ML13308B792

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Forwards Emergency Operating Instructions for Facilities Re LOCA Steam Generator Tube Rupture,Loss of Feedwater & Steam Generator Level & Determination of Adequate Core Cooling
ML13308B792
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 11/12/1980
From: Baskin K
Southern California Edison Co
To: Miraglia F
Office of Nuclear Reactor Regulation
Shared Package
ML13308B793 List:
References
NUDOCS 8011250460
Download: ML13308B792 (2)


Text

'UL~fJ INRTllU DIT inUfiJ rE) (RUDS)

ACCESSION Ni3R:BO11250460 0J0C,DATE:

/111/12 FcAf4RIZEZ 0

DJCET FACIL:50-361 3an Onofre Nuclear Station, Jnit 2, 3outhern Californ. Ji0003b1 50-362 3an Onofre u

ulear station, Unit 3, 3outrnern Califor n 0QO AU TH, AE A TH AF I LI 4 T I J N SA SKIN,.P.

Soutmern

.alifornia Edison Co.

R EC I P,1AAE RECI.P I E jT AFFiL Iwf

  • IR A GLLIA,F.

licensing dranch 3

SU6JECT: Forwards emergency ooerating instructions for facilities re LOCA stman qenerator tube ruoture,loss of feedwater

% stea generator level determination of adequate core cooling.

TIrLE : P'AR /F3Ar 4A1OTS ana ReIated Corresoondence

-quES:ena all FSAR aends to L

hndler.

5000361 1 cy:J

  • Mianrcnett (legion V)

Send all jFSR E ER -nends to L Chan1ler 0003 1 cy:J

-4ancnett (Region V)

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NOV 2 TOTAL NU'-i*5EfR UF CPIES RE JIRED: LT TR ENCL

Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD. CALIFORNIA 91770 K. P. BASKIN November 12 1980 TELEPHONE NAGER OF NUCLEAR ENGiNEERING, (213) 572-1401 SAFETY, AND LiCENSING Director, Office of Nuclear Reactor Regulation Attention: Mr. Frank Miraglia, Branch Chief Licensing Projects Branch 3 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:

Subject:

Docket Nos. 50-361 and 50-362 San Onofre Nuclear Generating Station Units 2 and 3 Enclosed are forty (40) copies of the following four Emergency Operating Instructions (EQI) for San.0nofre Nuclear Generating Station, Units 2&3:

o Loss of Coolant Accident o Steam Generator Tube Rupture o Loss of Feedwater and Steam Generator Level o Determination of Adequate Core Cooling Based upon clarification provided by Mr. D. Beckham of the NRC Procedures and Test Review Branch (PTRB) to Mr. F. R. Nandy of SCE Nuclear Licensing during a September 16, 1980 meeting with the NRC Human Factors Engineering Branch in Bethesda, SCE expedited completion of the four EDI's in order to facilitate the NRC PTRB review schedule for San Onofre Units 2&3.

During a telephone conversation on November 12, 1980 among Mr. Beckham, Mr. Nandy and Mr. H. E. Morgan (SCE Nuclear Operations), it was agreed that an operator walk through of the four EOI's utilizing the CE simulator would be schedulea between December 13 and December 19, 1980.

If you have any questions or comments concerning this matter, please contact me.

Very truly yours, Enclosure 5 0 4