ML20125D406
| ML20125D406 | |
| Person / Time | |
|---|---|
| Issue date: | 09/07/1976 |
| From: | Novak T Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20125D401 | List: |
| References | |
| REF-GTECI-A-26, REF-GTECI-RV, TASK-A-26, TASK-OR NUDOCS 8001140282 | |
| Download: ML20125D406 (2) | |
Text
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c,# UNITED STATES de[ /
y' \" NUCLEAR REGULATORY COMMISSION WASWNGTON, D. C. 266 ENCLOSURE 5 j
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\,*****/ SEP 7 1976 0"080%g MEMORANDUM FOR: Distribution FROM:
Thomas M. Novak, Chief, Reactor Systems Branch, 00R
SUBJECT:
RSB BRANCH TECHNICAL POSITION ON REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION A Branch Technical Position (RSB) on Overpressure Protection is being developed to document the requirements for overpressure protection to prevent the reactor coolant system (RCS) from exceeding pressure-temperature limitations. Such requirements are necessary as additional protection against brittle fracture of the reactor vessel when the RCS is in startup or shutdown conditions, particular'v when water-solid.
The fundamental criterion to be applied by the pr'posec Branch Technical Position is that no single e:uipment failure or s :ngle operator error shall result in Appendix G hmitacions :em escaded.
The Branch Technical Position would consider the followir,9-(1) The required seismic and quality group classification of proposed system modifications to prevent overpressurization transients, (2) The design and installation criteria for - ,- /
the overpressure protection components, rcc.
(3) Requirements for the adequacy of controls and instrumentation of the overpressure protection components with regard to the required features of automatic actuation, remote sensing and indication, remote control, emergency onsite power, and connections to the reactor protection system, (4) The mathematical models used to analyze the overpressure transients including the performance characteristics of the protection components such as relief valves while relieving water, (5)'IRequiFements for test programs to assure that the components that
- provide overpressure protection will perform their safety function,
Contact:
90017146
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. . se SEP 7 576 (6) The credit to be allowed for operator action, and (7) The establishment of a safety limit for startup and shutdown conditions that relates to the. Appendix G pressure-temperature limitations.
Your comments on any (or all) of the above seven areas are invited to aid in formulating the detailed requirements for the proposed Branch Technical Position. Since operating experience has shown that over-pressurization incidents have occurred with a greater frequency than originally anticipated, it is important to ensure timely resolution to preclude additional occurrences. Therefore, your comments are
< requested by September 15, 1976.
omas M. Novak, Chief Reactor Systems Branch Division of Systems Safety cc: D. Ross T. Ippolito G. Mazetis S. Israel J. Knight S. Pawlicki R. Kirkwood 5:s!"'SS* 90017147 Z. Rosztoczy
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