ML18047A440
| ML18047A440 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 04/01/1982 |
| From: | Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18047A442 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM NUDOCS 8207160337 | |
| Download: ML18047A440 (1) | |
Text
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consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Ml 49201 * (517) 788-0550 April 1, 1982 Mr. Harold Denton Director, Nuclear Reactor Regulations U.S. Nuclear Regulatory Commission Washington, D.C. 20555
'51J -255
SUBJECT:
TRANSMITTAL OF PWR SAFETY AND RELIEF VALVE TEST PROGRAM REPORTS In response to NUREG 0737 Item II.D.l.A, Performance Testing of Relief and Safety Valves, this letter transmits the following reports which document the results of the PWR Safety and Relief Valve Test Program conducted by EPRI on behalf of the PWR Utility participants.
- 1.
Valve Selection/Justification Report
- 2.
Valve Inlet Fluid Conditions for Pressurizer Safety and Relief Valves for B&W 177 and 205 FA Plants
- 3.
Valve Inlet Fluid Conditions,, for Pressurizer Safety and Relief Valves in Combustion Engineering - Designed Plants
- 4.
Valve Inlet Fluid Condition for Pressurizer Safety and Relief Valves in Westinghouse - Designed Plants
- 5.
Test Condition Justification Report
- 6.
Safety and Relief Valve Test Report
- 7.
Application of RELAP 5/MOD 1 for Calculation of Safety and Relief Valve Discharge Piping Hydrodynamic Loads The first report documents the basis and provides justification for the l\\.All.II valves selected for testing.
The next four reports document the basis and
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provides justification for the conditions selected for testing.
The sixth report documents the observed safety and relief valve test performance.
I The seventh report presents the verification of a discharge piping analyticalLhft,'7IP model for predicting associated hydrodynamic loads.
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The participating PWR Utilities will be referencing these reports as part of...,_________--
their plant specific submittals.
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David P Hoff~~~irman PWR Safety and Relief Valve Test Program Subcommittee cc:
PWR Utility Participants 8207160337 820401 PDR ADOCK 05000255 p