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| | number = ML17238A798 | | | number = ML17238A798 |
| | issue date = 04/02/1975 | | | issue date = 04/02/1975 |
| | title = Dresden Station Units 2 and 3 Quad-Cities Station Units 1 and 2 Reactor Water Chemistry Data | | | title = Quad-Cities Station Units 1 and 2 Reactor Water Chemistry Data |
| | author name = Abel J S | | | author name = Abel J |
| | author affiliation = Commonwealth Edison Co | | | author affiliation = Commonwealth Edison Co |
| | addressee name = Silver R J | | | addressee name = Silver R |
| | addressee affiliation = NRC/NRR | | | addressee affiliation = NRC/NRR |
| | docket = 05000237, 05000249, 05000254, 05000265 | | | docket = 05000237, 05000249, 05000254, 05000265 |
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| =Text= | | =Text= |
| {{#Wiki_filter:1-* -' .LCommonweAI Edison * . One First Nationai Plaza. Chicago. Illinois_ | | {{#Wiki_filter:.LCommonweAI Edison |
| | . One First Nationai Plaza. Chicago. Illinois_ |
| Address Reply to: Post Office Box 767 Chicago, Illinois 60690 | | Address Reply to: Post Office Box 767 Chicago, Illinois 60690 |
| * Docket Mr. R. J. Silver Operating Reactors -Branch 2 Office of Regulation U.S. Nuclear Regulatory . 'Washington, D.c. 20555 | | 'R\eg~Ja!ory. *Docket ~j~ |
| | Mr. R. J. Silver Operating Reactors - Branch 2 Office of Regulation U.S. Nuclear Regulatory |
| | . 'Washington, D.c. 20555 |
|
| |
|
| ==Subject:== | | ==Subject:== |
| Dresden Station Units 2 and 3 | | Dresden Station Units 2 and 3 |
| | .Quad-Cities Station Units 1 and 2 Reactor Water Chemistr~ata . |
| | NRC Dkts. 50-237, ¢o'.'""2!__ 50-254,. |
| | and 50--265 |
|
| |
|
| ==Dear Mr. Silver:== | | ==Dear Mr. Silver:== |
| .Quad-Cities Station Units 1 and 2 Reactor Water . NRC Dkts. 50-237, ¢o'.'""2!__
| | |
| 50-254,. and 50--265 Attached is the subject dat;.a_surrunarized in graphic form for an 11-month period of 1973. The data shown is tive of the -normal water during operating history o*f the subject reactors.
| | Attached is the subject dat;.a_surrunarized in graphic form for an 11-month period of 1973. The data shown is representa-tive of the -normal water che6is~ry during t~~ operating history o*f the subject reactors. Additional data is availa.ble for NRC review at the respective stations. |
| Additional data is availa.ble for NRC review at the respective stations. | |
| Also attached are excerpts from the GenE;!ral | | Also attached are excerpts from the GenE;!ral |
| * Elec.tric, Sargent & Lundy, and Graver chemistry specification | | * Elec.tric, Sargent & Lundy, and Graver chemistry specification *applicable to the subject units. |
| *applicable to the subject units. With respect to dissolved oxygen specifically, we have only scant data .for reactor water. The data we have, however, glves no*indication that our.BWR's are any-different than any others.** | | With respect to dissolved oxygen specifically, we have only scant data .for reactor water. The data we have, however, glves no*indication that our.BWR's are any-different than any others.** That is, the dissolved oxygen values are less than 0 .3 ppm at operating conditions. Such value~ were verified and are documented in the General Electric startup test re~orts. |
| That is, the dissolved oxygen values are less than 0 .3 ppm at operating conditions. | | One (1) signed orig.inal and 39 copies of this data are provided .for your information. |
| Such were verified and are documented in the General Electric startup test One (1) signed orig.inal and 39 copies of this data are provided .for your information. | | * Very truly yours, . |
| * Very truly yours, . /1/(:.. // -Z i | | /1/(:.. // - |
| ,.1 . '--v . y / --<./ . : J. S. Abel -*. f Nuclear Licensing Administrator
| | i'- ~:/_ |
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| | . : ~ |
| | J. S. Abel |
| | -*. f Nuclear Licensing Administrator |
| | / *Boiling Water Reactors ...-~. *--* _ |
| | . '"' { i'{ . |
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| | .'}} |
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Category:Letter
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Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000237/20230052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Dresden Nuclear Power Station, Units 2 and 3 (Report 05000237/2023005; 05000249/2024005) IR 05000254/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Quad Cities Nuclear Power Station (Report 05000254/2024005; 05000265/2024005) ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 RS-24-078, Alternative Request RV-08, Revision 1, Associated with Safety Relief Valve Testing Interval2024-08-20020 August 2024 Alternative Request RV-08, Revision 1, Associated with Safety Relief Valve Testing Interval ML24215A2912024-08-14014 August 2024 Request for Withholding Information from Public Disclosure Alternative Schedule to Complete Decommissioning Beyond 60-Years of Permanent Cessation of Operations IR 05000237/20240022024-08-14014 August 2024 Integrated Inspection Report 05000237/2024002 and 05000249/2024002 IR 05000237/20240102024-08-0909 August 2024 NRC Age-Related Degradation Inspection Report 05000237/2024010 and 05000249/2024010 ML24183A1082024-08-0808 August 2024 – Issuance of Amendment Nos. 302 and 298 Adoption of Tstf-505, Provide Risk Informed Extended Completion Times – RITSTF Initiative 4b SVP-24-049, Owners Activity Report Submittal Sixth 10-Year Interval 2024 Refueling Outage Activities2024-08-0707 August 2024 Owners Activity Report Submittal Sixth 10-Year Interval 2024 Refueling Outage Activities IR 