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| number = ML19316A053
| number = ML19316A053
| issue date = 04/04/1973
| issue date = 04/04/1973
| title = Responds to NRC 731215 Ltr Re Facility Operations.Comments on Tech Specs 3.9,3.10,4.2,4.11 & 6.1
| title = Responds to NRC Re Facility Operations.Comments on Tech Specs 3.9,3.10,4.2,4.11 & 6.1
| author name = Thies A
| author name = Thies A
| author affiliation = DUKE POWER CO.
| author affiliation = DUKE POWER CO.
Line 11: Line 11:
| contact person =  
| contact person =  
| document report number = NUDOCS 7911210623
| document report number = NUDOCS 7911210623
| title reference date = 12-15-1973
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 4
| page count = 4
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=Text=
=Text=
{{#Wiki_filter:'
{{#Wiki_filter:AEC DIS"MBUTION FOR PART 50 DOCIET !GT- ~ 'AL
                                  ~
~
AEC DIS"MBUTION FOR PART 50 DOCIET !GT- ~ 'AL           ~
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i A C. THIE S                                                                                               I P. O. Box 217s ELNeon VICE PasseDE NT                                                   _,      ,
C. THIE S P. O. Box 217s ELNeon VICE PasseDE NT PnODUC f sCao aseD TeaNsesessioN
PnODUC f sCao aseD TeaNsesessioN                                                   'r April 4, 1973                                           /     '
'r April 4, 1973
eF       M Mr. R. C. DeYoung, Assistant Director                           -
/
                                                                                                        ' L:
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for Pressurized Water Reactors Directorate of Licensing                                         _
' L:
U. S. Atomic Energy Commission                                                   .,,        ,,
Mr. R. C. DeYoung, Assistant Director for Pressurized Water Reactors Directorate of Licensing U. S. Atomic Energy Commission Washington, D. C.
Washington, D. C.             20545                                             Rg = '
20545 Rg = '
Re: Oconee Nuclene Reation Docket C                         -270, and -287
Re: Oconee Nuclene Reation Docket C
-270, and -287


