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.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- | .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. | ||
radiant energy source. | |||
B. Test' requirements | B. Test' requirements | ||
: 1. 150*C + 2*C | : 1. 150*C + 2*C | ||
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Latest revision as of 08:47, 18 February 2020
| ML19341B380 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 12/22/1980 |
| From: | Buckalew W SANDIA NATIONAL LABORATORIES |
| To: | Feit R NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| Shared Package | |
| ML19341B377 | List: |
| References | |
| 005340, 5340, NUDOCS 8101300841 | |
| Download: ML19341B380 (16) | |
Text
{{#Wiki_filter:. b Sandia Laboratories aw-a. v w. December 22, 1980 Mr. Ronald Feit Division of Reactor Safety Research Office of Nuclear Regulatory Research Mail Stop ll30SS U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Ron:
Enclosed is a revision of the most recent connector test pro-posal sent to you'. This revision primarily corrects the identifi-ication of the connectors as being from the Catawba Station. As we understand it the Catawba and McGuire connectors are practically identical. In any event the environmental soecifications and test requirements for the configurations are identical. Thus enclosed is a draft of the " Connector Assembly Test Plan for the Duke Power, Catawba Units 1 and 2 Connectors". This test plan follows closely that plan transmitted in April 1980 for the McGuire Connectors. As indicated in the November 1980 enclosure, the test item has been drastically redefined from that of the April tert proposal. As you are aware, the or Jinal proposal called for a test con-figuration consisting of conneetors (with cabling) and the minimum mating assembly consistant with the ability to perform the various required functional tests. Subsequently, the concept of connector / partial mating configuration was rejected on the basis that such a config ur ation , fabricated after the fact, would not be representa-tive of presently installed units. Alternate to the original test configuration, it has been pro-posed that a Duke Power spare Catawba penetration assembly complete with cables, connectors, and an inboard junction box be tested. Ac-cordingly we have proceeded with the design of a test chamber and auxilliary equipment necessary to subject such an assembly to the aging and accident sequence. Although a complete assembly is to be tested, the main intent,- as I understand it, is still that of verifying the assembly connec-tors. Should you have any questions or require additional information please call me. Yot 3 truly, W. H. Buckalew System Safety Information Division 4445 cc. W. Rutherford, USNRC 0053;+0, P. M. McBride, Duke Power Co. 4440 G.R. Otey 4445 L.O. Cropp, File 5.3 4445 L.L. Bonzon 4445 F.V. Thome 4445 W.H. Buckalew 8101300*3(\\ - JP
Connector Assembly Test Plan for Duke Power , Catawba 1 and 2, Connector s to be coordinated for the U. S. Nuclear Regulatory Commission Research Suoport Branch, RSR by Sandia Laboratories, Albuquerque Submitted: 4/28/80 Second Draft: 11/1/80 Third Draft: 12/22/80
-~
4/28/80 11/1/80 12/24/80 Pr oposed Vet ification Pr ogr am for the Duke Power /D. G. O'Br ien Type K Penetration Connector Assembly Program Objective Following the Union of Concer ned Scientist's petition of November 4, 1977, the NRC Commissioners ditected 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-tr ical components. These tests should be per-formed with a representative sample of commer-cially a/ailable electrical conncetors quali-fied 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 staf f have inter pr eted this action to be aimed at pro-viding information on the methodology of qualification test-ing using electr ical connector s which meet the provisions of IEEE-323. The staff responded by directing that electrical connector s 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. I l 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 l by IE, used Bendix connector assemblies as installed in Browns Ferry Unit 3; that test was documented as SAND 79-l 2311, NUREG/CR-1191, dated-December 1979. The second in l 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 and installed 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 wer e subjected to ~ the entire sequence 1 of aging, radiation and LOCA/MSLB environments. Specifically l the assembly connector component was only_ partially qualified. by test. L
