ML19317F749

From kanterella
Revision as of 00:49, 12 December 2019 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Notifies of Incorrect Uncertainty Value in Util 780424 Ltr to Nrc.Correct Value 2.2%.Forwards, Determination of Total Reactor Coolant Flowrate & Its Accuracy for Facility & Statement Re Secondary Sys Foreign Matl & Deposits
ML19317F749
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 05/26/1978
From: Roe L
TOLEDO EDISON CO.
To: Stolz J
Office of Nuclear Reactor Regulation
Shared Package
ML19317F750 List:
References
NUDOCS 8001230653
Download: ML19317F749 (2)


Text

i l NRC romu 196 $ u.s. NuctsAa nzutarcmv con .:iissicN occxr* NuM aan

} p1 go ,34/6

'

mei , _

'* * '"

NRC DISTRIBUTION ron PART 50 COCKET MATERIAL

! TO: FROM: cars oF CCCUMENT Mr. John F. Stolz Toledo Edisonn m f,,g,,,

t Toledo, Ohio 43652 cars mEcEivEo l Lowell E. Roe 05/30/78 2Larran CuoronizEo Pace iNPursoAM NuMSER CP CCPIES RECElV3o (cMiGIN AI. 2bNct.Asalpito C cC*Y IAILdPO l CESCRIPT1oM ENCLOSu RE

i Forwarding info re determination of

! total RC Flowrate and its accuracy for Subject

( Subject Facility...w/att " Statement Addressing

) Foreign Material and Deposits in Secondary System."

l I

! 1p 75p 6

6 l

!

,

!

!

i

! PLANT NAME : DAVIS-BESSE UNIT 1 ,

l Jcm 05/30/78 1 3 WCL lRePED NV)'l e u<,

, e 3 er-.y FOR ACTION /INFORMATION ENVIRON'4 ENTAL / l

!/ s e c Tc, Men AD- trf L/4M 44/A ASSIGNED AD: V. V00RC (L*R)

!^ Q ANCH CHII?* 2rf STD L 4 BRANCH CHIZ?: -

'/ I PROJECT '4ANAGER: I < m FNG,45 I ee0JTC* MANAGER

  • flLIC. ASST: LDit ! E MPI TD# l f 70 - ACE **

- I i i i 1 3. MARLESS

,

fA INTERNAL DISTRIBUTICN ,

/iM ?T7 FM i, eve *vv9 eATT7"? I PLriT SYS* EMS I ISI*E SAFETY & I

//'d /l o. v i~enN 42 A *TSESCO 47%L lENVIRCN ANALYSIS t

/l* CI ( 2.) /l scuRcE3ER 476  ! neyApr yA M DENTON & '4ULLER trR i

% et_, t.r-M' ,

6 i e s mr3e i teetycur-er ,  ;

l 1 GOSS!CX C STAFF ENGINEERING l Tre0LITO I i 1

'/i vprattro r7I / 'crTnw- Z772- I e onSA i It'ivv20N TrCH i i !vvoc 909NAv i iERNST I fl . s er 1.78 i c '=wr TT. never-TNG ReAC*0RS IBALLARD I

/i qnvn L TA2. I D i'd'ET T / S *T7

  • 0 - 1 T1E". 8 YOf5GELOCD  !

! I '/l e'e;Tur= r 4 T31' l  !

I Sco 'vC* 'Tr: AGE'ENT I suAo

'

ceACTOR SAFETT j ,

g 7--: *eCH i i iev0VuotT /_' goSS gAER } tcAyyrt , ( 2) i I ?. COLE *NS / NOVAK I23' 9U*LER I i

-

'

I=ctsTOs '

/ ROS*TOCrf fl GRre S ('Z- 3 I is- ANALY?!S I '3r* **

-

/ CHECK ( Al 1 M VOL'MER l M l :

/ e-** eves i A- -

_

-

l 13t Ncy  ! -

4 i :: 1 AT c I I i iz cettr:S i i i I 9AL** VAN l i ivueGrR- I i i t or'w e7G l I i t EXTERNAL DISTRIBUTICN CCNTRCL NUMBER I A LFOR: /1ht.v' C o u re + v3+ e so- t g d "IC A :s:C i i i i l

o nm_

s mw.s e-

-

Kl x

i Rea (J. wurCHE T) ! l , ; -- 230 ,,.s ,

ri a Cyo

,

x... mA EcCRm W e i r0 ACRS l i i . i ' [f)  ;

. , . . , , . . . . , , . . _. ._ _. .

. _ _ . . . . _ _ - -

._.

.

-

- ,

. e jh { f)

TOLEDO EDISON Docket No. 50-346 LOWELL E. ROE Operating License No. F 3 I.N.'E.*ioom.a.

(4191 259-5242 May 26, 1978 Serial No. 436 ,

-

'

Director of Nuclear Reactor Regulations Attention: Mr. John F. Stolz, Chief Light Water Reactors Branch No.1 -

Division of Project Management ,

United States Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Stolz:

As a result of our review of the uncertainties in the determination of the reactor coolant flow rate at the Davis-Besse Nuclear Power Station Unit No. 1, we have found that the value for the uncertainty given in our letter to you dated April 24, 1978 (Serial No. 428) is incorrect. Attach-ment I to this letter shows that the actual uncertainty value is 2.2%.

Attachment 2 is a ** Statement Addressing Foreign Material and Deposits in Secondary System."

The uncertainties on the reactor coolant flow rate are incorporated in the technical specification changes given in the attachment to our letter to you dated May 26,1978 (Serial No. 439).

The reactor coolant flow rate uncertainty also impacts the treatment of the rod bow ef fect as addressed in our letter to Mr. Roger S. Boyd dated April 10, 1978 (Serial No. 426).

Yours very truly,

,

f Attachment jh c/11 f THE TOLECO EDISCN COMPANY ECISCN PLAZA 300 MADISON AVENUE TOLECO. CHIO 43652