ML19319C060: Difference between revisions
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NRC ronu 195 u.s. NUCLEAQ HEGULATORY | NRC ronu 195 u.s. NUCLEAQ HEGULATORY | ||
* COMMISSION DOCKET NUMEE R g.a , .s . , ,50-3 % l | * COMMISSION DOCKET NUMEE R g.a , .s . , ,50-3 % l | ||
* NRC DISTRIBUTION FOR F ,dT 50 DOCKET MATERIAL! "''"""''" | * NRC DISTRIBUTION FOR F ,dT 50 DOCKET MATERIAL! "''"""''" | ||
FROM: DATE OF DOCUMENT | FROM: DATE OF DOCUMENT | ||
* TO *. | * TO *. | ||
J l' Stol: Toledo Edison CO 1-26-77 l | J l' Stol: Toledo Edison CO 1-26-77 l | ||
,;' Toledo, Ohio , | ,;' Toledo, Ohio , | ||
DATE RECEivEO j | DATE RECEivEO j | ||
._ L E Roe t_37 77 | ._ L E Roe t_37 77 | ||
@LETTE R - CNOTORIZED PROP INPUT FORM NUMDER OF COPIES RECEIVED l | @LETTE R - CNOTORIZED PROP INPUT FORM NUMDER OF COPIES RECEIVED l | ||
-%cn 6 GIN AL~ gUNC L ASSIFIE D ' | -%cn 6 GIN AL~ gUNC L ASSIFIE D ' | ||
,CCOPY ' .One,sicned CESCRIPTION E NCLOSU RE . | ,CCOPY ' .One,sicned CESCRIPTION E NCLOSU RE . | ||
8's Ltr clarifying impc.ct upon separation criteria - | |||
8's | |||
Ltr clarifying impc.ct upon separation criteria - | |||
m' by cable tray fill exceeding tray side rails , | m' by cable tray fill exceeding tray side rails , | ||
2p x . | |||
2p | |||
x . | |||
s - | s - | ||
I f | I f | ||
PLANT HAME: Davis Besse #1 LEDGED i | PLANT HAME: Davis Besse #1 LEDGED i i | ||
i | |||
, SAFETY FOR ACTION / INFO R'.! ATION - gran 1-5-77 ehr | , SAFETY FOR ACTION / INFO R'.! ATION - gran 1-5-77 ehr | ||
/ ASSIG:ED AD: V,y salIe 4,3n7c mn An. | / ASSIG:ED AD: V,y salIe 4,3n7c mn An. | ||
MJ:AUCE_c"C"- S to i 1 m A*: ~ r ~ - _. | MJ:AUCE_c"C"- S to i 1 m A*: ~ r ~ - _. | ||
zhJg)1ESI_;iiN!.cSa fe c /e. PROJECT :AN\GER: | zhJg)1ESI_;iiN!.cSa fe c /e. PROJECT :AN\GER: | ||
Z'_IJC_. ASsr. : W/ka | Z'_IJC_. ASsr. : W/ka LIC. ASST. : | ||
LIC. ASST. : | |||
INTERNAL DIST IIBUTION Q EG FILZ__ , SYS'Ip'.S SAFETY i FL.'';T SYSTE: S | INTERNAL DIST IIBUTION Q EG FILZ__ , SYS'Ip'.S SAFETY i FL.'';T SYSTE: S | ||
. l SITE SAFg*:TJ | . l SITE SAFg*:TJ | ||
| Line 72: | Line 50: | ||
PROJECT MA'!AGEMENT I I REACTOR SAFETY ' | PROJECT MA'!AGEMENT I I REACTOR SAFETY ' | ||
OPERATIUS TEC'i. / cat' MILL (2.) | OPERATIUS TEC'i. / cat' MILL (2.) | ||
BOYD I/! RO'SS EISENIiUT STEPP P,, COLLINS /! NOVAK SilA0 HULMAN IIOUSTO:i / ROSZTCC7.Y BAER PETERSON / CllECK . BUTLER SITE ANALYSIS MELTZ l ggnigs / VOLL!'ER llELTEMES AT & I / BUNCII SKOVHOLT SALTZ"AN / J. COLLT"S RUTEERG l / KREGER I EXTERNAL Ul5TRil3UTION CONTHOL .NU5.*dE A 7LPDR; # C/m4o e OHI _tjATm Ls3: I BR00KitAVF.N.liAT . LAL | |||
BOYD I/! RO'SS EISENIiUT STEPP P,, COLLINS /! NOVAK SilA0 HULMAN IIOUSTO:i / ROSZTCC7.Y BAER PETERSON / CllECK . BUTLER SITE ANALYSIS MELTZ l ggnigs / VOLL!'ER llELTEMES AT & I / BUNCII SKOVHOLT SALTZ"AN / J. COLLT"S RUTEERG l / KREGER I | |||
