ML20113G826: Difference between revisions

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| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 2
| page count = 2
| project =  
| project = TAC:M83382
| stage = Request
| stage = Request
}}
}}


=Text=
=Text=
{{#Wiki_filter:-.                ..
{{#Wiki_filter:-.
a CENTERIOR ENERGY Donald C. Shelton                                                     300 Maison Avenue Vee Pmident Nuclear                                                   Toiedo, OH 43652 0001 Dam                                                                   (419)249 2300 Docket Number 50-346 License Number NPF-3 Serial Number 2023 May 1, 1992 United States Nuclear Regulatory Commission Document Control Desk Vashington, D. C. 20555 Subj ec t :   License Amendment Request to Revise Technical Specification 3/4.4.6.2, Reactor Coolant System - Operational Leakage, and its Bases Gentlemen:
a CENTERIOR ENERGY Donald C. Shelton 300 Maison Avenue Vee Pmident Nuclear Toiedo, OH 43652 0001 Dam (419)249 2300 Docket Number 50-346 License Number NPF-3 Serial Number 2023 May 1, 1992 United States Nuclear Regulatory Commission Document Control Desk Vashington, D. C. 20555 Subj ec t :
Enclosed is an application for an amendme'it to Davis-Besse Nuclear                             -
License Amendment Request to Revise Technical Specification 3/4.4.6.2, Reactor Coolant System - Operational Leakage, and its Bases Gentlemen:
Power Station (DBNPS), Unit Number 1, Operating License Number NPF-3, Appendix A, Technical Specification (TS) 3/4.4.6.2, Reactor Coolant System - Operational Leakage and its Bases. This request proposes several changes to TS 3/4.4.6.2 and its Bases which involve clarifying the applicability of TS 4.0.4 exceptions, specifying alloved usage of the containment atmosphere gaseous rMioactivity monitoring system as an alternate method of determining the presence of Reactor Coolant System leakage (consistent with existing TS 3/4.4.6.1, Reactor Coolant System Leakage - Leakage Detection Systems), and clarifying other existing wording. The proposed revisions to the Bases clarify that leakage from the Reactor Coolant System Ptessure Isolation Valves is
Enclosed is an application for an amendme'it to Davis-Besse Nuclear Power Station (DBNPS), Unit Number 1, Operating License Number NPF-3, Appendix A, Technical Specification (TS) 3/4.4.6.2, Reactor Coolant System - Operational Leakage and its Bases. This request proposes several changes to TS 3/4.4.6.2 and its Bases which involve clarifying the applicability of TS 4.0.4 exceptions, specifying alloved usage of the containment atmosphere gaseous rMioactivity monitoring system as an alternate method of determining the presence of Reactor Coolant System leakage (consistent with existing TS 3/4.4.6.1, Reactor Coolant System Leakage - Leakage Detection Systems), and clarifying other existing wording.
                " identified leakage" under TS 3/4.4.6.2 and is considered a portion of the allowed limit.       Toledo Edison requests that this amendment be issued by the NRC by October 30, 1992.
The proposed revisions to the Bases clarify that leakage from the Reactor Coolant System Ptessure Isolation Valves is
9205120281 920501 s    PDR       ADOCK 05000346
" identified leakage" under TS 3/4.4.6.2 and is considered a portion of the allowed limit.
: 1. P                           PDR Operatmg Compon.es Clesetand Efectnc mummahrg
Toledo Edison requests that this amendment be issued by the NRC by October 30, 1992.
                                                                                                            /
9205120281 920501 PDR ADOCK 05000346 s1.
Toledo Ecson                                                                                     j4
P PDR Operatmg Compon.es
/
Clesetand Efectnc mummahrg Toledo Ecson j4


