ML20140G259
| ML20140G259 | |
| Person / Time | |
|---|---|
| Site: | Monticello, 05000000 |
| Issue date: | 06/15/1976 |
| From: | Teh-Chiun Su Office of Nuclear Reactor Regulation |
| To: | Lainas G Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20140F372 | List:
|
| References | |
| FOIA-85-665 NUDOCS 8604020041 | |
| Download: ML20140G259 (4) | |
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4 UNITED STATES NUCLEAR REGULATORY COMMISSION g
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JUN 15 W16 Gus C.' Lainas, Chief, Containment Systems Branch, DSS THRU:
John A. Kudrick, Section Leader A, Containment Systems Branch, DSS TRIP REPORT - MONTICELLO S/R VALVE TEST On May 29, 1976, I visited the Monticello Nuclear Power Plant to witness the safety / relief valve tests. The tests, however, were postponed because of an instrumentation problem that occurred in the start-up testing.
Nevertheless, I reviewed the tests' results from the start-up tests and also attended a working meeting with the representatives of the General Electric Company, NUTECH Corporation and Northern State Power. A list of attendees is attached. The status of the testing is sumarized as follows:
1.
During checkout testing by actuating one SRV (conducted on May 25),
all strain gauges recorded one-side movement'of the structures instead of the expected vibratory response.
The pressure transducers, on the other hand, measured 2-3 cycles of bubble oscillation. A reference strain gauge was installed and the recording system improved.
2.
Additional checkout testing was performed on May 28.
The results of these tests showed a peculiar response of all strain gauges including the reference strain gauge. They all recorded a " jump" during the very early transient before the pressure transducers showed any pres-sure response inside the pool.
The meeting held on May 29 was aimed at a resolution to pinpoint the problem.
3.
The effort appeared mainly on the fixes of the strain gauges.
- However, I had noticed some other concerns and discussed them with representatives of GE following the meeting. Those concerns are:
a.- Failure of both pressure transducers located on the ramshead discharge. The information from these two pressure transducers is important for verification of the analytical model.
b.
The I-beam which supports the ramshead and runs tangentially across the pool may affect the pressure field.
It will be difficult to justify the presence of this I-beam analytically.
c.
The test results indicated that the water leg inside the SRV pipe raised rapidly and reached more than 20 feet above the B604020041 860114 PDR FOIA FIRESTDO5-665 PDR x.
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5R Gus C. Lainas original water level after the SRV blowdown was over. This 3
nenamena was considered as a result of the relatively small p(3") vacuum breaker for the SRV line. Because of this rapid rise of water leg, the tests on subsequent actuations on the same valve will not be performed by predetermined time intervals between the sequence of each actuation.
Instead, they will be performed by predetermined levels of the water leg.
In other words, the second SRV actuation will not be initiated until the water leg falls to the predetermined level. This may not repre-sent the actual transient for SRV sequential actuation.
DlfA T. M. Su, is Containment Systems Brsnch, DSS
Enclosure:
As stated cc:
R. Tedesco J. Glynn J. Kudrick File: Monticello Nuclear Generating Plant V. Stello D. Eisenhut L. Shao R. Stuart J. Guibert C. Grimes e
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MONTICELLO S/R VALVE TESTS AND MEETING MAY 29-29,1976 1
l ATTENDANCE:
NSP NRC M. H. Clarity T. M. Su B. Hill J. Antony J. Thie (Consultant)
GE E. Mangrum J. Hosler j
H. Helmholz
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J. Houngount H. Chang NUTECH J. Arterburn K. A. Hoedeman e
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