==Dear Mr. DeYoung:==
==Dear Mr. DeYoung:==
In response to your letter of December 15, 1973, we wish to comment on those items enclosed in your letter under the heading, " Units 1 and 2 and Units 1, 2, and 3 Operations":
In response to your letter of December 15, 1973, we wish to comment on those items enclosed in your letter under the heading, " Units 1 and 2 and Units 1, 2, and 3 Operations":
Item 5         Specification 3.9 - Objective d.
Item 5 Specification 3.9 - Objective d.
The annual average concentration of dissolved gases in liquid waste of 4 x 10-7 pCi/ml is excessively conservative since it assumes complete immersion in water for a full year. An occupancy factor based on complete immersion for 200 hours per year yields an average concentration limit of 1.6 x 10-5 pCi/ml.                   The inclusion of the occupancy factor is in accordance with 10 CFR 20.106(b), and we propose to change the                                           .
The annual average concentration of dissolved gases in liquid waste of 4 x 10-7 pCi/ml is excessively conservative since it assumes complete immersion in water for a full year. An occupancy factor based on complete immersion for 200 hours per year yields an average concentration limit of 1.6 x 10-5 pCi/ml.
concentration limit in Objective d. to 1.6 x 10-5 pCi/ml.
The inclusion of the occupancy factor is in accordance with 10 CFR 20.106(b), and we propose to change the concentration limit in Objective d. to 1.6 x 10-5 pCi/ml.
I Item 6         Specification 3.9.2                                                                         l l
Item 6 Specification 3.9.2 l
Using the occupancy factor based on immersion for 200 hours per year,                                       i the appropriate quarterly average concentration is found to be 3.2 x 10-5 pCi/ml. Specification 3.9.2 will be revised to read:
Using the occupancy factor based on immersion for 200 hours per year, i
l "The release of radioactive liquid effluents, excluding I
the appropriate quarterly average concentration is found to be 3.2 x 10-5 pCi/ml. Specification 3.9.2 will be revised to read:
tritium and dissolved noble gases, shall not exceed 10 curies during any calendar quarter without specific approval of the Commission. The concentration of tritium prior to release from the Restricted Area shall not exceed an average of 4 x 10-5 pCi/ml during any calendar quarter. The con-
l "The release of radioactive liquid effluents, excluding tritium and dissolved noble gases, shall not exceed 10 curies during any calendar quarter without specific approval of the Commission.
        .          centration of dissolved noble gases prior to release from the                                     l Restricted Area shall not exceed an average of 3.2 x 10-5 pCi/ml during any calendar quarter."
The concentration of tritium prior to release from the Restricted Area shall not exceed an average of 4 x 10-5 pCi/ml during any calendar quarter. The con-centration of dissolved noble gases prior to release from the Restricted Area shall not exceed an average of 3.2 x 10-5 pCi/ml during any calendar quarter."
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Mr. R. C. DeYoung Page 2 April 4, 1973 Item 7_   Specification 3.9.3 The appropriate instantaneous concentration for dissolved noble gases, again using an occupancy factor based on 200 hours per year immersion, is 1.6 x 10-3 pCi/ml. We propose to revise Specification 3.9.3 by adding a maximum instantaneous concentration of 1.6 x 10-3 pCi/ml for dissolved noble gases.
Mr. R. C. DeYoung Page 2 April 4, 1973 Item 7_
Item 8     Specification 3.10, Objective 1 3                 3 Objective 1 will be changed from < 4340 m     /sec to < 5560 m   /sec in the next revision to the FSAR.
Specification 3.9.3 The appropriate instantaneous concentration for dissolved noble gases, again using an occupancy factor based on 200 hours per year immersion, is 1.6 x 10-3 pCi/ml. We propose to revise Specification 3.9.3 by adding a maximum instantaneous concentration of 1.6 x 10-3 pCi/ml for dissolved noble gases.
Item 9     Specification 3.10.2 This typographical error will be corrected in the next revision to the FSAR.
Item 8 Specification 3.10, Objective 1 3
Item 10   Specification 3.10, Bases
3 Objective 1 will be changed from < 4340 m /sec to < 5560 m /sec in the next revision to the FSAR.
                                                            -6 The dispersion factor will be changed from 4.61 x 10       sec/m to 3.6 x 10-6 sec/m3 in the next revision to the FSAR.
Item 9 Specification 3.10.2 This typographical error will be corrected in the next revision to the FSAR.
Item 11   Specification 4.11.1 This addition will be made in the next revision to the FSAR.
Item 10 Specification 3.10, Bases
Item 12   Specification 4.2.8 This specification was changed as requested in Revision 26 for Units 1 and 2. For Unit 3, the Reactor Vessel Surveillance Program is based on equivalent exposure times of 1.8, 13.3, 26.7, and 30.0 years. The specimens have been selected au.: fabricated as specified in ASTM-E-185-72.
-6 The dispersion factor will be changed from 4.61 x 10 sec/m to 3.6 x 10-6 sec/m3 in the next revision to the FSAR.
Item 13   Table 4.11.1 These additional analyses will be added in the next revision to the FSAR.
Item 11 Specification 4.11.1 This addition will be made in the next revision to the FSAR.
Item 14     Specification 6.1.1.6.b The assignment of a licensed Reactor Operator to a reactor, with a licensed Senior Reactor Operator available at the station at all times, is adequate to ensure plant safety when that reactor is in a cold shut-                                               1 I
Item 12 Specification 4.2.8 This specification was changed as requested in Revision 26 for Units 1 and 2.
down condition.                                                                                                       ,
For Unit 3, the Reactor Vessel Surveillance Program is based on equivalent exposure times of 1.8, 13.3, 26.7, and 30.0 years.
Item 15   Specification 6.1.1.6.e We believe one operator per shift can adequately handle all routine                                                     l station health physics requirements. For non-routine events, if additional                                             I
The specimens have been selected au.: fabricated as specified in ASTM-E-185-72.
Item 13 Table 4.11.1 These additional analyses will be added in the next revision to the FSAR.
Item 14 Specification 6.1.1.6.b The assignment of a licensed Reactor Operator to a reactor, with a licensed Senior Reactor Operator available at the station at all times, is adequate to ensure plant safety when that reactor is in a cold shut-1 down condition.
Item 15 Specification 6.1.1.6.e We believe one operator per shift can adequately handle all routine station health physics requirements.
For non-routine events, if additional


