Safety Evaluation Re Silicone Rubber Insulated Cables. Anaconda & Rockbestos Cables at Plant Environmentally Qualified for Intended Function at Plant & Use Acceptable for 40 YrsML20247G866 |
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Sequoyah ![Tennessee Valley Authority icon.png](/w/images/c/ce/Tennessee_Valley_Authority_icon.png) |
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Issue date: |
07/21/1989 |
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From: |
Office of Nuclear Reactor Regulation |
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To: |
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Shared Package |
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ML20247G855 |
List: |
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References |
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NUDOCS 8907280199 |
Download: ML20247G866 (4) |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively ML20212F0831999-09-23023 September 1999 Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval ML20196J8521999-06-28028 June 1999 Safety Evaluation Authorizing Proposed Alternative to Use Iqis for Radiography Examinations as Provided for in ASME Section III,1992 Edition with 1993 Addenda,Pursuant to 10CFR50.55a(a)(3)(i) ML20239A0631998-08-27027 August 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Sequoyah Nuclear Plant,Units 1 & 2 ML20236Y2091998-08-0707 August 1998 Safety Evaluation Accepting Relief Requests RP-03,RP-05, RP-07,RV-05 & RV-06 & Denying RV-07 & RV-08 ML20217K4471998-04-27027 April 1998 Safety Evaluation Supporting Requests for Relief 1-ISI-2 (Part 1),2-ISI-2 (Part 2),1-ISI-5,2-ISI-5,1-ISI-6,1-ISI-7, 2-ISI-7,ISPT-02,ISPT-04,ISPT-06,ISPT-07,ISPT-8,ISPT-01 & ISPT-05 ML20138D2581997-04-28028 April 1997 Safety Evaluation Authorizing Licensee Proposed Alternative to Use 1989 Edition of ASME Boiler & Pressure Vessel Code, Section XI for Performance of Containment Repair & Replacement Activities Until 970909 ML20057F8441993-10-14014 October 1993 SER Granting Relief Giving Due Consideration to Burden Upon Licensee That Could Result If Requirements Imposed on Facility ML20057D5321993-09-28028 September 1993 SER Granting Licensee 921117 Relief Requests ISPT-2 & ISPT-3 Re Inservice Pressure Test Program ML20057D6351993-09-28028 September 1993 SER Granting Relief as Requested for Both ISPT-2 & ISPT-3 Per 10CFR50.55a(a)(3)(i) & 10CFR50.55a(g)(6)(i) ML20128K0221993-02-11011 February 1993 SE Accepting Util Justification for Break Exclusion of Main Steam Lines in Valve Vaults Provisionally Until End of Refueling Outages ML20128E9161993-01-0606 January 1993 SE Approving Request for Relief from ASME Requirements Re First 10-yr Interval ISI Plan ML20247K3321989-09-14014 September 1989 Safety Evaluation Accepting ATWS Mitigation Sys,Pending Tech Spec Issue Resolution ML20245E6951989-08-0303 August 1989 Safety Evaluation Supporting Inclusion of Alternate Repair Method to Detect microbiologically-induced Corrosion in Previously Granted Request for Relief from ASME Section XI Code Repair Requirements ML20247G8661989-07-21021 July 1989 Safety Evaluation Re Silicone Rubber Insulated Cables. Anaconda & Rockbestos Cables at Plant Environmentally Qualified for Intended Function at Plant & Use Acceptable for 40 Yrs ML20247B4891989-07-19019 July 1989 Safety Evaluation Supporting Util 890330 Request to Eliminate Dynamic Effects of Postulated Primary Loop Pipe Ruptures from Design Basis of Plant,Using leak-before- Break Technology as Permitted by Revised GDC 4 ML20246N0321989-07-11011 July 1989 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Item 1.2, Post-Trip Review,Data & Info Capability ML20244D1771989-06-0909 June 1989 Safety Evaluation Re Generic Ltr 83-28,Items 2.1.1 & 2.1.2 NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley1989-05-26026 May 1989 Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley ML20245A1301989-04-14014 April 1989 Safety Evaluation Re Shutdown Margin.Procedural,Hardware & Training Enhancements Implemented & Committed to by Util Will Provide Reasonable Assurance That Adequate Shutdown Margin Will Be Maintained at Plant ML20244D8821989-03-14014 March 1989 Safety Evaluation Supporting Procedural,Hardware & Training Enhancements Implemented & Committed to by Util to Provide Reasonable Assurance That Adequate Shutdown Margin Will Be Maintained at Plants ML20195J0891988-11-28028 November 1988 Safety Evaluation Accepting Program for Plant in Response to Items 4.2.1 & 4.2.2 of Generic Ltr 83-28 Re Reactor Trip Sys Reliability ML20205T1621988-11-0707 November 1988 Safety Evaluation Supporting Improvement Plan for Emergency Diesel Generators Transient Voltage Response ML20206G4531988-11-0404 November 1988 SER Supporting Employee Concern Element Rept Co 15101, Floor Drains ML20206G3961988-11-0404 November 1988 SER Supporting Util