ML19276E889
| ML19276E889 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 02/27/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19276E886 | List: |
| References | |
| NUDOCS 7903210579 | |
| Download: ML19276E889 (3) | |
Text
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f'k NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPp0RTING AMENDMENT NO. 40 TO PROVISIONAL OPERATING LICENSE NO. DPR-19 COMMONWEALTH EDISON COMPANY DRESDEN UNIT N0. 2 DOCKET NO. 50-237 Introduction By letter received on February 4,1979, Commonwealth Edison Company (CECO) proposed an amendment to the Dresden Unit No. 2 Technical Specifications.
The proposed change requested authorization to operate Dresden Unit No. 2 after a negative pressure of 0.2 inches of water was established in the Reactor Duilding areas below the refueling floor to demonstrate secondary containment integrity.
This negative pressure was maintained in the Reactor Building area for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following initiation at 1:00 p.m. on February 4,1979.
Evaluation The existing Dresden Unit No. 2 Specification 4.7.C.l.c requires that the secondary containment be capable of maintaining 0.25 inches of water vacuum at each refueling outage prior to refueling.
On February 2,1979, several blowout panels on the Reactor Building for Dresden Unit Nos. 2 and 3 became detached as a result of a ventilation system malfunction that pressurized the Reactor Building.
The over-pressurization caused the blowout panels to fail, which resulted in a 22' x 40' opening in the Reactor Building superstructure at the refueling floor level.
We reviewed CECO's request and obtained additional related information from licensee representatives by a telephone conversation on February 4, 1979.
Tne following factors related to the proposed change were con-sidered in our review:
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ATTACHMENT TO LICENSE AMENDMENT NO. Q PROVISIONAL OPERATING LICENSE NO. DPR-19 DOCKET NO. 50-237 Change the Technical Specifications contained in Appendix A by removing Page 120 and inserting the enclosed Page 120.
The revised page contains the captioned amendment number and a vertical line indicating the area of change.
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C(2) of Provisional Operating License No. DPR-19 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 40, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION I)
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1 ww Dennis L. Zieman, Chief Operating Reactors Branch 42 Division of Operating Reactors
/:tachment:
C.anges to the Technical Specifications Date of Issuance:
February 27, 1979
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