ML17309A488: Difference between revisions

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| number = ML17309A488
| number = ML17309A488
| issue date = 05/08/1992
| issue date = 05/08/1992
| title = Responds to NRC 910821 & 900509 Ltrs Re Violations Noted in Edsfi Rept 50-244/91-80 & Insp Rept 50-244/89-81, Respectively.Corrective Actions:New molded-case Circuit Breaker Will Be Tested During 1993 Refueling Outage
| title = Responds to NRC 910821 & s Re Violations Noted in Edsfi Rept 50-244/91-80 & Insp Rept 50-244/89-81, Respectively.Corrective Actions:New molded-case Circuit Breaker Will Be Tested During 1993 Refueling Outage
| author name = Mecredy R
| author name = Mecredy R
| author affiliation = ROCHESTER GAS & ELECTRIC CORP.
| author affiliation = ROCHESTER GAS & ELECTRIC CORP.
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:~ . ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
{{#Wiki_filter:~. ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ESSION NBR:9205210005             DOC.DATE: 92/05/08       NOTARIZED: NO         DOCKET CIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester                 G 05000244 UTH.NAME             AUTHOR AFFILIATION MECREDY,R.C.           Rochester Gas & Electric Corp.
ESSION NBR:9205210005 DOC.DATE: 92/05/08 NOTARIZED:
RECIP.NAME           RECIPIENT AFFILIATION JOHNSON,A.R.               Project Directorate I-3                                           R
NO CIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
UTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
Project Directorate I-3 DOCKET 05000244 R


==SUBJECT:==
==SUBJECT:==
Responds to NRC 910821             &   900509   ltrs re violations noted in EDSFI Rept 50-244/91-80           & Insp Rept 50-244/89-81, respectively. Corrective actions:new molded-case circuit breaker will be tested during 1993 refueling outage.                             D DISTRIBUTION CODE: AOOID           COPIES RECEIVED:LTR         I ENCL 0 SIZE:
Responds to NRC 910821
TITLE:   OR Submittal: General Distribution
& 900509 ltrs re violations noted in EDSFI Rept 50-244/91-80
                                                                                                /
& Insp Rept 50-244/89-81, respectively. Corrective actions:new molded-case circuit breaker will be tested during 1993 refueling outage.
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).                     05000244 RECIPIENT             COPIES              RECIPIENT        COPIES            D ID CODE/NAME           LTTR ENCL          ID CODE/NAME    LTTR ENCL PD1-3 LA                                   PD1-3 PD                                D JOHNSON,A INTERNAL: NRR/DET/ECMB 7D                 1            NRR/DET/ESGB NRR/DOEA/OTSB11             1            NRR/DST       8E2 NRR/DST/SELB 7E              1             NRR/DST/SICB8H7 NRR/DST/SRXB 8E              1      1      NUDOCS-ABSTRACT OC                          1            OGC/HDS 1 G  PILE        Ol        1            RES/DS IR/EIB r lERNAL NRC PDR                                      NSIC D
DISTRIBUTION CODE:
AOOID COPIES RECEIVED:LTR I
ENCL 0 SIZE:
TITLE: OR Submittal:
General Distribution D
/
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: NRR/DET/ECMB 7D NRR/DOEA/OTSB11 NRR/DST/SELB 7E NRR/DST/SRXB 8E OC G PILE Ol r lERNAL NRC PDR COPIES LTTR ENCL 1
1 1
1 1
1 1
RECIPIENT ID CODE/NAME PD1-3 PD NRR/DET/ESGB NRR/DST 8E2 NRR/DST/SICB8H7 NUDOCS-ABSTRACT OGC/HDS 1 RES/DS IR/EIB NSIC COPIES LTTR ENCL D
D D
D D
NOTE TO ALL "RIDS" RECIPIENTS:
NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAMEFROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
jTAL NUMBER OF COPIES REQUIRED: LTTR                 18 ENCL     ~$
jTAL NUMBER OF COPIES REQUIRED:
LTTR 18 ENCL
~$
D D
 
