ML17264A622: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:CATEGORY 1 REGULAT INFORMATION DISTRIBUTIO
{{#Wiki_filter:CATEGORY 1 REGULAT     INFORMATION DISTRIBUTIO     ~ STEM   (RIDS)
~STEM (RIDS)g,P'CCESSION NBR:96100903(9 DOC.DATE: 96/10/04 NOTARIZED:
NBR:96100903(9 g,P'CCESSION DOC.DATE: 96/10/04     NOTARIZED: NO           DOCKET FAC/L:50.,~44 robert Emmet'inna Nuclear Plant, Unit 1, Rochester                       G 05000244 AUTH'zNAME                   AUTHOR AFFILlATION MECREDYl,R.C.                 Rochester Gas a Electric Corp.
NO DOCKET FAC/L:50.,~44 robert Emmet'inna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH'zNAME AUTHOR AFFILlATION MECREDYl,R.C.
RECIP.NAME                     RECIPIENT AFFILIATION VISSINGPG ~ ST
Rochester Gas a Electric Corp.RECIP.NAME RECIPIENT AFFILIATION VISSINGPG~ST  


==SUBJECT:==
==SUBJECT:==
Forwards rev 1 to COLR 6 pressure a temperature to support Cycle 26&amend 64 to TS.DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR i ENCL TITLE: OR Submittal:
Forwards rev           1 to COLR 6 pressure   a temperature   limits rept to support Cycle 26 & amend 64 to TS.
General Distribution limits rept SIZE: 2+NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
DISTRIBUTION CODE: AOOID TITLE:    OR COPIES RECEIVED:LTR i Submittal: General Distribution ENCL      SIZE: 2 +
05000244 E RECIPIENT ID CODE/NAME PD1-1 LA VISSINGPG.
NOTES:License Exp date               in accordance with 10CFR2,2.109(9/19/72).         05000244 E
INTERNAL.ILE CENTER 1 NR'DRCH"f CB NRR/DSSA/SRXB OGC/HDS3 EXTERNAL: NOAC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 0 1 1 RECIPIENT ID CODE/NAME PD1-1 PD NRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 0 D'C U M, E N, T NOTE TO ALL"RZDS" RECIPIENTS:
RECIPIENT                  COPIES          RECIPIENT           COPIES ID CODE/NAME               LTTR ENCL      ID CODE/NAME      LTTR ENCL PD1-1 LA                       1    1    PD1-1 PD                1    1 VISSINGPG.                     1    1                                                  0 INTERNAL.       ILE CENTER             1      1    1    NRR/DE/EMCB            1    1 NR     'DRCH"f       CB       1    1    NRR/DSSA/SPLB          1     1 NRR/DSSA/SRXB                  1    1    NUDOCS-ABSTRACT         1     1 OGC/HDS3                        1     0 EXTERNAL: NOAC                                1     1     NRC PDR                1     1 D'
PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME, OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 415-2083 iTOTAL'NUMBER OF COPIES REQUIRED: LTTR 12 ENCL ll ANDe ROCHESTER GAS AND ELECTRIC CORPGRATION
C U
~89 EASTAYENUE, ROCHESTER, N.Y 14649-0001 AREA CODE716 546-2700 ROBERT C.MECREDY Vice President Nvcleor Operotions October 4, 1996 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Guy S.Vissing Project Directorate I-l Washington, D.C.20555  
M, E
N, T
NOTE TO ALL "RZDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME,OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 iTOTAL'NUMBER OF COPIES REQUIRED: LTTR                   12 ENCL   ll
 
AND e
ROCHESTER GAS AND ELECTRIC CORPGRATION ~     89 EASTAYENUE, ROCHESTER, N. Y 14649-0001   AREA CODE716 546-2700 ROBERT C. MECREDY Vice President Nvcleor Operotions October 4, 1996 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I-l Washington, D.C. 20555


==Subject:==
==Subject:==
Transmittal of Core Operating Limits Report (COLR)and the Reactor Coolant System (RCS)Pressure and Temperature Limits Report (PTLR)Rochester Gas&Electric Corporation R.E.Ginna Nuclear Power Plant Docket No.50-244  
Transmittal of Core Operating Limits Report (COLR) and the Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
Rochester Gas & Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244


