ML19332D279
| ML19332D279 | |
| Person / Time | |
|---|---|
| Issue date: | 11/20/1989 |
| From: | Remick F Advisory Committee on Reactor Safeguards |
| To: | Carr K NRC COMMISSION (OCM) |
| References | |
| REF-GTECI-087, REF-GTECI-NI, TASK-087, TASK-87, TASK-OR ACRS-R-1377, GL-89-10, NUDOCS 8911300257 | |
| Download: ML19332D279 (1) | |
Text
m Gust-/377 UNITED STATES -
g NUCLEAR RECULATORY COMMISSION ppg' s.N'7 g
- g ADVISORY CDemelTTEE ON REACTOR SAFEGUARDS WASHfMOTON, D. C. 30805 November 20, 1989 The Honorable Kenneth M. Carr Chairman U.S. Nuclear Regulatory Commission Washington, D.C. 20555-5
Dear Chairman Carr:
SUBJECT:
PROPOSEDRESOLUTIONOFGENERICISSUE-87(GI-87),"HPCISTEAM LINE BREAK WITHOUT ISOLATION" During the-355th meeting of-the Advisory Committee on Reactor Safe-guards, November 16-18, 1989, we discussed the - NRC staff's proposed
-resolution of GI-87.
This subject was also considered during our 354th meeting on October 5-6, 1989. Our Subcomunittee on Mechanical Components met with -members of the NRC staff on October 3,1989 to discuss this matter.' We also had the benefit of the document referenced.
In spite of its title, the scope of GI-87 includes all' safety-related g
valves that may be required to close against high differential pressures J
-and/or: high -flows such as experienced during a large downstream cipe break.- Possible deficiencies in the performance of such : valves have been recognized recently as the.. result of operating experience.and of tests and have been addressed by. the staff in Generic Letter 89-10,
" Safety-Related Motor-Operated _ Valve Testing and Surveillance."
This p
generic letter requires each licensee to undertake a program to identify safety-related valves that may not-perform adequately under design-basis conditions.
Unfortunately, as pointed out in our May 9, -1989 report related to Generic Letter 89-10,"the design basis for the HPCI steam line and other valves-'in some plants-may not specify the. type of heavy duty that is of' concern. - This means simply thet the heavy duty loads for these'-valves do not have to be considered in the program required by Generic Letter 89-10, and the deficiencies addressed by GI-87 will not be remedied, Unless Generic Letter 89-10 is amended to require updating or revision i.
I of the design basis for valves of this type, we do not consider the requirements of Generic Letter 89-10 as a complete resolution of GI-87.
Sincerely, 4-.
Forrest J. Remick Chairman
Reference:
Memorandum dated July 17, 1989 from R. Wayne Houston, Office of Nuclear Regulatory Research, NRC, for R. F. Fraley, ACRS,
Subject:
Resolution i
of Generic Issue-87 (GI-87), "HPCI Steam Line Break Without Isolation" "89Tf3OO257 891120 6
37 PDC QD
.