ML19319C135: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
 
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:-____ ._              _ _ .        __            _ _
{{#Wiki_filter:-____._
NRC ronu 195                                                                         U.s. NUCLL AR NEGULATOR Y COYMISS60N GGr KET NUMCC R v rcs                                                           ...                                                                    ,50-3 %
NRC ronu 195 U.s. NUCLL AR NEGULATOR Y COYMISS60N GGr KET NUMCC R v rcs
                        . NRC Dif?"RIBUTION roR . .,RT 50 DOCKET MATERI AL TO:       y y "e , "o ~.,       4                                            FROM:
,50-3 %
Toledo Edison Co                                   ATE OF DOCUME NT l-26'77 p'                                                     Toledo, Ohio                                                                         l f
NRC Dif?"RIBUTION roR..,RT 50 DOCKET MATERI AL TO:
  ~
4 FROM:
                      ~                                                                       L E Roc                                           DATc REctivEot,7 7,g               j pr LCITE n                           ONOTORIZCD                               PROP                         INPUT FORM                 NUMCE R CF COPIES RECEIV E D jfoniGIN A L                 jdU NC LAS$1F I E D OcoPy                                                                                                                                   < cine : s ip,ned DESCRIPTION                                                                                       ENCLCOURE                           ,,-                        (
ATE OF DOCUME NT y y "e, o ~.,
                                                                                                                                                .                  i     ,.'.
Toledo Edison Co l-26'77 l
i Ltr furnishing indo concerning provisions for detecting reactor coolant system leakage                                                       -
p' Toledo, Ohio f
                                                                                                                              .                                                      1 l
~
2p
~
                                                                                                                          . ACKNOWLEDGED                                             I
L E Roc DATc REctivEot,7 7,g j
                                                                                                                                  .                                                  c PLANT NAIC:                   Davis Besse 4t                                                                           -
pr CITE n ONOTORIZCD PROP INPUT FORM NUMCE R CF COPIES RECEIV E D L
2210VE                       !
jfoniGIN A L jdU NC LAS$1F I E D OcoPy
i l
< cine : s ip,ned DESCRIPTION ENCLCOURE
t i
(
SAFETY                                                       FOR ACTION < tNFO U.iATION             -. r!T '? n   l-2!     'I             ehr AS3IGNED AD:                                   _h;p I.I e                                   l     Asarc.mn f,n.
i i
O"2"'"!__C"C :                                                                  2                          -"'!c:c'I_C--- -
Ltr furnishing indo concerning provisions for detecting reactor coolant system leakage 1
l 2p
. ACKNOWLEDGED I
c PLANT NAIC:
Davis Besse 4t 2210VE i
l t
i SAFETY FOR ACTION < tNFO U.iATION
-. r!T '? n l-2!
'I ehr AS3IGNED AD:
_h;p I.I e l
Asarc.mn f,n.
lip ~ nn.
lip ~ nn.
                                                                            -           /c                       PROJECT "ANAGER:                                                   '
O"2"'"!__C"C :
      .2[1
2
      . J,JL      P;;o#.CT ASST. :E'.;;AGim:                                   4/j#oA                             LIC. ASST., :
-"'!c:c'I_C--- -
I INTERNAL DISTR 13UTION 6?FC T21                         -                  I         SYSTEMS SAFETY                   I !         Pi.A::T S"ST MS                       g g; SA E7; r
.2[1 P;;o#.CT E'.;;AGim:
      /INnC i DR, )
/c PROJECT "ANAGER:
      -                -                                          HEI. UZMA..N l/. l ;    UECSCO-
4/j#oA LIC. ASST., :
                                                                                                                  -                                    r::"r"u'
. J,JL ASST. :
                                                                                                                                                          -      a' S s- t "e
