ML17238A683
ML17238A683 | |
Person / Time | |
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Site: | Dresden ![]() |
Issue date: | 03/29/1974 |
From: | Abel J Commonwealth Edison Co |
To: | Giambusso A US Atomic Energy Commission (AEC) |
References | |
Download: ML17238A683 (2) | |
Similar Documents at Dresden | |
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Category:Letter
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ML0715705012007-04-0505 April 2007 CC-AA-309-1001, Rev 3, Attachment 1, Design Analysis Major Revision Cover Sheet, 9389-46-19-1, Rev 003 Diesel Generator 3 Loading Under Design Bases Accident Condition ML0715705052007-04-0404 April 2007 CC-AA-309-1001, Rev 1, Attachment 1, Design Analysis Major Revision Cover Sheet, 989-46-19-2, Rev 003, Calculation for Diesel Generator 2 Loading Under Design Bases Accident Condition ML0634601312006-12-0707 December 2006 Attachment 11, Exelon/Amergen Response to the Request for Additional Information, EP-EAL-0611, Criteria for Choosing Containment Radiation Monitor Reading Indicative Loss of the RCS Barrier ML0621300322006-05-31031 May 2006 GE-NE-0000-0053-8435-R1-NP, Rev 1, Dresden 2 & 3 and Quad Cities 1 & 2, Safety Valve Setpoint Tolerance Relaxation, May 2006 ML0606203682006-01-26026 January 2006 Attachment 3 (Technical Specifications) and 4 (Affidavit and Non-Proprietary Version of Attachment 2 to Exelon Letter Dated January 26, 2006) ML1024201462005-12-0707 December 2005 Groundwater Tritium Investigation Report, Dresden Generating Station, Project Number EXENW-18513-400 RS-05-064, Commitments and Plans Related to Extended Power Uprate Operation2005-05-13013 May 2005 Commitments and Plans Related to Extended Power Uprate Operation ML0514400842005-05-0505 May 2005 Enclosure 1, Attachment 2, 26A6266AB, Revision 4, Steam Dryer, GE Nuclear Energy, Design Specification Data Sheet, Dated May 5, 2005 ML0513601002005-04-30030 April 2005 Enclosure 2, Attachment 2, Replacement Steam Dryer Reactor Vessel Bracket Stress Report for Quad Cities 1, 2, and Dresden 2,3, GE-NE-0000-0034-4803-02, Non-Proprietary, Dated April 2005 ML0513300532005-04-25025 April 2005 Enclosure 3, Dresden Strain Gage Uncertainty Evaluation, SIA File No.: EXLN-17Q-301, Revision 0, Dated April 25,2005 ML0514400812005-04-24024 April 2005 Enclosure 1, Attachment 1, 26A6266, Rev 3, Steam Dryer, GE Nuclear Energy, Design Specification, April 24, 2005 RS-05-042, Additional Information Related to Analysis and Design of New Quad Cities Steam Dryers, and Responses to Requests for Additional Information Related to EPU Operation at Dresden and Quad Cities Nuclear Power Stations2005-04-0606 April 2005 Additional Information Related to Analysis and Design of New Quad Cities Steam Dryers, and Responses to Requests for Additional Information Related to EPU Operation at Dresden and Quad Cities Nuclear Power Stations ML0507303262005-03-31031 March 2005 Non-Proprietary Dresden and Quad Cities Neutron Flux Evaluation ML0510902702005-01-31031 January 2005 Attachment 2, CDI Report No. 05-01, Rev 0, Revised Hydrodynamic Loads on Quad Cities Unit 2 Steam Dryer to 200 Hz, with Comparison to Dresden Units 2 & 3 Loads. RS-05-005, Letter RS-05-005, Dated 1/05/05, Submittal of Information Regarding Extended Power Uprate Vulnerability Reviews2005-01-0505 January 2005 Letter RS-05-005, Dated 1/05/05, Submittal of Information Regarding Extended Power Uprate Vulnerability Reviews 2022-06-30 |
Text
Commonw~ E4iscm_.. FHe Cy.
One First Nati;;,Wiaza, Chicago, Illinois Address Reply to: Post Office Box 767 Chicago, Illinois 60690 March 29, 1974 Mr. Angelo Giambusso Deputy Director for Reactor Projects Directorate of Licensing Off ice of Regulation U .:s. Atomic Energy Commission Washington, D.C. 20545
Subject:
Supplement to Report of Dresden Unit 3 Main Steam Isolation Valve Leakage Test -
AEC Dkt 50-249
Dear Mr. Giambusso:
A report of the Dresden Unit*3 Main Steam Isolation Valve Leakage testing was submitted .to you by letter dated August 20, 1973. The attached supplement provides additional information concerning the leakage rate "as found" during, the firs_t refueling outage in Spring, 1973.
One signed original and 39 copies of this report are included. for your use.
Very truly yours,
- ~
Nuclear Licensing Administrator Boiling Water Reactors Att.
. .* ,~t'**.*.
. 1**
- . /~~* l*
. .. ,....;... ~;.*c SIDil1ARY REPORT OF DRESDEN 3 MAIN STEAM ISOIATION VALVE LEAKAGE
. -~*
. Pursuant to th~ *~equirements of section6.6.E.3.d of the
- Technical Specifications, this report summarizes the results of the main steam isolation valve (MSIV) .leakage tests performed on Dresden 3.
The only leak tests done on the nresderi 3 MSIV 1 s to date were the pre-operational tests and the first refueling outage leak tests.
Included are th~: as found and after repair data for those valves that .
were repaired *.
- Leaka*ge (SCFH) **
- MSIV Number Pr.e~op,Test . . 1st Refueling Outag~
- As Found . After Repair
- .J-203-lA <**i . *~.' . 1. 02 . :
. 3-203-.lB 1.
3-203-iC r ----.
3-203-lD l.*,,*. *. 6.45 3-20J-2A. i' 1.20 J-203-2B .. 1 ..*.. 29.22 4*.85*
J-20J-2C . 4 . 49.00 1.62**-
. 3-20J-2D 2*' 0.00 The nia.;~um all~wable. le.akage' 'froin one valve is 11.5 SCFH.
All valves are *.well. within limits after repair.
- . *PaEP~ BY* **of! f)~ *.* .*
~> . .,;* .... . : .
-~ .
t:. .* 21/~
.* :i* ...
. APPROVED BY ....7
. .*. Represents leakage through bo:th 1B and 2B
- i:'* Represents leakage* through both. le. and 2C LJD:ls
~ -:
.-*- i*.*.
- J
. ':. *7'? . .:~. :