ML17250B174: Difference between revisions

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| issue date = 05/23/1990
| issue date = 05/23/1990
| title = Application for Amend to License DPR-18,revising Tech Spec Pages 4.2-2 & 4.2-4 Re Inservice Insp & Basis Section Concerning Steam Generator Tube & Sleeve Repair Criteria
| title = Application for Amend to License DPR-18,revising Tech Spec Pages 4.2-2 & 4.2-4 Re Inservice Insp & Basis Section Concerning Steam Generator Tube & Sleeve Repair Criteria
| author name = MECREDY R C
| author name = Mecredy R
| author affiliation = ROCHESTER GAS & ELECTRIC CORP.
| author affiliation = ROCHESTER GAS & ELECTRIC CORP.
| addressee name = JOHNSON A R
| addressee name = Johnson A
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000244
| docket = 05000244
Line 14: Line 14:
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS
| page count = 4
| page count = 4
| project =
| stage = Request
}}
}}


=Text=
=Text=
{{#Wiki_filter:A,CCELERATED DI UTION DEMONSTPA.TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9005310499 DOC.DATE: 90/05/23 NOTARIZED:
{{#Wiki_filter:A,CCELERATED DI                       UTION DEMONSTPA.TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
ACCESSION NBR:9005310499             DOC.DATE: 90/05/23     NOTARIZED: NO         DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester                 G 05000244 AUTH. NAME           AUTHOR AFFILIATION MECREDY,R.C.         Rochester Gas 6       Electric Corp.
Rochester Gas 6 Electric Corp.RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
RECIP.NAME           RECIPIENT AFFILIATION JOHNSON,A.R.             Project Directorate I-3                                           R
Project Directorate I-3 DOCKET 05000244 R  


==SUBJECT:==
==SUBJECT:==
Application for amend to License DPR-18,revising Tech Spec Page 4.2-4.DISTRIBUTION CODE: A054D COPIES RECEIVED:LTR ENCL SIZE: TITLE: OR Submittal:
Application for amend to License DPR-18,revising             Tech Spec           I Page   4.2-4.
Steam Generator Sleeving Review for PWR's NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
DISTRIBUTION CODE: A054D COPIES RECEIVED:LTR                 ENCL     SIZE:               D TITLE: OR Submittal: Steam Generator Sleeving Review for PWR's S
I D S 05000244/RECIPIENT ID CODE/NAME PDl-3 LA JOHNSON,A INTERNAL: AEOD NRR/DOEA/OGCB11 NRR/PMAS/ILRB12 OC/L M FILE EXTERNAL'PDR NSIC COPIES LTTR ENCL 1 0 1 1 1 1 1 0 1 0 1 0 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD1-3 PD NRR/DET/ECMB 9H NRR/DST/SPLB 8D NUDOCS-ABSTRACT OGC/HDS2 RES/DSIR/EIB NRC PDR COPIES LTTR ENCL 3 3 1 0 1 0 1 1 1 1 1 1 1 1 D D D NOTE TO ALL"RIDS" RECIPIENTS:
NOTES:License Exp date       in accordance with 10CFR2,2.109(9/19/72).             05000244
PLEASE HELP US TO REDUCE WASTE!CONTACI'HE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 18 ENCL 12/0 D NEw AaaK Awfu YORK';5YAYE///!////////I g!///I/////I
                                                                                              /
/I///////'////////////
RECIPIENT               COPIES            RECIPIENT          COPIES ID CODE/NAME            LTTR ENCL        ID CODE/NAME       LTTR ENCL PDl-3 LA                     1    0    PD1-3 PD                3  3            D JOHNSON,A                   1    1 D
//////Z////I//////I ZZ ROCHESTER GAS AND ELECTRIC CORPORATION o eg EAST AVENUE, ROCHESTER, N Y.1464g 0001 May 23, 1990 TELEPHONE AREA COOK YIO 546.2700 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Allen R.Johnson Project Directorate I-3 Washington, D.C.20555  
INTERNAL: AEOD                         1    1    NRR/DET/ECMB 9H        1    0 NRR/DOEA/OGCB11             1    0    NRR/DST/SPLB 8D        1    0 NRR/PMAS/ILRB12             1    0    NUDOCS-ABSTRACT        1    1 OC/L M                     1     0     OGC/HDS2                1   1 FILE                    1     1     RES/DSIR/EIB           1   1 EXTERNAL'PDR                            1     1     NRC PDR                1   1 NSIC                        1     1 D
                                                                                              /
0 D
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACI'HE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR             18   ENCL   12
 