I INTERNAL DISTR 13UTION 6?FC T21 I
      / i I & C (::-                                               SCHROEnZR                         vI         Pg ano"A                           _;Lr;.c :; r. m- n kOELD_                                                                                         71         uTris GOSSIC: & STrF M:GI :EEnI::G                         /j     IPrOLITO                             E:ryI ;o_;pgg, M I.I'C                                             FACARRY                                 I KInr.XCD                             FRNST CAS"                                       fl ic:IGHT                                       I                                     I DALLAED liA1AUER                                 l/         SI3'EIL                                       OPERATIIC REACTORS               i SPA::Gil?
SYSTEMS SAFETY I !
l hat:LESS                                 i/ ; IsfI'CKI                                 I         STELLO                           j l i                                         I I                                           I SITE TEC!!.
Pi.A::T S"ST MS g g; SA E7; r
PROJE_CT I'AMAGEMENT                                 REACTOR SAFETY                   j l         OPERATING TECH.               /! cat?i1LL f.N T.0YD                                       /       ROS_S                                         EISENEUT                         I STEPP P. COLLINS                                 /       N07AK                                         SJ!,y)                               HtiD'AN HOUSTON                                     /       }:0$ZTeczy                                   BAgg PETERSON                                   /       CIIECZ                                       BLTT.ER                               SITE ANALYSIS MELT 2                                                                                             CRI'd!;S                     '/ VOIf t'!ER HELTCMES                                             AT & I                                                                     / EUNCII
/INnC i DR, )
      ~
HEI. UZMA..N l/. l UECSCO-r::"r"u' a' S t "e s-
SKCVil0LT                                           SALTZMAN                                                                   fiJ.' COLLI"5
/ i I & C (::-
                                                            ! ncTahc                                 i                                       7KnFc::R EXTEHNAL UlSTHIGUTiON                                                                     CON THOL NU'.16E R 3
SCHROEnZR vI Pg ano"A
f ron:fr.t            Ci. 4.         .Oa               NAi,_LAn:                                       BaconitAyE'_UAr. Lan.
_;Lr;. :; r. m-n c
      /.'lTIC :                                                 nEG v.It                                       in.RIKCON Lo3t;L)                                                     ;
kOELD_
dNsiC:                                                   LA enn                                                                                       g Astu:                                             consuLTA::TS                                                                                                       .
71 uTris GOSSIC: & STrF M:GI :EEnI::G
DAC)U.](>CYS g                          HE..M. wW- IE..b
' /j IPrOLITO E:ryI ;o_;pgg, M I.I'C FACARRY I
                                                              ...f)j~G           C N:         /[MY     ,-
KInr.XCD FRNST CAS" fl ic:IGHT I
Tl
I DALLAED liA1AUER l/
[.y m i _                                                                                             1                                                                       #
SI3'EIL OPERATIIC REACTORS i SPA::Gil?
Nill i ohm tt)r (2.pg))                                                                                                               .
l hat:LESS i/ ; IsfI'CKI I
[                                                                                                                             8001310 k                                     [         ,
STELLO j
l i I I I SITE TEC!!.
PROJE_CT I'AMAGEMENT REACTOR SAFETY j l OPERATING TECH.
/! cat?i1LL f.N T.0YD
/
ROS_S EISENEUT I STEPP P. COLLINS
/
N07AK SJ!,y)
HtiD'AN HOUSTON
/
}:0$ZTeczy BAgg PETERSON
/
CIIECZ BLTT.ER SITE ANALYSIS MELT 2 CRI' !;S
'/
VOI t'!ER d
f HELTCMES AT & I
/
EUNCII SKCVil0LT SALTZMAN fiJ.' COLLI"5
~
! ncTahc i
7KnFc::R EXTEHNAL UlSTHIGUTiON CON THOL NU'.16E R 3
f ron:fr. Ci. 4.
.Oa NAi,_LAn:
BaconitAyE'_UAr. Lan.
t
/.'lTIC :
nEG v.It in.RIKCON Lo3t;L) dNsiC:
LA enn g
Astu:
consuLTA::TS DAC)U.](>CYS HE..M. wW-IE..b...f)j~G C N:
/[MY Tl g
[.y m i _
1 Nill i ohm tt)r (2.pg))
[
8001310 k
[