4/28/80 11/1/80 12/22/80 It is the objective of this pr ogt am to subject a Type K pene-tr ation assembly to the entir e environmental and accident aging processes. The complete assembly is to include mated cables and connector s and at least one j unction box. Test item Descriotion The Type K penetr ations and auxiliar ies ar e manuf ac-tured by the D. G. O'Br ien Co. in accordance with Duke Power specification CNS-1361.00-00-0003. Units of this type ar e 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 acquir ed, by Duke Power , at the time of acquisition of the instrumentation penetr ation units pr esently being installed at the Catawba Station. In Figure 1, a drawing of the type K instr umenttion penetr ation is pr esented. The penetration is shown complete with module, connectors (plugs), junction boxes, and flange pressur e gauge. For put poses of clar ity only one module appear s 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 connector s (plugs) and appropriate cabling, he penetr ation unit will be wir ed so that pairs of like modules will be interconnected. In Figur e 2 a typical inter connection between like modules is shown. Note the straightforward approach, i.e. Pin A is connected to Pin A, etc. The wiring necessar y 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 insur e that the above pr ecedures are followed. Assembly of the wired mating connectors to'the appropriate modules will be by Duke Power personnel. Every effort w~' be made to assure a pr oduct typical of field-installed units. S1 ? the assembly of connector s to modules requir es a special toi ting tool, a Duse Power recre.centative_will retorque all con.ectors on the penetration assembly after its receipt at Sandia and prior to any tests on the unit. Background-The qualification histor y of the type K module /connec-tor was discussed in detail in the April 1980 draf t of this test plan.
~. -- .. -
4/28/00 11/11/80 12/22/80 In that draft, the partially qualified component of 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 and accident sequence. The purpose of the mating assembly was not for verification but to serve as an intet f ace dur ing 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 necessar ily be representative of the pr e-sently installed units. It was subsequently proposed that a Duke Power penettation unit available at the Catawba Station be used in the connector ver ification pr ogr am. This penetration assembly, acquired with installed units, when assembled with mating connectors and inter connecting cabling would be quite r epr esentative of installed items; cer..ainly more so than any after the fact fabricated item. Test Ptocedures Gener al The penetration assembly will under go the aging - accident sequence in the as-received condition i.e., with a junction box installed on the inboar d side of the assembly. An example of the test configuration is shown in Figure 3. In Figure 3 the penetr ation 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 instr umentation/ test cabling extending f rom the outboar d side. Because the penetr ation assembly is mounted vertically, the pressure equalizing-condensation digin vent shown in Figur e 3 was r epositioned fr om position V to position V. One exception to the above configuration will occur during the radiation aging cycle. Dimensions of the .:obalt-60 irradiation chamber are such that the inboard assembly complete with junction box cannot be accommodated. It will be necessaty to ir r adiate the inboard penetr ation unit without the junction box. The junction box' dose attenuation effect will be measured and appropriate adjustment made in the irradiation time. Environments to which the assembly _will be subjected are:
- 1. Thermal aging
- 2. Radiation
- 3. LOCA-MSLB ~_ -
4/28/80 11/11/80 12/22/80 The above tests will be, gener ally, in accordance with i those descr ibed in the D. G. O'Brien teports ER-252 and con-forming to 0A-TM-185/191 of that r epor t. The test will be , performed in the following sequence and will adhete to the concepts contained in the Sandia Department 4440 Quality Assur ance Progr am Plan.
- 1. Baseline - visual and functional
- 2. Thetmal aging
- 3. Post aging functional - visual
- 4. Radiation 5
- 5. Post radiation functional - visual
! 6. Accident
- 7. Post accident - functional - visual
- Acceptable per formance of the assembly will be on the basis of accept-teject criteria listed in a succeeding section of this proposal.
Soecific I. Pretest - Baseline A. Visual inspection
- 1. gener a'. appear ance
- 2. radiogr aphs if appear ance war rants -
, B. Functional 1 , 1. continuity - check for continuity and correctness
- 2. insulation resistance - 10 M @ 500 VDC
- a. between each conductor and shell
- b. -between all conductors
- 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' hour s dur ation
- 3. check continuity and . insulation resistance onceE daily-
- 4. internal pressure - note and record
., , - . . - . - , , . . - , ~ , . . . - _ . - .-.