NEw
          ///!////////I     !///I/////I                                                             AaaK Awfu g
        /I/// ////'////////////
    //////Z           ////I//////I ROCHESTER GAS AND ELECTRIC CORPORATION o eg EAST AVENUE, ROCHESTER, N Y. 1464g 0001 ZZ            YORK ';
5YAYE May 23, 1990                     TELEPHONE AREA COOK YIO 546.2700 U.S. Nuclear Regulatory Commission Document                         Control Desk Attn: Allen R. Johnson Project Directorate I-3 Washington, D.C.                               20555


==Subject:==
==Subject:==
Technical Specification Paragraphs 4.2.1.4.a, 4.2.1.4.b and Basis R.E.Ginna Nuclear Power Plant Docket No.50-244  
Technical Specification Paragraphs     4.2.1.4.a, 4.2.1.4.b and Basis R.E. Ginna Nuclear Power Plant Docket No. 50-244
 
==Dear Mr. Johnson:==
 
License Amendment No.                              35 (issued April 24, 1989) added paragraphs 4.2.1.4.a, 4.2.1.4.b                              and a second paragraph in the Basis section regarding steam generator tube and sleeve repair criteria.
License Amendment No.                                37 (issued May 30, 1989) regarding the Inservice Inspection Program for snubbers, also made changes to Section 4.2 of the Technical Specifications.
The request for License Amendment for the snubber ISI Program was submitted prior to the request for steam generator tube and sleeve repair criteria. That License Amendment application consequently did not include paragraphs 4.2.1.4.a and 4.2.1.4.b or paragraph 2 of the Basis. When Amendment No. 37 was approved, page 4.2-2 was approved without paragraphs 4.2.1.4.a and 4.2.1.4.b and page 4.2-3 was approved without the complete Basis section.
RGGE requests that Technical Specification page 4.2-2 and new page 4.2-4, containing the remainder of the Basis, be issued reinstating these three approved paragraphs (page 4.2-3 remains the same).
In the meantime, RGGE has been, and will continue to, abide by the provisions of approved License Amendment No. 35 paragraphs 4.2.1.4.a and 4.2.1.4.b.
Very truly yours, Robert C. Me redy Division  Manager Nuclear Production GJWN105                                                                                        o~4 9005320499 900523 nOOCK 05000Z44 P                PDC
 
      ~c 1
E I


==Dear Mr.Johnson:==
xc: Mr. Allen R. Johnson (Mail Stop 14Dl)
License Amendment No.35 (issued April 24, 1989)added paragraphs 4.2.1.4.a, 4.2.1.4.b and a second paragraph in the Basis section regarding steam generator tube and sleeve repair criteria.License Amendment No.37 (issued May 30, 1989)regarding the Inservice Inspection Program for snubbers, also made changes to Section 4.2 of the Technical Specifications.
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}}
The request for License Amendment for the snubber ISI Program was submitted prior to the request for steam generator tube and sleeve repair criteria.That License Amendment application consequently did not include paragraphs 4.2.1.4.a and 4.2.1.4.b or paragraph 2 of the Basis.When Amendment No.37 was approved, page 4.2-2 was approved without paragraphs 4.2.1.4.a and 4.2.1.4.b and page 4.2-3 was approved without the complete Basis section.RGGE requests that Technical Specification page 4.2-2 and new page 4.2-4, containing the remainder of the Basis, be issued reinstating these three approved paragraphs (page 4.2-3 remains the same).In the meantime, RGGE has been, and will continue to, abide by the provisions of approved License Amendment No.35 paragraphs 4.2.1.4.a and 4.2.1.4.b.
Very truly yours, Robert C.Me redy Division Manager Nuclear Production GJWN105 9005320499 900523 nOOCK 05000Z44 P PDC o~4
~c 1 E I xc: Mr.Allen R.Johnson (Mail Stop 14Dl)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}}

