ML17264A828: Difference between revisions

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| contact person =  
| contact person =  
| document report number = NUDOCS 9703110202
| document report number = NUDOCS 9703110202
| document type = REPORTABLE OCCURRENCE REPORT (SEE ALSO AO,LER), TEXT-SAFETY REPORT
| document type = REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER), TEXT-SAFETY REPORT
| page count = 5
| page count = 5
}}
}}


=Text=
=Text=
{{#Wiki_filter:UA'l'EGORY             j REGULATO     INFORMATION DISTRIBUTION           TEM (RIDS)
{{#Wiki_filter:UA'l'EGORY j REGULATO INFORMATION DISTRIBUTION TEM (RIDS)
ACCESSION NBR:9703110202           DOC.DATE:   97/03/03     NOTARIZED: NO         DOCKET FACIL:50-244 Robert Emmet       Ginna Nuclear Plant, Unit 1, Rochester         G 05000244 AU%'H.NAb1E           AUTHOR AFFILIATION MECREDY,R.C.         Rochester Gas & Electric Corp.
ACCESSION NBR:9703110202 DOC.DATE: 97/03/03 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
RECIP.NAME           RECIPIENT AFFILIATION VISSINGFG.S.
05000244 AU%'H.NAb1E AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION VISSINGFG.S.


==SUBJECT:==
==SUBJECT:==
Special rept:on 970202,Plant Process Computer Sys received alarms on all points for Plant Vent Radiation Monitor R-14A.
Special rept:on 970202,Plant Process Computer Sys received alarms on all points for Plant Vent Radiation Monitor R-14A.
Skid was flushed & desired flow rate was reestablished.Skid
Skid was flushed
            -was taken OOS on 970210.Conducted monitoring of R-14A.
& desired flow rate was reestablished.Skid
DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR                   ENCL     SIZE:
-was taken OOS on 970210.Conducted monitoring of R-14A.
DISTRIBUTION CODE:
IE22D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:License Exp date       in accordance with 10CFR2,2.109(9/19/72).             05000244 RECIPIENT           COPIES            RECIPIENT          COPIES ID CODE/NAME         LTTR ENCL         ID CODE/NAME       LTTR ENCL PD1-1 PD                                VISSING G.
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
F INTERNAL: AEOD    S                                AEOD/SPD/RRAB NRR/DE/ECGB R          B                          NRR/DE/EMEB NRR/DRCH/HHFB                          NRR/DRCH/HICB NRR/DRCH/HOLB                          NRR/DRCH/HQMB NRR/DRPM/PECB                          NRR/DSSA/SPLB NRR/DSSA/SRXB                          RES/DET/EIB RGN1    FILE 01 EXTERNAL: L ST LOBBY WARD                           LITCO BRYCE,J    H NOAC POORE,W."                         NOAC QUEENER,DS NRC PDR                                NUDOCS FULL TXT NOTE TO ALL "RIDS" RECIPIENTS:
05000244 RECIPIENT ID CODE/NAME PD1-1 PD INTERNAL: AEOD S R
PLEASE HELP US TO REDUCE HASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
B NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRXB RGN1 FILE 01 COPIES LTTR ENCL RECIPIENT ID CODE/NAME VISSING F G.
TOTAL NUMBER OF COPIES REQUIRED: ITTR             24   ENCL
AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RES/DET/EIB COPIES LTTR ENCL EXTERNAL: L ST LOBBY WARD NOAC POORE,W."
NRC PDR LITCO BRYCE,J H
NOAC QUEENER,DS NUDOCS FULL TXT NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE HASTE!
CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT. 415-2083)
TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
ITTR 24 ENCL


V 4ND 0                                                    ~)
V
ROCHESTER GAS AND FIECTRIC CORPORAllON     ~ 89EASTAVENUE, ROCHESTE'R,     N Y ld6d9 %01 ~ - AREA CODE716 5862700 ROBERT C, MECREDY Vice 1'residee<
 
Noc)eor Ooerot or s March 3, 1997 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555 Subject;             Thirty (30) Day Special Report Inoperable Radiation Monitor R.E. Ginna Nuclear Power Plant Docket No. 50-244
0 4ND
~)
ROCHESTER GAS ANDFIECTRIC CORPORAllON
~ 89EASTAVENUE, ROCHESTE'R, N Y ld6d9 %01 ~ -
AREA CODE716 5862700 ROBERT C, MECREDY Vice 1'residee<
Noc)eor Ooerot or s March 3, 1997 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555 Subject; Thirty (30) Day Special Report Inoperable Radiation Monitor R.E. Ginna Nuclear Power Plant Docket No. 50-244


