ML20003C615
| ML20003C615 | |
| Person / Time | |
|---|---|
| Site: | Catawba |
| Issue date: | 01/30/1981 |
| From: | SANDIA NATIONAL LABORATORIES |
| To: | |
| Shared Package | |
| ML20003C611 | List: |
| References | |
| PROC-810130, NUDOCS 8103060589 | |
| Download: ML20003C615 (17) | |
Text
{{#Wiki_filter:-, ,t' 6 ( 4 'Y 5 Connector Assembly Test Plan { for Duke Power, Catawba 1 and 2, Connectors L__. to be coordinated for the U. S. Nuclear Regulatory Commission' Research Support Branch, RSR by Sandia Laboratories, Albuquerque a I f t 5 i l Submitted: 4/28/80 Second Draft: 11/1/80 f Third Draft: 12/22/80 Fourth Draft: 1/30/81 i l l 810soso E5i
O 4/38/80 11/1/80 12/22/80 1/30/81 ? Proposhd Verification Program for the Duke Power /D. G. O'Brien 1. Type K Penetration Connector Assembly Program Objective Following the Union of Concerned Scientist's petition of November 4, 1977, the NRC Commissioners directed the NRC staff to: " Arrange for a repeat of the tests to obtain data for the verification of current method-ology for environmental qualification of elec-trical components. These tests should be per-formed with a representative sample of commer-cially available electrical connectors quali-fled in accordance with IEEE-323 (1974) and in use in nuclear power reactor safety systems. When available, the test results are to be promptly provided to the Commission." The staff have interpreted this action to be aimed at pro-viding information on the methodology of qualification test-ing using electrical connectors which meet the provisions of IEEE-323. The staff responded by directing that electrical connectors previously qualified by licensees for use in operating plants be tested in accordance with the applicable version of IEEE-323. To the extent practicable, connector assemblies will be subjected to the actual aging, radiation, and LOCA-stimulation tests for which the connector assemblies have been qualified. Inspection and Enforcement (IE) staff have evaluated some of the various utilities' connector hardware and quali-fication documents. The first test in this series, selected by IE, used Bendix connector assemblies as installed in Browns Ferry Unit 3; that test was documented as SAMD 79-2311, NUREG/CR-1191, dated December 1979. The second in the series, as selected by IE staff and outlined in this test plan, will use D. G. O'Brien connector assemblies mated to an O'Brien instrumentation penetration. The connectors and penetration were among those acquired for installation in Catawba Units 1 and 2. During the development program of the Type K module-connector assembly, circumstances were such that only certain items of the assembly were subjected to the entire sequence of aging, radiation and LOCA/MSLB environments. Specifically the assembly connector component was only partially qualified by test.
M.7 o 4/28/80 11/1/80 12/22/80 1/30/81' It.is the objective of this program to subject a Type K pene-f c tration assembly to the entire environmental and accident 7 agindEprocesses. The complete assembly is to include mated 3L-cables and connectors and at least one junction box. Test Item Description The Type K penetrations and auxiliaries are manufac-tured by the D. G. O'Brien Co. in accordance with Duke Power specification CNS-1361.00-00-0003. Units of this type are used to penetrate the containment at Catawba Units 1 and 2. The unit to be used in this test is currently on hand at the Catawba Station. It was acquired, by Duke Power, at the time of acquisitiors of the instrumentation penetration units r -- presently being installed at the Catawba Station. In Figure 1, a drawing of the type K instrumentation penetration is presented. The penetration is shown complete with module, connectors (plugs), junction boxes, and flange pressure gauge. For ' purposes of clarity only one aodule appears in the drawing. However, the unit being acquired for this test has eight each of two module types for a total of 16 modules. Assembly,of Test Items Using mating connectors (plugs) and appropriate cabling, the penetration unit will be wired so that pairs of like modules will be interconnected. In Figure 2 a typical interconnection between like modules is shown. Note the straightforward approach, i.e. Pin A is connected to Pin A, etc. The wiring necessary to interconnect the paired modules will be the responsibility of Duke Power Company. The standard Duke procedures, CNM-1361.00-0011 and CNS-1390.01-0073, will be followed during connector (plug) wiring. Quality Control Inspection will be in effect to insure that the above procedures are followed. Assembly of the wired mating connectors to the appropriate modules will be by Duke Power personnel. Every effort will be made to assure a product typical of field-installed units. Since the assembly of connectors to modules requires a special torquing tool, a Duke Power representative will retorque all connectors on the penetration assembly after its receipt at Sandia and prior to any ttsts on the unit.
Background
The qualification history of the type K module /connec-tor was discussed in detail in the April 1980 draf t of this test plan.
