ML19210F030: Difference between revisions
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31513 FMS MR. JAMES P. O'REILLY UtlITED STATES f;UCLEAR REGULATORY COMMISSIO:1 DIRECTOR OF ItiSPECTIOl AtiD EliFORCEMEtlT | * SQ ' | ||
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R0 TELEGRAM FOR 'AT 01 BAXLEY, GA. 31513 FMS MR. JAMES P. O'REILLY UtlITED STATES f;UCLEAR REGULATORY COMMISSIO:1 | |||
Unit I was operating at full power at the time. | ~ | ||
Nature of Occurrence | DIRECTOR OF ItiSPECTIOl AtiD EliFORCEMEtlT REGIC:1 II SUITE 31C0 101 MARIETTA STREET ATLAtiTA, GEORGIA 30303 , | ||
SUEJECT: HATCH U:;IT I, DC:V,ET N0. 50-321, 10TIFICATICN CF REPORTAELE OCCURRENCE tio. 50-321/1979-089 t10TIFIED: Ross F. Rogers DATE: 11-6-79 CATE: 11-6-79 TIME: 15:00 EST DESCRIPTION OF REPORTABLE OCCURRENCE Initial Conditicn This occurrence was discovered by A/E while evaluating as-built seismic piping and supports per the requirements of IE Bulletin 79-14. Unit I was operating at full power at the time. | |||
Immediate Corrective Action The RHR piping has been modified since the evaluation was performed. This was accomplished per design change request 79-423. | . | ||
A design modification will be generated to provide seismic class I support for the by pass to con-denser valve chest and the reactor head vent lines near valve B21-F003 and F004.Cause These supports were omitted from .the original design. | Nature of Occurrence It was found that the following system piping is not supported seismic class I: the head vent line near valves B21-F003 & F004; a portion of RHR head spray piping near valve E11-F023; the bypass to condenser valve chest. | ||
Sucolemental Corrective Action | Immediate Corrective Action The RHR piping has been modified since the evaluation was performed. This was accomplished per design change request 79-423. A design modification will be generated to provide seismic class I support for the by pass to con-denser valve chest and the reactor head vent lines near valve B21-F003 and F004. | ||
Cause These supports were omitted from .the original design. | |||
Additional supports will be designed for the head vent piping and the change will also be implemented during the | Sucolemental Corrective Action ' | ||
The aforementioned modification on the bypass valve chest will be implement-ed during the next cold shutdown. Additional supports will be designed for the head vent piping and the change will also be implemented during the . | |||
[00) | next cold shutdown. | ||
'~ | # | ||
Impact to Other Unit | 1552 323 | ||
I;Justification for Continued Operation | .- | ||
.Even if this unlikely seismic event did occur there would exist no threat to public health or safety for the following reasons. | [00) 3 | ||
The RHR line supports have been modified; therefore, this item is no longer considered a problem. | /I 7912130 C. WnCIAL7kdh[8M t | ||
The bypass to condenser valve chest is downstream from the MSIV's and would be automatically isolated in the event of a line rupture. The worst case wculd be the ru;;ture of the two inch head vent line. | - | ||
Such an event is an analyzed accident for this unit. Any release of steam would be inside the primary con-tainment.Tione of the above situations would prevent a safe shutdcwn, nor would they pose any threat to public health or safety. | |||
7 N b j M'.Ma'rtry g Plant Managpf-1552 526 I.}} | ' | ||
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_ . . . | |||
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Status of Redundant or Backuo Systems fio redundant supports exist for any of these system portions. | |||
Impact to Other Unit l No other units were affected by this event. | |||
I | |||
; Justification for Continued Operation | |||
. | |||
Even if this unlikely seismic event did occur there would exist no threat to public health or safety for the following reasons. The RHR line supports have been modified; therefore, this item is no longer considered a problem. The bypass to condenser valve chest is downstream from the MSIV's and would be automatically isolated in the event of a line rupture. The worst case wculd be the ru;;ture of the two inch head vent line. Such an event is an analyzed accident for this unit. Any release of steam would be inside the primary con-tainment. Tione of the above situations would prevent a safe shutdcwn, nor would they pose any threat to public health or safety. | |||
7 N b j M'. Ma'rtry g Plant Managpf-1552 526 I | |||
.}} | |||
Revision as of 12:15, 19 October 2019
| ML19210F030 | |
| Person / Time | |
|---|---|
| Site: | Hatch |
| Issue date: | 11/06/1979 |
| From: | Manry M GEORGIA POWER CO. |
| To: | |
| References | |
| NUDOCS 7912130426 | |
| Download: ML19210F030 (2) | |
Text
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R0 TELEGRAM FOR 'AT 01 BAXLEY, GA. 31513 FMS MR. JAMES P. O'REILLY UtlITED STATES f;UCLEAR REGULATORY COMMISSIO:1
~
DIRECTOR OF ItiSPECTIOl AtiD EliFORCEMEtlT REGIC:1 II SUITE 31C0 101 MARIETTA STREET ATLAtiTA, GEORGIA 30303 ,
SUEJECT: HATCH U:;IT I, DC:V,ET N0. 50-321, 10TIFICATICN CF REPORTAELE OCCURRENCE tio. 50-321/1979-089 t10TIFIED: Ross F. Rogers DATE: 11-6-79 CATE: 11-6-79 TIME: 15:00 EST DESCRIPTION OF REPORTABLE OCCURRENCE Initial Conditicn This occurrence was discovered by A/E while evaluating as-built seismic piping and supports per the requirements of IE Bulletin 79-14. Unit I was operating at full power at the time.
.
Nature of Occurrence It was found that the following system piping is not supported seismic class I: the head vent line near valves B21-F003 & F004; a portion of RHR head spray piping near valve E11-F023; the bypass to condenser valve chest.
Immediate Corrective Action The RHR piping has been modified since the evaluation was performed. This was accomplished per design change request 79-423. A design modification will be generated to provide seismic class I support for the by pass to con-denser valve chest and the reactor head vent lines near valve B21-F003 and F004.
Cause These supports were omitted from .the original design.
Sucolemental Corrective Action '
The aforementioned modification on the bypass valve chest will be implement-ed during the next cold shutdown. Additional supports will be designed for the head vent piping and the change will also be implemented during the .
next cold shutdown.
1552 323
.-
[00) 3
/I 7912130 C. WnCIAL7kdh[8M t
-
'
' ~
_ . . .
~
.
Status of Redundant or Backuo Systems fio redundant supports exist for any of these system portions.
Impact to Other Unit l No other units were affected by this event.
I
- Justification for Continued Operation
.
Even if this unlikely seismic event did occur there would exist no threat to public health or safety for the following reasons. The RHR line supports have been modified; therefore, this item is no longer considered a problem. The bypass to condenser valve chest is downstream from the MSIV's and would be automatically isolated in the event of a line rupture. The worst case wculd be the ru;;ture of the two inch head vent line. Such an event is an analyzed accident for this unit. Any release of steam would be inside the primary con-tainment. Tione of the above situations would prevent a safe shutdcwn, nor would they pose any threat to public health or safety.
7 N b j M'. Ma'rtry g Plant Managpf-1552 526 I
.