ML17326B087: Difference between revisions

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{{#Wiki_filter:REGULA     Y   INFORMATION DISTRIBUTIO 'YSTEM (RIDS)
{{#Wiki_filter:REGULA Y INFORMATION DISTRIBUTIO 'YSTEM (RIDS)
ACCESSION NBR 821 1230131           DOO ~ DATE ~ 82/1 1/19   NO   RIZEDo NO         DOCKET FACIL:50 3)'5 Donald O, Cook Nuclear Power Pl anti Unit 1<               Indiana   8 05000315
ACCESSION NBR 821 1230131 DOO ~ DATE ~ 82/1 1/19 NO RIZEDo NO FACIL:50 3)'5 Donald O,
        '50 .316 Donal d O. Cook Nuclear Power Plant< Uni t 2p             Indiana   8 05000316 AUTH SHAME         AUTHOR   AFFILIATION HUNTERER,SB         Indiana   8   Michigan   Electric   Co,
Cook Nuclear Power Pl anti Unit 1< Indiana 8
  'OC IP, NAME         RECIPIENT AFF ILIATION DENTON~H,R ~         Of fice of Nuclear Reactor         Regulationi Director SUBJECT! Submits     estimate of required annual purge sys operation time during Operational Modes 1 4Ein response to request, Estimated annual purge operation;time 200 h for each unitr based on plant capacity factor of 77/>
'50.316 Donal d O.
DISTRIBUTION CODE: A0300 TITLE:  OR COPIES RECEIYED:LTR Submittal: Containment ',Purging 5 ENCL   j SIZE:.
Cook Nuclear Power Plant<
NOTES:
Uni t 2p Indiana 8
RECIPIENT           COPIES              RECIPIENT            COPIES ID CODE/NAME         L'TTR ENCL        ID CODE/NAME        LTTR ENCL NRR ORB1   BC   01         7      7 INTERNAL:   NRR   FIELDSgM 1i?       1     1     NRR REEVESgE      14    1     1 09        1     1     NRR/DS I/AEB             1     1 REG  FIL      04        1     1     RGN3                    1     1 EXTERNALS ACRS             13         4     b     LPDR              03    2    2 NRC PDR         02     -  1             NSIC             05     1     1 NTIS                      1      1 TOTAL NUMBER OF COPIES     REQUIRED: LTTR         24   ENCL     24
AUTH SHAME AUTHOR AFFILIATION HUNTERER,SB Indiana 8 Michigan Electric Co,
'OC IP, NAME RECIPIENT AFF ILIATION DENTON~H,R ~
Office of Nuclear Reactor Regulationi Director DOCKET 05000315 05000316 SUBJECT!
Submits estimate of required annual purge sys operation time during Operational Modes 1 4Ein response to request, Estimated annual purge operation;time 200 h for each unitr based on plant capacity factor of 77/>
DISTRIBUTION CODE:
A0300 COPIES RECEIYED:LTR
. 5 ENCL j SIZE:.
TITLE:
OR Submittal:
Containment ',Purging NOTES:
RECIPIENT ID CODE/NAME NRR ORB1 BC 01 INTERNAL: NRR FIELDSgM 1i?
09 REG FIL 04 COPIES L'TTR ENCL 7
7 1
1 1
1 1
1 RECIPIENT ID CODE/NAME NRR REEVESgE 14 NRR/DS I/AEB RGN3 COPIES LTTR ENCL 1
1 1
1 1
1 EXTERNALS ACRS 13 4
b NRC PDR 02 1
NTIS 1
1 LPDR NSIC 03 05 2
2 1
1 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 24 ENCL 24


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INDIANA 5 MICHIGAN ELECTRIC COMPANY P. 0. BOX 18 BOWLING GREEN STATION NEW YORK, N. Y. 10004 November 19, 1982 AEP:NRC:0370C Donald C. Cook Nuclear Plant Unit Nos.     1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 ANNUAL PURGE OPERATION TIME ESTIMATE Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C. 20555
INDIANA 5 MICHIGAN ELECTRIC COMPANY P. 0.
BOX 18 BOWLING GREEN STATION NEW YORK, N. Y. 10004 November 19, 1982 AEP:NRC:0370C Donald C. Cook Nuclear Plant Unit Nos.
1 and 2
Docket Nos. 50-315 and 50-316 License Nos.
DPR-58 and DPR-74 ANNUAL PURGE OPERATION TIME ESTIMATE 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:==
 