4/28/80 11/11/80 12/22/80 1/30/81 Ih that draf t, the partially-qualified component of f the penetration assembly was identified as the connector unit.:- As a result it was proposed that the connector, along with sufficient mating assembly, be subjected to the aging l~~ and accident sequence. The purpose of the mating assembly was not for verification but to serve as an interface during functional tests. The concept of a partial assembly was re-jected on the basis the assembly would need to be manufactured and hence would not necessarily be representative of the pre-sently installed units. It was subsequently proposed that a Duke Power penetration unit available at the Catawba Station be used in the connector verification program. This penetration assembly, acquired with installed units, when assembied with mating connectors and interconnecting cabling would be quite representative of installed items; certainly more so than any after the fact fabricated item. Test Procedures General The penetration assembly will undergo the aging - accident sequence in the as-received condition i.e., with a junction box installed on the inboard side of the assembly. An example of the test configuration is shown in Figure 3. In Figure 3 the penetration assembly is shown positioned in the LOCA/MSLB test chamber. Note that the inboard portion of the penetration assembly is completely enclosed in the inboard junction box. Note also the instrumentation / test cabling extending from the outboard side. Becaure the penetration assembly.is mounted vertically, the pressure equalizing-condensation dryin vent shown in Figure 3 was repositioned from position V to position V. One exception to the above configuration will occur during the radiation aging cycle. Dimensions of the Cobalt-60 irradiation chamber are such that the inboard assembly complete with junction box cannot be acccmmodated. It will be necessary to irradiate the inboard penetration unit without the junction box. The junction box dose attenuation ef fect will be measured dnd appropriate adjustment made in the irradiation time. Environments to which the assembly will be subjected are: 1. Thermal aging 2. Radiation 3. LOCA-MSLB
r- = 4/28/80 11/11/80 12/22/80 1/30/81 The above tests will be, generally, in accordance with f those* described in the D. G. O'Brien reports ER-252 and con-forming to QA-TM-185/191 of that report. The test will be performed in the following sequence and will adhere to II~ the concepts contained in the Sandia Department 4440 Quality Assurance Program Plan. 1. Baseline - visual and functional 2. Thermal aging 3. Post aging functional - visual 4. Radiation i 5. Post radiation functional - visual 6. Accident 7. Post accident - functional - visual Acceptable performance of the assembly will be on the basis of accept-reject criteria listed in a succeeding acetion of this proposal. Specific I. Protest - Baseline A. Visual inspection 1. general appearance 2. radiographs if appearance warrants B. Functional 1. continuity-checkforcontinugtyandcorrectness 2. insulation resistance - 5 x 10 ohms @ 500 VDC between each conductor and all other conductors connected to ground (shell). 3. Penetration internal pressure - note and record II. Thermal Aging A. General Thermal aging shall be conducted in a forced cir-culating air furnace. There shall be no obstruction to flow across the test specimen. Equipment is to be isolated from furnace walls and from any primary radiant energy source. B. Test requirements 1. 150*C + 2*C 2. 168 hours duration 3. check continuity and insulation resistance once daily 4. internal pressure - note and record n
sw.., 4/28/80 11/11/80 -12/22/80 1/30/81 [ C. Post test. [ 1. insulation resistance =__ 2. continuity 3. visual 4 internal pressure - note and record III. Radiation Exposure A. General The penetration assembly will be subjected to the dose rate and integrated dose specified in the succeeding section on test requirements. Configuration of the Sandia irradiation source geometry is adjustable so that dose rate. e-- and/or radiation field dimensions may be tailored to specific needs. Considering the penetration dimensions-less junction box-and the requirement to maintain the radiation dose rate below 1 megarad/hr a source configuration, considered compatible with the requirements, was assembled and mapped. In Figure 4 the results of that mapping are presented. As may be observed, extent of uniformity of the radiation field exceeds the penetration dimensions. Additionally radial placement of source pencils assures dose uniformity in the radial direction. Concerning removal of the inboard junction box, the following steps will be taken. With the desired source con-figuration, Figure 4, dose rate will be determined with a calibrated air ionization chamber both with and without the junction box. Very simply these differences in observed dose rates can be attributed te junction box perturbations. Then the penetration aging time will be adjusted to reflect the dose rate observed with the junction box in place. Temper-ature of the environment is to be monitored and maintained at or below the norm 51 110?P operating temperature. Dose measurement techniques and detector calibration will be traceable to the NBS. r Test requirgments B. 1. 2 x 10 rads (AIR) +10% 6 2. dose rate not to exceed 10 rad /hr 3. interr.1 pressure -- note and record C. Post test requirements 1. continuity I 2. insulation resistance 3. internal pressure - note and record ~
4/28/80 11/11/80 12/22/80 1/30/81 IV. Adhident Test ? Aj{ General [s. This test is to be a combination of LOCA, MSLB, and thermal shock environments. The LOCA and thermal shock environments are straight forward although the duration of the thermal shock has not been specified. The steam line break phase of this environment, as outlined in the Duke Power Specification CNS-1361.00 ! 0003, calls for an initial rise in temperature and pres-sure from ambient to 340*F and 15 psig, respectively, in 10 seconds. The Sandia facility, at this time, cannot r~ duplicate the specified transient rather, the temperature-time profile appearing in the Figure 5 is more typical of the Sandia facility capability. For improved perspective, Figure 6 has been included. In this figure are plotted the Duke-Power specified transient, an actual D. G. O'Brien qualification profile, and the estimated Sandia capability. Consideration of the specified thermal transient and the Sandia capability prompted an inquiry of several commercial laboratories as to their transient temperature capabilities. At the present time, none of those laboratories polled could duplicate the specified temperature-time profile. The rise time of the Sandia facility could probably be " sharpened" some with the variation of available parameters but it would in no way approach the specified 10 second value.