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      <   z8N     imzz ROCHESTER GAS AND ELECTRIC CORPORATION                 o 89 EAST AVENUE, ROCHESTER N.Y. 14649-0001 ROBERTC MECREDY                                                                          TELEPHONE Vice President                                                                    AstEA coDE 71B 548 2700 Clnne Nucteer Production May 8, 1992 U.S. Nuclear Regulatory Commission Document               Control Desk Attn:                   Allen R. Johnson Project Directorate I-3 Washington, D.C.                   20555
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< z8N imzz ROCHESTER GAS AND ELECTRIC CORPORATION ROBERTC MECREDY Vice President rr Kw Lear owl's o
89 EAST AVENUE, ROCHESTER N.Y. 14649-0001 TELEPHONE AstEA coDE 71B 548 2700 Clnne Nucteer Production May 8, 1992 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Allen R. Johnson Project Directorate I-3 Washington, D.C.
20555


==Subject:==
==Subject:==
Update/Extension   Request for Corrective Actions to be Taken   in Response to Notice of Violation Molded Case Circuit Breaker Testing - NRC Inspection Repor No. 50-244/89-81-06 dated May 9, 1990 R.E. Ginna Nuclear Power Plant Docket No. 50-244 Ref. (a): Letter dated. August 21, 1991 from M. W. Hodges, NRC, to RG&E, Subject Electrical Distribution System Functional Inspection for Ginna Nuclear Power Station (Report No.
Update/Extension Request for Corrective Actions to be Taken in Response to Notice of Violation Molded Case Circuit Breaker Testing - NRC Inspection Repor No. 50-244/89-81-06 dated May 9, 1990 R.E.
Ginna Nuclear Power Plant Docket No. 50-244 Ref. (a): Letter dated. August 21, 1991 from M. W. Hodges, NRC, to RG&E, Subject Electrical Distribution System Functional Inspection for Ginna Nuclear Power Station (Report No.
50-244/91-80)
50-244/91-80)


==Dear Mr. Johnson:==
==Dear Mr. Johnson:==
On page 27 of reference (a), the NRC closed Violation 50-244'/89 06 pertaining to a lack of scheduled periodic testing of Class 1E 480 V molded case circuit breakers (MCCB) as follows:
"In response to the NOV, the licensee stated that it was developing appropriate test methods for MCCBs as part of the Reliability Centered Maintenance (RCM) program.
Corrective Action Report 1985 was initiated to formally track and.
address the lack of MCCB testing.
A corrective action plan was developed to systematically evaluate the identified violation.
This consisted. of:"
"Initiation of 'a program for periodic MCCB testing by the next refueling outage."
"The team concluded that the corrective action plan initiated, to address the lack of MCCB testing was comprehensive and addressed the essential elements to develop an effective testing program.
Based on the licensee's continuing MCCB test program development and the revision of appropriate test procedures, this violation is closed."
Since the "next refueling outage" referred to above is the 1992 Refueling Outage, RG&E is providing the following update/extension request for corrective actions to be taken in response to Violation 50-244/89-81-06:
9205210005 920508 PDR ADOCK 05000244


On page 27                of reference (a), the NRC closed Violation 50-244'/89        06 pertaining to a                  lack of scheduled periodic testing of Class 1E 480 V molded case                  circuit breakers (MCCB) as follows:
I M) e
      "In response to the NOV, the licensee stated that appropriate test methods for MCCBs as part of the Reliability it was developing Centered Maintenance (RCM) program. Corrective Action Report 1985 was initiated to formally track and. address the lack of MCCB testing. A corrective action plan was developed to systematically evaluate the identified violation. This consisted. of:"
." "qpdgg g~~v
      "Initiation of 'a program for periodic MCCB testing by the next refueling outage."
      "The team concluded that the corrective action plan initiated, to address the lack of MCCB testing was comprehensive and addressed the essential elements to develop an effective testing program.
Based on the licensee's continuing MCCB test program development and the            revision of appropriate test procedures, this violation is closed."
Since the "next refueling outage" referred to above is the 1992 Refueling Outage, RG&E is providing the following update/extension request for corrective actions to be taken in response to Violation 50-244/89-81-06:
9205210005 920508 PDR        ADOCK 05000244


