for AFW and other plant modifications. What is the basis for removing 10 percent margin from the original fuel oil consumption calculation? Provide details on how instrument uncertainties, instrument errors, temperature effects and specific gravity variations were accounted for in the calculation.

Page 3 of 6

NextEra Res~onse The EDGs will remain within their rated loads with EPU, AFW, and alternative source term (AST) load additions. The EDG fuel oil consumption calculation determined fuel oil requirements based on the applicable EDG rated loads. Fuel oil consumption during the first 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of operation for Train A EDGs is based on the 2000-hour rating of the EDG.

Consumption during the first 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of operation for Train B EDGs is based on the 195-hour rating. Fuel oil consumption for 7-day operation is based on the 2000-hour rating for Train A EDGs and the 195-hour rating for the first two days of Train B EDGs combined with 2000-hour rating for the remainder of the 7 days. Calculations have demonstrated that with the EPU, AFW and AST modifications, the EDG loading would be within the rated load.

The initial sizing of the EDG G-03 and G-04 fuel oil day tanks was based on a nominal fuel consumption rate and included a 10% margin. The revised EDG fuel oil consumption and volume calculation transmitted by Reference (3) used a more accurate determination of the fuel oil consumption rate based on EDG performance testing with corrections for specific gravity based on PBNP Fuel Oil Acceptance Criteria and a correction for the use of Ultra Low Sulfur Diesel fuel. The 10% margin was provided for initial tank sizing and is not considered applicable to subsequent capacity evaluations.

The EDG fuel oil consumption calculation determines the process limit for the minimum indicated level for the fuel oil storage tanks to meet the TS. Note that the calculation has been revised to account for two EDGs in either Train A or Train B, starting, drawing fuel from a common fuel oil storage tank, and continuing to operate for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> at the most conservative analyzed EDG loading to satisfy license basis requirements. A change to the TS has been proposed to resolve this condition per Reference (4). The level switches used for alarms, "pump on" and "pump off" conditions on EDG fuel oil day tanks, high and low alarms for fuel oil day tanks, and low alarms on fuel oil storage tanks are GEMS (IMO) model LS-800 non-adjustable float switches. The repeatability uncertainty of the level switches is about 0.031 (1132) inches and the switches were factory set using water. The acceptable range for specific gravity of the diesel fuel oil is 0.89 to 0.83 (average = 0.86). This represents an uncertainty of 0.12 inches. The uncertainty associated with the level switches is considered to be negligible.

The calculation assumes that, for the purposes of determining fuel oil consumption, the average temperature of the fuel oil is nominally at 60°F. Fuel oil is stored in small day tanks near the EDGs and in buried large capacity storage tanks. Fuel in the day tanks is at the normal ambient temperature of the storage tank rooms prior to the start of the engines. These rooms will heat up as the engine operates. The buried storage tanks are normally at the soil temperature at their average depth. The volume of fuel below ground is significantly larger than that in the day tanks. Based on the fuel consumption rates and the day tank size, fuel pumped from the below ground storage tanks will not significantly heat up as the engine operates when used to support the 48-hour and 7-day fuel consumption calculations (which are based on the engine operating at rated capacity).

Page 4 of 6

Question 5 In response to the staff's RAI dated August 26,2009, regarding environmental parameters for the AFW motor location, the licensee stated that the normal radiation level is 1300 RAD for 60-year total integrated dose, and the AFW pumps and associated equipment will not be included in the environmental qualification (EQ) program since they are not credited in the accident analysis although they are sequenced loads used in a loss-of-coolant accident. The pen'ormance capabilities of the non EQ AFW motor may be degraded after exposure to potentially harsh environment during the accident, Explain the rationale for allowing operation of the degraded motor connected to a safety related bus which is supplying power to safe shutdown equipment.

NextEra Response In the event of a large break loss-of-coolant-accident (LBLOCA), radiological conditions could become harsh in the MDAFW pump area. However, for a LBLOCA the MDAFW pumps are not required for accident mitigation. Additionally, the AFW pumps are connected to safety-related busses through safety-related breakers. The breakers will prevent degraded MDAW pump motors from adversely affecting the safety related bus during the accident.

Question 6 In response to the staff's RAI dated June 2,2009, regarding the surveillance tests for EDGs, the licensee proposed new Technical Specification Surveillance Requirement 3.8.1.7 requirement (the performance of a 24-hour endurance and load margin test of each EDG). The staff notes that the proposed EDG endurance and margin test does not envelop the accident loads for the entire duration of the 24-hr run. Specifically, EDGs GO1 and G-02 are loaded to 98.2 percent to 100.9 percent of the 2000-hour load rating for, 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 90 to 100 percent of the 2000-hour load rating for the remaining 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />; G-03 and G-04 EDGs are loaded to 97.4 percent to 100 percent of the 200-hour load rating for ~2 hours and 90 to 100 percent of the 2000-hour load rating for the remaining 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> with EDGs operating at the highest end of the 2-hour load range for 5 minutes. This is not consistent with RG 1.9 recommendations. The intent of the 24-hr test is to demonstrate that the EDG can operate at maximum postulated accident loads for extended duration. The 2-hour test requirement at a higher loading demonstrates design margins. Therefore, staff requests the licensee to provide basis why the proposed loading ranges are adequate to demonstrate the capability of the EDGs to operate for its intended mission time. Also, explain why EDGs designated for each unit cannot be tested during modes other than modes I and 2 as recommended in NUREG-1431.

NextEra Response NextEra is currently evaluating options to reduce EDG loading and reduce the likelihood of overloading the EDGs during testing. As a result, additional time is required to complete the supporting engineering analyses and calculations. Accordingly, a response to this RAI will be provided by March 26,2010. This schedule was discussed with the NRC during a telephone conference on February 25,201 0.

In response to the question regarding testing in MODES 1 and 2, at PBNP the EDGs are train-specific rather than unit-specific. The two Train A EDGs are available to supply Unit 1 and Unit 2, as are the two Train B EDGs. As a result, each EDG is available to be lined up to either or both units.

Page 5 of 6

At least one reactor unit at PBNP is normally operating in MODE I, although the other reactor unit may be shut down. Therefore, it is not practical to perform this surveillance on each EDG on an 18-month interval with both units shut down. PBNP has been performing 24-hour EDG load testing on a 24-month frequency safely with both units typically operating in MODE 1.

References

( 1 NRC letter to NextEra Energy Point Beach, LLC, dated February I, 2010, Point Beach Nuclear Plant, Units I and 2 - Request For Additional lnformation From Electrical Engineering Branch Re: Auxiliary Feedwater - Round 2 (TAC NOS. ME1 081 and ME1082) (ML100120331)

(2)

NextEra Energy Point Beach, LLC letter to NRC, dated December 8, 2009, License Amendment Request 261, Supplement 3, Extended Power Uprate (ML093430114)

(3)

NextEra Energy Point Beach, LLC letter to NRC, dated September 25, 2009, License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Information (ML092750395)

(4)

NextEra Energy Point Beach, LLC letter to NRC, dated January 27, 2010, License Amendment Request 264, Diesel Fuel Oil Storage Requirements (ML100280230)

Page 6 of 6

ENCLOSURE 2 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS I AND 2 LICENSE AMENDMENT REQUEST 261 EXTENDED POWER UPRATE RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION OKONITE COMPANY ENGINEERING REPORT #527 29 pages follow

THE OKONUPE COMPANY Ramsey, Nd ENGlCNlEElRYNG REPORT #527 Class 1E Qualification of Okoguard Insulated Cables For Nuclear Power Generating Stations Class 1E qualification of The Olconite Company's Okoguard medium voltage 90°C rated ethylene R1 propylene rubber insulated cables is idocumented in this report. Qualification testing was conducted in accordance with the IEEE standards 323-2003 and 3B3-2003 which equal or exceed the requirements of the 1974 editions.

Class IE qualification is based on the generic qualification type test method and analy&.

Design basis eqent (DBE) and flame test I R1 qualifications are based on type testing. Theimal aging to demonstrate normal life is based on type tests and analysis.

~he' Olcoguai-d insulation systeni consists of The Okonite Company's proprietary Okoguard (EPR) insulation and extruded semiconducting EPR based conductor and insulation shields. The testing described and dbcumentedin this report demonstrates environmental qualification of all three components of the insulation system.