05000237/20230112024-08-0707 August 2024 Reissue - Dresden Nuclear Power Station, Units 2 and 3 Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 IR 05000237/20200012024-08-0606 August 2024 Reissue - Dresden Nuclear Power Station, Units 2 and 3 - Integrated Inspection Report 05000237/2020001 and 05000249/2020001 ML24184A1712024-08-0202 August 2024 SLRA Schedule Letter IR 05000254/20243012024-08-0101 August 2024 NRC Initial License Examination Report 05000254/2024301; 05000265/2024301 SVP-24-048, Registration of Use of Casks to Store Spent Fuel2024-07-31031 July 2024 Registration of Use of Casks to Store Spent Fuel RS-24-073, Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations – Additional Information Supporting Request to Withhold Security-Related Information2024-07-31031 July 2024 Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations – Additional Information Supporting Request to Withhold Security-Related Information ML24136A1322024-07-30030 July 2024 Transmittal Letter for Renewed License ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification ML24204A1862024-07-24024 July 2024 – Regulatory Audit in Support of License Amendment Requests to Adopt TSTF 505, Revision 2; TSTF-591, Revision 0; and 10 CFR 50.69 ML24193A0882024-07-24024 July 2024 Request for Withholding Information from Public Disclosure for Dresden Nuclear Power Station, Unit 1 Alternative Schedule to Complete Decommissioning Beyond 60-Years of Permanent Cessation of Operations (Docket 50-10) SVP-24-046, Turbine Trip and Automatic Scram Due to Digital EHC Power Supply Intermittent Failure2024-07-22022 July 2024 Turbine Trip and Automatic Scram Due to Digital EHC Power Supply Intermittent Failure RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions SVP-24-041, Regulatory Commitment Change Summary Report2024-07-0505 July 2024 Regulatory Commitment Change Summary Report SVP-24-043, Registration of Use of Casks to Store Spent Fuel2024-07-0505 July 2024 Registration of Use of Casks to Store Spent Fuel ML24162A0982024-07-0303 July 2024 – Issuance of Amendment Nos. 301 and 297 Adoption of 10 CFR 50.69 Risk Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors IR 05000237/20243012024-06-27027 June 2024 NRC Initial License Examination Report 05000237/2024301; 05000249/2024301 ML24138A0572024-06-26026 June 2024 – Issuance of Amendment Nos. 285 and 278 Application to Adopt TSTF-564, Safety Limit MCPR SVP-24-040, Registration of Use of Casks to Store Spent Fuel2024-06-25025 June 2024 Registration of Use of Casks to Store Spent Fuel ML24138A1812024-06-18018 June 2024 Aging Management Audit Plan Regarding the Subsequent License Renewal Application Review RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations RS-24-063, Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-222024-06-14014 June 2024 Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-22 ML24128A2742024-06-14014 June 2024 Notice of Acceptance and Opportunity for Hearing - Letter SVP-24-039, Ile Post Exam Package Letter2024-06-12012 June 2024 Ile Post Exam Package Letter ML24156A2332024-06-11011 June 2024 Letter Supplemental Information for Alternative Schedule to Complete Decommissioning Beyond 60-Years of Permanent Cessation of Operations RS-24-053, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed2024-06-0606 June 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24183A2752024-05-30030 May 2024 Registration of Use of Casks to Store Spent Fuel SVPLTR 24-0020, Registration of Use of Casks to Store Spent Fuel2024-05-30030 May 2024 Registration of Use of Casks to Store Spent Fuel RS-24-056, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2024-05-28028 May 2024 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML24110A0492024-05-28028 May 2024 Audit Report Related to the TSTF-505 and 10 CFR 50.59 Amendments SVPLTR 24-0019, Registration of Use of Casks to Store Spent Fuel2024-05-23023 May 2024 Registration of Use of Casks to Store Spent Fuel ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24145A0432024-05-23023 May 2024 Registration of Use of Casks to Store Spent Fuel 10 CFR 72.212 2024-09-06
[Table view] |
Text
.LCommonweAI Edison
. One First Nationai Plaza. Chicago. Illinois_
Address Reply to: Post Office Box 767 Chicago, Illinois 60690
'R\eg~Ja!ory. *Docket ~j~
Mr. R. J. Silver Operating Reactors - Branch 2 Office of Regulation U.S. Nuclear Regulatory
. 'Washington, D.c. 20555
Subject:
Dresden Station Units 2 and 3
.Quad-Cities Station Units 1 and 2 Reactor Water Chemistr~ata .
NRC Dkts. 50-237, ¢o'.'""2!__ 50-254,.
and 50--265
Dear Mr. Silver:
Attached is the subject dat;.a_surrunarized in graphic form for an 11-month period of 1973. The data shown is representa-tive of the -normal water che6is~ry during t~~ operating history o*f the subject reactors. Additional data is availa.ble for NRC review at the respective stations.
Also attached are excerpts from the GenE;!ral
- Elec.tric, Sargent & Lundy, and Graver chemistry specification *applicable to the subject units.
With respect to dissolved oxygen specifically, we have only scant data .for reactor water. The data we have, however, glves no*indication that our.BWR's are any-different than any others.** That is, the dissolved oxygen values are less than 0 .3 ppm at operating conditions. Such value~ were verified and are documented in the General Electric startup test re~orts.
One (1) signed orig.inal and 39 copies of this data are provided .for your information.
/1/(:.. // -
i'- ~:/_
Z y
-v,.1
/ --<./
. : ~
J. S. Abel
-*. f Nuclear Licensing Administrator
/ *Boiling Water Reactors ...-~. *--* _
. '"' { i'{ .
..., i.t
.'