ML17251A135: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:, ACCELERATED DFRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:8806300083 DOC.DATE: 88/06/21 NOTARIZED:
{{#Wiki_filter:, ACCELERATED         DFRIBUTION         DEMONSTRATION         SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
NO DOCKET FACIL:50-244 Robert Emmet, Ginna Nuclear Plant, Unit 1, Rochester G 05000244'UTH.NAME AUTHOR AFFILIATION SNOW,B.A.Rochester Gas&Electric Corp.RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
ACCESSION NBR:8806300083       DOC.DATE: 88/06/21   NOTARIZED: NO       DOCKET FACIL:50-244 Robert   Emmet, Ginna Nuclear Plant, Unit 1, Rochester   G 05000244 NAME        AUTHOR AFFILIATION                                                'UTH.
SNOW,B.A.         Rochester Gas & Electric Corp.
RECIP.NAME         RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)


==SUBJECT:==
==SUBJECT:==
Requests that Tech Spec 1.4 be amended to include word"supports" after word"lubrication." DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR (ENCL~SIZE: 3+2 TITLE: OR Submittal:
Requests that Tech Spec 1.4 be amended   to include word "supports" after word "lubrication."
General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
DISTRIBUTION CODE: AOOID TITLE: OR Submittal:
05000244 RECIPIENT ID CODE/NAME PD1-3 LA STAHLE,C INTERNAL: ARM/DAF/LFMB NRR/DEST/CEB 8H NRR/DEST/MTB 9H NRR/DOEA/TSB 11 STRACT REG F 01 EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1 0 1 1 1 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD1-3 PD NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/RSB 8E NRR/PMAS/ILRB12 OGC 15-B-18 RES/DE/EIB NRC PDR COPIES LTTR ENCL 5 5 1 1 1 1 1 1 1 1 1 0 1 1 1 1 8 A D D 8 D:,''" A D 9~TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 19 I t e
COPIES RECEIVED:LTR ( ENCL ~
I SIIIFIII IZIEif AIVO i IIIIIIIIIIII IIIIIIIIIIII ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y.14649-0001 June 21, 1988 TELEPHONE AREA CODE 716 546-2700 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Mr.Carl Stahle PWR Project Directorate No.1 Washington, D.C.20555  
General  Distribution SIZE: 3+ 2 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).         05000244 8
RECIPIENT         COPIES          RECIPIENT        COPIES ID CODE/NAME     LTTR ENCL      ID CODE/NAME      LTTR ENCL PD1-3 LA             1    0    PD1-3 PD              5    5            A STAHLE,C             1    1 D
INTERNAL: ARM/DAF/LFMB           1    0    NRR/DEST/ADS 7E      1    1 NRR/DEST/CEB 8H      1    1    NRR/DEST/ESB 8D      1   1 D
NRR/DEST/MTB 9H      1    1    NRR/DEST/RSB 8E      1    1 NRR/DOEA/TSB 11      1    1    NRR/PMAS/ILRB12       1    1 STRACT      1    1    OGC 15-B-18         1    0            8 REG F        01      1    1    RES/DE/EIB           1   1 EXTERNAL: LPDR                  1     1     NRC PDR              1   1 NSIC                  1     1 D:,''"
A D
9   ~
TOTAL NUMBER OF COPIES REQUIRED: LTTR       22   ENCL   19 I
t
 
e I SIIIFIII         IZIEif AIVO i IIIIIIIIIIII IIIIIIIIIIII ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 TELEPHONE June 21, 1988             AREA CODE 716 546-2700 U.S. Nuclear Regulatory Commission Document                     Control Desk Attn: Mr. Carl Stahle PWR Project Directorate       No. 1 Washington, D.C.                       20555


==Subject:==
==Subject:==
Technical Specification Testing Requirements for Snubbers R.E.Ginna Nuclear Power Plant Docket No.50-244  
Technical Specification Testing Requirements for Snubbers R.E. Ginna Nuclear Power Plant Docket No. 50-244
 
