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{{#Wiki_filter:REGULATO         INFORMATION DISTRIBUTION                                                             TEM   ('RI DS)
{{#Wiki_filter:REGULATO INFORMATION DISTRIBUTION TEM ('RI DS)
  'ACCESSION NBR!8311110135                     DOC ~ DATES 83/11/04                                                     NOTARIZED'NO                       DOCKET  ¹
'ACCESSION NBR!8311110135 DOC ~ DATES 83/11/04 NOTARIZED'NO
        " '.50 3i5
.FACIL:50 3i5 Donal.d'.6 ~ 'Cook>> Nuclear>>Power-.->>Plantg ',Uni,t'i Indiana 8
    .FACIL:50             Donal.d'.6 ~ 'Cook>>   Nuclear>>Power-.->>Plantg                                                   ',Uni,t'i Indiana             8 0500031'5 316 Donald O ~ ">>Cook'uclear Power .Planti 'Uni,t 2i Indiana                                                                             8 05000316 AUTH;NAME'AUTHOR AFFILIATION ALEXICH~M,P,             -
" '.50 316 Donald O ~ ">>Cook'uclear Power.Planti
Indiana 8 'Mjchigan =-Electr RECIPIKNT AFFILIATION ic,Co,'REOIP NAMEi
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:-DENTONgH,Rs..             Of fice>> of Nucl'ear tReactor I Regul                                                     ation'ir       ector>>
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- Indiana 8 'Mjchigan =-Electr ic,Co,'REOIP NAMEi RECIPIKNT AFFILIATION
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    .NOTES!
'ables found w/o sufficient"fire barrier ~to:provide" 3 h
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INDIANA 8 MICHIGAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 November 4, 1983 AEP:NRC:0692I Donald C. Cook Nuclear Plant, Unit Nos. 1 and     2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 FIRE PROTECTION FOR EMBEDDED CABLES Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555
INDIANA8 MICHIGAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 November 4, 1983 AEP:NRC:0692I Donald C. Cook Nuclear Plant, Unit Nos.
1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 FIRE PROTECTION FOR EMBEDDED CABLES Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C.
20555


==Dear Mr. Denton:==
==Dear Mr. Denton:==
The purposes of this letter are (1) to provide additional information related to our previous submittal (AEP:NRC:0692H) dated August 22, 1983 and (2) to confirm the telephone conversation we had with your staff on Friday, October 21, 1983 concerning three-hour fire protection of embedded cables at the Donald C. Cook Nuclear Plant.
The previous submittal transmitted a report, dated March 1983, which was prepared by our consultants, Engineering Planning Management Incorporated (EPM).
That report was titled "Supplemental Information Safe Shutdown Capability Assessment and Proposed Modifications, 10 CFR 50, Appendix R, Section III G."
Section 2 of the Supplemental Report stated, in part, that the additional barrier mass between the embedded cables and the cold side (of the wall) will function as a heat sink, lowering the actual in-wall temperature at the embedded cable to a number substantially lower. than the 322 F used for the standard NFPA barrier rating.
At our request, EPM reviewed the bases employed in the Supplemental Report.
We received a letter from EPM, dated September 28, 1983, concerning the additional reviews.
The information attached to the EPM letter stated that the critical temperatures at a four inch depth reached between 500 F and 600 F after three hours.
As discussed during the telephone conversation, we have traced all safety related cables in fire zones to determine which zones included more than one Essential Safety Features (ESF) train.
As a result, we found two cases in which embedded cables did not have a sufficient fire barrier to provide a three-hour zating.
In both of these
: cases, the cables were in concrete pilasters, which are not part of the structural wall.
The affected pilasters are located in Fire Zone 15 in Unit 1 (i.e., the red ESF divisional diesel generator room) and Fire Zone 19 in Unit 2 (i.e., the green ESF divisional diesel generator room).
In both
: cases, we will add sufficient insulation to provide a three-hour 8311110135 831104 PDR ADOCK 05000315 F
PDR


