ML20039F901
| ML20039F901 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 12/23/1981 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20039F902 | List: |
| References | |
| NUDOCS 8201140053 | |
| Download: ML20039F901 (4) | |
Text
-
SA MGo o
UNITED STATES 8
.-[( (',j NUCLEAR REGULATORY COMMISSION
=. 's - ' " /+ C WASHINGTON D. C. 20555 Y.4,,W.ej x
9 p
l
+....
t COP.MONWEALTH EDISON COMPANY DOCKET NO. 50-249 i
i DRESDEN STATION UNIT NO. 3 j
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No, 57 License No. DPR-25 i
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated November 23, 1981 complies with standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application,
~
the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities a'uthorized by this amendment can be conducted without endan.gering the health
])
and safety of the public, and (ii) that such activities will be conducted in compli nce with the Commission's regulations; I
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and :afety of the public; and i
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the licens'e is amended by changes to the Technical Specifications as indicated in the attachment to this license amend-ment, and paragraph 3.B of Facility Operating License No. DPR-25 is hereby amended to read as follows:
3.B Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 57, are hereby incorporated in the license.
The licensee.shall operate the facility in accordance with the Techhical Specifications.
r 9201140053 911223 PDR ADOCK 05000249 p
o 2
3.
This license amendment is effective as of November 23, 1981.
FOR THE NUCLEAR REGULATORY COMMISSION
,jf Thomas A.'Ippolito, Chief i
Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 23, 1981 4
1
)
- v-m
~
e-
-r 4
,w=
M-y
ATTACHMEilT TO LICE!!SE AMENDMENT NO. 57 FACILITY OPERATING LICENSE NO. DPR-25 DOCKET NO. 50-249 Replace page 77 with the enclosed page 77.
l l
l l
l y
e
- 3..~e LIMITING CONDITION Full OPEHATION 4.5 SUllVEILLANCE IlEQUIllEMENT containment coolin subsystem, both core spray subsystems and both diesel gencr-ators required for operation of such components if no exter nal source of power were available, shall be operable.
4.
If the requirements cf 3.5.B cannot be met an orderly shutdown s.iall be initiated and the reactor shall be in a Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
C.
IIPCI Subsystem C.
Surveillance of IIPCI Subsystem shall be performed as follows:
1.
Except as specified in 3.5. C.2 below, the IIPCI subsystem shall be operable IIPCI Subsystem Testing shall tw as spect-1.
whenever the reactor pressure is greater
' fled: lit 4. 5. A.1.a, b, c, d, and f, except than 90 psig and irradiated fuel is in the that the llPCI pump shall deliver at least
. reactor vessel.
5000 gpm against a system head correspond-Ing to a reactor vessel pressure of 1150 psig I
2.
From and after the date that the IIPCI to 150 psig.
subsystem is made or found to be inoper-2.
able for any reason, reactor operation is When it is determined that itPCI subsystem permissible only during the succeeding is inoperable, the LPCI subsyste m, both seven days unless such subsystem is core spray subsystems, the automatic sooner made operable, provided that dur-pressure relief subsystem, and the motor ing such seven days all active components operated isolation valves and shell side of the Automatic Pressure Helief Sub-make-up system for the isolation condenser system, the core spray subsystems, LPCI system shall be demonstrated to be operable subsystem, and isolation cooling system immediately. The automatic pressure relief
- k are operable.
and motor operated isolation vahes and shcIl side make-up system of the isolation conden-ser shall be demonstrated to be cperable daily thereafter.
3.
If the requirements of 3.5.t; cannot be met an orderly shutdown shall be Initiated and
- Note:
From November 23, 1981 through November 29, 1981, the reactor pressure shall be reduced t ith the HPCI inoperable, CECO is not required 90 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
to demonstrate 'the operability of the automatic re' lief subsystem daily.
During this ss period, two feedwater pumps shall be operating i
at power levels above 300 We and one feedwater pump operating as normally re.tuired and one additional feedwater pump shall be operable at Amendment No. 57 i
II t
!