- However, when the thermal lag introduced by the junction box presence is considered, the actual connector environment probably rises much more slowly than the specified environment rise time.
Actual positioning of temperature sensors its the test chamber and about the penetration will depend upon the temperature distribution within the test chamber. This distribution will be determined during pretest steam per-formance evaluation of the chamber. A tentative temperature and pressure diagnostic scheme is shown in Figure 7. Temper-ature sensors will be placed so that spatial temperature distributions near the junction box surface may be monitored. At least one temperature sensor will be positioned in box interior so that some knowledge of module temperature history may be obtained. Access to the junction box interior will be i through vent "V"--a pressure equalizing and condensate drain vent. B. Test Requirements (see also Figure 8) 1. 340*F + 10*F @ 15 psig + 5 psig for 10 minutes -- rise tTme 10 seconds, but see also above and en-l closed temperature profile l 2. drop to 300*F in 10 to 30 minutes ~ o
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.-.-.- -. _.- ~... 4/28/80 11/11/80 12/22/80 1/30/81 = 3 J:.. 30 0
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- F @ 15 psig 1 5.psig for 80 minutes 4 e-drop to 250'F + 5'F @ 15 psig ~+ 5 psig hold for
? 18 hours P a. when temperature stabilizes @ 250*F a thermal shock to consist of either water spray at 40*F directly onto junction box - time duration to be not less than one minute. b. following thermal shock . chemical spray to be used for duration of test. Composition of the spray (IEEE-323(1974)) is as follows: .028 molar H B .004 molar N O NaOH to make a pH b lb.5 @ 77 F 5. drop to 228'F i 5'F @ 5 psig i 5 psig hold for 12v hours a. spray continues 6. 600 VAC to be applied between all conductors and the connector shell during entire test--see Figure 9. 7. contincity and ineulation resistance to be checked daily 8. penetration internal pressure - note and record daily C. Post test 1. insulation and continuity tests 2. internal pressure - note and record Acceptance-Rejection Criteria General Acceptable electrical performance of the penetration assembly is based on the Duke Power Company specification CNS-1361.00-00-0003. This specification requires that " Type K penetration assemblies shall be designed to maintain a minimum 7 insulation resistance of 1 x 10 ohms when tested at a potential of 500 volts DC.... All resistance measurements are to be made between each conductor and all other conductors connected to ground." So that functional tests may be performed, the penetration unit to be supplied to Sandia will have like pairs of modules l connected, electrically, in series. Although Duke Power selected this wiring configuration, they questioned the applicability of the CNS-1361.00-00-0003 insulation resistance requirement for
4/28/80 11/11/80 12/22/80 1/30/81 this wiring. configuration and agreed to determine what effect, if iny, .intercondecting modules should have on the minimum acceptable T insulatigD resistance requirements. gr. The Duke. position, regarding series connected modules was tran-r .mitted to Sandia in a letteg dated January 23, 1981, Dover (Duke Power) to Buckalew (Sandia) The Duke position is as follows. Since the series arrangement of modules will provide parallel resistance paths to ground for the interconnected modules, the minimum insulation resistance should be lowered to reflect this condition. This position is interpreted, by Sandia, to mean that theminimumacceptayleinsulationrgsistancerequirementshouldbe lowered from 1 x 10 ohms to 5 x 10 ohms.
Response
It is not anticipated that performance criteria will influence the mechanics of this test, i.e. the test will proceed to completion regardless of measured insulation resistance values. During the performance of this test the following actions will apply. A. Aging Sequences -- nonpowered phases 6 should insulation resistance le than 5 x 10 ohms be observed at the specified measurement intervals, appropriate NRC and Duke Power persons will be promptly advised. Suspect circuits will continue to be tested throughout the aging sequences. B. Accident Sequence -- 600 VAC power phase. The actions of A (above) will be appropriate except in the case that the insulation resistances fall to a level that leakage currents become excessive. In the case of excessive leakage current, the circuits responsible for the excessive current will be removed from the power buss. Again this condition will be promptly reported. Final Report A final report will be issued on this test. It will in-clude all data sheets and other pertinent details.
- See also the addendum to this test plan.
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