Investigation of Employee Concerns as Described in Element Rept 308.03 ML20206G5341988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 30114, Malfunction of Doors ML20206G4621988-11-0404 November 1988 SER Supporting Employee Concern Element Rept 204.8(B), Communication & Interface Control ML20206G5291988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 301112, Sys 31 Not Operated Properly ML20206G5241988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 30111, Valve Closure ML20206G5191988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 30105, Questionable Design & Const Practices ML20206G5091988-11-0404 November 1988 SER Supporting Employee Concern Element Rept 23706, Gassing of Current Transformers ML20206G5021988-11-0404 November 1988 SER Supporting Employee Concern Element Rept 23504, Exposed HV Cable Routed W/O Raceway - Personnel Hazard ML20206G4571988-11-0404 November 1988 SER Supporting Employee Concern Element Rept Co 15105-SQN, Flex Hose Connections ML20206G4971988-11-0404 November 1988 SER Supporting Employee Concern Element Rept 23501, 480 Volt Power Receptacles Unsafe ML20206G4861988-11-0404 November 1988 SER Supporting Employee Concern Element Rept EN 232.9(B), Freezing of Condensate Lines ML20206G4591988-11-0404 November 1988 SER Supporting Employee Concern Element Rept 204.7(B), Vendor Documents Legibility & Dissemination Sys ML20206G4801988-11-0404 November 1988 SER Supporting Element Rept EN 232.2, Carbon Steel Vs Stainless Steel Drain Pipes ML20206G4721988-11-0404 November 1988 SER Supporting Employee Concern Element Rept 22912, Panel- to-Equipment Distances ML20206G4661988-11-0404 November 1988 SER Supporting Employee Concern Element Rept EN 229.6(B), Lack of Valves in Sampling & Water Quality Sys ML20206G5431988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 30301, Difficulty in Obtaining Obsolete Equipment ML20206G6111988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 31105, Alara ML20206G6161988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 31106, Health Physics Facilities,Clothing & Protective Equipment ML20206G6211988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 31204-SQN, Mgt & Personnel Issues ML20206G6321988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 31208-SQN, Security at Plant Entrances ML20206G6371988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 31201-SQN, Adequacy of Public Safety Svc (Pss) Officer Uniforms in Nuclear Plant Environ ML20206G4351988-11-0404 November 1988 SER Supporting Employee Concern Element Rept Co 11101-SQN, Contact Between Dissimilar Metals ML20206G4381988-11-0404 November 1988 SER Supporting Employee Concern Element Rept Co 11202-SQN, Craft-Designed Hangers as Related to Const ML20206G4081988-11-0404 November 1988 SER Supporting Employee Concern Element Rept Co 10307-SQN, Uncoated Welds as Related to Const ML20206G3661988-11-0404 November 1988 SER Supporting Employee Concern Element Rept EN 21002, Inadequate Environ Qualification of Electrical & Instrumentation Control 1999-09-23
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 ML20217G3721999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Sequoyah Nuclear Plant.With ML20212F0831999-09-23023 September 1999 Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively ML20212C4761999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Sequoyah Nuclear Plant.With ML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20216E3781999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20210L4451999-07-31031 July 1999 Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20210G6631999-07-28028 July 1999 Cycle 9 90-Day ISI Summary Rept ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209H3831999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Sequoyah Nuclear Plant.With ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage ML20196J8521999-06-28028 June 1999 Safety Evaluation Authorizing Proposed Alternative to Use Iqis for Radiography Examinations as Provided for in ASME Section III,1992 Edition with 1993 Addenda,Pursuant to 10CFR50.55a(a)(3)(i) ML20195K2951999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20206Q8951999-05-0505 May 1999 Rev 0 to L36 990415 802, COLR for Sequoyah Unit 2 Cycle 10 ML20206R5031999-04-30030 April 1999 Monthly Operating Repts for April 1999 for Sequoyah Units 1 & 2.With ML20205P9811999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20204C3111999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20205B6631999-02-28028 February 1999 Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys ML20203H7381999-02-18018 February 1999 Safety Evaluation of Topical Rept BAW-2328, Blended U Lead Test Assembly Design Rept. Rept Acceptable Subj to Listed Conditions ML20211A2021999-01-31031 January 1999 Non-proprietary TR WCAP-15129, Depth-Based SG Tube Repair Criteria for Axial PWSCC Dented TSP