The purposes    of this letter are (1) to provide additional information related to our previous submittal (AEP:NRC:0692H) dated August 22, 1983 and (2) to confirm the telephone conversation we had with your staff on Friday, October 21, 1983 concerning three-hour fire protection of embedded cables at the Donald C. Cook Nuclear Plant. The previous submittal transmitted a report, dated March 1983, which was prepared by our consultants, Engineering Planning Management Incorporated (EPM). That report was titled "Supplemental Information Safe Shutdown Capability Assessment and Proposed Modifications, 10 CFR 50, Appendix R, Section    III G."
0 t "0; f F
Section 2 of the Supplemental Report stated, in part, that the additional barrier mass between the embedded cables and the cold side (of the wall) will function as a heat sink, lowering the actual in-wall temperature at the embedded cable to a number substantially lower. than the 322 F used for the standard NFPA barrier rating. At our request, EPM  reviewed the bases employed in the Supplemental Report. We received a  letter  from EPM, dated September 28, 1983, concerning the additional reviews. The information attached to the EPM letter stated that the critical  temperatures at a four inch depth reached between 500 F and 600 F after three hours.
t, h P
As discussed during the telephone conversation, we have traced all safety related cables in fire zones to determine which zones included more than one Essential Safety Features (ESF) train. As a result, we found two cases in which embedded cables did not have a sufficient fire barrier to provide a three-hour zating. In both of these cases, the cables were in concrete pilasters, which are not part of the structural wall. The affected pilasters are located in Fire Zone 15 in Unit 1 (i.e., the red ESF divisional diesel generator room) and Fire Zone 19 in Unit 2 (i.e., the green ESF divisional diesel generator room). In both cases, we will add sufficient insulation to provide a three-hour 8311110135 831104 PDR ADOCK 05000315 F                      PDR
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Mr.'Harold   R.     on                                     AEPsNRC:0692I barrier, without any reliance on the insulation properties of the concrete. The insulation modification will not rely on any conditions addressed in the Supplemental Report.
Mr.'Harold R.
This information should be factored into the data-base for your Safety Evaluation Report on fire protection which, we understand we will be receiving shortly.
on AEPsNRC:0692I barrier, without any reliance on the insulation properties of the concrete.
The insulation modification will not rely on any conditions addressed in the Supplemental Report.
This information should be factored into the data-base for your Safety Evaluation Report on fire protection which, we understand we will be receiving shortly.
This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.
This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.
Very   truly yours, M   .~      i Al ich Vice Pre ident MPA/pb cc:   John E. Dolan W. G. Smith, Jr.   - Bridgman R. C. Callen G. Charnoff E. R. Swanson,   NRC Resident Inspector Bridgman
Very truly yours,
~
i M
. Al ich Vice Pre ident MPA/pb cc:
John E. Dolan W. G. Smith, Jr. - Bridgman R. C. Callen G. Charnoff E. R.
: Swanson, NRC Resident Inspector Bridgman


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Latest revision as of 16:23, 7 January 2025

Provides Addl Info Re Util 830822 Submittal & 831021 Telcon Re 3 H Fire Protection of Embedded Cables.Two Embedded Cables Found W/O Sufficient Fire Barrier to Provide 3 H Rating.Addl Insulation Will Be Provided
ML17320A813
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 11/04/1983
From: Alexich M
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To: Harold Denton
Office of Nuclear Reactor Regulation
References
AEP:NRC:0692I, AEP:NRC:692I, NUDOCS 8311110135
Download: ML17320A813 (6)


Text

REGULATO INFORMATION DISTRIBUTION TEM ('RI DS)

'ACCESSION NBR!8311110135 DOC ~ DATES 83/11/04 NOTARIZED'NO

.FACIL:50 3i5 Donal.d'.6 ~ 'Cook>> Nuclear>>Power-.->>Plantg ',Uni,t'i Indiana 8

" '.50 316 Donald O ~ ">>Cook'uclear Power.Planti

'Uni,t 2i Indiana 8

AUTH;NAME'AUTHORAFFILIATION ALEXICH~M,P,

- Indiana 8 'Mjchigan =-Electr ic,Co,'REOIP NAMEi RECIPIKNT AFFILIATION

-DENTONgH,Rs..