                              ~
~
em4,. s
em4,. s
                                              /               ..
/
        .'                              ,!.          Launc'
Launc'
                                                                    -a
% >A ti
                                                % >A ti
/
                                        /                                           votee-ig      i-E e ISON
-a votee-E e ISON ig
                                        \$               .,
\\ $
Docket No. 50-346                   Jd. ,      $"        .
i-LOWELL E. ACE Jd.,
A>
Docket No. 50-346 A>
LOWELL E. ACE
# c. p,.....e.
                                                                                    # c. p,.....e.
sffN
sffN                                   . .c... . c ..or. .
..c.... c
Jtnuary 26, 1977                       %              e                     4.m -- ,s242 NY                                         .
..or..
V*
Jtnuary 26, 1977 e
Serial No. 193 Director of Nuclear Reactor Regulations                             g   40I pU,                 w Attention: lir. John F. Stolz, Chief                               i -                            .--
4.m --,s242 NY V*
Serial No. 193 40I pU Director of Nuclear Reactor Regulations g
w 27)g77,M Attention:
lir. John F. Stolz, Chief i
Light Water Reactor Branch No. 1
Light Water Reactor Branch No. 1
                                                                          $ E4 poew   27)g77,M n
' $ E4 poew n D %f Division of Project Management y
Division of Project Management                             y           D %f United States Nuclear Regulatory Commission                                                     g/
United States Nuclear Regulatory Commission g/
Washington, D.C. 20555
Washington, D.C.
                                                                                                *9 N
20555
*9 N


==Dear Mr. Stolz:==
==Dear Mr. Stolz:==
 
The following additional information is submitted with respect to provisions for detecting reactor coolant system leakage at the Davis-Besse Nuclear Power Station Unit 1.
The following additional information is submitted with respect to provisions for detecting reactor coolant system leakage at the Davis-Besse Nuclear Power Station Unit 1. The item was identified as outstanding review item (3) in the NRC's Safety Evaluation Report for Davis-Besse Unit 1.
The item was identified as outstanding review item (3) in the NRC's Safety Evaluation Report for Davis-Besse Unit 1.
The reactor coolant system leakage detection system includes the following:
The reactor coolant system leakage detection system includes the following:
a) The containment atmosphere particulate radioactivity monitoring system.
a)
b) The containment sump level / flow monitoring system.
The containment atmosphere particulate radioactivity monitoring system.
c)   The containment atmosphere gaseous radioactivity monitoring system.
b)
The containment sump level / flow monitoring system.
c)
The containment atmosphere gaseous radioactivity monitoring system.
Tae containment atmosphere particulate radioactivity monitoring system incorporates monitors which are seismic, redundant, with essential power supplies, and Q-listed.
Tae containment atmosphere particulate radioactivity monitoring system incorporates monitors which are seismic, redundant, with essential power supplies, and Q-listed.
The containment sump level and flow monitoring system design includes containment vessel normal sump totalized flow indication in the control room. This is shown on FSAR Figure 9-9, and is c' ;ignated FQI-2801.
The containment sump level and flow monitoring system design includes containment vessel normal sump totalized flow indication in the control room.
The flow element is scismic and is not redundant                   Instrumentation and power supplies are not essential. The transmitter is mounted seismically.
This is shown on FSAR Figure 9-9, and is c'
;ignated FQI-2801.
The flow element is scismic and is not redundant Instrumentation and power supplies are not essential. The transmitter is mounted seismically.
There are redundant normal sump levels and alarms, as shown on FSAR Figure 6-17, with control room indication. They are non-essential, no n-s e ismic.
There are redundant normal sump levels and alarms, as shown on FSAR Figure 6-17, with control room indication. They are non-essential, no n-s e ismic.
959 THE TCLECO ECrSCN CCMPANY     ECISCN PLAZA       3CO MACISCN AVENUE       TOLEOO. CHO 40652 i
959 THE TCLECO ECrSCN CCMPANY ECISCN PLAZA 3CO MACISCN AVENUE TOLEOO. CHO 40652 i
I
I


