ML20083F916
| ML20083F916 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 01/04/1984 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20083F917 | List: |
| References | |
| NUDOCS 8401100415 | |
| Download: ML20083F916 (5) | |
Text
UtdTED STATES
'8 "
- F',n NUCLEAR REGULATORY COMMISSION
$.g WASHINGTON. D. C. 20555 o, a
..... /e COMMONWEALIHEDIS0NCOMPANY Docket No.
50-249 DRESDEN NUCLEAR POWER STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 71 License No. DPR-25 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Commonwealth Edison Company (the licensee) dated August 25, 1983, as supplemented November 23, 1983, complies with the standards and re Energy Act of 1954, as amended (the Act)quirements of the Atomic
, 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 authorized by this amendmen't 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; D.
The issuance of this amendmer:t will not be inimical to the common defense and security tr to the health and safety of the public; E.
The issuance of this amendmer,t is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
.e 8401100415 840104 PDR ADOCK 05000249 p
' f 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendaent and paragraph 3.8 of Facility Operating License No. DPR-25 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained 1n Appendix A, as revised through Amendment No. 71, 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 M x Ns W b Y
Dennis M. Crutch iel Chief Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of_ issuance: January 4,.1984 h.
ATTACHMENT TO LICENSE AMENDMENT NO. 71 FACILITY OPERATING LICENSE DPR-25 DOCKET NO. 50-249 Revise the Technical Specifications by replacing the following pages with attached re~ vised pages. These_ revised pages contain the captioned amendment number and marginal lines to reflect the area of change.
Replace Pages 19 90 o
b I'
l.2
- AI ETY I.llitT 2.2 L1tiLTitlG SAFETY SYSTEM SETTING D R-25
_a-l.2 Ill OR C00L'AllT SYSTEli
~
~ pp l i en b i l i ty,,:
A
~pplienbility:
A Applies to limitn on renctor coolnnt nystem
~
prenoure.
Applien. to trip settin8s of the instruments and devices which are provided to prevent the reactor nyntem nafety limits from being exceeded.
g ective:
Objective:
To entnblinh a limit below which the inte-To define the level of the process verlab'les at P.rity of the reactoc coolant nyntem in not which automatic protective action is initinted threatened due to an overprenoure condition.'
to prevent the safety Lltalta from being exceeded.
Specification:
_ Specification:
The renetor coolant system pressure shall not A.
Renctor Coolant liigh Pressure Scram shall be l
exceed 1345 psig at any time when irradiated
<1060 pelg.,
fuel is present in the reactor vessel.
B.
Primary Syntem Safety Valve Noelnal Settings shall be as follows:
I valve at 1835 psig*
l 2 valven at 1240 psig 2 valves at 1250 psig 2 valves at 1260 psig-2 valves at 1260 psig The allowable setpoint error for each vnive shall be +l%.
- Target Rock combination safety / relief valve.
9 i
\\
19 knendrnent flo.%Jy3I71
-3.6 LIMITING CONDITION FOR OPERATION 4.6 ' SURVEILLANCE REQUIREMENT DPR-25 an orderly shutdown shall be initiated and the reactor shall be in a cold shutdown condition with 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
The primary containment sump sampling system 2.
The primary containment sump sampling and-and air sampling system shall be operable air sampling system operability will be during power operation.
If either a sump observed as part of 4.6.0.2.
water sample or a containment air sample cannot be obtained for any reason, reactor operation is permissible only during the E.
Safety and Relief Valves succeeding seven days unless the system is made operable during this period.
A minimum of 1/2 of all safety valves shall be bench checked or replaced with a bench checked E.
Safety and Relief Valves valve each refueling outage.
The popping point of the safety valves shall be set as follows:
1.
During reactor power operating conditions and whenever the reactor coolant pressure is greater than 90 psig and temperature greater Number of Valves Set Point (psig)-
than 3200F, all nine of the safety valves shall be operable.
The solenoid activated 1
1135 I
presstfre valves shall be operable as required 2
1240 by Specification 3.5.0.
2
-1250 2
1260 2
1260 2.
If specification 3.6.E.1 is not met, an orderly The allowable setpoint error for each valve shutdown shall be initiated and the reactor is + 1%.
coolant pressure and temperature shall be
-( 90 psig and f 3200F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
All relief valves shall be checked for set pressure each refueling outage.
The set pressures shall be:
Valve No.
Set Point (psig) i 203-3A 1124*
203-3B 1101 203-3C 1101 203-30 1124 203-3E 1124 l
- Target Rock combination safety / relief valve I
The allowable setpoint error for each valve is +_
90 Amendment No.g 71
,