ML19317F740

Forwards Corrected Page 7-24a of 780526 Revision 1 to Attachment 1 to OL Amend for Removal of Burnable Poison Rod & Orifice Rod Assemblies

ML19317F740
Person / Time
Site:	Davis Besse
Issue date:	06/02/1978
From:	Roe L TOLEDO EDISON CO.
To:	Stolz J Office of Nuclear Reactor Regulation
References
NUDOCS 8001230642
Download: ML19317F740 (3)

Text

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,l O fo 0 4 / '/ V REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-346 REC: STOLZ J F ORG: POC L E DOCDATE: 06/02/78 NRC TOLEDO EDISON DATE RCVD: 06/06/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 12 FORWARDING CORRECTED PAGE TO APPLICANT"S 05/26/78 SUBMITTAL CONSISTING OF AMEND TO OPERATING LIC FOR RENEWAL OF BURNABLE POISON ROD ASSEMBLIES AND ORIFICE ROD ASSEMBLIES.

PLANT NAME: DAVIS BESSE - UNIT 1 REVIEWER INITIAL:

XJM DISTRIBUTOR INITI AL: (

oc*oo************ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ******************

NOTES:

1.

SEND ALL AMENDMENTS TO J.

ROE PSAR/FSAR AMDTS AND RELATED CORESPONDENCE (DISTRIBUTION CODE BOO 1)

FOR ACTION:

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1R ENGLE**W/ ENCL LIC ASST HYLTON**LTR ONLY INTERNAL:

REG FILC W/ ENCL NRC PDR**W/ ENCL

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THE END

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800123 o hg

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%mm EDISON LOWELL E. ROE Docket No. 50-346 5.c,.... c.. -.a.

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Operating License No. NPF-3 Serial No. 442 June 2, 1978 Director of Nuclear Reactor Regulation Attention:

Mr. John F. Stolz, Chief Lightwater Reactors Branch No. 1 Division of Project Management United States Nuclear Regulatory Commission Washington, D.C.

20555

Dear Mr. Stolz:

As discussed between our Mr. F. R. Miller and your Licensing Project Manager, Mr. Leon Engle on May 30, 1978, Page 7-24a of the Revision 1 to the " Davis-Besse Nuclear Power Station Unit No. 1, Attachment 1 to Amend Operating License For Removal of Burnable Poison Rod Assemblies and Orifice Rod Assemblies," as submitted to you in my letter dated May 26, 1978 is in error. Twelve copies of the corrected page are attached. We apologize for any inconvenience this error may have incurred.

Very truly yours, ks c/8 Attachments Y

.. Jg.

bo*'&

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THE TOLECO EDISCN COMPANY EDISCN PLAZA 300 MACISCN AVENUE TOLEDO. CHIO 43652 4 hetsk 5

T E

TABLE 3.2-1

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5 DNB MARGItl

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LIMITS a

Four Reactor Three Reactor One Reactor Coolant Pumps Coolant Pumps Coolant Pump c.5 Parameter Opera ting Opera tinq Operating in Each Loop

-4 7 -"

Reactor Coolant llot Leg

< 611.1

< 611.l II)

< 611.1 y

Temperature T *F o

11 ReactorCoolantPressure,psig.I2)

> 2062.7

> 2058.7(I)

> 2091.4 Reactor Coolant Flow Rate, gpm (3)

>_ 395,700

> 296,500 195,200 l

u i

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\\

03 Applicable to the loop with 2 Reactor Coolant Pumps Operating.

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I2) Limit not applicable during either a TilERMAL POWER ramp increase in excess of 5% of RATED TilERMAL POWER per minute or a TilERMAL POUER step increase of greater than 10%

of RATED TitERMAL POWER.

(3) These flows include a flow rate uncertainty of 2.2%.

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