Intersections ML20198S7301998-12-31031 December 1998 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20199G3641998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20197J5621998-12-0303 December 1998 Unit 1 Cycle 9 90-Day ISI Summary Rept ML20197K1161998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20195F8061998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Sequoyah Nuclear Plant.With ML20154H6091998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20154H6251998-09-17017 September 1998 Rev 0 to Sequoyah Nuclear Plant Unit 1 Cycle 10 Colr ML20153B0881998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Sequoyah Nuclear Plant.With ML20239A0631998-08-27027 August 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Sequoyah Nuclear Plant,Units 1 & 2 ML20236Y2091998-08-0707 August 1998 Safety Evaluation Accepting Relief Requests RP-03,RP-05, RP-07,RV-05 & RV-06 & Denying RV-07 & RV-08 ML20237B5221998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Snp ML20237A4411998-07-31031 July 1998 Blended Uranium Lead Test Assembly Design Rept ML20236P6441998-07-10010 July 1998 LER 98-S01-00:on 980610,failure of Safeguard Sys Occurred for Which Compensatory Measures Were Not Satisfied within Required Time Period.Caused by Inadequate Security Procedure.Licensee Revised Procedure MI-134 ML20236R0051998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Sequoyah Nuclear Plant ML20249A8981998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Sequoyah Nuclear Plant,Units 1 & 2 ML20247L5141998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Sequoyah Nuclear Plant ML20217K4471998-04-27027 April 1998 Safety Evaluation Supporting Requests for Relief 1-ISI-2 (Part 1),2-ISI-2 (Part 2),1-ISI-5,2-ISI-5,1-ISI-6,1-ISI-7, 2-ISI-7,ISPT-02,ISPT-04,ISPT-06,ISPT-07,ISPT-8,ISPT-01 & ISPT-05 ML20217E2221998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Sequoyah Nuclear Plant ML20248L2611998-02-28028 February 1998 Monthly Operating Repts for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2571998-01-31031 January 1998 Cycle 9 Voltage-Based Repair Criteria 90-Day Rept ML20202J7911998-01-31031 January 1998 Monthly Operating Repts for Jan 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2441998-01-29029 January 1998 Snp Unit 2 Cycle Refueling Outage Oct 1997 ML20199F8531998-01-13013 January 1998 ASME Section XI Inservice Insp Summary Rept for Snp Unit 2 Refueling Outage Cycle 8 ML20199A2931997-12-31031 December 1997 Revised Monthly Operating Rept for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20198M1481997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20197J1011997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199C2951997-11-13013 November 1997 LER 97-S01-00:on 971017,vandalism of Electrical Cables Was Observed.Caused by Vandalism.Repaired Damaged Cables, Interviewed Personnel Having Potential for Being in Area at Time Damage Occurred & Walkdowns ML20199C7201997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Sequoyah Nuclear Plant L-97-215, SG Secondary Side Loose Object Safety Evaluation1997-10-23023 October 1997 SG Secondary Side Loose Object Safety Evaluation 1999-09-30
[Table view] |
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
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ENCLOSURE l
1 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SILICONE RUBBER INSULATED CABLES SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 i TENNESSEE VALLEY AUTHORITY
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DOCKET NOS. 50-327 AND 50-328
1.0 INTRODUCTION
1 The NRC has received a number of employee concerns reldted to inadequate cable ;
installation practices at the Watts Bar plant. These concerns were extended to I the Sequoyah plant because of the similar design and installation practices at ,
both plants. The staff and its consultant, Franklin Research Center (FRC),
evaluated these concerns by plant walkdowns, review of the installation pro-cedures at Sequoyah, and interviews with the craft personnel. A staff Safety Evaluation Report (SER) including the Technical Evaludtion Report prepared by FRC was transmitted to TVA by letter dated on March 9,1987. The SER identi-fied concerns related to cable damage caused by pullbys, jamming, and verti-cally run cable.s supported by 90 condulets. These concerns required resolu-tion prior to plant restart. Other concerns related to cabic bend radii, revision of genera'i construction specifications and cable installation proce-dures, support of long vertical runs of cable, and the cable monitoring program were scheduled for resolution post restart. By letter dated July 31, 1987, TVA submitted a cable test program to address the concerns stated above. The program called for testing of 15 worst-case conduits to determine cable damage 4 from pull.bys, jamming, and vertically run cables supported by 90 condulets.