Office>> of Nucl'ear tReactor I Regul ation'ir ector>>

.-SUBJECT;=-)Provides addi info re>>.ut) 1 8308224 submittal "L 834021 tel con r e" 34 h-fire pr otection-of >>embedded cabl es 'Two embedded

'ables found w/o sufficient"fire barrier ~to:provide" 3 h

r at ing, Addi insu1 a tion ~ wi l l"be; pr ovided.

.DISTRIBUTION iCODE>> 'AOOSS iCOPIES

'RECEIVED:LTR,J,'NCL:,P'SIZE:."'TITLE>,

OR 'Submittal: Fir e>>iProtection

.NOTES!

DOCKET ¹ 0500031'5 05000316 RECIPIENT>>

ID CODE/NAME, NRR" ORB1 >>BC'1.

  • INTERNALR ELD/HDS3 IE'i'WHITNEYg L NRR= WAMBACH

.NRR'/DL-"'DIR RGN3>>

COPIES I;TTR"ENCL>>

434 1

=1,i.

.1 RECIPIENT ID CODE/NAME, IE:;F ILE>>

06 NRR FIORAVANT07 DE/CEB 09 RK L

04

>>COPIES LTTR ENCL 1

2 2

1 EXT'ERNAL~

ACRS

.NRC>>PDR NTIS 11 02 534 1>>

LPDR

NSIC, 03

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INDIANA8 MICHIGAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 November 4, 1983 AEP:NRC:0692I Donald C. Cook Nuclear Plant, Unit Nos.

1 and 2

Docket Nos.

50-315 and 50-316 License Nos.

DPR-58 and DPR-74 FIRE PROTECTION FOR EMBEDDED CABLES Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C.

20555

Dear Mr. Denton:

The purposes of this letter are (1) to provide additional information related to our previous submittal (AEP:NRC:0692H) dated August 22, 1983 and (2) to confirm the telephone conversation we had with your staff on Friday, October 21, 1983 concerning three-hour fire protection of embedded cables at the Donald C. Cook Nuclear Plant.

The previous submittal transmitted a report, dated March 1983, which was prepared by our consultants, Engineering Planning Management Incorporated (EPM).

That report was titled "Supplemental Information Safe Shutdown Capability Assessment and Proposed Modifications, 10 CFR 50, Appendix R, Section III G."

Section 2 of the Supplemental Report stated, in part, that the additional barrier mass between the embedded cables and the cold side (of the wall) will function as a heat sink, lowering the actual in-wall temperature at the embedded cable to a number substantially lower. than the 322 F used for the standard NFPA barrier rating.

At our request, EPM reviewed the bases employed in the Supplemental Report.

We received a letter from EPM, dated September 28, 1983, concerning the additional reviews.

The information attached to the EPM letter stated that the critical temperatures at a four inch depth reached between 500 F and 600 F after three hours.

As discussed during the telephone conversation, we have traced all safety related cables in fire zones to determine which zones included more than one Essential Safety Features (ESF) train.

As a result, we found two cases in which embedded cables did not have a sufficient fire barrier to provide a three-hour zating.

In both of these

cases, the cables were in concrete pilasters, which are not part of the structural wall.

The affected pilasters are located in Fire Zone 15 in Unit 1 (i.e., the red ESF divisional diesel generator room) and Fire Zone 19 in Unit 2 (i.e., the green ESF divisional diesel generator room).

In both

cases, we will add sufficient insulation to provide a three-hour 8311110135 831104 PDR ADOCK 05000315 F

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on AEPsNRC:0692I barrier, without any reliance on the insulation properties of the concrete.

The insulation modification will not rely on any conditions addressed in the Supplemental Report.

This information should be factored into the data-base for your Safety Evaluation Report on fire protection which, we understand we will be receiving shortly.

This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.

Very truly yours,

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. Al ich Vice Pre ident MPA/pb cc:

John E. Dolan W. G. Smith, Jr. - Bridgman R. C. Callen G. Charnoff E. R.

Swanson, NRC Resident Inspector Bridgman

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