ML19305E424
| ML19305E424 | |
| Person / Time | |
|---|---|
| Issue date: | 04/02/1980 |
| From: | Eisenhut D, Mattson R, Murley T Office of Nuclear Reactor Regulation, NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | Budnitz R NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| References | |
| NUDOCS 8004240141 | |
| Download: ML19305E424 (4) | |
Text
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UNITED STATES g
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NUCLEAR REGULATORY COMMisslON f
I WASHINGTON, D.
C.
20555 3
5 APR 2 1980 MEMORANDUM FOR: Robert J. Budnitz, Director Office of Nuclear Regulatory Research FROM:
Thomas E. Murley, Director Division of Reactor Safety Research Darrell G. Eisenhut, Acting Director Division of Operating Reactors Roger J. Mattson, Director Division of Systems Safety Harold D. Thornburg, Director Division:of Reactor Construction Inspection
SUBJECT:
APPROVAL 0F THE COMMISSION-DIRECTED ELECTRICAL CONNECTOR TESTS On February 14, 1980, members of our staffs met in conjunction with the Qualification Testing Evaluation Review Group to discuss the subject test (Enclosure 1).
These tests were requested by the Commission following hearings conducted on the Union of Concerned Scientists Petition, dated November 4,1977, with regard to defective safety connectors in use in
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operating power plants. The Commission directive to RES was as follows:
" Additional tests of connectors in a simulated LOCA environment be conducted by Sandia' Laboratories using connectors qualified according to the IEEE-323 standard when a suitable test facility is available."
The first series of tests on connectors in use in Browns Ferry Unit 3 was completed in November 1979, with all units tested performing as required. The meeting on February 14, 1980, was to reach agreement on the next and last series of connector tests.
During the meeting it was agreed that the electrical connectors, which are a part of the McGuire~ penetration assemblies, should be used for the next series of tests.
It was further agreed that Sandia should be requested'to prepare a detailed test plan, as outlined in the enclosed minutes, to the review group meeting.
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Robert J. Budnitz APR 2 1980 It should be pointed out that we are requesting Sandia to include thermal aging and radiation testing in their test plan even though the McGuire
. t connectors were not tested in this manner. NRC current practice is to require that LOCA qualification be demonstrated by thermal aging and radiation testing in addition to steam testing.
In previous years, some applicants chose to demonstrate the aging and radiation portions of the LOCA qualification by analysis or comparison to test data for similar materials.
It was on this basis that the McGuire penetration assembly qualification was approved. Our current licensing requirement is to demonstrate by test that the component will survive the full LOCA after an aging cycle equivalent to the operational life of the component.
Although this change means that the Sandia tests will not duplicate the exact test run by the applicant and, therefore, is not a repeat of an industry test, we feel that our approach will meet the intent of the Commission directive.
We expect that the detailed test plan will be approved in writing by members of our staffs before the actual test is run.
I-Thomas E. Murley, Dlirector V
Division of Reactor Safety Research f
rrel' ut, Acting Director Division of Operating Reactr.3 Il Y
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c+ s stoger8.Matson, Director Division of'tystemr Safety 0-Harold D. Thornburg, Dirertor Division of Reactor Consttuction Inspection
Enclosure:
Minutes of the QTE Review Group Meeting held on February 14, 1980
QUALIFICATION TESTING EVALUATION (QTE) REVIEW GROUP MEETING Name: Ronald Feit i
Date and Place: February 14, 1980; Bethesda, MD
Purpose:
To discuss 1) Comission-directed connector test QTE research, f
and 2) future QTE research work.
Discussion 1.
In accordance with a pre.vious Commission directive RSR initiated a project to conduct confimatory LOCA qualification tests on electrical connectors identical to those in use in operating power plants. The first test series on Browns Ferry Unit 3 connectors was completed in November 1979. The current program plan calls for conducting one more l
series of tests.
IE has identified connectors from the McGuire plant manufactured by the D.G. O'Brien Company (as part of their containment penetrations) to be used in the next series of tests.
Detailed review of the LOCA qualification data showed that a seal material change was made during the sequential test series after the themal aging and radiation portions of the test were complete. However, the themal aging and radiation part of the test was not rerun and qualification was established by analysis of the material and comparison to other radiation data on similar material. Although this approach is allowed by the IEEE standard, current regulatory practice is to require that aging and radiation I
qualification be demonstrated by test. Accordingly, the Chairman recomended to the Review Group that the McGuire test be conducted including both themal aging and radiation. The remainder of the test sequence would be identicil to that used by Duke Power. A letter of agreement will be prepared to be cosigned by the responsible Division Directors from IE, NRR and RES.
Sandia will be requested to prepare a test plan for review by the QTE Review Group as was done for the Browns Ferry Unit 3 test series. This test plan will cover the following issues which will have to be agreed to by NRR and IE in writing prior-to initiation of the tests:
a.
the specific test sequence and profiles, b.
thedesignofthetestspecimen(specifically,howmuchofthepene-tration face plate will be duplicated),
procurement and fabrication details, and c.
d.
acceptance criteria.
Test procedures will be prepared and sent to the Review Group after the test plan is agreed to.
2.
The status of the LOCA facility upgrade and initial plans were discussed.
The facility will be operational about April 1,1980. The initial plans include the following.
Synergistic testing of pressure transmitters is planned for generic a.
designs in comon use today. This testing will be a continuation of the previous synergistic testing conducted in the old facility.
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. b.
Evaluation of LOCA post-test acceleration methods is planned using Current testing is usually for a 30-day typical LOCA profiles.
It is questionable whether this period is sufficient.. Also, period.
if an acceptable way of accelerating the end part of the test (where the pressures and temperatums are low and at saturated conditions) can be found, it would enable LOCA tests to be run on more components.
As discussed previously, this would help the qualification reviews of operating plants.
Thermal aging sensitivity tests are planned to study the sensitivity c.
of the LOCA test to the current extremes of acceptable thermal aging.
Also, it is important for the reviews of the LOCA qualification for operating plants to determine the significance of not including aging at all in the LOCA qualification test.
d.
Oxygen depletion studies are planned to determine if the qualification tests currently conducted are less severe than a real LOCA where more oxygen is present during the test.
The status of the new materials aging study which has been discussed previously, was given by the Chairman. This addition to the current materials aging effort would consist of a complete review of the data for all non-metal materials currently used in plants as part of safety related eqiupment. The results would be used initially by IE inspectors to screen items for further review by the headquarters staff and ultimately for more detailed review and to identify FY 1980 supplemental funds of $50K materials that require further aging study.
have been requested and work could start as soon as funds are available.
E. Butcher (NRR) indicated that a user's request should be sent to RES shortly.
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.t ATTENDEES
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Ronald Feit RES Herb Conrad DSS Jim Stone IE E. Butcher D0R W. R. Rutherford IE r
A. R. Ungaro PSB l
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