4/28/80 11/11/80 12/22/80 C. Post test , 1. insulation resistance
- 2. continuity
- 3. visual
- 4. internal pressur e - note and record III. Radiation Exoosur e A. General The penetr ation 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 and/or radiation field dimensions may be tailored to specific needs. Considering the penetr ation dimensions-less junction box-and the requirement to maintain the radiation d3se rate below 1 m' rad /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 inboard junction box, the following steps will be taken. With the desired source configuration, Figure 4, dose rate will be determined with a calibrated air ionization chamber both with and without the junction box. Very simply these dif ferences in observed dose rates can be attributed to junction box perturbations. Then the penetration aging time will be adjusted to reflect the dose rate observed with the junction box in place. Temperatuae.of the environ-ment is to be monitored and maintained at or below the normal 110'F operating temperature. Dose measurement techniques and detector calibration will be traceable to the NBS. B. Test requirements
- 1. 2 x 10 8 rads (AIR) +10%
- 2. dose rate not-to exceed 10 6 rad /hr
- 3. internal pressure - note and record C. Post test requiremento
- 1. continuity
- 2. insulation resistance
- 3. internal pressure - note and record
_a_
4/28/80 11/11/80
- 12/22/80 IV. Accident Test A. General This test is to be a combination of LOCA, MSLB, and thermal shock environments. The LOCA and thermal shock environments are straight for ward although the dur ation of the thermal shock has not been soecified.
The line break phase of this environment, as outlined in the Duke Power Specification CNS-1361.00 0003, calls for an initial r ise in temperatur e and pr es-sure fr om ambient to 340*F and 15 psig, r espectively, in 10 seconds. The Sandia facility, at this time, cannot duplicate the specified transient rather , the temperature-time profile appearing in the Figure 5 is mor e typical of the Sandia facility capability. For impr oved perspective, Figure 6 has been included. In this figure are plotted the Duke Power specified transient, an actual D. G. O'Brien qualification pr ofile, and the estimated Sandia capability. Consideration of the specified thermal transient and the Sandia capability prompted an inquiry of sever al commer cial labor atories 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 soecified environment rise time. Actual positioning of temperature sensors in 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 sur f ace may be monitored. At least one temperature sensor will be positioned in' bo : interior so that some knowledge of module temperature history may be obtained. Access to the junction box interior will be through vent "V"--a pressure equalizing and. condensate drain vent. B. Test Requirements (see also Figure 8)
- 1. 340*F i 10*F @ 15 psig i 5 psig for 10 minutes --
rise time 10 seconds, but see also above and en-closed temperature profile
- 2. drop to 300*F in 10 to 30 minutes 4/28/80 11/11/80 12/22/80
- 3. 300*F i 10*F @ 15 psig i 5 psig for 80 minutes
- 4. drop to 250*F 1 5'F @ 15 psig i 5 psig hold for 18 hours
- a. when temper atur e stabilizes @ 250*F a pro-posed thermal shock to consist of either water c: chemical spray at 40*F directly onto junction box - time dur ation to be determined
., but not less than one minute. 4 b. following thermal shock - chemical spray to be used for duration of test. t
! 5. drop to 228'F i 5'F @ 5 psig 1 5 psig hold for 120 hours
- a. sprey continues
- 6. 600 VAC to be applied between all conductors and
' the connector shell dur ing entire test--see Figur e 9.
- 7. continuity and insulation resistance to be checked daily
- 8. penetration internal pr essur e - note and record daily ,
C. Post test
- 1. insulation and continuity tests
- 2. internal pressure - note and record Acceptance-Rejection Criteria Acceptable performance will be on the basis of. accept-reject criteria obtained from Duke Power Co. At this. time, due
- to unavoidable circumstances, this information has not been received from Duke. Upon receipt of the data this. section will be completed and forwarded. Note that insulation resistance requirements cited earlier in this report will probably require revision upon receipt of the Duke criteria.
Final Report A final report will be issued'on this test. .It will in-clude all data sheets and _ other pertinent details.
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