EXTERNAL Ul5TRil3UTION CONTHOL .NU5.*dE A 7LPDR; # C/m4o e OHI _tjATm Ls3: I BR00KitAVF.N.liAT . LAL | |||
_[ TIC: I;EC V.IE ULRIKSON (0!tML) : | _[ TIC: I;EC V.IE ULRIKSON (0!tML) : | ||
(_NSTC: LA PDR QI - . | (_NSTC: LA PDR QI - . | ||
ASLn: COM S L'LTA~;.'TO : , | ASLn: COM S L'LTA~;.'TO : , | ||
[Alcas 76 cvs no.ne_.ww T.E..id Ed A7".8 | [Alcas 76 cvs no.ne_.ww T.E..id Ed A7".8 | ||
_ _ _ _ . / / J.3.7_ r/ @ | _ _ _ _ . / / J.3.7_ r/ @ | ||
; | ; | ||
NRcioRuiosa.m k | NRcioRuiosa.m k | ||
1 000 1310 V3f | 1 000 1310 V3f | ||
. ; . ... | . ; . ... | ||
Y Ofg SG k,b TOLEDO | Y Ofg SG k,b TOLEDO | ||
| Line 99: | Line 67: | ||
January 26, 1977 So | January 26, 1977 So | ||
_a Y | _a Y | ||
// 1 Director of Nuclear Reactor Regulation % | // 1 Director of Nuclear Reactor Regulation % | ||
el i e Attn: Mr. John F. Stolz, Chief Light Water Reactors Branch No. 1 k eldflyg | el i e Attn: Mr. John F. Stolz, Chief Light Water Reactors Branch No. 1 k eldflyg | ||
- v,g, | - v,g, Division of Project Management Mig | ||
* United States Nuclear Regulatory Commission | * United States Nuclear Regulatory Commission | ||
{ | { | ||
| Line 121: | Line 87: | ||
^ | ^ | ||
e, a m, s | |||
Mr.. John'F. Stolz January 26, 1977 | |||
: 4) By not exceeding the 60% fill limit on each leg, recognizing that cables cannot terminate within a Tee, the exceeding of the 60% fill of the Tee is prevented. | : 4) By not exceeding the 60% fill limit on each leg, recognizing that cables cannot terminate within a Tee, the exceeding of the 60% fill of the Tee is prevented. | ||
The above information should allow the conclusion of Mr. Szukiewicz's review of this matter. | The above information should allow the conclusion of Mr. Szukiewicz's review of this matter. | ||
Yours truly, CCs 1 | |||
Yours truly, | s i | ||
h i | |||
CCs | |||
i | |||
i i | i i | ||
I | |||
; | ; | ||
l | l | ||
., _ . -- . . .}} | ., _ . -- . . .}} | ||
Revision as of 05:23, 1 February 2020
| ML19319C060 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse |
| Issue date: | 01/26/1977 |
| From: | Roe L TOLEDO EDISON CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8001310439 | |
| Download: ML19319C060 (3) | |
Text
,'
NRC ronu 195 u.s. NUCLEAQ HEGULATORY
- COMMISSION DOCKET NUMEE R g.a , .s . , ,50-3 % l
- NRC DISTRIBUTION FOR F ,dT 50 DOCKET MATERIAL! """""
FROM: DATE OF DOCUMENT
- TO *.
J l' Stol: Toledo Edison CO 1-26-77 l
,;' Toledo, Ohio ,
DATE RECEivEO j
._ L E Roe t_37 77
@LETTE R - CNOTORIZED PROP INPUT FORM NUMDER OF COPIES RECEIVED l
-%cn 6 GIN AL~ gUNC L ASSIFIE D '
,CCOPY ' .One,sicned CESCRIPTION E NCLOSU RE .
8's Ltr clarifying impc.ct upon separation criteria -
m' by cable tray fill exceeding tray side rails ,
2p x .
s -
I f
PLANT HAME: Davis Besse #1 LEDGED i i
, SAFETY FOR ACTION / INFO R'.! ATION - gran 1-5-77 ehr
/ ASSIG:ED AD: V,y salIe 4,3n7c mn An.