The DBE tests were conducted on the thinnest insulation wall used by Okonite on medium voltage rated products. Qualification of the thinnest wall qualifies all thicker insulation walls used in all Olcoguard medium voltage cab\\es.,

This report is divided into several sections. These sections address the testing and documentation required to demonstrate class 1E qualification and are supported by the listed appendices.

Section Title 1

DBE-LO~A Qualification 2

A Review of Design Life of Okoguard (Research Report No. 597 and Appendix tb Research Report 597 2-13-07)

Rl 3

Testing and Analysis to Determine Sequence of Thermal and Radiition Aging (Research Report No. 596 dated 12-08-05)

R I 4

~ualifichtioh

.. for Normal Operation 5

Vertical Tray Flame Test Qualification 6

Moisture Resistance 7

DBE-~igh Energy Line Break Qualification The testing conducted to demonstrated DBELLOCA qualification is documented in Wyle Report No. 51 055-2 and is provided as part of this report as Appendix A.

The testing conducted to demonstrated qualification for normal operation is documented in Wyle Report No. 5 1055-1 and is provided as part of this report as Appendix B.

Okoguard insulated cables have been to IEEE 383-1974 for Class lE,safety related use since 1977: This earlier qualification is documented in Okonite report--3 and is provided as part of this report as Appehdix C.

Appendices Title A

. DBE-LOCA Test Report - Wyle Report 51 055-2 Rev B B

Normal Operation Test Report - Wyle Report 51055-1 C

Nuclear Environmental Qualification Report NQRN-3 Rev 4 D

DBE-HELB Test ~ e ~ p r t. - ~ ~ ~

TR62871-06~

R1

1.

The test results included in this report bembnstrate the ability of Olcoguard insulated cable to perform its intended function.

I R1 Prepared by: J. R. Cuncelos'i C. P. Zuidema Manager Application Engineering Director Polymer Research Reviewed by: J. I? FiIz~eralp V. P. ~pplicat'ton Engineering Approved by: F. R. ICenerise V. P. Research f

Signature J. R. Cancelosi J. R. Cancelosi C. P. Zuidenza J: 6: FMegerald W; R Kegerise Reason New Issue Added rated temperature, IEEE Standard dates, additional informatiori in Sections 1,2 & 4, additional VTFT data, Section 7, revision 2 to Appendix A and new Appendix D.

Also - made editorial changes '

Rev.

0 Date 12-09-05 05"24-07

THE BKOMliVE d=OMVBPANV Ramsey, Wd Eng. Report 527 Section I SECTION 1

'.DBE-LOCA Qualification The Olcoguard insulation system was LOCA qualified basis a type test, generic qualification method as allowed by jEEE 323-2003 and IEEE 383-2003. The temperature/pressure/time/spray R]

profile selected was based on IEEE 323-1 974, Appendix-A, Figure Al. This profile was chosen since it had been used in previous Olconite tests and was accepted by nuclear utilities as meeting their specific plant profiles.

The LOCA test was conducted on the thinnest insulation wall used by OIconite on medium voltage rated products. Quilification of the thinnest wall qualifies all thicker insulation walls used in all Olcoguard medium voltage cables.

The 'Okoguard insulation system consists of Olcoguard insulation (0-63), extruded semiconducting EPR based conductorish'ield (C-52) and extruded semiconducting EPR based insulation shield (C-53). The LOCA testing demonstrates environmental qualification of all three components of the insulation system.

The Olcoguard test specimens were manufactured at Okonite under production run number X4668. A description of the specimens, voltage and current loads, and aging conditions are given in Table 1. Completed cable spepi,mens were tested to determine if any detrimental synergistic affects due to the shield, tape and jacket layers would occur.

I I

I R1 LOCA qualification was conducted by Wyle Laboratories, Huntsville, AL. A mutually agreed upon test procedure plan was deveIoped and folIowed.

The performance requirements to demonstrate Class 1E qualification are:

I. Maintain electrical'load as given in Table I.

2. Pass the dielectric withstand test - post accident (prior to removal from the test chamber.)

Charging current not to exceed I0 mA.'

3. Pass the Post DBE Simulation Test pending Test). Charging current not to exceed 10 m A, Insulation resistance and charging current rniasurements, talcen during the test profile on each of the three specimens, could be used to demonstrate additional perfbrrnance criteria.

Based on the analysis to determine the proper sequential order for thermal aging and radiation aging (see Section 3), the spedimeris were first exposed to 50 Mrads of gamma radiation. The specimens were then subjected to thermal aging. he thermal aging was selected to be three weelcs at I5OoC to simulate a 40 5eBr design life arid two weeics at 165OC to simulate a 60 year design life. Following the thermal 'aging conditioning, the specimens were exposed to an accident dose of 150 Mrads gamma radiation.

Eng. Report 527 Section 1 The Olcoguard specimens were installed in the test vessel and subjected to the temperature/pressure/chemical spray profile. shown in Wyle Report 51055-2. The specimens were voltage and current loaded in accordance with Table 1. Charging current was monitored throughout the profile.

To determine the specimen cohdition throughout the qualification test, the following additional Insulation Resistance measurements and ac withstand test (80 volts/mil) were made and results documented.

IR and ac withstand prior to aging R

post aging hse' radiation IR post thermal aging IR post accident dose radiation IR at 345"F, 338"F, 31 8"F, 269°F IR at 265°F (4" day)

IR at 212°F (191h day and 3oLh day)

Ac withstand test after removal from test vessel and prior to removal From support mandrel The specimens were then removed from their support mandrels, straightened and recoiled around a 40 x O.D. steel mandrel. Each specimen, while on' the mandrel, was immersed in room temperature water for a minimum 05 one hour. While still immersed, each specimen was subjected to an 80 vlmil ac withstand'test. The test voltage and charging current vdues were recorded.

All samples passed the Post DBE 'Simulation Test (Bending Test). All qualification testing is documented in Wyle Report NO. 51055-2 (See Appendix.A). Note that the Wyle repoit includes R1 other specimeris (low ~olta~e~insui~tions) that'are not included in this qualification report.

I Table 1 Description of Test ~ ~ e c i m e n s,

Electrical.Loads and Aging Conditions J R. Cancelosi Manager Application Engineering I

I t

I,

Test i

Required, I

I Voltage :

i Required Required i Radiation j phase i Test j

Thermal Thermal \\ Dose Mmds Specimen Production j

. : to grd i Current i Aging Time j Aging i

No.

I Run No.

Description (volts) I (amps) I (hours)

Temp C :

431x4568 i

5kV#6AWG;.015'1C-$2, i

5000 j 80 Unaged j - '

f 150 44 / ~4668

/

0.1 15" G63,0.024 C-53,.O05" TC

/

5000 :

80 504 04 150 200 j tape, cable tapes, 0.060" R-14 (TS-j I

I 45 : X4668 I

CPE) ]kt I

5000 !

80 336 1

165 200 R.1 R1 R 1 Material G63 (EPR)

C-52 & C-53 R14 (TS-CPE)

Trade Name Okoguard Semiconducting EPR Shield ORolon-CPE (Okosheath)

-. I....

THE 8K6LBNUY'E C0MPANPb Ramsey, Nd Eng. Report 527 Section 2 j Section 2 Design Life Based on Thermal Aging Study

.Research Division Report

' No. 597 A Review of Design Life of Okoguard, G63 December 01, '2005 By,; Carl Zuidema

==

Introduction:==

The demonstration of the design life of G63 was presented in the Nuclear Environmental Qualification Report NQRN 3, Appendix 2. That appendix referenced aging data, both natural and accelerated, for a number of Okonite aompounds. The data in this report have been extracted from those earlier reports..

Discussion:

Appendix 2 of NQRN 3 inclubed laboratoj accelerated aging data for EPR and XLPE compounds analyzed via an Arrhenius type treatment.and compared these data to similar data for butyl rubber, natural rubber.and Neoprene. Results oftensile and elongation measurements on some service aged cable with natural rubber, Neoprene and butyl rubber components were also discussed. These results indicated that for cable aged in service, elongation retention values were much greater than those predicted by the extrapolation of the Arrhenius plots. It also showed that the life projections for EP and XLPE were greater than butyl rubber by a factor of 7.5 and better than natural rubber bx a factor of at least 40. Data for the aging characteristics of single conductors aged as complete cables, [that is in jacltets), were also presented to demonstrate the superior aging performance under installed conditions. Since the naturaI rubber compounds had been in service in ge'neraii,ng stations for greater than forty years and butyl had been in sewice for greater than ten years it was argued that an aging regimen that met or exceeded the design life of butyl rubber was suficient to simulate forty year aging of EPR.