The contain=ent atmosphere gaseous radioactivity monitoring system utilizes monitors which are seismically qualified with essential power supplies. They are described in FSAR Section 12.1.4.
The contain=ent atmosphere gaseous radioactivity monitoring system utilizes monitors which are seismically qualified with essential power supplies. They are described in FSAR Section 12.1.4.
All systems used for reactor coolant system leakage detection can be calibrated during operation except the normal sump level.
All systems used for reactor coolant system leakage detection can be calibrated during operation except the normal sump level.
In addition to the systems described abovt, a reactor coolant system water inventory balance will be conducted at least once per 72 hours during steady state operation in Mode 1. This Surveillance Test ST5042.02 provides an accurar.e determination of RCS leakage.
In addition to the systems described abovt, a reactor coolant system water inventory balance will be conducted at least once per 72 hours during steady state operation in Mode 1.
This Surveillance Test ST5042.02 provides an accurar.e determination of RCS leakage.
Yours very truly, k
Yours very truly, k
db c/ll-12}}
db c/ll-12}}

Latest revision as of 19:44, 1 January 2025

Submits Addl Info Re RCS Leakage Detection Provisions.Rcs Leakage Detection Sys Includes Containment Atmosphere Particulate & Gaseous Radioactivity Monitoring Sys & Containment Atmosphere Gaseous Radioactivity Monitoring Sys
ML19319C135
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 01/26/1977
From: Roe L
TOLEDO EDISON CO.
To: Stolz J
Office of Nuclear Reactor Regulation
References
193, NUDOCS 8001310493
Download: ML19319C135 (3)


Text

-____._

NRC ronu 195 U.s. NUCLL AR NEGULATOR Y COYMISS60N GGr KET NUMCC R v rcs

,50-3 %

NRC Dif?"RIBUTION roR..,RT 50 DOCKET MATERI AL TO:

4 FROM:

ATE OF DOCUME NT y y "e, o ~.,

Toledo Edison Co l-26'77 l

p' Toledo, Ohio f

~

~

L E Roc DATc REctivEot,7 7,g j

pr CITE n ONOTORIZCD PROP INPUT FORM NUMCE R CF COPIES RECEIV E D L

jfoniGIN A L jdU NC LAS$1F I E D OcoPy

< cine : s ip,ned DESCRIPTION ENCLCOURE

(

i i

Ltr furnishing indo concerning provisions for detecting reactor coolant system leakage 1

l 2p

. ACKNOWLEDGED I

c PLANT NAIC:

Davis Besse 4t 2210VE i

l t

i SAFETY FOR ACTION < tNFO U.iATION

-. r!T '? n l-2!

'I ehr AS3IGNED AD:

_h;p I.I e l

Asarc.mn f,n.

lip ~ nn.

O"2"'"!__C"C :

2

-"'!c:c'I_C--- -

.2[1 P;;o#.CT E'.;;AGim:

/c PROJECT "ANAGER:

4/j#oA LIC. ASST., :

. J,JL ASST. :

I INTERNAL DISTR 13UTION 6?FC T21 I

SYSTEMS SAFETY I !

Pi.A::T S"ST MS g g; SA E7; r

/INnC i DR, )

HEI. UZMA..N l/. l UECSCO-r::"r"u' a' S t "e s-

/ i I & C (::-

SCHROEnZR vI Pg ano"A

_;Lr;. :; r. m-n c

kOELD_

71 uTris GOSSIC: & STrF M:GI :EEnI::G

' /j IPrOLITO E:ryI ;o_;pgg, M I.I'C FACARRY I

KInr.XCD FRNST CAS" fl ic:IGHT I

I DALLAED liA1AUER l/

SI3'EIL OPERATIIC REACTORS i SPA::Gil?

l hat:LESS i/ ; IsfI'CKI I

STELLO j

l i I I I SITE TEC!!.