MJ:AUCE_c"C"- S to i 1 m A*: ~ r ~ - _.
zhJg)1ESI_;iiN!.cSa fe c /e. PROJECT :AN\GER:
Z'_IJC_. ASsr. : W/ka LIC. ASST. :
INTERNAL DIST IIBUTION Q EG FILZ__ , SYS'Ip'.S SAFETY i FL.;T SYSTE: S
. l SITE SAFg*:TJ
/INRC rd IIEI';E".AN d T"DZ100 ENvin02' alm s
/ :I & E f 2.) SCiROEDER /l eel {al;Q"A DE:'TC!i & 'r ~.LZ2
/ OELD_ ~ /1 tj,1 :as GOSS'OR & STA7F ENGINEERING d IPPSLITO E? VIB.O TECIL MIPC l'4 CARRY I KIpy.*0cn ERNST CASE / KNIGt!T I EALI.ARD HANAUER /: SII *?EIL I OPERATING REACTORS
~
SPAUCLER 11ARLESS I/ PAWLICXI } STELLO j
} } I SITE TECI!.
PROJECT MA'!AGEMENT I I REACTOR SAFETY '
OPERATIUS TEC'i. / cat' MILL (2.)
BOYD I/! RO'SS EISENIiUT STEPP P,, COLLINS /! NOVAK SilA0 HULMAN IIOUSTO:i / ROSZTCC7.Y BAER PETERSON / CllECK . BUTLER SITE ANALYSIS MELTZ l ggnigs / VOLL!'ER llELTEMES AT & I / BUNCII SKOVHOLT SALTZ"AN / J. COLLT"S RUTEERG l / KREGER I EXTERNAL Ul5TRil3UTION CONTHOL .NU5.*dE A 7LPDR; # C/m4o e OHI _tjATm Ls3: I BR00KitAVF.N.liAT . LAL
_[ TIC: I;EC V.IE ULRIKSON (0!tML) :
(_NSTC: LA PDR QI - .
ASLn: COM S L'LTA~;.'TO : ,
[Alcas 76 cvs no.ne_.ww T.E..id Ed A7".8
_ _ _ _ . / / J.3.7_ r/ @
NRcioRuiosa.m k
1 000 1310 V3f
. ; . ...
Y Ofg SG k,b TOLEDO
,I S.q(q1 rY- -
EDISON Docket No. 50-346 .-t M, -5
- LOWELL E. RCE 49 Seria1 No. 195 \0 &' k T';[,*E",',,,,,,,,,,
January 26, 1977 So
_a Y
// 1 Director of Nuclear Reactor Regulation %
el i e Attn: Mr. John F. Stolz, Chief Light Water Reactors Branch No. 1 k eldflyg
- v,g, Division of Project Management Mig
- United States Nuclear Regulatory Commission
{
Washington, D. C. 20555
Dear Mr. Stolz:
This letter presents our response to a clarification requested orally by staff member Mr. Andy Szukiewicz at our meeting in Bethesda on January 14, 1977, re-garding the Davis-Besse Nuclear Power Station Unit No. 1 Mr. Szukiewicz asked for clarification of the impact upon separation criteria by :able tray fill exceeding tray side rails as allowed in section 8.3.1.2.20 of che FSAR (page 8-21d), and the impact of such fill practices upon the 60%
fill limitation for control cable trays related to essential systems. This item also relates to SER Outstanding Review Item 15.
We have the following responses to Mr. Szukiewicz's requests:
- 1) Where the intent of vertical cable tray separation criteria would be negated by cable exceeding the tray rail heights, the inclusion of thermal insulating material provides the required separation in accordance with the criteria of the last paragraph of FSAR section 8.3.1.2.20.
- 2) The cable cross-sectional area above the tray side rails is included with the cable cross-sectional area within the side rails in deter-mining tray fill percentage.
- 3) The minimum cross-sectional area of the cable tray cross fittings used is 90% of the combined cross-sectional area of the two (2) intersecting trays, and therefore, in veder to maintain the 60% fill limitation within the cross fitting, limits the fill to 54% (90% of 60%) in the entering and exiting legs of the cross. We have verified that in no instance is there any essential system tray cross fitting with entering or exiting legs having a cable fill in excess of 54%. The identified 54% fill limitation will be maintained for tray cross fittings' legs on essential system trays.
953 l l
THE TCLEDO ECISCN CCMPANY EDISCN PLAZA 300 MADISCN AVENUE TCLECO, CHIO 43652 l
l 4
^
e, a m, s
Mr.. John'F. Stolz January 26, 1977
- 4) By not exceeding the 60% fill limit on each leg, recognizing that cables cannot terminate within a Tee, the exceeding of the 60% fill of the Tee is prevented.
The above information should allow the conclusion of Mr. Szukiewicz's review of this matter.
Yours truly, CCs 1
s i
h i
i i
I
l
., _ . -- . . .