==Dear Mr. Vissing:==
==Dear Mr. Vissing:==
Radiation Accident Monitoring Instrument R-14A was inoperable for more than seven days.
In accordance with the Ginna Station Offsite Dose Calculation Manual (ODCM) Procedure CHA-RETS-ODCM, Section III.A.2.a.iiiand Table III-2, the following constitutes a Special Report outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to operable status.
On February 2, 1997, the Plant Process Computer System (PPCS) received alarms on all points for Plant Vent Radiation Monitor R-14A. In response to these alarms, personnel at the local R-14A skid identified that the alarm was from low sample flow and that the sample pump would not maintain the desired flow rate.
Plant administrative controls were initiated to track the apparent inoperability of the R-14A system and to investigate / repair the problem.
The skid was flushed, and the desired flow rate was reestablished.
The R-14A system continued
. to operate and function properly. Monitoring equipment was subsequently placed on the pump, and no anomalies were observed or recorded.
On February 10,
: 1997, the R-14A skid was taken out of service to perform an annual calibration.
No calibration parameters were found out of tolerance.
The monitoring equipment was reinstalled on February 10, after completion of the calibration, and the R-14A system continued to operate satisfactorily.
Although the R-14A system was being administratively tracked as inoperable since February 2, 1997, it was operating in its normal manner.
Therefore, R-14A would have performed its intended functions in the intended manner.
9703il0202 970303 PDR ADOCK 05000244 S
PDR L.li9072 lllHtmllll81IIEIIElirlmll85llllli
~@~ yY


Radiation Accident Monitoring Instrument R-14A was inoperable for more than seven days. In accordance with the Ginna Station Offsite Dose Calculation Manual (ODCM) Procedure CHA-RETS-ODCM, Section III.A.2.a.iii and Table III-2, the following constitutes a Special Report outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to operable status.
Page 2 On February 17, 1997, it was observed that the moisture separator on the flow regulator had caused a reduction in fiow rate.
On February 2, 1997, the Plant Process Computer System (PPCS) received alarms on all points for Plant Vent Radiation Monitor R-14A. In response to these alarms, personnel at the local R-14A skid identified that the alarm was from low sample flow and that the sample pump would not maintain the desired flow rate. Plant administrative controls were initiated to track the apparent inoperability of the R-14A system and to investigate / repair the problem.
The ball that stops moisture from entering the R-14A pump had been sucked up into the flow regulator intake opening.
The skid was flushed, and the desired flow rate was reestablished. The R-14A system continued to operate and function properly. Monitoring equipment was subsequently placed on the pump, and no anomalies were observed or recorded.
Once the ball was released, the desired flow rate reestablished itself.
On February 10, 1997, the R-14A skid was taken out of service to perform an annual calibration. No calibration parameters were found out of tolerance. The monitoring equipment was reinstalled on February 10, after completion of the calibration, and the R-14A system continued to operate satisfactorily. Although the R-14A system was being administratively tracked as inoperable since February 2, 1997, it was operating in its normal manner. Therefore, R-14A would have performed its intended functions in the intended manner.
The cause of the'nadvertent plugging of the moisture separator is believed to be the result of vibration, in the area of the local skid, that was not adequately dampened by the pump insulating bushings.
9703il0202 970303 PDR          ADOCK  05000244
Corrective actions have been taken to reduce the effect of vibration by replacing the insulating bushings.
                                                                                                          ~@~    yY S                          PDR L.l i9072                lllHtmllll81IIEIIElirlmll85llllli
Performance monitoring of R-14A will be conducted to identify any change in vibration.
 
Page 2 On February 17, 1997, it was observed that the moisture separator on the flow regulator had caused a reduction in fiow rate. The ball that stops moisture from entering the R-14A pump had been sucked up into the flow regulator intake opening. Once the ball was released, the desired flow rate reestablished itself. The cause of the'nadvertent plugging of the moisture separator is believed to be the result of vibration, in the area of the local skid, that was not adequately dampened by the pump insulating bushings.
Corrective actions have been taken to reduce the effect of vibration by replacing the insulating bushings. Performance monitoring of R-14A will be conducted to identify any change in vibration.
The R-14A system has been returned to service.
The R-14A system has been returned to service.
l Very truly yours, Robert C. Mecredy xc:     Mr. Guy S. Vissing (Mail Stop 14C7)
l Very truly yours, Robert C. Mecredy xc:
PWR Project Directorate I-1 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector
Mr. Guy S. Vissing (Mail Stop 14C7)
PWR Project Directorate I-1 Washington, D.C.
20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector


~ ~}}
~
~}}

Latest revision as of 09:49, 8 January 2025

Special Rept:On 970202,Plant Process Computer Sys Received Alarms on All Points for Plant Vent Radiation Monitor R-14A. Skid Was Flushed & Desired Flow Rate Was Reestablished.Skid Was Taken OOS on 970210.Conducted Monitoring of R-14A
ML17264A828
Person / Time
Site: Ginna Constellation icon.png
Issue date: 03/03/1997
From: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
To: Vissing G
NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9703110202
Download: ML17264A828 (5)


Text

UA'l'EGORY j REGULATO INFORMATION DISTRIBUTION TEM (RIDS)

ACCESSION NBR:9703110202 DOC.DATE: 97/03/03 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G

05000244 AU%'H.NAb1E AUTHOR AFFILIATION MECREDY,R.C.

Rochester Gas

& Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION VISSINGFG.S.

SUBJECT:

Special rept:on 970202,Plant Process Computer Sys received alarms on all points for Plant Vent Radiation Monitor R-14A.

Skid was flushed

& desired flow rate was reestablished.Skid

-was taken OOS on 970210.Conducted monitoring of R-14A.

DISTRIBUTION CODE:

IE22D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.

NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

05000244 RECIPIENT ID CODE/NAME PD1-1 PD INTERNAL: AEOD S R

B NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRXB RGN1 FILE 01 COPIES LTTR ENCL RECIPIENT ID CODE/NAME VISSING F G.

AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RES/DET/EIB COPIES LTTR ENCL EXTERNAL: L ST LOBBY WARD NOAC POORE,W."

NRC PDR LITCO BRYCE,J H

NOAC QUEENER,DS NUDOCS FULL TXT NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE HASTE!

CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT. 415-2083)

TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED:

ITTR 24 ENCL

V

0 4ND

~)

ROCHESTER GAS ANDFIECTRIC CORPORAllON

~ 89EASTAVENUE, ROCHESTE'R, N Y ld6d9 %01 ~ -

AREA CODE716 5862700 ROBERT C, MECREDY Vice 1'residee<

Noc)eor Ooerot or s March 3, 1997 U.S. Nuclear Regulatory Commission Document Control Desk Attn:

Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555 Subject; Thirty (30) Day Special Report Inoperable Radiation Monitor R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Vissing:

Radiation Accident Monitoring Instrument R-14A was inoperable for more than seven days.

In accordance with the Ginna Station Offsite Dose Calculation Manual (ODCM) Procedure CHA-RETS-ODCM,Section III.A.2.a.iiiand Table III-2, the following constitutes a Special Report outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to operable status.

On February 2, 1997, the Plant Process Computer System (PPCS) received alarms on all points for Plant Vent Radiation Monitor R-14A. In response to these alarms, personnel at the local R-14A skid identified that the alarm was from low sample flow and that the sample pump would not maintain the desired flow rate.

Plant administrative controls were initiated to track the apparent inoperability of the R-14A system and to investigate / repair the problem.

The skid was flushed, and the desired flow rate was reestablished.

The R-14A system continued

. to operate and function properly. Monitoring equipment was subsequently placed on the pump, and no anomalies were observed or recorded.

On February 10,

1997, the R-14A skid was taken out of service to perform an annual calibration.

No calibration parameters were found out of tolerance.

The monitoring equipment was reinstalled on February 10, after completion of the calibration, and the R-14A system continued to operate satisfactorily.

Although the R-14A system was being administratively tracked as inoperable since February 2, 1997, it was operating in its normal manner.

Therefore, R-14A would have performed its intended functions in the intended manner.

9703il0202 970303 PDR ADOCK 05000244 S

PDR L.li9072 lllHtmllll81IIEIIElirlmll85llllli

~@~ yY

Page 2 On February 17, 1997, it was observed that the moisture separator on the flow regulator had caused a reduction in fiow rate.

The ball that stops moisture from entering the R-14A pump had been sucked up into the flow regulator intake opening.

Once the ball was released, the desired flow rate reestablished itself.

The cause of the'nadvertent plugging of the moisture separator is believed to be the result of vibration, in the area of the local skid, that was not adequately dampened by the pump insulating bushings.

Corrective actions have been taken to reduce the effect of vibration by replacing the insulating bushings.

Performance monitoring of R-14A will be conducted to identify any change in vibration.

The R-14A system has been returned to service.

l Very truly yours, Robert C. Mecredy xc:

Mr. Guy S. Vissing (Mail Stop 14C7)

PWR Project Directorate I-1 Washington, D.C.

20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector

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