This test program consisted of in-situ Hi-Pot testing of these cables (925 cables for pullby and jamming) in dry / wet conditions by subjecting them to a voltage level equivalent to 240 Vdc/ mil of insulation based on the minimum qualified insulation thickness of the cable. TVA completed testing for pullbys and jamming, and the results were submitted to NRC by letter dated November 20, !
1987.
The staff and its consultant witnessed part of the testing performed at the Sequoyah site. The test results demonstrated that no gross cable damage had resulted from pullby or jamming during installation. The majority of cables tested for pullby or jamming damage were not insulated with silicone rubber.
The few silicone rubber insulated cables included in this test met the dCCeptance criteria for this test.
A high rate of test failures resulted during Hi-Pot testing conducted to demonstrate the adequacy of cable installation for cables which are vertically supported by 90 condulets. All of these cables were silicone rubber insulated cables. The majority of these failures were attributed to cables manufactured 8907280199 890721 PDR P ADOCK 05000327 PDC
. i 4
j by the American Insulating Wire (AIW) Company ar.d to a lesser extent to cables j manufactured by the Rockbestos company. TVA informed the staff about these j failures in a meeting held on September 10, 1987. The staff's concern regarding l l the integrity of these cables is documented in the NRC letter to TVA dated j November 13, 1987. As a result of the staff's concerns, TVA conducted environ- "
mental qualification (EQ) testing of the silicone rubber insulated cables at Wyle Laboratory to demonstrate adequacy of the cables for a ten year life. . TVA submitted the test results to NRC by letter dated November 24, 1987. TVA also elected to remove all AIW cables from its Sequoyah plant as a result of the previous high rate of failures of these cables during tests.
By letter dated December 28, 1987, TVA documented their basis for concluding that the remaining silicone rubber insulated cables (Rockbestos and Anaconda) are adequate to perform their intended function. The staff reviewed the test results and concluded (1) that these cables were acceptable for interim use and (2) that TVA should qualify these c3 h les for the expected life of the plant at Sequoyah.
The NRC staff in a letter to TVA, dated May 25, 1988, provided the guidelines for a complete environmental qualification test program required to be con-ducted by TVA to ascertain the integrity of the remaining silicone rubber insulated cables instelled at Sequoyah and Watts Bar for the life of the plants. In this letter, the staff requested that TVA remove installed cable from Sequoyah or Watts Bar for testing. TVA, in letters dated July 6, 1988 and October 31, 1988, provided the details of their cable test program, the sample selection, sample size, cable removal from Watts Bar, and resolution of test anomalies and test failures. The staff's evaluation of the TVA program is documented in Section 3.12 of NURG-1232, Vol. 2, Supplement 1, which was issued in the staff's letter dated February 3,1989.
The staff also witnessed the cable removal at the Watts Bar plant on September 12-13, 1988, to ensure that the cable removal would not result in any damage to the cables.