However, the aging regimen chosen, a time and temperature to 40% elongation retention for EPR, greatly exceeds the design life of the older insulations. This time and temperature, 21 days at I SO0C, is still used as the simulation of 40 year design life.

I The data for G63 was collected on specimens of insulated wire, #14 tinned copper, with 47 mils of insulation. The ovens were forced draft type similar to those used in the recent work but of an earlier manufacture. The data reported in Appkndix 2 included oven aging data &om 136°C to 180°C. That report referenced additional data colleqted at 121°C that were not included in the calculations. These 121 "C dblta are included in the presentation below and illustrate one of the 1

1 P

L;

Eng. Report 527 Section 2 main contentions of the earlier report, na&ly that e~tri~olation of the data to temperatures.

outside the tested range will be erroneous. The data reported in Appendix 2 give an activation energy for G63 of 1.05 eV and an extrapolated life of 7.5 years at 90°C. When the data at 121°C are included the activation energy becomes 1.15. eV and an extrapolation to 90°C gives 10 years.

If only the four lowest temperatures are used, - temperatures nearest the use temperature -the activation energy is 1.29 and the extrapolation to 909C is 16 years. The data'do not fit an Arrhenius treatment very well, so clearly, ihe best use for this type of data is to establish a means of comparing new materials So materials that have a proven service record. The class of EPR with the trade name Okoguard has a service record as a 90°C rated insulation of over forty years.

This use includes generating stations. Butyl rubber has an even longer history as a 90°C rated insulation. The EPR compounds presented in Appendix 2 of NQRN 3, as a class, have a.

performance advantage over Butyl rubber by a factor of 7.5.

I Oven Aging'af (363, (ca. 1976)

Time to 40% Elong.

. Temp Retention 1 f l "K

" C Hours

"'02207 wl 0.002282 0.002363 420 0.002444 i 136 1344 d.002537 121 5664 Table No. 6

Eng. Report 527 Section 2 0.0021 0.00215

.0.0022 0.00225 0.0023 0.00235 0.0024 0.00245 O.OD25 0.00255 0.0026 Temp., (IWK)

'Chart No. 3

THE QKONUVE @&BWIJPAMY i

Ramsey, Nd Eng. Report 527 Section 2 Appendix to Research Division Report No. 597 Thermal Aging Study of Semiconducting Compounds Compounds C52 and C53 February 13,2007 By: Carl Zuidema

==

Introduction:==

This report covers the results of a study of Olconite's insulation shield and conductor shield compounds. Accelerated agings of pressed cured plaques were conducted in a manner similar to that used for the insulation compounds, G63 (reported in the body of this report), as well as B0304 and B22; (covered in ~esearch Report No. 595).

Procedure:

Die cut tensile specimens were prepared fram press cured plaques, as per ASTM D412 die "D",

of Okonite compounds C52, (conductor shield) and C53, (insulation shield).

Factory prepared compound, lot no. 5285 for C52 and lot no. 5335 for C53 were used for the evaluation. Specimens were suspeded in forced convection ovens consistent with ASTM D5423 type 11. ~aboratory ovens #6, #I 0, #I 1 and #I2 were used. The temperature consistency ofthe ovens was recorded via a chart recorder and daily readings of each oven thermometer were also ~ecorded.

The procedure again generally followed UL 746B, as was used for B0304 and B22. In this case 50% retention of original elongation is used as the end point for each temperature studied. For these compounds the 50% value was chosen since it provided a determination with the least variance..

The aging data were plotted and a best fit polynomial used to determine the 50%

retention value. Time to 50% elongation retention is plotted versus inverse absolute temperature and a best fit exponenfial was detem'ined in accordance with the Arrhenius equation:

k=Ae-L*IRT

THE CDKONBTiE COMMIIPAWY Rsmsrey, NJ Eng. Report 527 Section 2 Where k, (the rate constant), is represented by the time required to reach the designated end point and T is the aging temperature in degrees Kelvin. The terms "A", referred to as the pre-exponential or frequency factor, and "E"', referred to as the activation energy are constants derived from the equation generated by the data: "1c" and "T".

These data are presented below in graphic format. Chart No. l presents the aging data for C52 and Chart No. 2 presents the aging data for C53. The best fit polynomial constants are presented in Table No. 2 with the solutions for the calculated 50% retention point. '

Chart no. 3 shows the Arrhenius treatment with log time to 50% elongation retention plotted versus inverse absolute temperature. For reference the a aster plot" of earlier Olconite compounds is also displayed as is the curve for B22. The plot for C52 displays a frequency factor somewhat lower than that of the "Masterplot" but the slopes of the two curves are approximately equal. The equation derived for C53 has a frequency factor similar to the "Masterplot" equation but a moderately different slope. The fit of the C53 data to the Arrhenius equation is significantly poorer than for C52 with a correlation coefficient of around 0.970 versus about 0.999 for $52. Given that there is no theoretical justification for the application ofthe Arrhenius equation to this type of data, the laclc of fit is not surprising and serves to demonstrate the limited usefulness of extrapolation as a means of determining design life at temperatures that are not readily testable. From the derived parameters of the Arrhenius equations the calculated activation energies would be 1.13eV for C52 and I.32eV for C53, The line labeled " ~ a s t e r ~ l o t ~ ~

on chart no. 3 is representative of a number of Olconite compounds whose qualification for use on Class 1E cables in nuclear power stations was reported in NQRN 1 A, NQRN 2 and NQRN 3. For all of these cables, 21 days oven aging at I 50°C was used to simulate 40 yebrs of natural aging in a nuclear power plant.

This choice was discussed in the appendix to each of these reports and summarized in the body of this report, That aging criteria was also'applied to B0304 and B22, which display similar mechanisms in their,aging performance. Research Report No. 595 and 597 discussed the selection of 14 days oven aging at 165°C to simulate 60 years of natural aging for B0304,322 and G63, Since the aging characteristics of C53 and C52 are also showing a convergence of mechanisms with the other compounds, (as indicated by Chart No. 3), the accelerated aging criteria selected to represent natural aging for C52 and C53 is also identical to that of these other compounds.

TIWE QKONilf & COMPANY Raumsey, Nd Eng. Report 527 Section 2 Oven Aging Data Analysis, C53 Oven Aging Data Analysis, C52 Polynomial Constants Temp "C IITaK

. a b

c d

hours

. Polynomial Constants 136 0.002444 1.ME-07 -3.00E-04 5.73E-02 9.96E+01 150 0.002363 1.08E-05 -6.30E-03 6.14E-01 9.99Ej-01 165 0.0022.82 5.87E-05 -1.31E-02 1.44E-02 I.00E+02 175 0.002231 2.40E-04 -2.82E-02 -4.92E-0 1 1.00EJ-02 Temp "C 117°K a

b c

,hours I

136 0.002444 3.07~-06 -3.34E-02 1.00~+021 1.79~+031' 6.65E1-02 2.1 2E+02 7.75E+01 4,04E+01 Table No. 2 Arrhenius Plot, Seniiconducting Compounds Chart No. 3

THE OKCBMIITIE COMiflDANY Remsey, NZII

+

Eng. Report 527 Section 3 Section 3 Testing and Analysis to Determine Sequence of Thermal and Radiation Aging Research Division Report No. 596 Sequential Effects of ~hermal and Radiation Aging om EPR Compounds

. December 8,2005 By: Carl Zuidema

==

Introduction:==

An investigation was conducted into the effect of sequential aging exposure on two EP FMR type compounds, B0304 and B0305, (also referred to as B22). This evaluation was performed to determine whether the sequence of thermal aging before radiation exposure or radiation exposure before thermal aging produced significant differences in final properties. These two compounds were likely candidafes'for a I-E nuclear qualification program which requires both thermal aging to simulate natural aging and radiation exposure to simulate the radiation exposure during the lifetime in a nuclear power plant.

