ML17265A706: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:CATEGORY REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9907280113 DOC.DATE: 99/07/22 NOTARIZED:
{{#Wiki_filter:CATEGORY REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
NO FACXL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
                                                                                                        '
Rochester Gas 8 Electric Corp..-RECXP.NAME RECIPIENT AFFILIATION VISSZNG,G.S.
ACCESSION NBR:9907280113             DOC.DATE: 99/07/22       NOTARIZED: NO               DOCKET FACXL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester                       G 05000244 AUTH. NAME           AUTHOR AFFILIATION MECREDY,R.C.         Rochester Gas 8 Electric Corp..-
RECXP.NAME           RECIPIENT AFFILIATION VISSZNG,G.S.


==SUBJECT:==
==SUBJECT:==
Forwards LER 98-003-02,re actuations of CR emergency air treatment sys.All'REATS actuations,including those originally believed to be valid actuations,were, in fact invalid actuations.
Forwards LER       98-003-02,re actuations of CR emergency air treatment sys.All'REATS actuations,including those originally believed to be valid actuations,were, in fact invalid actuations.
'DOCKET 05000244 DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL J 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).
DISTRIBUTION CODE: IE22T           COPIES RECEIVED:LTR         ENCL J     SIZE:
05000244 RECIPIENT ZD CODE/NAME LPD1-1 PD INTERNAL'/DRIP/REXB RES/DET/ERAB RGN1 FILE 01 COPIES LTTR ENCL 1 1 1 1 1 1~1 1 1 1 RECIPIENT ID CODE/NAME VZSSING,G.
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NRR/DIPM/ZOLB NRR/DSSA/SPLB RES/DRAA/OERAB COPIES LTTR ENCL 1 1 1 1 1'1 1 EXTERNAL: L ST LOBBY WARD NOAC POORE,W.NRC PDR 1 1 1 1 1 1 LMITCO MARSHALL NOAC QUEENER,DS NUDOCS FULL TXT 1 1 1~1 1 1 NOTE TO ALL"RIDS" RECIPIENTS:
NOTES:License Exp date         in accordance with 10CFR2,2.109(9/19/72).                 05000244 RECIPIENT           COPIES              RECIPIENT            COPIES ZD CODE/NAME         LTTR ENCL          ID CODE/NAME        LTTR ENCL LPD1-1 PD                 1     1       VZSSING,G.                1       1 INTERNAL                              1     1       NRR/DIPM/ZOLB            1       1
PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LIS'R REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTRi DESK (DCD)ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 15 ENCL 15 0 4ND ROCHESTER GAS AND ElECTRIC CORPORATION
          '/DRIP/REXB                1     1 ~
~89 EAST AtrrENUE, ROCHESTER, N.Y.Id6d9-OOOI l'OBERT C.MECREDY Vice President Nvcleor Operotions AREA CODE 716 5'-2700 July 22, 1999 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Guy S.Vissing Project Directorate I-1 Washington, D.C.20555  
NRR/DSSA/SPLB            1  '
RES/DET/ERAB              1      1      RES/DRAA/OERAB           1       1 RGN1    FILE    01      1     1 EXTERNAL: L ST LOBBY WARD             1      1      LMITCO MARSHALL          1      1 NOAC POORE,W.             1     1       NOAC QUEENER,DS           1     ~ 1 NRC PDR                  1     1       NUDOCS FULL TXT          1       1 NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT               LIS'R DESK (DCD) ON EXTENSION 415-2083                                             THE DOCUMENT CONTRi FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR               15   ENCL     15
 
0 4ND ROCHESTER GAS AND ElECTRIC CORPORATION ~   89 EAST AtrrENUE, ROCHESTER, N.Y. Id6d9-OOOI AREA CODE 716 5'-2700 l'OBERT C. MECREDY Vice President Nvcleor Operotions July 22,         1999 U.S. Nuclear Regulatory Commission Document           Control Desk Attn:                   Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555


==Subject:==
==Subject:==
LER 1998-003, Revision 2, Actuations of Control Room Emergency Air Treatment System Due to Invalid Causes R.ED Ginna Nuclear Power Plant Docket No.50-244  
LER 1998-003, Revision 2, Actuations of Control Room Emergency Air Treatment System Due to Invalid Causes R.ED Ginna Nuclear Power Plant Docket No. 50-244
 
==Dear Mr. Vissing:==
 
In accordance with                10 CFR  50.73, Licensee Event Report System, item (a) (2) (iv), which requires a report of, "any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature (ESF), including the Reactor Protection System (RPS)", the attached Licensee Event Report LER 1998-003 (Revision 2) is hereby submitted.
It    has been determined that there were various degraded components in the Control Room Radiation Monitoring system.
These degraded components resulted in electronic spikes in the readings on the monitors. The higher concentrations of Radon and Radon decay products caused the margin to the trip setpoint to be reduced.                Thus, in the presence of elevated Radon levels, the electronic spikes caused a setpoint to be exceeded. When elevated Radon levels were not present, larger spikes also caused a setpoint to be exceeded.                    The degraded components, resulting in electronic spikes, were the root cause of the Control Room Emergency Air Treatment System (CREATS) actuations.                                  All CREATS actuations, including those originally believed to be valid actuations, were, in fact, invalid actuations.
Very    truly yours, F'
Robert      C. Mecred 9907280i13 990722 PDR          ADOCK        05000244 8                                PDR