2.0 EVALUATION In a letter dated March 13, 1989, TVA submitted for staff review the EQ test report No. 18056-1, " Qualification Test Program for Silicone Rubber Insulated Cables For Use In Tennessee Valley Authority's Sequoyah and Watts Bar Nuclear Plants," prepared by Wyle Laboratory. Cables tested at Wyle were placed in six different trays, each tray containing five cables from one manufacturer.
Four of the trays were designated for Sequoyah, two to hold Anaconda cables and two to the hold Rockbestos cables. The other two trays were designated for Watts Bar Rockbestos cables. There are no Aneconda cables installed at Watts Bar. One tray was aged for 15 years of life and another tray was aged for 40 years of life. Insulation resistance (IR) measurements were taken of each cable specimen and each cable was immersed in water and had 500 Vdc applied to it for one minute. Subsequently, the cables were subjected sequen-tially to the normal radiation dose, thermal aging, and accident radiation dose, i
1 wm._-._._.. _ . _ . _ . _ . .
Measurements of IR were taken after each step. At the end of the accident radiation dose, two of the five cable specimens tested for Watts Bar, for. ,
a 40-year life, recorded very low IR readings. The IR readings for the two cables recorded values in the order of 1 mega ohm, compared to other test specimens which measured four or five decades higher. IR readings of all cables tested for Sequoyah recorded acceptable values. It should be noted, however, thag the integrated radiation dose (normal + accident) for Wagts Bar was 2.585x10 rads while, for Sequoyah, the dose was lower at 1.527x10 rads. l Because of the low IR readings, TVA decided to discontinue the qualification testing for Watts Bar but continued testing the cables aged for Sequoyah. The staff inspected the cables at the Wyle Laboratory before the loss-of-coolant accident (LOCA) test chamber was sealed.
The test specimens were subjected to the LOCA environment and were energized continuously with the expected service voltage and current. Leakage current was measured throughout the test. All cables performed according to their functional requirement, 1.e., the cables carried the required current at the ;
service voltages. ;
After the LOCA test, IR measurements were taken for all test samples with the LOCAchambergryandflooded.STwo of the Rockbestos cables recorded an IR value of 5x10 ohms and 1.0x10 ohms at 109 Vdc with the LOCA chamber dry.
The remaining Rockbestos and Anaconda cables recorded an IR reading above 1 mega ohm. One of the Rockbestos cables shorted at 10 Vdc when the IR measurements were taken with the LOCA chamber flooded, which demonstrated that no margin is available for uncertainty in these cables. The acceptance criteria generally require a minimum IR value of 1 mega ohm. However, these smaller IR values.are acceptable because silicone rubber insulated cables are not used for the instrumentation circuits where high leakage currents due to low insulation resistance could cause instrument inaccuracies.
After the LOCA test, the test samples were taken out of the LOCA chamber, wrapped around metal mandrels, submerged in water, and subjected to DC Hi-Pot testing while the test voltage was increased at a constant rate to 6600 Vdc.
This post-LOCA Hi-Pot test was conducted to determine whether there is additional margin on these cables to resolve any uncertainties associated with the EQ test.
The staff witnessed this test and noted that all Rockbestos cables exhibited abnormal conditions, i.e., insulation breakdown, severe voltage fluctuation, arcing and smoking during this test whereas all Anaconda cables successfully passed this test.
i Based on the overall tests results, it is eviGent that although both Anaconda-and Rockbestos cables passed the required LOCA test, the Anaconda .
- . cables appear to have additional margin, which is consistent with the Hi-Pot l testing conducted in prior test programs on these cables.
l
3.0 CONCLUSION
l Based on the staff's review of the Wyle Laboratory test report, the staff i concludes it is evident that both the Anaconda and Rockbestos cables at j L- _ - ___ - _ -
.l 1
- > ..~ j
' 4-Sequoyah are environmentally qualified for their intended function at Sequoyah - 3 and their use at Sequoyah is acceptable for 40 years. ' The staff's conclusion .)
is based on the following:
'1. The test environment envelops the Sequoyah environmental conditions that would be present during a design basis accident, The test samples were selected from the worst case conduit installation, 2.
at Watts Bar, with the highest potential for installation damage, and
- 3. These cables are only used for low voltage power and ' control; therefore, the reduced insulation resistance during a LOCA would not affect the performance of these cables.
Principal Contributor: H. Garg Dated : July 21, 1989
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