Procedure:

The experiment was labeled with the laboratory number LE 0121 04. Press cured plaques of the two compounds were prepared.and treated via the design matrix described below and in the attached tables, The materials were tested in the original condition and after each step in the exposure'sequence. That is, unaged, oven aged 21 days at 150°C or oven aged 14 days at 165"C, 50 Mrads radiation, and 150 Mrads radiation, The sequence of interest is between oven aging and the 50 Mrads e~posure since these are intended to simulate the life time exposure of the materials. The two oven aging exposures are intended to represent 40 and 60 year design life. The properties of the hyo materials that were followed were tensile strength, elongation, hardness and density.. It was found that the elongation was the only property that demonstrated a consistent response to aging sequence and was therefore used as the basis judging the severity of any effects. Oven aging was conducted in ASTM type I I forced draft ovens and the radiation exposure was performed at Sterisllsomedix in Whippany NJ. The physical property data is recorded in Insulations Log Bookf17, pp 434-436.

Eng. Report 527 Section 3 Results:

I Oven aging alone produced insighifiqant changes in the elongation and other bropertiei as expected. 50 Mrads of radiation reduced the elongation to approximately 40% of the original value for all samples whether o\\;en aged or not. When the radiation exposure preceded oven aging the elongation'retention was approximately 10%. After.the full 200 Mrads exposure the samples with no oven aging retained approximately IQ% of the original elongation. Those samples that were oven aged prior to the 50 Mrads exposure were also around 10% of the original value while those that were radiated first retained around 2% of their original elongation.

Discussion:

These results indicate that radiation exposure produces a much more significant effect on mechanical properties than either of the thermal aging conditions. Exposure to 50 Mrads of radiation prior to'thermal aging causes the subsequent thermal aging to be much more deleterious than the reverse sequence. However, after the final 150 Mrad exposure all materials experienced a severe loss of elongation to the point where the difference between all samples is very small. This difference in final elongation values is not clearly beyond normal variance for elongation tests but since the trend was observed in both materials it is recommended that radiation aging precede thermal aging for purposes of I-E nuclear qualification testing of these compounds. Since the chemical nature of EPR insulation compounds are quite similar it is'also recommended that the same aging sequence be followed for the re-qualification of. Okoguard G63 compound.

The tables below out~ine.the.desi~n'h&~x for this evaluation, (table I), and the data '

generated, (tables 2 & 3). The elongatjon retention and tensile strength retention data is presented graphically in chart I.for compound 00305. The behavior of 80304 is nearly identical to 60305.

Effect of Sequential Aging: Oven Aging with Irradiation

~ 0 3 0 5

& I30305 6" x 8" x 0,075" slabs B0304 set #32611001.

6" x 8" x 0.075" slabs B0305 set #33391001 I. Original

2. Oven aged, (2 conditions)

3. Original followed by 5 0. ~ r a d s '

' 4. Oven aged, (2 conditions), followecj by 50 Mrads

5. 50 Mrads followed by oyen agipg, (2 Conditions),

6. 50 Mrads followed by; 1.50 Mrads 7, Oven aged, (2 Conditions), followed by 50 Mrads plus additional 150 Mrads

8. 50 Mrads followed by oven dging, (2 Conditions), followed by additional A50 Mrads Table I 14

Eng. Report 527 Section 3 Test Results, B0304 Press Cured Plaques, 6" x 8" x 0.075" Sample Id. '

Unaged Pre Aged Pre Aged

.21.Days 14Days.

Tensile Strength & Elong -

1 5 0 °.. :

165"

%.Retained after Aging Durometer & Specific gravity - measured Tests

%'~etentioh value Tensile Strnth Elongation Durometer Spec. Grav.

After 50 Mrads Unaged Pre Aged Pre Aged Aged, 21 Days Aged 14 Days 21.Days 14 Days 150" I

650

@ 150°C

@ I6S0C Tests

% Retention

% Retention % Retention after 50 Mrads after 50 Mrads Tensile Strnth 117 121 103 45 30 Elongation 46 3$

31 I 0 9

Durometer C 77 77 77 74.

76 Spec. Grav.

1.345 1.365 1~369 1.392 1.398 After 150 Mrads Unaged

' Pre &g6d Pre.Aged ' ' Aged, 21 Days Aged 14 Days 21 ~ a y s. 14 Days 15d"

,: 165"

@ 150°C

@ 165°C Tests after 50 Mrads after 50 Mrads Tknsile Strnth 82 QO 75 41

28.

'Elongation 12 13 10 2

2 Durometer C 84 84 84 85 87 Spec. Grav.

1.370 I

.373 1.372 1.387 I

.390 Table 2

Eng. Report 527 Section 3 Test Results B0305 Press Cured Plaques, 6" x 8" x 0.'075" Unaged Pre Aged Pre Aged Sample Id.

21 Days i

14 Days 150" 165" Tensile Strength & Elong - % Relained after Aging Tests

% Retention Duron Tensile Strnth Elongation Durometer C Spec. Grav.

Tests Tensile Strnth Elongation Durorneter C Spec. Grav.

After 50 Mrads Unaged Pre Aged Pre Aged Aged, 21 Days Aged 14 Days 21 Days 14 Days 150" 165"

@ 150°C

@ 165°C'

% ~etention % Retention % Retention after 50 Mrads after 50 Mrads 125 125 131 65 62 47 45 47 13 12 83 83 83 80 82 1.425

.1.447 1.439 1.460 I

.477 t

After 150 Mrads Unaged Pre Aged Pre Aged Aged, 21 Days Aged 14 Days 21 Days 14'~ays 1 507

. 165"

@ 150°C

@ 76S°C Tests

.. after 50 Mrads after 50 Mrads.

Tensile Strnth 89

' 90 89 65

60.

Elongation 8

8 8

3 2

Durometer 88 88 :

88 88 88 Spec. Grav.

7.445 1.450 I

.462 1.478 I

.482 Table 3

Eng. Report 527 Section 4 Section 4 Qualification for Normal Operation This section demonstrates compliance to TEEE 383-2003,Section 4.6.2. Okoguard insulation '

~1 was qualified for normal plaint operation based on the generic qualification type test method and analysis. The normal plant qualification testing was conducted on the thinnest insulation wall used by Okonite on medium voltage rated products. Qualification of the thinnest wall qualifies all thicker insulation walls used in all Olcoguard. medium voltage cables.

The Okoguard test specimens were manufactured at Olconite under production run number X4668. A description of the specimens and aging conditions are given in Table 1.

The performance requirement to demonstrate Normal Operation qualification is that each specimen passes the post aging simulation test (bending test). Charging current is not to exceed 10 mA.

Normal plant operation qualification was conducted by Wyle Laboratories, Huntsville, AL. A

.... mutually agreed upon tesf procedure $Ian was developed and followed. See Wyle Report No.

51 055 (Appendix B of this report).

Based on the analysis to determine the proper sequentiil order for thermal aging and radiation aging (see Section 3), the specimens were first exposed to 50 Mrads of gamma radiation.

The specimens were subjected to fherrnal aging. The thermal aging was selected to be three weelcs at 150DC to simulate a 40 year dpigri life and two weelcs at 165°C to simulate a 60.year design life.

I After removal from the oven the specimens were allowed to reach room temperature, The specimens were then straightened and recoiled around a 20 x O.D. steel mandrel. Each specimen was immersed in room temperature water for a minimum of one hour. The effective length (immersed length) of each specimen was an approximately 14 feet. While still immersed each specimen was subjected to an 80 $/mil ac withstand test. The test voltage and charging current values were recorded.

All samples passed the post aging simulation test (bending test). Charging current measurements were below 10 mA. mote that the charging current was measured on specimens without special end leakage (guarded) terminations.] All qualification testing is documented in Wyle Report No.

51055-1 (Appendix B of this report). The spechiens are identified as numbers 88 & 89. Note that the Wyle report includes other specimens (low voltage insulations) that are riot included in this qualification report.

. Table. 1 Specimen Idpntification and Test Conditions Eng. Report 527 Section 4 J. R. Cancelosi Manager Application Engineering Required Radiation Dose Mrads 150 Required Thermal Aging Temp C 150 q

(TS-CPE) jkt

. Required Thermal Aging Time (hours) 504 Description 5 kV #6 AWG,.015" 6-52, 0.1 15" G65,0;024 C-53,.005" TC tape, cable tapesi;'0.060" R-14 Specimen No.

88 200 _

336 Production Run No.

X4668 165.

I Material G63 (EPR)

C-52 & G53 R14 (TS-CPE)

Trade Name Olioguard Semiconducting EPR Shield okolon-CPE (Okosheath)

THE OKONITE GOIibrPANV 1

Ramsey, N4 Eng. Report 527 Section 5 Section 5 Vertical Tray Flame Test In accordance with IEEE 383&the completed cables must meet a.vertica1 tray flame test.

