ML17199F617
| ML17199F617 | |
| Person / Time | |
|---|---|
| Site: | Dresden  (DPR-19-A-006, DPR-19-A-6) |
| Issue date: | 04/16/1975 |
| From: | Ziemann D US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML17199F614 | List: |
| References | |
| NUDOCS 8601290181 | |
| Download: ML17199F617 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 COMMONWEALTif EDISON COMPANY DOCKET NO. 50-237 DRESDEN UNIT 2 L
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AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 6 License No. DPR-19
- 1. The Nuclear Regulatory Conunission (the Conunission) has found that:
A.
The application for amendment by the Conunonwealth Edison Company (the licensee) dated April 4, 1975, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Conunission's niles and regulations set forth in 10 CFR Chapter I; B.
The facility will pperate in conformity with the application, the provisions. of the Act,. and the rules and regulations of the Conuniss ion;;
C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii)* that *such activities
- will be conducted in compliance with the Commission's regulations, and D.
The issuance of this amendment will not be inimical to the conunon defense and security or to the health and safety of the public.
- 2.
Accordingly, the license is amend*ed by a change to the Technical.
Specifications as indicated in the attachment to this license amendment and Paragraph 3.B of Facility License No. DPR-19 is hereby amended to read as follows:
- "3.B Technical Specifications The Technical Specifications contained in Appendix A, as revised, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications, as revised by issued changes thereto through Change No. 33."
- 3.
This license amendment is effective as of the date of its issuance.
Attachment:
Change No. 32. to the Technical Specifications Date of Issuance: April 16, 1975 FOR THE NUCLEAR REGULATORY COMMISSION g~-£2; Dennis L. Ziemann~;;~
Operating Reactors Branch #2 Division of Reactor Licensi_ng
ATTACHMENT TO LICENSE AMENDMENT NO. 6 CHANGE NO. 32 TO THE TECHNICAL SPECIFICATIONS FACILITY OPERATING LICENSE NO. DPR-19 DOCKET NO. 50-237 Replace existing page 75 of the Technical Specifications with the attached revised p'age 75.
Changed area on the revised page is
'reflected by a marginal line..
- 32
- 3. S LIMITING CONDITION FOR OPERATION
- 4.
From and after the date* that one of the LPCI pumps is made or found to be inoper-.
able for any reason, reactor operation is permissible only during the succeeding 30*.
days unless. such pump is sooner made oper-able, provided that during such 30 days the remaining active components of the LPCI and containment cooling subsystem and all active components of both core spray subsystems and the diesel genera-tors required for operation of such com-ponents if no external sour~e of power were available shall be operable.
- 5.
From and after the date that the LPCI*
subsystem is made or found to be oper-
. able for any reason, reactor operation is permissible only during the succeeding 7 days unless it is sooner made operable, provided that during such 7 days all active components of both core spray sub-systems, the containment cooling subsystems (including 2 LPCI pumps) and the diesel generators required for operation of such components if no external source of power were available shall be operable.
- 6.
Cont.ainment cooling spray loops are re-quired to be operable when the r*eactor water temperature is greater than 212°F except that a maximum of one drywell spray loop may be inoperable for 30 days when the reactor water temperature is greater than 212°F.
- 7. If the requirements.of 3.5.A cannot be met, an orderly shutdown of the reactor shall be initiated and the reactor shall be in Cold Shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Sub-sequently, the reactor may be placed in Refuel, for post maintenance testing of control rod drives only provid*ed no work is being performed which has the potential to drain the reactor vessel.
.~. '
4.5 SURVEILLANCE REQUIREMENTS
\\
- 4.
When it is determined that one of the
~. *,
LPCI pumps is inoperable, the remainingr ~
active components of the LPCI and con-tainment cooling subsystem, both core a
spray subsystems and the diesel genera-tors required for operation of such components if no external source of power were available shall be demonstrated to be operable immediately and the operable LPCI pumps daily thereafter.
- 5.
When it is determined that the LPCI subsystem is inoperable, both core spray subsystems, the containment cooling subsystem, and the diesel generators required for operation of such components if no external source of power were available shall be demonstrated to be operable im-mediately and daily thereafter.
- 6.
During each five-year period, an air test shall be performed on the dry-well spray headers and nozzles.
Rev. w/ch. No. 32 dated 4/16/75.
75