Docket. Number 50-346 License Number NPF-3
Docket. Number 50-346 License Number NPF-3
    -Serial Number 2023 Page-2 Should further information be required, please contact Mr. R. V. Schrauder. Manager - Nuclear Licensing, at (419) 249-2366.
-Serial Number 2023 Page-2 Should further information be required, please contact Mr. R. V. Schrauder. Manager - Nuclear Licensing, at (419) 249-2366.
Very truly yours, f             1
Very truly yours, f
      ,B /dlm et? closure cc     A. B. Davis, Regional Administrator, NRC Region III J. B. Hopkins, NRC/NRR DB-1 Senior Project Manager V. Levis, NRC Region III, DB-1 Senior Resident Inspector J. R. Villiams, Chief of Staf f, Ohio Emergency Haragement Agency, State of Ohio (NRC Liaison)
1
Utility Radiological Safety Board 1
,B /dlm et? closure cc A. B. Davis, Regional Administrator, NRC Region III J. B. Hopkins, NRC/NRR DB-1 Senior Project Manager V. Levis, NRC Region III, DB-1 Senior Resident Inspector J. R. Villiams, Chief of Staf f, Ohio Emergency Haragement Agency, State of Ohio (NRC Liaison)
1}}
Utility Radiological Safety Board 1}}

Latest revision as of 00:08, 13 December 2024

Forwards Application for Amend to License NPF-3,revising TS 3/4.4.6.2, RCS Operational Leakage & Bases, Specifying Allowed Usage of Containment Atmosphere Gaseous Activity Monitoring Sys
ML20113G826
Person / Time
Site: Davis Besse 
Issue date: 05/01/1992
From: Shelton D
CENTERIOR ENERGY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20113G827 List:
References
TAC-M83382, NUDOCS 9205120281
Download: ML20113G826 (2)


Text

-.

a CENTERIOR ENERGY Donald C. Shelton 300 Maison Avenue Vee Pmident Nuclear Toiedo, OH 43652 0001 Dam (419)249 2300 Docket Number 50-346 License Number NPF-3 Serial Number 2023 May 1, 1992 United States Nuclear Regulatory Commission Document Control Desk Vashington, D. C. 20555 Subj ec t :

License Amendment Request to Revise Technical Specification 3/4.4.6.2, Reactor Coolant System - Operational Leakage, and its Bases Gentlemen:

Enclosed is an application for an amendme'it to Davis-Besse Nuclear Power Station (DBNPS), Unit Number 1, Operating License Number NPF-3, Appendix A, Technical Specification (TS) 3/4.4.6.2, Reactor Coolant System - Operational Leakage and its Bases. This request proposes several changes to TS 3/4.4.6.2 and its Bases which involve clarifying the applicability of TS 4.0.4 exceptions, specifying alloved usage of the containment atmosphere gaseous rMioactivity monitoring system as an alternate method of determining the presence of Reactor Coolant System leakage (consistent with existing TS 3/4.4.6.1, Reactor Coolant System Leakage - Leakage Detection Systems), and clarifying other existing wording.

The proposed revisions to the Bases clarify that leakage from the Reactor Coolant System Ptessure Isolation Valves is

" identified leakage" under TS 3/4.4.6.2 and is considered a portion of the allowed limit.

Toledo Edison requests that this amendment be issued by the NRC by October 30, 1992.

9205120281 920501 PDR ADOCK 05000346 s1.

P PDR Operatmg Compon.es

/

Clesetand Efectnc mummahrg Toledo Ecson j4

Docket. Number 50-346 License Number NPF-3

-Serial Number 2023 Page-2 Should further information be required, please contact Mr. R. V. Schrauder. Manager - Nuclear Licensing, at (419) 249-2366.

Very truly yours, f

1

,B /dlm et? closure cc A. B. Davis, Regional Administrator, NRC Region III J. B. Hopkins, NRC/NRR DB-1 Senior Project Manager V. Levis, NRC Region III, DB-1 Senior Resident Inspector J. R. Villiams, Chief of Staf f, Ohio Emergency Haragement Agency, State of Ohio (NRC Liaison)

Utility Radiological Safety Board 1