Flame testing was conducted in accordance with IEEE 383-1 974 as modified by US ~e~ulaiory Guide 1.131. Compliance to the vertical bay flame test requirement is demonstrated in the following "Vertical Trav Flame Test Data Sheet SUMIvIARY OF FLAME TEST RESULTS". $ R1 In addition, in order to meet the vertical tray flame test requirements of IEEE 383-2003 paragraph 8.0 "Flame Test Qualification",;cables were subjected to the IEEE 1202-1 991 vertical tray flame test procedure. Both unaged and aged cable specimens were tested.

Compliance to IEEE 1202-1991 is demonstrated in the following summary sheet labeled "IEEE 1202 Vertical Tray Fire Propapation Test Data Sheet."

R 1

Eng. Report 527 Section 5 WRTICAL TRAY FLAME TEST DATA SJBET

SUMMARY

OF FLAME TEST RESULTS Test Procedure:

lEEE 383-1974, Paragraph 2.5 as modified by US Reg. Guide 1.I31 Flame Source:

Ribbon Gas Burner Sample Construction:

5 lcV 3-11C 410 AWG Cu, extruded semicon (C-52), 0.115" ~ l c o ~ u a r d ' ( ~ ~ ~ )

(G-63), extruded insulation screen (C-53), 0.005 tinned copper tape shield, cable tapes, 0.080" Okolon (CSPE) (R-09) jaclcet. Triplexed with one # 3 AWG Olcolon jacketed ground. OD = 2.38" 04-X4654 (Reference # 02:022-Test Results:

U n

a g

e d

Test #

1.

Afterburn, min:sec 0:06 i Jacket Damage, inches 18 20 17 Core Damage, inches 10 11 10 Propagation No No No PassFail Pass.

Pass Pass Test #

-. 1, Afterburn, min:sei:

605 Jaclcet Damage, inches

.30 35 27 Core Damage, inches 19 27 I8 Propagation Pass/Fail No Pass No Pass

THE OKOA~TIE COBIdilPANY Ramsey, Nd Eng. Report 527 Section 5 IEEE 1202 VERTICAL TR&Y FIRE PROPAGATION TEST DATA SHEET TestProcedure:

IEEE 1202 - 1991 standard foroi?lame Testing df,Cables f o r Use i n Cable Tray i n Industrial'& Commercial Oc~upancies:~

Conskruetrion:

5.kV /C 2/0 AWG Cu, extruded semicon (C-52), 0.115" Okoguard (EPR)

(G-63), extruded 'insulation screen (C-53),

0.005" tinned copper tape shield, cable tapes, 0,080" Olcolon-CPE (R-14N) jacket. OD = 0.945" 04-X4683B Tesk Results :

Unaged I

06-056 2: 55 3 2 2 8 06-055 3: 45 3 4 2 9 Aged 3 weeks a t 150 c t,

Maximum Allowable Damage, i n.

Propagation Pass/Fail T e s t Number Afterburn, min:se'c Jacket Dama.ge, in.

Core Damage, in,06-031 4 : 10 37 3 1

'Test Number Afterburn,.min : sec Jacket ama age, i n.

Core Damage, i n.

5 9 06-030 8 : 1 0 5 1 4 5 No Pass Maximum Allowable Damage, i n.

Propagation Pass/Fail No Pass 5 9 No Pass No Pass

THE 16BKgbNffTE C(pBMPABVI11 Ramsey, Ndlrdl Eng. Report 527 Section 6 Section 6 Moisture Resistance Long Term 90°C Water Immersion Accelerated Test i

To demonstrate long water stability of Okoguard insulated wire, specimens were directly immersed in 90°C water to accelerate the deteriorating effects of moisture. Testing was conducted in accordance with ICEA T-27-581, paragraph 2.6, "Accelerated Water Absorption test, Electrical Method at 60 Hz (EM-60)" except that the time was extended and 600 volts continuous stress was applied. Dielectric constant, dissipation factor and insulation resistance were monitored. Insulation resistance, measured at

-500 volts dc, was also monitored. Results are tabulated below, Sample: # 14 AWG copper, 0.030" Okoguard (G-63)

Method: ICE. T-27-581, paragraph 2.6, except test fime extended 600 volts ac continuous stress applied and insulation raslstance measured at -500 volts dc

Reference:

LE 102299A 9OC Dielectric Dissipation SIR Immersion Stress

. Constant factor -%

megs-kft Time vlm I

Day 40 2.74 1.10 383 80 2.74 1.16 I Week 40 2.76 0.83 488 80 2.76' 0.86 3 Months 6 Months 9 Months 12 Months

'ITHE OKBBNUUE COMPANY Ramsey, Md Eng. Report 526 Section 7 DBE-1YELB Qualification The Okoguard insulation system was DBE qualified basis a type test, generic qualification method.

The temperature/pressure/time/spray profile selected is shown in Figure 1. This profile was chosen since it had been used in a previous Oiconite qualification test and was accepted by nuclear utilities as meeting their specific plant profiles. Qualification was conducted in accordance with the 'Test Plan for DBE-HELB Qualification to JEEE 383'>*This test plan is included in this section as Appendix 1.

The H

~

B test &as condukted on the thinnest insulation wall used by Olconite on medium voltage rated Olcoguard products. The Olcoguard cable test specimens were manufactured at Okonite under production run number X4668.

Specimen descriptions, voltage and current loads and aging conditions are given in Table I. Okonite was responsible for Specimen Coiling, Aging Radiation Exposure and Thermal Aging Expoiure.

Table '1 HELB qualification (DBE-HBLB and, ~unctianhl Test After DBE-HELB Conditions) was conducted by National Technical Systems (NTS), Acton MA. A mutually agreed upon test procedure plan was developed and followed (see Section 7, Appendix 1).

The performance requirements to demonstrate class I E qualification are:

FQ #

04-X4668 Specimen 11 12 13 I. Maintain electrical load as giyen in Table 1.

Description 5lcV #6 (7X)

AWG Bare copper, 0.1 15" C-52 0.1 15" G-63 (Olcoguard), C-53,0.060n R-14 (Okolon CPE)

Specimen Chad, WELB, (25 ft. specimens)

PO#

O.D.

Radiation Oven Aging Regimen X4468 0.720 0.

N/A X4668 21 Days @, 150C X4668 0.720 50 Wads 14 Days @ I65C

2. Pass the dielectric withstand test - post accident (prior to removal from the test chamber.)

Charging current not to exceed. 10 mA.

3. Pass the Post DBE Simulation Test (Bending Test). Charging current not to exceed 10 mA.

Based on the analysis to determine the proper sequential order for thermal aging and radiation aging (see Section 3), the specimens were first exposed to 50 Wads of gamma radiation. The specimens.

were then subjected to thermal aging. The thermal aging was selected to be three weeks at 150°C to simulate a 40 year design life and two weeks at 165OC to simulate a 60 year design life. Oven aging

Eng. Report 526 Section 7 was conducted 'at Oltonite in ASTM type I1 forced draft ovens and the radiation exposure was performed at Sterisfisomedix, in Whi pany, NJ. Radiation services for these specimens are 4'

documented in Section 7, Appendix 2, able 1, specimens 1 1, 12 & 13.

At NTS, the three specimens were installed in the test vessel and were subjected to the temperature/pressure/chemical spray profile shown in NTS Report TR.62871-06N. Olcoguard (G-63) specimens are identified as specimens 1 1, 12 & 13. Specimens 1 through 10 are low voltage insulations and are not a part of fhis qualification report.

The specimens were voltage and current loaded in'accordance with Table 1. Voltage, current and charging current were monitored throughout the profile.. Temperature, pressure, and chemical spray flow rate were also monitored throughout the duration of the test.

During the test program, four deviations occurred. ~ h e s e deviations are documented in Appendix I of NTS report TR62871-06N. Notice of Deviation NOD-001 identified incorrect wiring when the voltage load was applied to the three specimens. After the load wiring was corrected (and other modifications were made - see NOD-OOI), ail specimens were re-energized and the test profile resumed. Since the specimens were not energized throughout the double pealc to 455F (due.to the wiring error), it was decided to add a second double peak at the end of the 190F, 9 psig dwell peak.

This additional double peak made the test more severe than originally intended. A11 three specimens maintained electrical load throughout the remainder of the test including the second double pealc.