This letter supplements our previous submittal AEP:NRC:0370B, dated August 30,
This letter supplements our previous submittal AEP:NRC:0370B, dated August 30, 1982, and provides, at the request of your staff, an estimate of the required annual purge system operation time for the Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 during operational modes 1, 2, 3, and 4.
: 1982, and provides, at the request of your staff, an estimate of the required annual purge system operation time for the Donald C. Cook Nuclear Plant Unit Nos.
We estimate that the required annual purge operation time in modes 1 through 4 will be two hundred (200) hours for each unit. This purge estimate is based on a plant capacity factor of 77%, and accounts for two purge operations per week. Each purge operation is assumed to be approximately 2 4 hours in duration. The annual 200-hour purge operation time limit amounts to less than 3% of the estimated plant operation time in Modes 1 through 4.
1 and 2 during operational modes 1, 2, 3, and 4.
In accordance with our Technical Specification     change request (AEP:NRC:0370B) referenced     above, we will operate the containment purge system only for safety     related reasons. The ability to purge when needed will improve work conditions for plant maintenance and inspection personnel by reducing airborne radioactivity, reducing the       .
We estimate that the required annual purge operation time in modes 1 through 4 will be two hundred (200) hours for each unit.
need for respiratory equipment, and increasing worker safety on the job. We believe this to be consistent with our ALARA obgectives.
This purge estimate is based on a plant capacity factor of 77%, and accounts for two purge operations per week.
Furthermore,   we note that Mr. S. A. Varga's letter of October 30, 1981,   states that units not meeting 10 CFR 100 radiation dose limits for a postulated LOCA coincident with purge system operation would be limited to 90 hours per year of purging. As explained in our letter of 8211230131   S21119 PDR ADOCK   05000315 P                   PDR
Each purge operation is assumed to be approximately 2 4 hours in duration.
The annual 200-hour purge operation time limit amounts to less than 3% of the estimated plant operation time in Modes 1 through 4.
In accordance with our Technical Specification change request (AEP:NRC:0370B) referenced
: above, we will operate the containment purge system only for safety related reasons.
The ability to purge when needed will improve work conditions for plant maintenance and inspection personnel by reducing airborne radioactivity, reducing the need for respiratory equipment, and increasing worker safety on the job.
We believe this to be consistent with our ALARA obgectives.
Furthermore, we note that Mr. S. A. Varga's letter of October 30, 1981, states that units not meeting 10 CFR 100 radiation dose limits for a postulated LOCA coincident with purge system operation would be limited to 90 hours per year of purging.
As explained in our letter of 8211230131 S21119 PDR ADOCK 05000315 P
PDR


0 8
0 8


Mr. Harold R. Denton                                       AEP:NRC: 0370C October 3l, 1977, John Tillinghast (Indiana 6 Michigan Power Co.) to Edson G. Case (NRC), such a postulated accident scenario at D. C. Cook will not lead to doses exceeding 10 CFR 100 limits. The analysis performed at that time in support of our position was consistent with NRC Branch Technical Position CSB 6-4. As noted in our AEP:NRC:0370B submittal referenced above,   we are replacing all containment purge isolation valves during the 1982 refueling outages. These new valves have the same isolation time as the old valves, but are of superior leak tightness. Thus, we believe the requested 200-hour annual purge limit is a "reasonable goal" as stated in Mr. Varga's letter referenced above.
Mr. Harold R. Denton AEP:NRC: 0370C October 3l, 1977, John Tillinghast (Indiana 6 Michigan Power Co.) to Edson G. Case (NRC), such a postulated accident scenario at D. C. Cook will not lead to doses exceeding 10 CFR 100 limits.
The analysis performed at that time in support of our position was consistent with NRC Branch Technical Position CSB 6-4.
As noted in our AEP:NRC:0370B submittal referenced
: above, we are replacing all containment purge isolation valves during the 1982 refueling outages.
These new valves have the same isolation time as the old valves, but are of superior leak tightness.
: Thus, we believe the requested 200-hour annual purge limit is a "reasonable goal" as stated in Mr. Varga's letter referenced above.
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' S. unter Vice President RSH/sag cc:. John E. Dolan Columbus M. P. Alexich R. W. Jurgensen W. G. Smith, Jr. - Bridgman R. C. Callen G. Charnoff Joe Williams, Jr.
Very truly yours' S.
NRC Resident Inspector at. Cook Plant Bridgman
unter Vice President RSH/sag cc:.
John E. Dolan Columbus M. P. Alexich R. W. Jurgensen W. G. Smith, Jr. - Bridgman R. C. Callen G. Charnoff Joe Williams, Jr.
NRC Resident Inspector at. Cook Plant Bridgman


  " ~
~
~}}
~}}

Latest revision as of 15:09, 7 January 2025

Submits Estimate of Required Annual Purge Sys Operation Time During Operational Modes 1-4,in Response to Request. Estimated Annual Purge Operation Time of 200-h for Each Unit Based on Plant Capacity Factor of 77%
ML17326B087
Person / Time
Site: Cook  
Issue date: 11/19/1982
From: Hunter R
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To: Harold Denton
Office of Nuclear Reactor Regulation
References
AEP:NRC:0370C, AEP:NRC:370C, NUDOCS 8211230131
Download: ML17326B087 (6)


Text

REGULA Y INFORMATION DISTRIBUTIO 'YSTEM (RIDS)

ACCESSION NBR 821 1230131 DOO ~ DATE ~ 82/1 1/19 NO RIZEDo NO FACIL:50 3)'5 Donald O,

Cook Nuclear Power Pl anti Unit 1< Indiana 8

'50.316 Donal d O.

