ML17263A625

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Submits 1994 Steam Generator Eddy Current Examination 15-day Summary Rept for Re Ginna Nuclear Plant,Including Summary of Number of Repairs Required Resulting from Insp Performed During 1994 Outage
ML17263A625
Person / Time
Site: Ginna Constellation icon.png
Issue date: 04/11/1994
From: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
To: Andrea Johnson
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9404200188
Download: ML17263A625 (5)


Text

ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM

,REGULATORY XNFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9404200188 DOC.DATE: 94/04/11 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 AFFXLIATION JOHNSON,A.R.

Project Directorate I-3

SUBJECT:

Submits 1994 Steam Generator Eddy Current Examination 15-day summary rept for RE Ginna Nuclear Plant, including summary of number of repairs required resulting from insp performed during 1994 outage.

DISTRIBUTION CODE:

A001D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal:

General Distribution R

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

05000244 A

RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: NRR/DE/EELB NRR/DRCH/HICB NRR/DSSA/SPLB NUDOCS-ABSTRACT OGC/HDS1 EXTERNAL: NRC PDR COPIES LTTR ENCL 1

1 2

2 1

1 1

1 1

1 1

1 1

0 1

1 RECIPIENT ID CODE/NAME PD1-3 PD NRR/DORS/OTS B NRR/DRPN NRR/DSSA/SRXB OC FDCB RE F

01 NSIC COPIES LTTR ENCL 1

1 1

1

'1 1

1 1

1 0

1 1

1 1

D D

D NOTE TO ALL"RIDS" RECIPIENTS:

A D

D PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LIS1S FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED:

LTTR 16 ENCL 14

IIIIIIIII'IIIIIIIZ Arm i

Srr@III IIIIIIIII i zzzzllk uziizuzi-ROCHESTER GAS AND ELECTRIC CORPORATION o

89 EAST AVENUE, ROCHESTER N.Y. 14649.0001 ROBERT G MECREDY Vice President Clnna Nudear Production lKLEPHONE AREACODE 71B 54e 2700 April 11, 1994 U.S. Nuclear Regulatory Commission Document Control Desk Attn:

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

20555

Subject:

1994 Steam Generator Eddy Current Examination 15 Day Summary Report R.E.

Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Johnson:

In accordance with Appendix B, Section 11, Paragraph 2.8.2 of the Ginna Station Quality Assurance

Manual, we are submitting the 1994 Steam Generator Eddy Current Examination 15-day Summary Report for R.

E.

Ginna Nuclear Power Plant.

This report, Attachment A,

summarizes the number of repairs required resulting from inspections performed during the 1994 outage and the number of tubes which have been plugged or sleeved.

Very truly yours, Robert C. Mecredy Attachment GAH/326 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 USNRC Ginna Senior Resident Inspector 9404200188 940411 PDR 'DOCK 05000244 9 :

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~ p ATTACHMENT A Pursuant to Section 11, Paragraphs 2.8.2 of Appendix B of the Ginna Station Quality Assurance

Manual, the following information is submitted in regard to the number of tubes requiring repair in each steam generator:

At>

S G

IIB It S

G Number of Tubes Plugged Number of Tubes Sleeved Total Repairs 21 143 164 31 103 134 Of the 21 tubes plugged in "A"

Steam Generator 15 were CE mechanical plugs, 5 were CE welded plugs and 1 was a BGW explosive sleeve plug (A parent tube defect in the sleeve upper weld zone was discovered during baseline eddy current examination of Row 9, Col 59).

In "B" Steam Generator, 29 CE mechanical plugs were installed and 2

CE welded plugs were installed on the hot leg side.

Only 30 mechanical plugs were installed on the cold leg side due to the fact that. the BGW explosive tube plug in Row 42, Col 56 was removed from the hot leg as a result of an indication found during the eddy current examination.

The breakdown of the number of repairs required by defect mechanism is listed below:

II All S

G IIB II $

G Roll Transition PWSCC Crevice IGA/SCC PWSCC in Roll Region Obstructed Sleeves PWSCC in BGW Explosive Plugs Sludge Pile Thinning/Wastage 120

  • 42
  • 66
  • 74 *
  • Includes tubes with both PWSCC and IGA/SCC

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