==Reference:==
==Reference:==
Technical Specification 5.6.5 and 5.6.6
==Dear Mr. Vissing,==
Ginna Station Technical Specifications 5.6.5 and 5.6.6 require that R&GE provide the NRC with any revisions of the COLR and PTLR. As such, attached please find a copy of Revision 1 of these two documents. The COLR was revised to support Cycle 26 while the PTLR was revised per Amendment No. 64 to the Technical Specifications. Future revisions to these documents will be forwarded to the NRC in accordance with the applicable technical specification.
Very truly yours, OP0035 Robert C. Mecredy MDF3879 Attachments xc:          U.S. Nuclear Regulatory Commission Mr. Guy S. Vissing (Mail Stop 14C7)
PWR Project Directorate I-1 Washington, D.C. 20555 9b10090389 9bi004 PDR          ADOCK 05000244 P                          PDR
sV C
J K


Technical Specification 5.6.5 and 5.6.6
                                    'I U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406
  'I Ginna Senior Resident Inspector


==Dear Mr.Vissing,==
I
Ginna Station Technical Specifications 5.6.5 and 5.6.6 require that R&GE provide the NRC with any revisions of the COLR and PTLR.As such, attached please find a copy of Revision 1 of these two documents.
    ~ ~
The COLR was revised to support Cycle 26 while the PTLR was revised per Amendment No.64 to the Technical Specifications.
.I}}
Future revisions to these documents will be forwarded to the NRC in accordance with the applicable technical specification.
Very truly yours, OP0035 Robert C.Mecredy MDF 3879 Attachments xc: U.S.Nuclear Regulatory Commission Mr.Guy S.Vissing (Mail Stop 14C7)PWR Project Directorate I-1 Washington, D.C.20555 9b10090389 9bi004 PDR ADOCK 05000244 P PDR sV C J K  'I U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406'I Ginna Senior Resident Inspector
~~I.I}}

Revision as of 17:03, 29 October 2019

Forwards Rev 1 to COLR & Pressure & Temperature Limits Rept to Support Cycle 26 & Amend 64 to TS
ML17264A622
Person / Time
Site: Ginna 
Issue date: 10/04/1996
From: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
To: Vissing G
NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17264A623 List:
References
NUDOCS 9610090389
Download: ML17264A622 (5)


Text

CATEGORY 1 REGULAT INFORMATION DISTRIBUTIO ~ STEM (RIDS)

NBR:96100903(9 g,P'CCESSION DOC.DATE: 96/10/04 NOTARIZED: NO DOCKET FAC/L:50.,~44 robert Emmet'inna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH'zNAME AUTHOR AFFILlATION MECREDYl,R.C. Rochester Gas a Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION VISSINGPG ~ ST

SUBJECT:

Forwards rev 1 to COLR 6 pressure a temperature limits rept to support Cycle 26 & amend 64 to TS.

DISTRIBUTION CODE: AOOID TITLE: OR COPIES RECEIVED:LTR i Submittal: General Distribution ENCL SIZE: 2 +

NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 E

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-1 LA 1 1 PD1-1 PD 1 1 VISSINGPG. 1 1 0 INTERNAL. ILE CENTER 1 1 1 NRR/DE/EMCB 1 1 NR 'DRCH"f CB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D'

C U

M, E

N, T

NOTE TO ALL "RZDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME,OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 iTOTAL'NUMBER OF COPIES REQUIRED: LTTR 12 ENCL ll

AND e

ROCHESTER GAS AND ELECTRIC CORPGRATION ~ 89 EASTAYENUE, ROCHESTER, N. Y 14649-0001 AREA CODE716 546-2700 ROBERT C. MECREDY Vice President Nvcleor Operotions October 4, 1996 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I-l Washington, D.C. 20555

Subject:

Transmittal of Core Operating Limits Report (COLR) and the Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)

Rochester Gas & Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244

Reference:

Technical Specification 5.6.5 and 5.6.6

Dear Mr. Vissing,

Ginna Station Technical Specifications 5.6.5 and 5.6.6 require that R&GE provide the NRC with any revisions of the COLR and PTLR. As such, attached please find a copy of Revision 1 of these two documents. The COLR was revised to support Cycle 26 while the PTLR was revised per Amendment No. 64 to the Technical Specifications. Future revisions to these documents will be forwarded to the NRC in accordance with the applicable technical specification.

Very truly yours, OP0035 Robert C. Mecredy MDF3879 Attachments xc: U.S. Nuclear Regulatory Commission Mr. Guy S. Vissing (Mail Stop 14C7)

PWR Project Directorate I-1 Washington, D.C. 20555 9b10090389 9bi004 PDR ADOCK 05000244 P PDR

sV C

J K

'I U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406

'I Ginna Senior Resident Inspector

I

~ ~

.I