J The specimens were then subjected t,o the Post DBE Simulation Test @ending Test). The specimens were removed from the support!mandrel, straightened and recoiled around a 40 x O.D.

steel mandrel. Each specimen, while on the mandrel, was immersed in room temperature water for a minimum of one hour. While still immersed, each specimen was withstand tested at 80 v/mil.ac (conductor to shield tape and water bath) for five minutes. The test voltage and charging current values were recorded.

All samples passed the Post' DEE Simulation Test (Bending Test). All qualification testing is documented in NTS report TR62871-06N (see Appendix D).

Test Plan for DBE-KELB Oualification to IEEE 383 Eng. Report 527 Section 7, Appendix 1 1.0 SCOPE This document has been prepared to present the procedures for subjecting the cables described in Paragraph 1.1, hereinafter referred to as the specimens, to a Nuclear Environmental Qualification Test Program fn accordance with the standards, specifications, and other documents listed in Paragraph 1.2.

1.1 Specimen Description The specimens for the test program consist.of three constructions of single conductor Olconite insulated wire. Two low voltage constructi~ns will be represented by six specimens each. One medium voltage rated ~roduction run will'be represented by two specimens. Factory order numbers and specimen details are listed in Appendix,l.

1.2 Qualification Standards, Specifications and Documents D IEEE Standard 323-2003, "IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations".

IEEE Standard 383-2003, " ~ ~ ~ d ~ t a n d a r d for Type Test of Class 1E Electric Cables, Field Splices, and Connections for Nuclear Power Generating Stations".

o. U.S. Nuclear Regulatory Guide 1.13 1 "~ualification Tests of Electric Cables, Field Splices, and Connections for Ligfit-Water-cooled Nuclear Power Plants".

I B

I OCFR.21 I "Reporting of bifects and Non-compliance".

e IOCFRSO, Appendix B, "Quality ~ssurance Criteria for Nuclear Power Plants".

B The Okonite Company Quality Assurance Program Manual. (Okonite Only) 2.0 QUALITY ASSURANCE All work on this test program shall be performed in accordance with The Oltonite Company's Quality Assurance Program, which complies with the applicable requirements of 10 CFR 50 Appendix B, ANSI N45.2, and Regulatory Guides.

3.0 TEST EQUIPMENT AND INSTRUMENTATION

.i AII instrumentation, measuring and test eguipment used in the performance of this test program were calibrated in accordance with Olconite's Quality Assuiance Program which complies with the requirements of IS0 10012-1. Standards used in performing all calibrations are traceable to the National Institute of Standards and ~echno1,ogy (NIST) by report number and date. When no

THE QKOWBTE COMPANY Rsamsey, NJ Eng. Report 527 Section 7, Appendix 1 national standards exist, the standards are traceable to international standards or the basis for calibration is otherwise documented.

4.0 TEST REQUIREMENTS The test program shall be performed in the sequence shown below. The tests are described in Paragraphs 4.1 through 4.5.

I. Specimen Coiling (OKONITE)

2. Aging Radiation Exposure (OKONITE)

' 3. Thermal Aging Exposure (OKONITE)

4. DBE-HELB WTS)

5. Functional Test After DBE-TLB Conditions @ITS) 4.1 Specimen CoiIing (QKONI'I'E);

he non-shielded specimens shall be wound into approximately 12" coils. The shielded specimens shall be wound into approximately 24" coils.

Each specimen shall be identified with.the appropriate specimen number (as shown in Table I) by attaching a metal identification tag, The tag will be positioned so that it does.not contact the specimen cable.

4.2 Aging Radiation Exposure (OKQMT;E)

The specimens which are to be exposed to radiation aging will be shipped by a dedicated shipper or Oltonite personnel to and from the irradiation vendor for radiation aging.

The specimens detailed in able I shall be carefully paclcaged and delivered. The specimen's will be exposed to a Cobalt 60 radiation sourc: to obtain the does specified in Table I. The specified radiation dose shall be controlled to 'the specified value within +lo/-0%. The dose rate shall not exceed one megarad per hour. The irradiated specimens shall be returned to Okonite upon completion of radiation exposure.

4.3 Thermal Aging Exposu.re (OKONITE)

The specimens shall be placed,in blionite Thermal Aging Ovens and aged in. air at 150C or 165C for the duration specified'in Tsible 1. for each specimen. The specimens shall be installed such that a minimum of ten feet will be exposed to the aging conditions. The ends of the specimens shall exit the oven to prevent exposure. The specified thermal aging duration shall be kept within 4-2, -0% of the specified value. At the specified time, the specimens shall be removed from the thermal aging oven. During the Thermal Aging process, a chart recorder shall monitor chamber temperature. The chart shall be used to document the temperature consistency. Valid calibration certificates shall be available for the aging chamber instrumentation. The specimens shall not be energized for thermal aging.

The ends of the specimens identified in Table I may be placed through a penetration in the oven to prevent exposure of approximately 7 feet of each end to the elevated temperature inside the oven.

Eng. Report, 527 Section 7, Appendix 1 Special care will be used during hanallng'of the specimens (during installation or removal fiom chamber) to prevent any damage.

4.4 Design Basis Event - High Energy Line BreaIc (NTS)

Test Setup The specimens shall be placed on the mandi-els and installed inside the test chamber. The unaged ends of each specimen shall be.routed through a chamber penetration. Each specimen will have an effective minimum length of ten feet. Each penetration shall then be potted. The specimens shall be placed to prevent direct steam impingement. Following installation in the test chamber, a 500 volt dc Insulation Resistance Test shall be performed to. ensure no damage was caused during installation.

t.

Electrical power in^ and ~ o a d i n ~

The specimens shall be powered and loaded as indicated in Attachment I, Table 1.

Monitoring The specimens shall be monitored for applied voltage, circuit current, and leakage current throughout the duration of the High Energy Line Brealc Test.

At least three thermocouples shall be p\\ace&at points around and within two inches ofthe specimen fixture. The average of these thermocouples shall be used to control the test chamber temperature.

The test chamber temperature shall be recorded throughout the duration of the test.

The test chamber pressure shall be monitored and recorded throughout the duration of the test.

The chemical spray flow rate shall be monitored and recorded throughout the duration of the test.

Temperature versus time plots shall be provided for all thermocouples. Additionally, average chamber temperature versus time, chamber pressure versus time, and chemical spray flow ate versus time plots shall be providkd.

Accident Test The specimens shall be exposed to the temperature and pressure profile as indicated in Attachment I, able 2. The transient shall be on a best-effort basis holding as close to the required temperature as pussible to achieve the conditions specified. The transient shall be continued until the peak conditions are achieved. he temperature shall then envelop the Accident Test Profile.

4.5 Functional Test after DBE-IEIELB 'Conditions (NTS)

I The following steps shall be talcen (ii otder) 'following completion of the normal radiation and thermal aging:

THE OKONUTE @OMPAMY '

Ramsey, Ndl Eng. Report 527 Section 7, Appendix 1 o

~ & r the test chamber has been allowed to cool to room temperature, each specimen shall be removed from the chamber, straightened and recoiled on a mandrel approximately 40 times the diam'eter of the cable..

0

~ach'coil shall be submerged in foom.ternperature water for a period of at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

I Each specimen shall be ac high'potential tested by applying voltage between each.specimen and the tap water:The test voltage shall be 80 volts (ac) per mil of nominal insulation thickness. The voltage shall be increased to the full value rapidly, but not to exceed 500 volts per mil per second. Full voltage shall be maintained for 5 minutes and then reduced to zero in not more than I5 seconds. The circuit breaker of the dielectric tester shall interrupt the test if leakage current exceeds 10 milliamps. Charging current shall be recorded.

0 The specimens will then be removed from the water, carefully packed and held for disposition, 5.O TEST REPORT (NTS to provide a complete repoh on parts 4.4.& 4.5 of this test plan)

A test report describing the test requirements, procedures.and results shall be issued. The test report sliall contain any anomalies, if any anomalies occur during the test program, tables, data sheets, sketches, etc. to document test setups, tests performed and results.

