ML20126F710
| ML20126F710 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 12/16/1992 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20126F714 | List: |
| References | |
| NUDOCS 9212310083 | |
| Download: ML20126F710 (5) | |
Text
-/
"'q UNITED STATES Ig
[" 3 g
NUCLEAR REGULATORY COMMISSION 5
'E W ASHING TON. D. C. 20555 y.....)
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URION ELECTRIC COMPANY CALLAWAY PLANT. UNIT 1 DOCKET N0. 50-483 SMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 74 License No. NPF-30 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by Union Electric Company (UE, the licensee) dated December 20, 1991, as clarified by letter -
dated October 30, 1992, complies with the 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 ap.lication, 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 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of-'the public;
- and, 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 license is amended-by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-30 is hereby amended to read as follows:
9212310083 921216 PDR ADOCK 05000483 p-PDR
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
74, and the Environmental Protection Plan contained in Appendix B, both of whicn are attached hereto, are hereby incorporated into the license.
VE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
The Technical Specifications are to be implemented within 50 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
'k John N. Hannon, Director Project Directorate 111-3 Division of Reactor Projects Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
December 16, 1992
ATTACHMENT-T0 LICENSE AMENDMENT NO. 74 OPERATING LICENSE NO. NPF-30 DOCKET N0. 50-4H1-3
- k Revise Appendix A Technical Specifications by removing the page identified below and inserting the enclosed page.
The revised page is identified b;; the-captioned amendment number and contains marginal lines indicating the area of change. The corresponding overleaf page is provided to maintain document completeness.
REMOVE INSERT 3/4 3-27 3/4 3-27 b
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TABLE 3.3-4 (Continued) n2
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ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS
.E TOTAL SENSOR TRIP ALLOWABLE g
FUNCTIONAL UNIT ALLOWANCE (TA)
Z ERROR (5)
SETPOINT VALUE I;
8.
Loss of Power (Continued) s b.
4 kV Urdervoltage
-Grid' Degraded Voltage' O.73 0.53 0
107.47 V 107.47 + 0.38 Y (120V Bus)
(120V Bus) w/119s delay w/119 i 11.6s delay 9.
Control Room Isolation a.
Manual Initiation N.A.
N.A.
N.A.
N, 'e N.A.
b.
Automatic Actuation N.A.
N.A.
N.A.
N.A.
N.A.
Y togic and Actuation U
Relays (SSPS) c.
Automatic Actuation Logic and Actuation Relays (80P ESFAS)
N.A.
N.A.
N. A.
N.A.
N.A.
27 d.
Phase "A" Isolation See Item 3.a. above for all Phase "A" Isolation Trip 5etpoints and Allowable g
Values.
10.. Solid-State Load Sequencer N.A.
N.A.
'N.A.
N.A.
N.A.
- 11. Engineered Safety se
?
Features Actuation System Interlocks
,,u a.
Pressurizer Pressure, P-11 N.A.
N.A.
M.A.
< 1970 psig
$ 1981 psig b.
Reactor Trip, P-4 N.A.
N.A.
N.A.
N.A.
N.A.
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! TABLE 3.3-4'(Continuedf m[
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. c TABLE NOTAT'!ONSL
- 11me constants utilized-in the-lead-lag controller for Steam Pressure-Low-are Ti.) 50 seconds:and tr < 5 seconds. CHANNEL CALIBRATION shall ensure i
that'these-time constants are adjusted to these values.
-**The time constant utilized in the rate-lag controller-for Steam-Line Pressure -
Negative Rate High is greater than-or equal to.50 seconds. CHANNEL CALIBRATION shall. ensure that this time constant is adjusted to this v lue.--
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