ML20140G538
| ML20140G538 | |
| Person / Time | |
|---|---|
| Site: | Monticello, 05000000 |
| Issue date: | 11/04/1977 |
| From: | Sobon L GENERAL ELECTRIC CO. |
| To: | Stello V Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20140F372 | List:
|
| References | |
| FOIA-85-665 NUDOCS 8604020454 | |
| Download: ML20140G538 (20) | |
Text
GENER AL h ELECTRIC NUCLEAR ENERGY SYSTEMS DIVISION GENERAL ELECTRIC COMPANY,175 CURTNER AVE., SAN JOSE, CALIFORNIA 95125 NUCLEAR ENERGY MC 681, (408) 925-3495 PRO S DIVISION N 90~, g
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b November 4, 1977
[p NOV8 1977 k
U. S. Nuclear Regulatory Comission 4
Office of Nuclear Reactor Regulation f
Washington, D.C. 20555 Attention:
Mr. Victor Stello, Jr., Director Division of Operating Reactors Gentlemen:
SUBJECT:
MARK I CONTAINMENT PROGRAM IN-PLANT SAFETY / RELIEF VALVE DISCHARGE LOAD TEST WITH A T-QUENCHER Task 5.1.2 of the Mark I Containment Program consists of an in-plant safety / relief valve discharge load test with a T-Quencher to be performed at the Monticello Nuclear Generating Plant.
During the Mark I Program status report meeting held in Bethesda on August 24 and 25,1977, members of your staff requested a description of this test plan.
Enclosed is a description of this test plan which is intended to respond to that request.
Sincerely,
/
p o-L. J. Sobon, Manage BWR Containment Licensing l
l LJS: pat /ll Enclosure cc: L.S.Gifford(GE,Bethesda)
J. C. Guibert (NRC) l C. I. Grimes NC J. A. Kudrick NC 8604020454 060114 t
7 7 7 1 2 1 1,-
.gf3 FIRESTOB5-665
MONTICELLO IN-PLANT SAFETY / RELIEF VALVE TEST WITH l
T-QUENCHER The inplant safety / relief valve discharge load testing with a new dis-charge device (called a T-quencher) is one of the major activities of the Mark I Long-Term Program.
The objective of the T-quencher is to reduce safety / relief valve (SRV) air-clearing loads and to discharge with stable condensation over the J
full operating range.
The objective of the Monticello T-quencher test is to provide the data necessary for developing the containment loads resulting from T-quencher discharge,into the suppression pool. To provide data to meet this objective, instrumentation will be used to measure acceleration, strain, pressure, temperature, and water level.
The T-quencher installed on the Monticello safety / relief valve discharge line (SRVDL) is shown in Figure 1.
The device consists of perforated arms attached to the discharge of a ramshead; the ramshead being similar to the device presently installed on the SRVDL. The T-quencher is i
designed to obtain a gradual discharge of air into the torus water during the air-clearing transient associated with SRV actuation, thereby reducing the hydpdyoamic pressure transient. The quencher is supported at the ramshead'and at the mid-span of the quencher arus as shown in Figures 2 and 3.
These quencher supports are connected to a beam made from 14-inch Schedule 120 pipe, which is attached to the ring girders.
The long air-clearing times associated with the T-quencher results in l
lower decompression wave loads than are presently imposed on the SRVDL by the existing ramshead device. Higher peak pipe pressures are experi-enced within the T-quencher than within the existing ramshead device; however, these peak pressures and associated loads are well within design limits.
Pressure transducers located on the torus skin will provide measurements of surface pressure acting on the torus during the relief valve actuations.
(The location of these sensors is shown in Figures 10 and 11). Special attention was given to epoxy mounting of sensors directly to the torus skin and protection of instrumentation lead wires by anchoring with stainless steel straps every 6 inches.
Pressure transducers and temper-ature detectors in the relief valve discharge pipa.will provide further data for the forcing function model.
An 3dditio.ial sophistication of these test measurements will be the recording of water level in the discharge piping to evaluate the effect of consecutive valve actuation. Until the discharge pipe vacuum breaker 4
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Monticello In-Plant Safety / Relief Valve Test with T-Quencher Page 2 admits sufficient air to the pipe following closure of the relief valve, i
the water level may be higher than normal. This higher water level would increase the bubble pressure during a subsequent valve reactuation although the effect may be partially offset by the smaller volume of air in the bubble (because of the partial vacuum). The consecutive valve actuation tests will further explore this phenomenon.
Pressure data at the torus skin will be utilized to confirm development of the analytical model for prediction of loads on the torus. Strain gage data from sensors on the torus skin will be utilized to determine the design margin of the torus for the full design life expectation of' relief valve actuations. Strain gages will measure the response of the torus support columns.
Temperature sensors located in the torus pool will be monitored to evaluate mixing effects in the pool during relief valve actuation.
Strain gages will measure the response of the relief valve discharge piping, the quencher and their structural supports. Accelerometers will measure the response of the torus shell, the quencher and the quencher l
support.
'h.
The number of sensors of each type is tabulated in Table 1.
Test instruments and their locations (except for the pool temperature sensors) are shown in attached Figures 4 through 12.
Thirty-four(34) pool temperature sensors are installed in the torus pool at selected circumfer-ential and vertical locations.
As shown in Figure 4, the torus bay designated as "D" (containing valve RV2-71A) is most heavily instrumented, and this "A" valve will be involved, in all the tests. Each test, except the extended blowdown, will consist of manual actuation of the same relief valve for a period of approximately 5 seconds during which the instrumentation,is actuated to record the response.
The test sequence is as follows:
1 valve cold pipe, normal water leg, full steam pressure 1 valve warm pipe, normal water leg, full steam pressure 1 valve hot pipe, normal wtter leg, full steam pressure 1 valve cold pipe, normal water leg, extended blowdown from full steam pressure.
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l Monticello In-Plant Safety / Relief Valve Test with T-Quencher Page 3 After each test, the results will be evaluated before proceeding to the next test. The wam pipe and extended bloudown tests will be run once each. All other tests will be perfomed several times to assure repeat-ability of the data.
The above constitutes the test as presently planned. Considering that this testing is being perfomed on a production facility, the scope of tests is quite extensive.
The number of relief valve actuations imposes a financial exposure due to power availability and potential maintenance outage considerations that may exceed the direct cost of perfoming the test. This is an extensive program capable of quantitatively defining the loads and structural re:ponses of interest.
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TABLE 1 SENSOR TYPES NUSER AND GENERAL LOCATION Torus Tr,. m Torus T-Quencher SRV Vacuta Gauges /
Region Paul
' Support
& Support
' Piping' ' Breaker Channels Penetration Strain Gauges III -
64/12 2/2 8/8 84/32 64 Single 10/10 50/150 234 7/21 3/9 j,
Rosette 40/120 9
Accelerometers II 7/7 Uni-axial 7/7 2/4 8
Bi-axial 2/4 2/2 5/5 1/1 46/46 194 Pressure Sensors 34/34 4/4 2/2 6
2/2 Water Leg Probes 10/10 10/10 50 Temperature Sensors (Resistance Tempera-ture Detectors, RTD)
I3}
TOTALS 91/171 4/4 64/12 13/29 28/34 1/1 201/251 556 39/39 5/5 34/34
~
Other RTD (Not on PCH)
)
b)No. of gauges /No. of channels.
(2)ilo; of penetrations through manway cover and drain flange on torus.
(3) Total number of gauges / channels connected to PCM recording system.
- 34) Total number of gauges / channels connected to D5-83 Scan recorder.
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