J. R. Cancelosi

ENCLOSURE 3 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS I AND 2 LICENSE AMENDMENT REQUEST 261 EXTENDED POVVER UPRATE RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION OKONITE COMPANY CERTIFIED TEST REPORT #34549 13 pages follow

THE OKONITE COMPANY

. 1740 BEREA ROAD RICHMOND KY 40475 CERTIFIED TEST REPORT CERTIFICATE OF COMPLlkNCE Report No: 34549 DATE : 42/27/2007 Rea No : 34-6956 page I of, /L NUCLWR PLT Customer: NMC SITE INV Customer Order Number 00020066 Item No: NIA Code No: NIA Manufacturing Order No: 0 ct Code No: 114-23-2 Manufacturing Spec: Applicable IOEA andlor AElC andlor UL Specifics Cable

Description:

1IC 410 AWG 19X BC C-RD.I15 OKOGUARD -024 SC EPR.005 TC TAPE DW TAPE TAPE.080 OKOSHEATH CP-TS 5/8KV FOR CT USE CERTIFICATE OF COMPLIANCE:

Issued in conjunction with and subject to OKONITEJs standard Warranty and Limitation Liability.

THE OKONITE COMPANY hereby certifies to the customer named above that the above described materials were duly tested during manufacture and that fhe materials meet or exceed the applicable requirements.

Quantity Order Accepted Number Cable QC Quantity for Shipment of Reels Length No Footage 4050 41 24 3

CERTIFIED TEST REPORT 770812B1 J 1417 770812B2 $

1417 The insulated conductor(s) withstood the following tests:

770812~3 /

1290 23 kV AC for 5.00 Min The insulated cable conductor(s) has an INSULATION RESISTANCE of not less than that corresponding to a constant of 50000 at 15.6 C.

The DC RESISTANCE of fhe conductor(s) at 25 C does not exceed ICEA values of 0.05200 Ohms per 1,000 fL Conductor Continuity PASSED Shield Continuity PASSED Corona Level (cables over 3kV ONLY) PASSED lCEA S-93-639 This report covers material shipped from RICHMOND to POINT BEACH NUCLEAR PLANT 6610 NUCLEAR ROAD TWO RIVERS WI 54241 We hereby certify this to be a true and eccurate copy of results of tests conducted in accordance with orders and specifications listed.

Special Statements for this CTWCOC "Cables shipped are qualified by Okonite EQ Report 527" -

THE OKONITE COMPANY a%&

M. MARRiNER EngineerlManager of Test Q-123-Gel REV I 1.4 06/10102 Q

ELECTRICAL AND DIMENSIONAL RESULTS THE OKONITE COMPANY 1740 BEREA ROAD RICHMOND W 40475 Page 2 of DATE : 12/27/2007 Customer: NMC SITE INVOICINGIPB NUCLEAR PLT.

Customer Order Number, 00020066 item No: NIA Code No: NIA Manufacturing Order No: 07-3192-1 Cable

Description:

1/C 410 AWG 19X BC C-RD -1 15 OKOGUARD,024 SC EPR,005 TC TAPE DW TAPE TAPE.080 OKOSHEATH CP-TS 518KV FOR CT USE The following DATA SUPPORTS ACCEPTANCE OF CABLE SHIPPED on the above FACTORY ORDER ELECTRICAL REQUIREMENTS - FINAL DRY TEST 23 kV AC for 5-00 Min IR Constant (K value) 50000 CEV (min kV) PASSED ICEA 5-93-639 Jacket was continuously SPARK TESTED at 7.0 KV AC.

I R-MEG DC Cond QUALITY No OHMS1 Resistance.

CONTROL LENGTH of M f t COND OHMIMft PRINT NUMBER FEET Cond 15.6 C SIZE 25 C Sequential Numbers r

< r cMlN>c

<MAX>

c Top >

c Bottom>

REQUIREMENTS 8440 0.05200 770812Bl 1417 1

21750 4lOAVVG 0.05119 7001468 7000040 77081262 1417 I

18097 4lOAWG 0.05129 7002880 7001472 77081283 1290 1

16812 41OAWG 0.05151 7004172 7002886 WALL DIMENSIONS QUALITY STRAND SHIELD INSULATION INS SHIELD JACKET CONTROL MlN AVG MlN AVG MIN AVG MlN AVG NUMBER POINT WALL POINT'WALL POINT WALL POINT WALL r

e REQUIREMENTS 0.006 0.103 0.115.

0.024 0.000 0.079 0.080 770812B 0.013 0.014 0.120 0.122 0.029 0.030 0.070 0.083 Q-117E-el R N 1 I

.4 0611 0102 Q Prepared by:

TRACEABILITY SCHEMATIC THE OKONITE COMPANY Report No: 34549 1740 BEREA ROAD DATE : 12/27/2007 RICHMOND KY 40475 Reg No ' 34-6956 Page $

of

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Customer: NMC SITE INVOICINGIPB NUCLWR PLT.

Customer Order Number: 00020066 Item No: NIA Code No: NIA Manufacturing Order No: 07-31 924 Product Code No: 114-23-2631 Manufacturing Spec:

Cable

Description:

IIC 410 AWG 19X BC C-RD.I15 OKOGUARD.024 SC EPR -005 TC TAPE DM TAPE TAPE.080 OKOSHEATH CP-TS 5/8KV FOR CT USE Okonite Traceability consists of assigning a Quality Control Number as each reel of wire is insulated. When lengths are combined into cable or units, a new Quality Control Number is assigned. Whenever a length is cut, an Alpha-Numeric designation is added to the Quality Control Number.

Approved l/C (LotlBatch) Compound Identification 1 IC Quality Control Numbers Strand Shield Insulation Ins. JkVShield 770812B 71 8420242 722620282 72001 01 64 722620277 Cabled QC Length #

Single Conductors and / or Units dontained in each cabled length NIA NIA Shipping Shipping Customer QC Length #

Length Reel ID 77081281 1417 NIA 77081282 1417 NIA 77081283 1290 NIA Approved Jacket (LoffBatch) Compound Identification 7337161 04;733716106 Q130D REV 1 1.4 0611 0102 (3)

Prepared by: -

60 NMC SIT INVOICING SPECIFICATION 50 40 30 20 10 5

0 0 kV 4.6 kV 9 2 kV 13.9 kV 18.5 kv 24.0 kV S w MS 6 2 5 APPLIED VOLTAGE IN kV a-1~44 aim

F.O.NO.

3192-1 CABLE NO. 770812-82 CABLE RATING 5h kV LENGTH.

1417 ft PHASE CUSTOMER NMC SIT INVOICING SPECIFICATION DESCRIPTlON 1/C 410 AWG 19 X BC C-RD - 115 OKOGUARD

/EQUIP. ~0.1 PIF 1 I N S U ~ T I O N MATERIAL EPR.

n 40 30 20 l o 5

0 0 kV 4.6 kV 9.2 kV 13.9 kV 18.5 kV 24.0 kV See MS 6.25 APPLIED VOLTAGE IN kV Q-164-04 8/04 1 1 1

1 1

1 1

1 1

1 i

1 1

1 a

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@THE ~ K ~ N I T E E ~ N ~ A N Y PLANT 7

60 F.O.NO..

3192-4 CABLE NO. 770812-83 CABLERATING 5,h LENGTH

. 1393 ft PHASE

- CUSTOMER NMC SIT INVOICING SPECIFICATION 50 50 = DESCRIPTION l/C 410 AWG 19 X BC C-RD - 115 OKOGUARD VOLTAGE-AC 23 kV FOR 5 MIN.

REVIEWED BY 9

1 PASS /

DATE 12/2%007 1

SENTTO 6.1 HOLD I

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i 0 kV See M-S 6.25 9.2 kV 13.9 kV APPLIED VOLTAGE IN kV

THE OKONITE COMPANY PLANT NO 07 PHYSICAL TEST REPORT CUSTOMER: NMC SITE INVOICING FACTORY ORDER NO: 07-3192-1 (89223)

GABLE DESCRIPTION: 1IC 410 AWG 19X BC C-RD - 115 OKOGUARD 024 SC EPR -

005 TC TAPE DW TAPE TAPE - 080 OKOSHEATH CP-TS - 518KV SPECIFICATION:

PREPARED BY: K. CAMERON THE FOLLOWING PHYSICAL TEST DATA SUPPORTS ACCEPTANCE OF CABLE SHIPPED ON THE ABOVE FACTORY ORDER.

COMPOUNDS USED ON THIS ORDER ARE AS LISTED IN THE QUALlFlCATlOM REPORT.

