ML17262A569
| ML17262A569 | |
| Person / Time | |
|---|---|
| Site: | Ginna |
| Issue date: | 07/29/1991 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| IEB-89-001, IEB-89-1, NUDOCS 9108050133 | |
| Download: ML17262A569 (14) | |
Text
'ACCELERATED DISTRIBUTION DEMOIRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9108050133 DOC.DATE: 91/07/29 NOTARIZED-YES DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFXLIATION MECREDY,R.C.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFXLIATION'ocumentControl Branch (Document Control Desk)
SUBJECT:
Forwards response to Suppl 2 to NRC Bulletin 89-001, "Failure of Westinghouse Steam Generator Tube Mechanical Plugs." Item 2c inapplicable since Westinghouse mechanical plugs from Heat Batch NX-5222 not installed at facility.
DISTRIBUTION CODE:
IE31D COPIES RECEIVED:LTR l ENCL SIZE:
TITLE: Bulletin Response 89-01 re Failure of Westinghouse Steam en.
Mech.
T R
/
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: AEOD/DOA NRR/DET/EMCB 9H NRR/DOEA/OEAB11 NRR/DREP/PEPB9D NRR/PMAS/ILRB12 RES/DSIR/EIB EXTERNAL: NRC PDR COPIES LTTR ENCL 1
1 1
1 1.
1 1
1 1
1 1
-1 1
1 1
1 1
1 RECIPIENT ID CODE/NAME PD1-3 PD AEOD/DSP/TPAB NRR/DET/EMEB 7E NRR/DOEA/OGCB11 2
REG FILE 0 RGN1 FILE= Ol NSIC COPIES LTTR ENCL 1
1 1
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D S
D NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOb,'I Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPXES REQUIRED:
LTTR 17 ENCL 17 D
D
ROCHESTER GAS AND ELECTRIC CORPORATION
~
89 EAST AVENUE, ROCHESTER N. Y. 14649-0001+.
ROBERT C, hkE( REDY Vice Pier tdenr Clnna Nuclear Pioduction TELEPHONE AREAcoDET le 546 2700 July 29, 1991 U.S. Nuclear Regulatory Commission Attn:
Document Control Desk Washingtoni D ~ C ~
20555
Subject:
Response
to Bulletin 89-01, Supplement 2
Failure of Westinghouse Steam Generator Tube Mechanical Plugs R.E.
Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Johnson:
NRC Bulletin 89-01, Supplement 2
requested that licensees verify installation of thermally treated inconel 600 steam generator tube mechanical plugs supplied by Westinghouse, and if applicable, address action Items 1 and 2a through 2f.
Enclosed is the Rochester Gas and Electric
Response
to actions requested.
Very truly yours, Robert C. Mecredy Subscribed and sworn to before me on this 29th day of July, 1991.
ek uAMES C. MoGUIRE NOTARYPUSUC, State ot New Yottt QuatIiedin Montoe County MIComnisske &pins Doc.mt,1@Z-P.tOSO.tOi3.~ vt07 5
AitOCI; 0:-t.'tt.to~2< 4 9
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(
U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector Ginna Station
I
References 1)
Addendum 2 to Revision 3 of Westinghouse Report WCAP-12244, "Steam Generator Tube Plug Integrity Summary Report",
June 1991 Res onse to Item 1
Rochester Gas
& Electric has reviewed the information provided by Westinghouse in Table 2 of Reference 1.
The listing of'hot and cold leg temperatures, the number of mechanical plugs installed, date of installation and plug heat-batches was correct for plant conditions prior to the 1989 Refueling Outage.
- However, during the 1989 Refueling, Outage, Rochester Gas
& Electric removed seven (7)
Westinghouse mechanical plugs.
Consequently, Table 2 of Reference 1 needs to be revised as shown in Attachment 1.
The present number of Westinghouse mechanical plugs still installed in the Ginna steam generators is 176.
All of these plugs are located in Steam Generator "B" with a distribution of 89 hot leg plugs and 87 cold leg plugs.
Rochester Gas
& Electric has also reviewed the Westinghouse
'stimates on the Effective Full Power Days (EFPD) 'of cumulative operation for each set of plugs identified in Table 2 of Reference 1.
Due to the higher operating capacity factor (approximately 804) achieved by the Ginna Nuclear Power Plant during the 1980's, the Westinghouse estimates of remaining plug life as presented in Table 2 of Reference 1 are too high.
