ML17309A653

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Rev 1 to FIG-2.0, Figure Sdm. with 990413 Ltr
ML17309A653
Person / Time
Site: Ginna Constellation icon.png
Issue date: 04/13/1999
From: Widay J
ROCHESTER GAS & ELECTRIC CORP.
To: Vissing G
NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
FIG-2.0, NUDOCS 9904210180
Download: ML17309A653 (3)


Text

CATEGORY 1 REGULAR Y INFORMATION DISTRIBUTI . SYSTEM (RIDS)

ACCESSION NBR:9904210180 DOC.DATE: 99/04/13 NOTARIZED: NO DOCKET I FACIL:50-.244 Robert .Emmet Ginna Nuclear Plant, Unit 1, Rochest'er G 05000244 AUTH. i%TAME . AUTHOR. AFFILIATION WIDAY,J.A. Rochester Gas & Electric Corp.

RECIP.NAME VISSING,G.S.

RECIPIENT AFFILIATION g

SUBJECT:

Forwards revised Ginna Station EOPs.,

DISTRIBUTION CODE: A002D COPIES RECEIVED:LTR ) ENCL i SIZE:

TITLE: OR Submittal:Inadequate Core Cooling (Item II.F.2) GL 82-28 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 LPD1-1 PD 1 1 VISSING,G. 1 1 INTERNAL 1 1 NRR/DSSA/SRXB 1 1 RES DE 1 1 RES/DET/EIB 1 1 RES/DSIR/RPSB 1 1 EXTERNAL: NOAC NRC PDR 1 1 D

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 TOTAL NUMBER OF COPIES REQUIRED: LTTR 9 ENCL 9

r/ /////I/////I j I/I//ZS

'///// .I / i'//tt/I ROCHESTER GASAND ELECTRIC CORPORATION o 89EASTA VENUE~ ROCHESTER~ N. Y. 14649%001 JOSEPH A. WIDAY TELEPHONE Plont Monogor AREA CODE 71B 546.2700 Gfnno Nuclear Plont April 13, 1999 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate l-1 Washington, D.C. 20555

Subject:

Emergency Operating Procedures R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Vissing:

As requested, enclosed are Ginna Station Emergency Operating Procedures.

Very truly yours, s h A. Widay JAW/jdw /g xc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Ginna USNRC Senior Resident Inspector Enclosure(s):

FIG-2.0, Rev. 1 P:

99042iOi80 9'904i3 PDR ADQCK 05000244I PDR"

'i...,,

fOP: TITLf:

.i FIG-2.0 REV: 1 FIGURE SDM PAGE 1 of 1

+ /8+

1

,Responsible Manager Date FIGURE SDM NOTE o Curve includes allowance for one stuck rod. Add 100 ppm for each additional stuck rod.

o To obtain core burnup, use PPCS point ID BURNUP.

BORON CONCENTRATION (PPH) 1800 BORON INCREMENTS 20 PPH 1600 1400 ADEQUATE SOM 1200 100 PPH CONSERVATISM'NCLUOEO 1000 800 600 400 BORATE 200 BURNUP INCREMENTS 200 HWO/HTU 2000 4000 6000 8000 10000 12000 14000 16000 '8000 20000 CYCLE 28 BURNUP (MWD/HTU)