Latest revision as of 08:54, 10 November 2019

Application for Amend to License DPR-18,revising Tech Spec Pages 4.2-2 & 4.2-4 Re Inservice Insp & Basis Section Concerning Steam Generator Tube & Sleeve Repair Criteria
ML17250B174
Person / Time
Site: Ginna Constellation icon.png
Issue date: 05/23/1990
From: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
To: Andrea Johnson
Office of Nuclear Reactor Regulation
Shared Package
ML17250B175 List:
References
NUDOCS 9005310499
Download: ML17250B174 (4)
v • d • e


Text

A,CCELERATED DI UTION DEMONSTPA.TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9005310499 DOC.DATE: 90/05/23 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas 6 Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R. Project Directorate I-3 R

SUBJECT:

Application for amend to License DPR-18,revising Tech Spec I Page 4.2-4.

DISTRIBUTION CODE: A054D COPIES RECEIVED:LTR ENCL SIZE: D TITLE: OR Submittal: Steam Generator Sleeving Review for PWR's S

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 PDl-3 LA 1 0 PD1-3 PD 3 3 D JOHNSON,A 1 1 D

INTERNAL: AEOD 1 1 NRR/DET/ECMB 9H 1 0 NRR/DOEA/OGCB11 1 0 NRR/DST/SPLB 8D 1 0 NRR/PMAS/ILRB12 1 0 NUDOCS-ABSTRACT 1 1 OC/L M 1 0 OGC/HDS2 1 1 FILE 1 1 RES/DSIR/EIB 1 1 EXTERNAL'PDR 1 1 NRC PDR 1 1 NSIC 1 1 D

/

0 D

NOTE TO ALL "RIDS" RECIPIENTS:

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

TOTAL NUMBER OF COPIES REQUIRED: LTTR 18 ENCL 12

NEw

///!////////I  !///I/////I AaaK Awfu g

/I/// ////'////////////

//////Z ////I//////I ROCHESTER GAS AND ELECTRIC CORPORATION o eg EAST AVENUE, ROCHESTER, N Y. 1464g 0001 ZZ YORK ';

5YAYE May 23, 1990 TELEPHONE AREA COOK YIO 546.2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson Project Directorate I-3 Washington, D.C. 20555

Subject:

Technical Specification Paragraphs 4.2.1.4.a, 4.2.1.4.b and Basis R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Johnson:

License Amendment No. 35 (issued April 24, 1989) added paragraphs 4.2.1.4.a, 4.2.1.4.b and a second paragraph in the Basis section regarding steam generator tube and sleeve repair criteria.

License Amendment No. 37 (issued May 30, 1989) regarding the Inservice Inspection Program for snubbers, also made changes to Section 4.2 of the Technical Specifications.

The request for License Amendment for the snubber ISI Program was submitted prior to the request for steam generator tube and sleeve repair criteria. That License Amendment application consequently did not include paragraphs 4.2.1.4.a and 4.2.1.4.b or paragraph 2 of the Basis. When Amendment No. 37 was approved, page 4.2-2 was approved without paragraphs 4.2.1.4.a and 4.2.1.4.b and page 4.2-3 was approved without the complete Basis section.

RGGE requests that Technical Specification page 4.2-2 and new page 4.2-4, containing the remainder of the Basis, be issued reinstating these three approved paragraphs (page 4.2-3 remains the same).

In the meantime, RGGE has been, and will continue to, abide by the provisions of approved License Amendment No. 35 paragraphs 4.2.1.4.a and 4.2.1.4.b.

Very truly yours, Robert C. Me redy Division Manager Nuclear Production GJWN105 o~4 9005320499 900523 nOOCK 05000Z44 P PDC

~c 1

E I

xc: Mr. Allen R. Johnson (Mail Stop 14Dl)

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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