Using actual cycle burn-up
- data, the estimated cumulative operating time up through the 1991 Refueling Outage and remaining plug life in EFPDs have been revised.
These revised results are shown in Attachment 1.
Based upon the correlation for mechanical plug operating life developed by Westinghouse in Reference 1 for the various batches of plugs installed at Ginna and the cumulative operating time to
- date, the remaining EFPDs for the various batches of hot and cold leg plugs have been re-calculated and are presented in Attachment l.
Using the remaining EFPDs for the hot leg plugs and assuming an average cycle length of 300 EFPDs, Rochester Gas
& Electric has estimated the latest Refueling Outage year that would require either repair or remedial action for the installed-hot leg plugs.
These estimated years are presented in Attachment 1.
It should be noted that the tabulated repair years do not include the one year buffer that Westinghouse used in Reference 1 to calculate repair years.
Additionally, the calculated repair year is based upon an estimate of future plant operating performance.
Actual operating data for future cycles could affect the actual plug specific repair years.
1 I~
Res onse to Item 2a Rochester Gas
& Electric will perform appropriate remedial actions for all Westinghouse Alloy 600 mechanical plugs prior to their cumulative operating time exceeding the effective operating life for the plugs as provided by Westinghouse in Reference 1.
'es onse to Item 2b Due to actual operating data for the Ginna Nuclear Power Plant during the 1980's, the remaining EFPDs for the installed mechanical plugs is lower than the estimates provided by Westinghouse in Reference 1.
Actual operating time to date and revised remaining.
operating life for the installed mechanical plugs are provided in the response to Item 1.
These values in conjunction with future operating characteristics will be used by Rochester Gas
& Electric to determine when remedial actions are needed for the various batches of hot leg
. mechanical plugs installed at the Ginna Nuclear Power Plant.
Due to the extremely large effective lifetime calculated by Westinghouse in Reference 1 for all of the cold leg
- plugs, Rochester Gas
& Electric believes no future remedial actions will be required for these plugs.
Res onse to Item 2c This item is not'pplicable to Rochester Gas
& Electric since Westinghouse mechanical plugs from heat batch NX-5222 are not installed at the Ginna Nuclear Power Plant.
Res onse to Item 2d 0
Rochester Gas
& Electric discontinued installing Westinghouse Alloy 600 mechanical plugs after 1982.
Rochester Gas
& Electric will not install any Westinghouse Alloy 600 mechanical plugs in the future.
Res onse to Item 2e Cf Rochester Gas
& Electric undertakes any actions other than repair or replacement of mechanical plugs for insuring plug integrity, Rochester Gas
& Electric will inform the NRC of the actions taken and provide the NRC with the necessary technical justification to support these actions.
This information will be provided to the NRC at least 30 days before the end of the Refueling Outage in which these actions are performed.
'Res onse to Item 2f All remedial actions undertaken by Rochester Gas
& Electric to insure mechanical plug integrity will be reviewed prior to implementation to ensure that ALARA considerations have been properly addressed.
Rochester Gas F Electric Revisions to Table 2 of Addendum 2 of MCAP-12244, Rev.3 Plug Install Date Ho. of Plugs lnstal led Plug Heat Ho.
HL or CL Initial EFPD to Hin.
Ref.
Calc Date EFPD to Ref.
Date Remain.
EFPD to Hin.
Year to Repair Plug Plugs Removed 12-79 OC-80 OC-80 02.82 10-82 10-82 12-79 04-80 04-80 02-82 10-82 12-82 8
32 1
16 1
33 8
33 1
16 1
33 9789 9789 9789 1660 2386 2386 9789 9789 9789 1660 2386 2386 HL HL HL HL KL HL CL CL CL CL CL CL 4734 473C 473C 4734 4734 4734 53262 53262 53262 53262 53262 53262 3/91 3/91 3/91 3/91 3/91 3/91 3/91 3/91 3/91 3/91 3/91 3/91 3215 3120 3120 2615 2515 2515 3215 3120.
3120 2615 2515 2515 1519 1614 1614 2119 2219 2219 50047 50142 50142 50647 50747 50747 1996 1996 1996 1998 1998 1998 i2009
>2009
>2009
>2009
>2009
>2009 0
0 1
0 1
0 1
0 1
2 1
0
t
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