ML20041F125: Difference between revisions
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| contact person = | | contact person = | ||
| document report number = NUDOCS 8203160212 | | document report number = NUDOCS 8203160212 | ||
| document type = REPORTABLE OCCURRENCE REPORT (SEE ALSO AO | | document type = REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER), TEXT-SAFETY REPORT | ||
| page count = 1 | | page count = 1 | ||
}} | }} | ||
=Text= | =Text= | ||
{{#Wiki_filter:f | {{#Wiki_filter:f W | ||
<v STATE OF RHODE ISLAND AND PROVIDENCE PLANTATIONS j | |||
RHODE ISLAND ATOMIC ENERGY COMMISSION Nuclear Science Center South Ferry Road l | |||
Narragansett, R. I. 02882 | ,,g | ||
' ],,., | |||
March 5, 1982 | Narragansett, R. I. 02882 March 5, 1982 k | ||
C Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission IEECEfVED 9 | |||
Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission | Region 1 b | ||
MARI'57982 h | |||
=0 631 Park Avenue 2 | |||
l' a | |||
King of Prussia, Pa. 19406 License R-95 | |||
/f Docket 50-193 f$ | |||
~ | |||
Gentlemen: | Gentlemen: | ||
On March 3, 1982, during maintenance of the reactor system, we learned that components in the process instrumentation, which monitor primary coolant flow and primary coolant core outlet temperature, would not provide a scram for power failure. After approval of our Reactor Utilization Committee (safety review com-mittee), the components were reworked so that in addition to pro-viding a scram for loss of flow and high temperature, they would cause a scram for power loss to individual components. | On March 3, 1982, during maintenance of the reactor system, we learned that components in the process instrumentation, which monitor primary coolant flow and primary coolant core outlet temperature, would not provide a scram for power failure. After approval of our Reactor Utilization Committee (safety review com-mittee), the components were reworked so that in addition to pro-viding a scram for loss of flow and high temperature, they would cause a scram for power loss to individual components. | ||
At no time during the almost 18 years of operating history has a power failure occurred which did not shut down the reactor. In addition, at no time did process control instrumentation compo-nents fail without causing a shutdown of the reactor. | At no time during the almost 18 years of operating history has a power failure occurred which did not shut down the reactor. | ||
In addition, at no time did process control instrumentation compo-nents fail without causing a shutdown of the reactor. | |||
This situation was discussed by telephone with R. Starostecki, R. | This situation was discussed by telephone with R. Starostecki, R. | ||
Gallo and E. Greenman of NRC, Region 1 on March 3, 1982. | Gallo and E. Greenman of NRC, Region 1 on March 3, 1982. | ||
Very truly yours, s v:rt&M A. Francis DiMeglio Director AFD:ag cc: RUC RIAEC 8203160212 820305 | Very truly yours, s v:rt&M A. Francis DiMeglio Director AFD:ag cc: RUC RIAEC | ||
PDR ADOCK 05000193 S | }h 8203160212 820305 | ||
$1 PDR ADOCK 05000193 S | |||
PDR}} | |||
Latest revision as of 19:20, 19 December 2024
| ML20041F125 | |
| Person / Time | |
|---|---|
| Site: | Rhode Island Atomic Energy Commission |
| Issue date: | 03/05/1982 |
| From: | Dimeglio A RHODE ISLAND, STATE OF |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 8203160212 | |
| Download: ML20041F125 (1) | |
Text
f W
<v STATE OF RHODE ISLAND AND PROVIDENCE PLANTATIONS j
RHODE ISLAND ATOMIC ENERGY COMMISSION Nuclear Science Center South Ferry Road l
,,g
' ],,.,
Narragansett, R. I. 02882 March 5, 1982 k
C Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission IEECEfVED 9
Region 1 b
MARI'57982 h
=0 631 Park Avenue 2
l' a
King of Prussia, Pa. 19406 License R-95
/f Docket 50-193 f$
~
Gentlemen:
On March 3, 1982, during maintenance of the reactor system, we learned that components in the process instrumentation, which monitor primary coolant flow and primary coolant core outlet temperature, would not provide a scram for power failure. After approval of our Reactor Utilization Committee (safety review com-mittee), the components were reworked so that in addition to pro-viding a scram for loss of flow and high temperature, they would cause a scram for power loss to individual components.
At no time during the almost 18 years of operating history has a power failure occurred which did not shut down the reactor.
In addition, at no time did process control instrumentation compo-nents fail without causing a shutdown of the reactor.
This situation was discussed by telephone with R. Starostecki, R.
Gallo and E. Greenman of NRC, Region 1 on March 3, 1982.
Very truly yours, s v:rt&M A. Francis DiMeglio Director AFD:ag cc: RUC RIAEC
}h 8203160212 820305
$1 PDR ADOCK 05000193 S