I M)
1)
  ." "qpdgg g~~v e
Development of the
: 1)  Development of the   'MCCB test program is in progress and is being coordinated. with   Reliability Centered Maintenance (RCM) program commitments as well as the Maintenance Procedure Upgrade Project (MPUP) schedule.       The RCM preventive main-tenance (PM) enhancements and the MCCB testing program are being implemented into interactive PM procedures.       The RCM project has a MCCB PM initiation date of 12/31/92. Current plans are to procure MCCB test. equipment and finalize pro-cedures for the MCCB program during 6/92 8/92.
'MCCB test program is in progress and is being coordinated. with Reliability Centered Maintenance (RCM) program commitments as well as the Maintenance Procedure Upgrade Project (MPUP) schedule.
: 2)   To gain breaker testing experience,   a non-safety related MCC will be tested first under the new program. In keeping with the EPRI breaker maintenance guidelines, the initial testing will proceed cautiously and will not be conducted during a plant outage. This will facilitate resource allocation and keep the initial testing from becoming a critic@1 path activity. Initial MCCB testing will be conducted sometime late in 1992.
The RCM preventive main-tenance (PM) enhancements and the MCCB testing program are being implemented into interactive PM procedures.
: 3)   Scheduling for safety related MCC's will be completed by 12/92. Testing of safety related'CC's wi21 be initiated during the 1993 refueling outage.
The RCM project has a
Very truly yours, Robert C. Mecredy GJWN225 xc: Mr. Allen R. Johnson (Mail Stop   14D1)
MCCB PM initiation date of 12/31/92.
Project Directorate I-3 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia,   PA   19406 Ginna Senior Resident Inspector
Current plans are to procure MCCB test.
equipment and finalize pro-cedures for the MCCB program during 6/92 8/92.
2)
To gain breaker testing experience, a non-safety related MCC will be tested first under the new program.
In keeping with the EPRI breaker maintenance guidelines, the initial testing will proceed cautiously and will not be conducted during a
plant outage.
This will facilitate resource allocation and keep the initial testing from becoming a
critic@1 path activity.
Initial MCCB testing will be conducted sometime late in 1992.
3)
Scheduling for safety related MCC's will be completed by 12/92.
Testing of safety related'CC's wi21 be initiated during the 1993 refueling outage.
Very truly yours, GJWN225 Robert C. Mecredy xc:
Mr. Allen R. Johnson (Mail Stop 14D1)
Project Directorate I-3 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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Latest revision as of 01:09, 8 January 2025

Responds to NRC 910821 & s Re Violations Noted in Edsfi Rept 50-244/91-80 & Insp Rept 50-244/89-81, Respectively.Corrective Actions:New molded-case Circuit Breaker Will Be Tested During 1993 Refueling Outage
ML17309A488
Person / Time
Site: Ginna Constellation icon.png
Issue date: 05/08/1992
From: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
To: Andrea Johnson
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9205210005
Download: ML17309A488 (6)


Text

~. ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ESSION NBR:9205210005 DOC.DATE: 92/05/08 NOTARIZED:

NO CIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G

UTH.NAME AUTHOR AFFILIATION MECREDY,R.C.

Rochester Gas

& Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.

Project Directorate I-3 DOCKET 05000244 R

SUBJECT:

Responds to NRC 910821

& 900509 ltrs re violations noted in EDSFI Rept 50-244/91-80

& Insp Rept 50-244/89-81, respectively. Corrective actions:new molded-case circuit breaker will be tested during 1993 refueling outage.

