ML20084G653: Difference between revisions

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Your letter of August 2, 1972, requested information concerning the baffles installed in the Dresden Units 2 and 3 tori. Responses were submitted on November 27, 1972 and March 26, 1973.        The March 26 letter indicated the baffle analysis performed for Oyster Creek Nuclear Generating Station was applicable for the Dresden Units 2 and 3 torus baffles and the baffles would be removed from both Dresden Units 2 and 3.
Your letter of August 2, 1972, requested information concerning the baffles installed in the Dresden Units 2 and 3 tori. Responses were submitted on November 27, 1972 and March 26, 1973.        The March 26 letter indicated the baffle analysis performed for Oyster Creek Nuclear Generating Station was applicable for the Dresden Units 2 and 3 torus baffles and the baffles would be removed from both Dresden Units 2 and 3.
As indicated, the baffles have been removed completely from the Dresden Unit 3 torus and will be removed from the Unit 2 torus during the next refueling outage.                        The November 27, 1972 letter provided a safety evaluation justifying continued operation with the baffles in place.
As indicated, the baffles have been removed completely from the Dresden Unit 3 torus and will be removed from the Unit 2 torus during the next refueling outage.                        The {{letter dated|date=November 27, 1972|text=November 27, 1972 letter}} provided a safety evaluation justifying continued operation with the baffles in place.
The March 26, 1973 letter also indicated that a generic report on the results of torus testing at Quad-Cities Station is being prepared by the General Electric Company and that we would review the applicability of this report to Dresden Units 2 and 3.
The {{letter dated|date=March 26, 1973|text=March 26, 1973 letter}} also indicated that a generic report on the results of torus testing at Quad-Cities Station is being prepared by the General Electric Company and that we would review the applicability of this report to Dresden Units 2 and 3.
A discussion of the applicability of the General Electric report, i
A discussion of the applicability of the General Electric report, i
         "NEDO-10859, Steam Vent Clearing Phenomena and Structural Response of the EWR Torus (Mark I Containment) ", was submitted in our letter dated July 11, 1973 concerning Torus Ring Header Analyses.
         "NEDO-10859, Steam Vent Clearing Phenomena and Structural Response of the EWR Torus (Mark I Containment) ", was submitted in our {{letter dated|date=July 11, 1973|text=letter dated July 11, 1973}} concerning Torus Ring Header Analyses.
As discussed in Section 6 of the General Electric report NEDO-10859, the results of the Quad-Cities structural analysis can be extended to all Mark I containments with design internal pressures of 56 psig or greater.                        The design pressure of the Dresden Units 2 and 3 containments was 62 psig.
As discussed in Section 6 of the General Electric report NEDO-10859, the results of the Quad-Cities structural analysis can be extended to all Mark I containments with design internal pressures of 56 psig or greater.                        The design pressure of the Dresden Units 2 and 3 containments was 62 psig.
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Latest revision as of 00:37, 26 September 2022

Submits Completed Info Re Torus Baffles,In Responseto 720802 Request.Baffles Removed from Both Units
ML20084G653
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 07/16/1973
From: Abel J
COMMONWEALTH EDISON CO.
To: Skovholt D
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20084G655 List:
References
5585, NUDOCS 8304220181
Download: ML20084G653 (2)
v • d • e


Text

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4 Comm One First ealth Edison tional Plaza, Chicago, Ithnois O Address Reply to: Post Office Box 767 Chicago, Ilknois 60690 July 16, 1973 / / .g3 LS $$$5 Mr. D. J. Skovholt N" Assistant Director for Operating Reactors g7gd Directorate of Licensing U.S. Atomic Energy Commission Washington, D.C. 20545

Subject:

Torus Baffle Studies for Dresden Units 2 and 3, AEC Dkt[50'T3'7s and 50-249 N /

Dear Mr. Skovholt:

Your letter of August 2, 1972, requested information concerning the baffles installed in the Dresden Units 2 and 3 tori. Responses were submitted on November 27, 1972 and March 26, 1973. The March 26 letter indicated the baffle analysis performed for Oyster Creek Nuclear Generating Station was applicable for the Dresden Units 2 and 3 torus baffles and the baffles would be removed from both Dresden Units 2 and 3.

As indicated, the baffles have been removed completely from the Dresden Unit 3 torus and will be removed from the Unit 2 torus during the next refueling outage. The November 27, 1972 letter provided a safety evaluation justifying continued operation with the baffles in place.

The March 26, 1973 letter also indicated that a generic report on the results of torus testing at Quad-Cities Station is being prepared by the General Electric Company and that we would review the applicability of this report to Dresden Units 2 and 3.

A discussion of the applicability of the General Electric report, i

"NEDO-10859, Steam Vent Clearing Phenomena and Structural Response of the EWR Torus (Mark I Containment) ", was submitted in our letter dated July 11, 1973 concerning Torus Ring Header Analyses.

As discussed in Section 6 of the General Electric report NEDO-10859, the results of the Quad-Cities structural analysis can be extended to all Mark I containments with design internal pressures of 56 psig or greater. The design pressure of the Dresden Units 2 and 3 containments was 62 psig.

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8304220181 730716 5585 PDR ADOCK 05000237 P pop I9/

G-COPY SENT REGION y

  1. (^ Commonwealth Edison Comps-fn Mr. D. J. Skovholt July 16, 1973 This report completes our response concerning evaluation of torus baffles at Dresden Units 2 and 3.

One signed original and 39 copies of this report are provided for your use. ,

Very truly yours,

. S. Abe Nuclear Licensing Administrator -

Boiling Water Reactors

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