Cook Nuclear Power Plant<

Uni t 2p Indiana 8

AUTH SHAME AUTHOR AFFILIATION HUNTERER,SB Indiana 8 Michigan Electric Co,

'OC IP, NAME RECIPIENT AFF ILIATION DENTON~H,R ~

Office of Nuclear Reactor Regulationi Director DOCKET 05000315 05000316 SUBJECT!

Submits estimate of required annual purge sys operation time during Operational Modes 1 4Ein response to request, Estimated annual purge operation;time 200 h for each unitr based on plant capacity factor of 77/>

DISTRIBUTION CODE:

A0300 COPIES RECEIYED:LTR

. 5 ENCL j SIZE:.

TITLE:

OR Submittal:

Containment ',Purging NOTES:

RECIPIENT ID CODE/NAME NRR ORB1 BC 01 INTERNAL: NRR FIELDSgM 1i?

09 REG FIL 04 COPIES L'TTR ENCL 7

7 1

1 1

1 1

1 RECIPIENT ID CODE/NAME NRR REEVESgE 14 NRR/DS I/AEB RGN3 COPIES LTTR ENCL 1

1 1

1 1

1 EXTERNALS ACRS 13 4

b NRC PDR 02 1

NTIS 1

1 LPDR NSIC 03 05 2

2 1

1 TOTAL NUMBER OF COPIES REQUIRED:

LTTR 24 ENCL 24

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INDIANA 5 MICHIGAN ELECTRIC COMPANY P. 0.

BOX 18 BOWLING GREEN STATION NEW YORK, N. Y. 10004 November 19, 1982 AEP:NRC:0370C Donald C. Cook Nuclear Plant Unit Nos.

1 and 2

Docket Nos. 50-315 and 50-316 License Nos.

DPR-58 and DPR-74 ANNUAL PURGE OPERATION TIME ESTIMATE Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C.

20555

Dear Mr. Denton:

This letter supplements our previous submittal AEP:NRC:0370B, dated August 30,

1982, and provides, at the request of your staff, an estimate of the required annual purge system operation time for the Donald C. Cook Nuclear Plant Unit Nos.

1 and 2 during operational modes 1, 2, 3, and 4.

We estimate that the required annual purge operation time in modes 1 through 4 will be two hundred (200) hours for each unit.

This purge estimate is based on a plant capacity factor of 77%, and accounts for two purge operations per week.

Each purge operation is assumed to be approximately 2 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> in duration.

The annual 200-hour purge operation time limit amounts to less than 3% of the estimated plant operation time in Modes 1 through 4.

In accordance with our Technical Specification change request (AEP:NRC:0370B) referenced

above, we will operate the containment purge system only for safety related reasons.

The ability to purge when needed will improve work conditions for plant maintenance and inspection personnel by reducing airborne radioactivity, reducing the need for respiratory equipment, and increasing worker safety on the job.

We believe this to be consistent with our ALARA obgectives.

Furthermore, we note that Mr. S. A. Varga's letter of October 30, 1981, states that units not meeting 10 CFR 100 radiation dose limits for a postulated LOCA coincident with purge system operation would be limited to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per year of purging.

As explained in our letter of 8211230131 S21119 PDR ADOCK 05000315 P

PDR

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Mr. Harold R. Denton AEP:NRC: 0370C October 3l, 1977, John Tillinghast (Indiana 6 Michigan Power Co.) to Edson G. Case (NRC), such a postulated accident scenario at D. C. Cook will not lead to doses exceeding 10 CFR 100 limits.

The analysis performed at that time in support of our position was consistent with NRC Branch Technical Position CSB 6-4.

As noted in our AEP:NRC:0370B submittal referenced

above, we are replacing all containment purge isolation valves during the 1982 refueling outages.

These new valves have the same isolation time as the old valves, but are of superior leak tightness.

Thus, we believe the requested 200-hour annual purge limit is a "reasonable goal" as stated in Mr. Varga's letter referenced above.

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' S.

unter Vice President RSH/sag cc:.

John E. Dolan Columbus M. P. Alexich R. W. Jurgensen W. G. Smith, Jr. - Bridgman R. C. Callen G. Charnoff Joe Williams, Jr.

NRC Resident Inspector at. Cook Plant Bridgman

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