Mr. R. C. DeYoung                                           .
Mr. R. C. DeYoung Page 3 April 4, 1973 health physics personnel are needed, they will be called in to assist.
Page 3 April 4, 1973 health physics personnel are needed, they will be called in to assist.
Item 16 Proposed Specification 6.1.1.6.f For three-unit operation, we have made provisions for a minimum shift complement of three licensed Senior Reactor Operators, four persons with Reactor Operator licenses, and four unlicensed operators.
Item 16   Proposed Specification 6.1.1.6.f For three-unit operation, we have made provisions for a minimum shift complement of three licensed Senior Reactor Operators, four persons with Reactor Operator licenses, and four unlicensed operators. This shif t staffing is more than adequate for station operation, even during periods when the. computer may be inoperable. Additional manpower can be called in, if necessary, for special tests.
This shif t staffing is more than adequate for station operation, even during periods when the. computer may be inoperable. Additional manpower can be called in, if necessary, for special tests.
Sincerely, A. C. Thies ACT:vr l
Sincerely, A. C. Thies ACT:vr l
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                                      .}}
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Latest revision as of 00:40, 2 January 2025

Responds to NRC Re Facility Operations.Comments on Tech Specs 3.9,3.10,4.2,4.11 & 6.1
ML19316A053
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 04/04/1973
From: Thies A
DUKE POWER CO.
To: Deyoung R
US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 7911210623
Download: ML19316A053 (4)


Text

AEC DIS"MBUTION FOR PART 50 DOCIET !GT- ~ 'AL

~

(TFJ203ARY FORM)

C0iiTROL R3:_226;

~

I FII2 f,4UM" DAE OF DOC:

DATE REC'D LG isi.0 RPr crrdza Duke Power Company

.. Charlotte, N. C.

28201 A. C. Thicc P3 ~

h 4-73 h 6-73 X

ORIG CG (miER set.T AEC PD3 y

i SE?iT LOCAL PDR x

Mr. A Younc 1

'CIAS5:

(U//r7wP IiiF0 INPUT iiO CYS REC'D DO 7'

lic:

h0-2'/270/287 1

I)ESCRIPIIOli;

'Ltr re our 12-15-72.....f'urnishing comments

, ENCLOSURES:

on items enclosed in our 12-15-72 ltr under h;ading" Unit' 1 & 2 & Units 1,2 & 3 Operations' m-b...

PLANT NAES:

Otonee Units 1,2 & 3 c

FOR ACTIO:;/;;;70.:.:.ATIO:.

__BUILER(L)

A CHWENCER(L)

ZIEMAIGl(L)

YCUNGELCOD(E) u-7 n

c. 3

~/ Copies W/9 Copics W/ Copies W/ Copies W

CIARK(L)

STOLZ(L)

ROUSE (m)

REGAN(E)

W/ Copies W/ Copies W/ Copies W/ Copies GOLLER(L)

VASSALLo(L)

DICKER (E)

W/ Copies W/ Copies W/ Copies W/ Copies KNIEL(L)

SCHE!2L(L)

KNIGHICN(E)

W/ Copies W/ Copies W/ Copies W/ Copies Ilm.HNAL DISTRIBUTION kih FIIM)

TECH REVIEW DENTCN F&M WADE E

/AEC PDR (3)

ENDRIE GRIMES SMILEY BROWN

-E V'OGC, ROOM P-506A SCHROEDER GAMMILL NUSSBAUMER G. WILLIAMS E

,MUNIZING/ STAFF IGCCARY KASTNER SHEPPARD E

CASE KNIGHT BALLAIID LIC ASST.

