ML20086C015
| ML20086C015 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 11/19/1991 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20086C017 | List: |
| References | |
| NPR-43-A-076, NPR-43-A-76, NUDOCS 9111210318 | |
| Download: ML20086C015 (5) | |
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NUCLEAR REGULATORY COMMISSION
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WASmNGTON, D. C. 20$M
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- p DETROIT EDIS0N COMPANY LERMI-2 DOCKET NO. 50-341, AMENDHENT TO FACILITY OPERATING llCENSE Arnendment No. 76 License No. NPF-43 1.
The Nuclear Regulatory Comission (the Conrnission) has found that:
A.
The application for arnendment by the Detroit Edison Company (the licensee) dated December 22, 1988, complies with the standards and requirements of the Atcmic Energy Act of 1954, as amended (the Act),
and the Commission't rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conforrr.ity 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 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; 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 regulaticos and all applicable requirements have been satisfied.
2.
Accordingly, the license is emended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating Licensc t'o. NPF-43 is hereby amended to read as follows:
Technical 3pecifications and Environmental Protection Plan The Technical Specificationc contained in Appendix A, as revised through Amendment No. 76, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
DECO shall operate the facility in accordance with the Technical Specifications and the i
Environmental Protection Plan.
9111210310 911119 DR ADOCK OSOO 1
2 3.
This 11 cense amendment is effective as of its date of issuance with full i
implementation within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMIS$10N Ac.. AR r-L. B. Marsh, Directot' Project Directorate !!1-1 Division of Reactor Pro'ects Ill/IV/V Office of Nuclear Reactor Regulatinn
Attachment:
Changes to the Technical Specifications Date of issuance:
November 19, 1991 b
V
ATTACHMENT TO LICENSE A>.ENDMENT NO. 76_
FACILITY OPERATING LICENSE NO. NPF-43 DOCKET NO. 50 341 l
Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
REMOVE INSERT 3/4 3-12 3/4 3-12 3/4 3-14e 3/4 3-14a i
l
e i
TABLE 3.3.2-1. (Continued)
ISOLATION ACTUAT;0N INSTRUMENTATION VALVE GROUPS MINIMUM APPLICABLE E2 OPERATED BY OPERABLE CHANNE S OPERATIONAL m
SIGNAL PER TRIP SYSTEM a)
CONDITION ACTION E5 TRIP FUNCTION 2.
REACTOR WATER CLEANUP SYSTEM ISOLATION g-a.
A Flow - Hich 10, 11 1(h) 1, 2, 3 23 I
((
b.
Heat Exchang:er/ Pump /High Energy Piping Area Temperature - High 10, 11 6
1,2,3 23 i
c.
Heat Exchanger / Pump / Phase Separator Area Ventilation A Temp. - High 10, 11 2
1,2,3 23 l
d.
SLCS Initiation 11 NA 1, 2, 3 23 ReactorVesselLow(ggter Level - Level 2 1
10, 11 2
1, 2, 3 23 e.
's
=
Y f.
Deleted C
g.
Manual Initiation 10, 11 1/ valve 1, 2, 3 26 3.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION RCIC Steam Line Flow - High 1.
Differential Pressure 8
I 1, 2, 3 23 a.
l[
2.
Time Delay 8
1 1,2,3 23 g[
a f.
b.
RCIC Steam Supply 8, 9(f) 2 1, 2, 3 23 Pressure - Low 5
c.
RCIC Turbine Exhaust
(,
l-Diaphragm Pressure - High 8
2 1, 2, 3 23 35 d.
RCIC Equipment Room Temperature - High 8
I 1, 2, 3 23 c.
Manual Initiation 8, 9 1/ valve 1, 2, 3 26 e
\\
l TABLE 3.3.2-1 (Continued) 1$3LAT10N ACTUATION INSTRUMENTATION 1ABLE NOTATIONS (Continued)
(f)
Isolates with simultaneous RCIC Steam Supply Pressure-Low (Isolation Instrumentation) and Drywell Pressure High (ECCS Actuation Instrumentation).
(9)
Isolates with simultaneous HPCI Steam Supply Pressure Low (Isolation Actuation Instrumentation) and Drywell Pressure High (ECCS Actuation Instrumentation).
(h)
This trip function is derived from three non-redundant flow transmitters and a non-redundant flow summer.
Inoperability of the non-redundant circuitry causes the channels in both trip systems to be inoperable.
The remainder of the circuit is redundant and can be considered on a per trip system basis.
Both trip systems may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance of the non-redundant circuitry without taking the required ACTION provided that the remainder of the Reactor Water Cleanup System Isolation channels (except the SLCS Initiation) are OPERABLE.
(I)
Secondary Containmer.t Isolation Push-buttons.
(d) pressure signal actuates Groups 2, 12, 13, 14, 15, 16, 17, 18, and With time delay of 45 seconds.
U These trip function (s) are common to the RPS trip function.
FERMI - UNIT 2 3/4 3 241 Amendment No. AJ, JE, 76
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