ML17083B869
| ML17083B869 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 03/27/1987 |
| From: | Wegner M NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) |
| To: | Lam P NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) |
| References | |
| NUDOCS 8704270034 | |
| Download: ML17083B869 (2) | |
Text
FROM:
Mary S.
- Wegner, Reactor Systems Engineer Reactor Systems Section 2
Reactor Operations Analysis Branch Office for Analysis and Evaluation of Operational Data MEMORANDUM FOR:
Peter Lam, Chief Reactor Systems Section 2
Reactor Operation Analysis Branch Office for Analysis and Evaluation of Operational Data DISTRIBUTION:
I"mm AEOD CF ROAB CF MWegner PLam SRubin WLanning KBlack MWilliams
, FHebdon CHeltemes
SUBJECT:
TECHNICAL REVIEW REPORT:
PRESSURIZER CODE SAFETY VALVE RELIABILITY The subject technical review report is enclosed for your consideration.
The study was initiated as a result of the screening of a Diablo Canyon I licensee event report (LER 86-018).
Our evaluation found that upon testing their pressurizer Code safety valves with the unit at hot standby, Diablo Canyon I personnel found their lift setpoints to be above their technical specifications (TS) limits.
The test method was questioned and its proper use was determined.
The valves were correctly reset.
A data search indicated that a total of 34 pressurizer Code safety valves at 17 plants had setpoint drift, leakage, misadjusted ring settings, or maintenance/installation problems since January I, 1983.
These problems could lead to inadvertent reactor
- scrams, overpressur-ization of the reactor coolant system (RCS), or degradation of the reactor coolant pressure boundary.
These problems appear to be generic to all safety/
relief valves.
It is suggested that AEOD initiate a case study to determine the extent of the problems and to assess the adequacy of present efforts toward increasing safety valve reliability.
Enclosure:
As stated Mary S.
- Wegner, Reactor Systems Engineer Reactor Systems Section 2
Reactor Operations Analysis Branch Office for Analysis and Evaluation of Operational Data cc w/enclosure:
T. Gwynn, OCM C. Brinkman, CE R.
- Borsum, B8W OFC:
R B
SC:R B
NAME :
MWegne
.as PLam DATE : 3/g /87
- 3/Z7/87 L. Gifford, GE W. Beaumont, W
OFFICI L REC RD COPY 8704270034 870327 tt DR ADOCK 0500027(5 PDRJ
- b. PiA!.(