~

'IAFBUSSO PAWLICKI SPANGLER SERVICE L

A/T IND G~

'B0YD SHA0 WIISON L

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C. THIE S P. O. Box 217s ELNeon VICE PasseDE NT PnODUC f sCao aseD TeaNsesessioN

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Mr. R. C. DeYoung, Assistant Director for Pressurized Water Reactors Directorate of Licensing U. S. Atomic Energy Commission Washington, D. C.

20545 Rg = '

Re: Oconee Nuclene Reation Docket C

-270, and -287

Dear Mr. DeYoung:

In response to your letter of December 15, 1973, we wish to comment on those items enclosed in your letter under the heading, " Units 1 and 2 and Units 1, 2, and 3 Operations":

Item 5 Specification 3.9 - Objective d.

The annual average concentration of dissolved gases in liquid waste of 4 x 10-7 pCi/ml is excessively conservative since it assumes complete immersion in water for a full year. An occupancy factor based on complete immersion for 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> per year yields an average concentration limit of 1.6 x 10-5 pCi/ml.

The inclusion of the occupancy factor is in accordance with 10 CFR 20.106(b), and we propose to change the concentration limit in Objective d. to 1.6 x 10-5 pCi/ml.

Item 6 Specification 3.9.2 l

Using the occupancy factor based on immersion for 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> per year, i

the appropriate quarterly average concentration is found to be 3.2 x 10-5 pCi/ml. Specification 3.9.2 will be revised to read:

l "The release of radioactive liquid effluents, excluding tritium and dissolved noble gases, shall not exceed 10 curies during any calendar quarter without specific approval of the Commission.

The concentration of tritium prior to release from the Restricted Area shall not exceed an average of 4 x 10-5 pCi/ml during any calendar quarter. The con-centration of dissolved noble gases prior to release from the Restricted Area shall not exceed an average of 3.2 x 10-5 pCi/ml during any calendar quarter."

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Mr. R. C. DeYoung Page 2 April 4, 1973 Item 7_

Specification 3.9.3 The appropriate instantaneous concentration for dissolved noble gases, again using an occupancy factor based on 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> per year immersion, is 1.6 x 10-3 pCi/ml. We propose to revise Specification 3.9.3 by adding a maximum instantaneous concentration of 1.6 x 10-3 pCi/ml for dissolved noble gases.

Item 8 Specification 3.10, Objective 1 3

3 Objective 1 will be changed from < 4340 m /sec to < 5560 m /sec in the next revision to the FSAR.

Item 9 Specification 3.10.2 This typographical error will be corrected in the next revision to the FSAR.

Item 10 Specification 3.10, Bases

-6 The dispersion factor will be changed from 4.61 x 10 sec/m to 3.6 x 10-6 sec/m3 in the next revision to the FSAR.

Item 11 Specification 4.11.1 This addition will be made in the next revision to the FSAR.

Item 12 Specification 4.2.8 This specification was changed as requested in Revision 26 for Units 1 and 2.

For Unit 3, the Reactor Vessel Surveillance Program is based on equivalent exposure times of 1.8, 13.3, 26.7, and 30.0 years.

The specimens have been selected au.: fabricated as specified in ASTM-E-185-72.

Item 13 Table 4.11.1 These additional analyses will be added in the next revision to the FSAR.

Item 14 Specification 6.1.1.6.b The assignment of a licensed Reactor Operator to a reactor, with a licensed Senior Reactor Operator available at the station at all times, is adequate to ensure plant safety when that reactor is in a cold shut-1 down condition.

Item 15 Specification 6.1.1.6.e We believe one operator per shift can adequately handle all routine station health physics requirements.

For non-routine events, if additional

Mr. R. C. DeYoung Page 3 April 4, 1973 health physics personnel are needed, they will be called in to assist.

Item 16 Proposed Specification 6.1.1.6.f For three-unit operation, we have made provisions for a minimum shift complement of three licensed Senior Reactor Operators, four persons with Reactor Operator licenses, and four unlicensed operators.

This shif t staffing is more than adequate for station operation, even during periods when the. computer may be inoperable. Additional manpower can be called in, if necessary, for special tests.

Sincerely, A. C. Thies ACT:vr l

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