==Dear Mr.Vissing:==
xc: Mr. Guy S. Vissing (Mail Stop 8C2)
In accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(iv), which requires a report of,"any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature (ESF), including the Reactor Protection System (RPS)", the attached Licensee Event Report LER 1998-003 (Revision 2)is hereby submitted.
Project Directorate I-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector}}
It has been determined that there were various degraded components in the Control Room Radiation Monitoring system.These degraded components resulted in electronic spikes in the readings on the monitors.The higher concentrations of Radon and Radon decay products caused the margin to the trip setpoint to be reduced.Thus, in the presence of elevated Radon levels, the electronic spikes caused a setpoint to be exceeded.When elevated Radon levels were not present, larger spikes also caused a setpoint to be exceeded.The degraded components, resulting in electronic spikes, were the root cause of the Control Room Emergency Air Treatment System (CREATS)actuations.
All CREATS actuations, including those originally believed to be valid actuations, were, in fact, invalid actuations.
Very truly yours, Robert C.Mecred F'9907280i13 990722 PDR ADOCK 05000244 8 PDR xc: Mr.Guy S.Vissing (Mail Stop 8C2)Project Directorate I-1 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555 Regional Administrator, Region I U.S.Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S.NRC Ginna Senior Resident Inspector}}

Revision as of 17:45, 29 October 2019

Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations
ML17265A706
Person / Time
Site: Ginna Constellation icon.png
Issue date: 07/22/1999
From: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
To: Vissing G
NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17265A707 List:
References
NUDOCS 9907280113
Download: ML17265A706 (3)
v • d • e


Text

CATEGORY REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

'

ACCESSION NBR:9907280113 DOC.DATE: 99/07/22 NOTARIZED: NO DOCKET FACXL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas 8 Electric Corp..-

RECXP.NAME RECIPIENT AFFILIATION VISSZNG,G.S.

SUBJECT:

Forwards LER 98-003-02,re actuations of CR emergency air treatment sys.All'REATS actuations,including those originally believed to be valid actuations,were, in fact invalid actuations.

DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL J 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 COPIES RECIPIENT COPIES ZD CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL LPD1-1 PD 1 1 VZSSING,G. 1 1 INTERNAL 1 1 NRR/DIPM/ZOLB 1 1

'/DRIP/REXB 1 1 ~

NRR/DSSA/SPLB 1 '

RES/DET/ERAB 1 1 RES/DRAA/OERAB 1 1 RGN1 FILE 01 1 1 EXTERNAL: L ST LOBBY WARD 1 1 LMITCO MARSHALL 1 1 NOAC POORE,W. 1 1 NOAC QUEENER,DS 1 ~ 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT LIS'R DESK (DCD) ON EXTENSION 415-2083 THE DOCUMENT CONTRi FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 15 ENCL 15

0 4ND ROCHESTER GAS AND ElECTRIC CORPORATION ~ 89 EAST AtrrENUE, ROCHESTER, N.Y. Id6d9-OOOI AREA CODE 716 5'-2700 l'OBERT C. MECREDY Vice President Nvcleor Operotions July 22, 1999 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555

Subject:

LER 1998-003, Revision 2, Actuations of Control Room Emergency Air Treatment System Due to Invalid Causes R.ED Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Vissing:

In accordance with 10 CFR 50.73, Licensee Event Report System, item (a) (2) (iv), which requires a report of, "any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature (ESF), including the Reactor Protection System (RPS)", the attached Licensee Event Report LER 1998-003 (Revision 2) is hereby submitted.

It has been determined that there were various degraded components in the Control Room Radiation Monitoring system.

These degraded components resulted in electronic spikes in the readings on the monitors. The higher concentrations of Radon and Radon decay products caused the margin to the trip setpoint to be reduced. Thus, in the presence of elevated Radon levels, the electronic spikes caused a setpoint to be exceeded. When elevated Radon levels were not present, larger spikes also caused a setpoint to be exceeded. The degraded components, resulting in electronic spikes, were the root cause of the Control Room Emergency Air Treatment System (CREATS) actuations. All CREATS actuations, including those originally believed to be valid actuations, were, in fact, invalid actuations.

Very truly yours, F'

Robert C. Mecred 9907280i13 990722 PDR ADOCK 05000244 8 PDR

xc: Mr. Guy S. Vissing (Mail Stop 8C2)

Project Directorate I-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector

Retrieved from "https://kanterella.com/w/index.php?title=ML17265A706&oldid=1996721"