PHYSICAL PROPERTIES REQMENTS OKON EP SEMI.COND OKON EP SEMI.COND STRAND SHIELD STRAND SHIELD SAMPLE IDENTIFICATION (QC LENGTH NO) 7709128 VOLUME RESISTIVITY (METERIOHMS)

MAXllVtUM 90 C I00 0.031 130 C 100 0.022 BRIITLENESS (NOT WARMER THAEI)

-4OC PASS WAFER BOIL MUST PASS PASS Q11BC Rev 2.991 91103103

THE OKONiTE COMPANY PHYSICAL TEST REPORT PLANT NO 07 P A G E ~ O F L ~

DATE: 12127/2007 CUSTOMER: NMC SITE INVOICING FACTORY ORDER NO: 07-3192-1 (89223)

CABLE DESCRIPTION: 1/C4/0 AWG 49X BC C-RD - 115 OKOGUARD 024 SC EPR -

005 TC TAPE DW TAPE TAPE - 080 OKOSHEATH CP-TS - 518KV SPECIFICATION:

PREPARED BY: K. CAMERON THE FOLLOWING PHYSICAL TEST DATA SUPPORTS ACCEPTANCE OF CABLE SHIPPED ON THE ABOVE FACTORY ORDER.

COMPOUNDS USED OM THIS ORDER ARE AS LISTED IN THE QUALIFICATION REPORT.

PHYSICAL PROPERTIES SAMPLE IDENTIFICATION (QC LENGTH NO)

VOLUME RESlSTlVlN (METEWOHMS) 90 C 110 C BRIITLENESS (NOT WARMERTHAN)

ADHESION (LBSI.5")

SCORE TEST WAFER BOIL REQMENTS OKON EP SEMIGOND OKON EP SEMI-COND INSULATION SCREEN INSULATlON SCREEN MAXIMUM 50 0.223 50 0,054

-4OC PASS NO TEARS PASS OR RESIDUE CONTINUOUS PASS COVERAGE Q118C Rev 2991 14103103

' THE OKONITE COMPANY PHYSICAL TEST REPORT PLANT NO 07 P A G E ~ O F DATE: I 2 1 2 7 1 2 F

- CUSTOMER: NMC SITE INVOICING FACTORY ORDER NO: 07-3192-t (89223)

CABLE DESCRIPTION: IIC 410 AWG 19X BC C-RD - 115 OKOGUARD 024 SC EPR -

OD5 TC TAPE DW TAPE TAPE - 080 OKOSHEATH CP-TS - 518KV SPECIFICATION:

PREPARED BY: K. CAMERON THE FOLLOWING PHYSICAL TEST DATA SUPPORTS ACCEPTANCE OF CABLE SHIPPED ON THE ABOVE FACTORY ORDER.

COMPOUNDS USED ON THIS ORDER ARE AS LISTED IN THE QUALIFICATION REPORT.

PHYSICAL PROPERTIES REQMENTS OKOGUARD EPR OKOGUARD EPR INSULATION INSULATlON SAMPLE IDENTIFICATION (QC LENGTH NO) 7708128 MODULUS - 100%

UNAGED TENSILE STRENGTH.

ELONGATION ARZR AIR OVEN AGING (168 HRS @ 136C)

TENS STRENGTH-% UNAGED AFTER AIR OVEN AGING (168 HRS @ 136C)

ELONGATION HOT CREEP (@I50 C)

ELONGATION %

SET %

MINIMUM 500 MINIMUM 1200 250 MINIMUM 90 MINIMUM 85 MAXIMUM 50.00 5.00 VOIDS, CONTAMINANTS, AND EXTRUDED SHIELD PROTRUSIONS MEET AElC SPECIFICATIONS WAFER BOIL MUST PASS PASS

CHE OKONITE COW~PAN'I PHYSICAL TEST REPORT PLANT NO OT P

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DATE: I212812007 CUSTOMER: NMC SITE INVOICING FACTORY ORDER NO: 07-31 92-1 GABLE DESCRIPTION: IlC 410 AWG 19X BC C-RD - 115 OKOGUARD 024 SC EPR -

006 TC TAPE DW TAPE - 080 OKOSHEATH CP-TSdl8KV SPECIFICATION:

PREPARED BY: TLA THE FOLLOWING PHYSICAL TEST DATA SUPPORTS ACCEPTANCE OF CABLE SHIPPED ON +E ABOVE FACTORY ORDER.

COMPOUNDS USED ON THIS ORDER ARE AS LISTED IN THE QUALIFICATION REPORT.

PHYSICAL PROPERTIES REQMENTS CHLORINATED PE CHLORINATED PE JACKET JACKET SAMPLE IDENTIFICATION (QC.LENGTH NO) 7708128 MODULUS - 200%

UNAGED TENSILE STRENGTH ELONGATION AF~ER AIR OVEN AGING (168,HRS @! 121~)

TENS STRENGTH-% UNAGED AFTER AIR OVEN AGING (168 HRS @ 121C)

ELONGATION SET TEST ('10) MAXIMUM OIL IMMERSION (18 HRS @ 121C)

TENS STRENGTH - % OF UNAGED ELONGATION MINIMUM 1400 MINIMUM 2000 300 MINIMUM 85 MINIMUM 70 Q118C Rev 2.991 11103103

Page /I of /z--

CERTIPTca'IIION for MEDIUM VOLTAGE OKOEWW SHIELDED POMER Ci?BLE Accelerated Water Absorption Fkoperties Okoguard insulation meets the requirements of 5-97-682, paragraph 4.3.2.2.4. Typical values are shown in the following table.

These values were obtained on samples measured in our electrical laboratoiy.

Accelerated Water Absorption Properties

{Electrical Method )

Water Immersion Tempemture Dielectric Constant after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, max.

increase in capacitance, rnax percent I to 14 days 7 to 14 days Stability Factor after 14 days, max Alternate to Stability Factor - Stability Factor

. Difference. 1 to 14 days, rnax Application Engineering Requirement 75Cor90C 4.0 Okoguard 75C 2.76 3.5 I.5 1.0 0.5 90C 2.84 0.4 0.2 0.01 0.00.

0.05 0.03 0.05 0.01

Post; Office Box 3.40 page /z of )z Ramsy, New Jersey 07446 0 OKOMNTE Telephone: [ ~ O I I 825-0300 COMPANY Telefax:

C20 1 3 825-9026

-Mail: okonitie@okonite.com FOR Medium voltage OSCOGUaP33 SHIELDED Power Cable Quality Plan Conduiotox & Insulation Shields Elongation:

.When tested i n accordance with 5-97-682, paragraph 9.4.14, the semiconducting EPR conductoz screen material meets the 100%

minimum elongation after 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> at 121'~.

Certification is based routine t e s t i n g i n the Okonite Materials ~&oxatoxy.

C&g*d&&

Carl Zuidema cz/ jv d

Ref: Certification fox Conductor & Insulation Shields

Okonite Olcoguard@-0lcosealGD Type MV-105 518kV Shielded Power Cable One Okopact... Page 1 of 3

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@ THE ~KaNBTE GaMPAWIY Product Data COMPACT STRAND CONSTRUCTION Section 2: Sheet 4

0.,

OkoguardB-~koseal Type ~ - i 6 ) 5 518kV Shielded Power Cable One Okopacta (Compact Stranded) Copper Conductor/l0S0C Rating 5kcV-133 % or 81cV-100% Insulation Level A Uncoated, Okopact (Compact Stranded) Copper Conductor B Strand Screen-Extruded Semiconducting EPR C Insulation-Olcoguard EPR D Insulation Screen-Extruded Semiconducting EPR E shielding-copper Tape.

Insulation Okoguard is Olco3lite's registered trade name for its exclusive etliylene-propylene rubber O R ) based, thermosetting compound, whose optimum balance of electrical and physical properties is unequalled in other solid dielectrics. Okoguard insulation, with the distinctive red color and a totally integrated EPR system, provides the optimum balance of electrical and physical properties for long, problem free service.

The triple tandem extrusion of the screeris with the insulation provides optimum electrical characteristics.

Jacket The Okoseal (PVC) jacket supplied with this cable is mechanically rugged and has excellent resistance to oil, acids and most chemicals.

Applications Olcoguard shielded Olcoseal Type MV-105 power cables are recommended for distribution circuits, and for feeders or branch circuits.

Type MV cables may be installed in wet or dry locations, indoors or outdoors (exposed to sunlight), in any raceway or underground duct, directly buried if installed in a system with a grounding conductor in close proximity that conforms with W C Section 3 10.7, or messenge~s~p~poxted inlndustriaI. establishments and. electric utilities.

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