DISTRIBUTION CODE:

AOOID COPIES RECEIVED:LTR I

ENCL 0 SIZE:

TITLE: OR Submittal:

General Distribution D

/

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

05000244 RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: NRR/DET/ECMB 7D NRR/DOEA/OTSB11 NRR/DST/SELB 7E NRR/DST/SRXB 8E OC G PILE Ol r lERNAL NRC PDR COPIES LTTR ENCL 1

1 1

1 1

1 1

RECIPIENT ID CODE/NAME PD1-3 PD NRR/DET/ESGB NRR/DST 8E2 NRR/DST/SICB8H7 NUDOCS-ABSTRACT OGC/HDS 1 RES/DS IR/EIB NSIC COPIES LTTR ENCL D

D D

NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAMEFROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

jTAL NUMBER OF COPIES REQUIRED:

LTTR 18 ENCL

~$

D D

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t zruznz ziziirzz

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m7jjz~

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< z8N imzz ROCHESTER GAS AND ELECTRIC CORPORATION ROBERTC MECREDY Vice President rr Kw Lear owl's o

89 EAST AVENUE, ROCHESTER N.Y. 14649-0001 TELEPHONE AstEA coDE 71B 548 2700 Clnne Nucteer Production May 8, 1992 U.S. Nuclear Regulatory Commission Document Control Desk Attn:

Allen R. Johnson Project Directorate I-3 Washington, D.C.

20555

Subject:

Update/Extension Request for Corrective Actions to be Taken in Response to Notice of Violation Molded Case Circuit Breaker Testing - NRC Inspection Repor No. 50-244/89-81-06 dated May 9, 1990 R.E.

Ginna Nuclear Power Plant Docket No. 50-244 Ref. (a): Letter dated. August 21, 1991 from M. W. Hodges, NRC, to RG&E, Subject Electrical Distribution System Functional Inspection for Ginna Nuclear Power Station (Report No.

50-244/91-80)

Dear Mr. Johnson:

On page 27 of reference (a), the NRC closed Violation 50-244'/89 06 pertaining to a lack of scheduled periodic testing of Class 1E 480 V molded case circuit breakers (MCCB) as follows:

"In response to the NOV, the licensee stated that it was developing appropriate test methods for MCCBs as part of the Reliability Centered Maintenance (RCM) program.

Corrective Action Report 1985 was initiated to formally track and.

address the lack of MCCB testing.

A corrective action plan was developed to systematically evaluate the identified violation.

This consisted. of:"

"Initiation of 'a program for periodic MCCB testing by the next refueling outage."

"The team concluded that the corrective action plan initiated, to address the lack of MCCB testing was comprehensive and addressed the essential elements to develop an effective testing program.

Based on the licensee's continuing MCCB test program development and the revision of appropriate test procedures, this violation is closed."

Since the "next refueling outage" referred to above is the 1992 Refueling Outage, RG&E is providing the following update/extension request for corrective actions to be taken in response to Violation 50-244/89-81-06:

9205210005 920508 PDR ADOCK 05000244

I M) e

." "qpdgg g~~v

1)

Development of the

'MCCB test program is in progress and is being coordinated. with Reliability Centered Maintenance (RCM) program commitments as well as the Maintenance Procedure Upgrade Project (MPUP) schedule.

The RCM preventive main-tenance (PM) enhancements and the MCCB testing program are being implemented into interactive PM procedures.

The RCM project has a

MCCB PM initiation date of 12/31/92.

Current plans are to procure MCCB test.

equipment and finalize pro-cedures for the MCCB program during 6/92 8/92.

2)

To gain breaker testing experience, a non-safety related MCC will be tested first under the new program.

In keeping with the EPRI breaker maintenance guidelines, the initial testing will proceed cautiously and will not be conducted during a

plant outage.

This will facilitate resource allocation and keep the initial testing from becoming a

critic@1 path activity.

Initial MCCB testing will be conducted sometime late in 1992.

3)

Scheduling for safety related MCC's will be completed by 12/92.

Testing of safety related'CC's wi21 be initiated during the 1993 refueling outage.

Very truly yours, GJWN225 Robert C. Mecredy xc:

Mr. Allen R. Johnson (Mail Stop 14D1)

Project Directorate I-3 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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