ML19351D291
| ML19351D291 | |
| Person / Time | |
|---|---|
| Issue date: | 06/12/1980 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-MS-0599, ACRS-MS-599, NUDOCS 8010090466 | |
| Download: ML19351D291 (4) | |
Text
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REVISED 6/12/80ji' ; - l h4 ACRS SUBCOMMITTEE MEETING ON METAL COMPONENTS
[ C l- [f!if U JUNE 17 & 18, 1930 WASHINGTON, DC TENTATIVE SCHEDULE JUNE 17, 1980 SPEAKER APPROXDtATE TIME 8:30 a.m.
Chairman's Opening Statement Shewnon 8:40 a.m.
Overview Serpan, Muscara (NRC) 9:00 a.m.
Reliability of Piping Harris (SAI) 9:30 a.m.
Steam Generator Integrity Clark (PNL)
- BREAK ********
10:30 a.m.
10:45 a.m.
Steam Generator Tube Corrosion vanRooyen (BNL) 5.1:15 p.m.
Eddy Current ISI McClung (ORNL)*
11:30 a.m.
Pipe Cracking and Environmental Effects Shack (ANL)
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- LUNCH ********
12:45 p.m.
1:45 p.m.
Qualification Tests of Safety Relief Valves, PORV, etc.
Noonan(NRC) 2:45 p.m.
Continuous Acoustic Emmission Monito.-ing Hutton (PNL) 3:15 p.m.
Incipient Crack Monitoring Yeager(Daedalean) 3:45 p.m.
Reliability of NDE Becker(PNL)
- BREAK ********
4:15 p.m.
4:45 p.m.
SAFT-UT Development Ganapathy (U. of Michigan) 5:15 p.m.
Adaptation of SAFT-UT to ISI Jackson (SwRI) 5:45 p.m.
Low Shelf Energy Concerns (Pressure Vessels, Basis for Operating below 50 ft.lb., eg., Yankee Rowe)
Hazeiton(NRC) 6:30 p.m.
Caucus by Subcommittee 6:45 p.m.
Adjournment
- Early plane out 8010 0 90 Y647
4.
ACRS SUBCO'NITTEE f1EETING ON '4ETAL COMPONENTS JUNE 17 L 18, 1980 WASHINGTON, DC JUNE 18, 1980 SPEAKER APPROXIMATE TIME Shewmon 8:30 a.m.
Chairman's Remarks Richardson, O'Brien (NRC) 8:40 a.m.
Overview 9:00 a.m.
SSMRP Mechanical Engineering Portion Mechanical Safety and Performance of Systems and Components 9:45 a.m.
- BREAK 10:30 a.m.
Structural Safety and Performance of Systems and Components 10:45 a.m.
11:15 a.m.
General Safety and Performance of Systems and Components
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- LUNCH 12:30 p.m.
1:30 p.m.
NRC Technical Assistance Programs Engineering Bosnak/Noonan Johnson Safety Technology Anderson Standards Jordan Inspection & Enforcement
- BREAK ********
3:00 p.m.
Hazelton(NRC) 3:15 p.m.
Turbine Disc Failures 4:15 p.m.
Safety Aspects of Turbine Disc Failures (NRC) 4:45 p.m.
Probability of Turbine Disc Failures (NRC) 5:15 p.m.
Caucus by Subcommittee 5:30 p.m.
Adjournment NOTES:
1.
Sudgetary discu's'sions are proprietary.
Turbine Disc Failures Presentation by W. Hazelton is expected to be 2.
proprietary.
Safety Aspects and Probability of Failure of Turbine Disc presentations 3.
are being negotiated with the Staff at the present time.
I
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.r May 28, 1980 EPRI SAFETY / RELIEF VALVE TEST PROGRAM OUESTI0'is 1.
One of the major objectives of the safety / relief valve test program is to verify that these valves will open and close as required:
What type of instrumentation will be employed to determine a.
the flow conditions (saturated, two-phase, subcooled) at the valve disc face when the valve first opens and thereafter throughout the blowdown?
b.
Will the test program evaluate the huddling chamber action (valve pop), blowdown, accumulation, and simmer margin for safety valves?
c.
Is the blowdown test duration sufficient to prove the sur-vivability of the valves and associated piping?
d.
Will these tests prove that the valves will close when required?
What is the permissible valve seat leakage following valve e.
closure after blowdown?
f.
Will the valve reaction time (time required to go from close to full open) be measured?
g.
What considerations are provided to test valve capacity for limiting system overpressure in normal system applications?
2.
How will the ATWS testing be factored into the program?
3.
What type of instrumentation will be employed to measure valve discharge i
rate?
4.
The NRC is considering the requirement to add an automatic PORY block valve closing feature:
a.
Will this test program prove the operability of PORV block valves to open under system differential pressure and close under various (subcooled water, two-phase flow, etc.) flow conditions?
b.
Valve operator action has been an area of concern in the past.
Will the tests of the block valves include a variety of pro-totypical valve operators as well as valves?
EPRI SAFETY / RELIEF VALVE TEST PR03 RAM QUESTIONS May 28, 1980 5.
Will the various means of positive valve position indication be evaluated up to rated valve discharge?
6.
Waterhammer is being studied as a generic problem.
Pressure transients in the valve piping may be caused by closure of the valves under test.
What type of data can and may be collected to aid in the study of water-hammer and its effects on valves and piping?
7.
Temperature effects may cause spring relaxation and valve seat distortion.
a.
Will the valves be tested at their normal operating temperatures?
b.
What procedures will be used to establish the lift pressure for the valves prior to the tests?
How long will the valves be subjected to system pressure prior c.
to the tests?
d.
Will the valves be calibrated in service at operating temperature and pressure?
8.
Will this current test program verify the ASME Code requirements which allow the testing of reduced sized safety / relief valves in order to validate the proper operation of the actual valves where full-scale test facilities have not been available?
9.
The test program will investigate piping effects that influence valve operability. What effects are expected (thermal-hydraulic, pipe reaction forces, backpressure, etc.)? How will these effects be monitored?
10.
Information on the BWR Safety Relief Valve Testing Program has not been available at prior presentations. The above questions (appli-cable to DWRs) should be addressed at the upcoming meeting.
(This test program is completely separate from the EPRI program.)
- 11. What funding and manpower are committed to the safety / relief valve test programs?
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