==Dear Mr. Stahle:==


==Dear Mr.Stahle:==
As a result of a June 7, 1988 telecon between RG&E and NRC         personnel, RG&E wishes to clarify one aspect of the subject Technical Specification Change request, as submitted by letter dated. July 24, 1987.                             Operability of certain snubbers under cold shutdown conditions is required, as the result of the present system operability requirements of Technical Specification 3.1.1.1.e.                           To ensure clarity, we request that Technical Specification 1.4 be amended to include the word "supports" after the word "lubrication", as shown in Attachment 1 and that this page become a part of our Application submitted on July 24, 1987.
As a result of a June 7, 1988 telecon between RG&E and NRC personnel, RG&E wishes to clarify one aspect of the subject Technical Specification Change request, as submitted by letter dated.July 24, 1987.Operability of certain snubbers under cold shutdown conditions is required, as the result of the present system operability requirements of Technical Specification 3.1.1.1.e.
In Attachment 2, RG&E is providing an explanation of two additional issues: steam generator snubber seal service life monitoring, maintenance and documentation; and mechanical snubber degradation monitoring and preventive maintenance.
To ensure clarity, we request that Technical Specification 1.4 be amended to include the word"supports" after the word"lubrication", as shown in Attachment 1 and that this page become a part of our Application submitted on July 24, 1987.In Attachment 2, RG&E is providing an explanation of two additional issues: steam generator snubber seal service life monitoring, maintenance and documentation; and mechanical snubber degradation monitoring and preventive maintenance.
These explanations                         provide the reasons for differences between the Ginna Station snubber Technical Specifications and the "Standard Technical Specifications".
These explanations provide the reasons for differences between the Ginna Station snubber Technical Specifications and the"Standard Technical Specifications".
Very truly yours, d~
Attachments Very truly yours, d~Bruce A.Snow Superintendent Nuclear Production goe I 8806300083 88062i PDR ADOCK 05000244 P DCD}}
Bruce A. Snow Superintendent Nuclear Production goe I Attachments 8806300083 88062i PDR ADOCK 05000244 P                                   DCD}}

Revision as of 20:44, 29 October 2019

Forwards Corrected Tech Spec 1.4, Operable-Operability, Adding Word Supports After Word Lubrication & Explanation of Addl Issues Re Monitoring & Documentation,Per Util 870724 Application for Amend to License DPR-18
ML17251A135
Person / Time
Site: Ginna Constellation icon.png
Issue date: 06/21/1988
From: Snow B
ROCHESTER GAS & ELECTRIC CORP.
To: Stahle C
NRC, NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML17251A136 List:
References
NUDOCS 8806300083
Download: ML17251A135 (3)


Text

, ACCELERATED DFRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8806300083 DOC.DATE: 88/06/21 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet, Ginna Nuclear Plant, Unit 1, Rochester G 05000244 NAME AUTHOR AFFILIATION 'UTH.

SNOW,B.A. Rochester Gas & Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Requests that Tech Spec 1.4 be amended to include word "supports" after word "lubrication."

DISTRIBUTION CODE: AOOID TITLE: OR Submittal:

COPIES RECEIVED:LTR ( ENCL ~

General Distribution SIZE: 3+ 2 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 8

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-3 LA 1 0 PD1-3 PD 5 5 A STAHLE,C 1 1 D

INTERNAL: ARM/DAF/LFMB 1 0 NRR/DEST/ADS 7E 1 1 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 D

NRR/DEST/MTB 9H 1 1 NRR/DEST/RSB 8E 1 1 NRR/DOEA/TSB 11 1 1 NRR/PMAS/ILRB12 1 1 STRACT 1 1 OGC 15-B-18 1 0 8 REG F 01 1 1 RES/DE/EIB 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 D:,"

A D

9 ~

TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 19 I

t

e I SIIIFIII IZIEif AIVO i IIIIIIIIIIII IIIIIIIIIIII ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 TELEPHONE June 21, 1988 AREA CODE 716 546-2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Mr. Carl Stahle PWR Project Directorate No. 1 Washington, D.C. 20555

Subject:

Technical Specification Testing Requirements for Snubbers R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Stahle:

As a result of a June 7, 1988 telecon between RG&E and NRC personnel, RG&E wishes to clarify one aspect of the subject Technical Specification Change request, as submitted by letter dated. July 24, 1987. Operability of certain snubbers under cold shutdown conditions is required, as the result of the present system operability requirements of Technical Specification 3.1.1.1.e. To ensure clarity, we request that Technical Specification 1.4 be amended to include the word "supports" after the word "lubrication", as shown in Attachment 1 and that this page become a part of our Application submitted on July 24, 1987.

In Attachment 2, RG&E is providing an explanation of two additional issues: steam generator snubber seal service life monitoring, maintenance and documentation; and mechanical snubber degradation monitoring and preventive maintenance.

These explanations provide the reasons for differences between the Ginna Station snubber Technical Specifications and the "Standard Technical Specifications".

Very truly yours, d~

Bruce A. Snow Superintendent Nuclear Production goe I Attachments 8806300083 88062i PDR ADOCK 05000244 P DCD