PROJE_CT I'AMAGEMENT REACTOR SAFETY j l OPERATING TECH.

/! cat?i1LL f.N T.0YD

/

ROS_S EISENEUT I STEPP P. COLLINS

/

N07AK SJ!,y)

HtiD'AN HOUSTON

/

}:0$ZTeczy BAgg PETERSON

/

CIIECZ BLTT.ER SITE ANALYSIS MELT 2 CRI' !;S

'/

VOI t'!ER d

f HELTCMES AT & I

/

EUNCII SKCVil0LT SALTZMAN fiJ.' COLLI"5

~

! ncTahc i

7KnFc::R EXTEHNAL UlSTHIGUTiON CON THOL NU'.16E R 3

f ron:fr. Ci. 4.

.Oa NAi,_LAn:

BaconitAyE'_UAr. Lan.

t

/.'lTIC :

nEG v.It in.RIKCON Lo3t;L) dNsiC:

LA enn g

Astu:

consuLTA::TS DAC)U.](>CYS HE..M. wW-IE..b...f)j~G C N:

/[MY Tl g

[.y m i _

1 Nill i ohm tt)r (2.pg))

[

8001310 k

[

~

em4,. s

/

Launc'

% >A ti

/

-a votee-E e ISON ig

\\ $

i-LOWELL E. ACE Jd.,

Docket No. 50-346 A>

  1. c. p,.....e.

sffN

..c.... c

..or..

Jtnuary 26, 1977 e

4.m --,s242 NY V*

Serial No. 193 40I pU Director of Nuclear Reactor Regulations g

w 27)g77,M Attention:

lir. John F. Stolz, Chief i

Light Water Reactor Branch No. 1

' $ E4 poew n D %f Division of Project Management y

United States Nuclear Regulatory Commission g/

Washington, D.C.

20555

  • 9 N

Dear Mr. Stolz:

The following additional information is submitted with respect to provisions for detecting reactor coolant system leakage at the Davis-Besse Nuclear Power Station Unit 1.

The item was identified as outstanding review item (3) in the NRC's Safety Evaluation Report for Davis-Besse Unit 1.

The reactor coolant system leakage detection system includes the following:

a)

The containment atmosphere particulate radioactivity monitoring system.

b)

The containment sump level / flow monitoring system.

c)

The containment atmosphere gaseous radioactivity monitoring system.

Tae containment atmosphere particulate radioactivity monitoring system incorporates monitors which are seismic, redundant, with essential power supplies, and Q-listed.

The containment sump level and flow monitoring system design includes containment vessel normal sump totalized flow indication in the control room.

This is shown on FSAR Figure 9-9, and is c'

ignated FQI-2801.

The flow element is scismic and is not redundant Instrumentation and power supplies are not essential. The transmitter is mounted seismically.

There are redundant normal sump levels and alarms, as shown on FSAR Figure 6-17, with control room indication. They are non-essential, no n-s e ismic.

959 THE TCLECO ECrSCN CCMPANY ECISCN PLAZA 3CO MACISCN AVENUE TOLEOO. CHO 40652 i

I

The contain=ent atmosphere gaseous radioactivity monitoring system utilizes monitors which are seismically qualified with essential power supplies. They are described in FSAR Section 12.1.4.

All systems used for reactor coolant system leakage detection can be calibrated during operation except the normal sump level.

In addition to the systems described abovt, a reactor coolant system water inventory balance will be conducted at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during steady state operation in Mode 1.

This Surveillance Test ST5042.02 provides an accurar.e determination of RCS leakage.

Yours very truly, k

db c/ll-12