ML20091B196

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Amend 70 to License NPF-43,modifying Numbers for Two Primary Containment Isolation Valves
ML20091B196
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 05/16/1991
From: Marsh L
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20091B199 List:
References
NUDOCS 9105300281
Download: ML20091B196 (5)


Text

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UNITED STATES

-y-E NUCLEAR REGULATORY COMMISSION I

O, WASHINGTON. D.C. 20556 gw,/

DETROIT EDIS0N COMPANY DOCKET NO. 50-341 FERMI-2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 70 License No. NPF-43 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by the Detroit Edison Company (the licensee) dated January 28, 1991, 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 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 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-43 is hereby l

amended to read as follows:

Technical Specifications and Environmental Protection Plan l

The Technical Specifications contained in Appendix A, as revised l

through Amendment No. 70, and the Environmental Protection Plan I

contai.ied in Appendix B, are hereby incorporated in the license.

l DECO shall operate the facility in accordance with the Technical l

Specifications and the Environmental Protection Plan.

l 9105300201 910516 DR ADOCK 0500 1

l

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION L. B. Marsh, Director Project Directorate 111-1 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

May 16, 1991 1

ATTACHMENT TO llCENSE AMENDMENT N0. 70 EAClllTY OPERATING LICENSE N0. NPF-43 DOCKET NO 50-341 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. The corresponding overleaf pages are also provided to maintain document completeness.

REMOVE INSERT

  • 3/4 6-31
  • 3/4 6-31 3/4 6-32 3/4 6-32
  • 0verleaf page provided to maintain document completeness.

No changes contained in these pages.

~

..7 TABLE 3.6.3-1 (Continued) 53 PRIMARY CONTAINMENT ISOLATION VALVES MAXIMUM ISOLATION TIME a

gg (Seconds)

q VALVE FUNCTION AND NUMBER B.

Remote-Manual Isolation Valves '*' (Continued) 19.

Primary Containment Monitorina _ System Torus Suction Isolation Valves NA Division I:

T50-F407A Division II:

T50-F407B 20.

Drywell Atmosphere Sample Isolation Valves NA Division I:

T50-F401A T50-F402A u,

];

T50-F403A T50-F404A 4,

T50-F405A Division II:

T50-F401B j

T50-F402B T50-F403B T50-F404B T50-F4058 1

21.

Drywell to Suppression Chamber Vacuum Breakers N, Supply Isolation Valves NA T48-F416 T48-F417 j"

T48-F418 g

T48-F419

[t T48-F420 g

T48-F421 T48-F422 i

r*

!?

T48-F423 T48-F424 1

3; T48-F425 T48-F426 r

T48-F427

t TABLE 3.6.3-1 (Cont:aued)

?

SE PRIMARY CONTAINMENT ISOLAlION VALVES

~~

MAXIMUM ISOLATION TIME EE (Seconds)

El VALVE FUNCTION AND NUMBER

~

B.

Remote-Manual Valves

( (Continued) 22.

Drywell Pressure Instrumentation Isolation Valves NA Division I:

T50-F420A Division II:

T50-F4208 23.

Suporession Pool Level Instrumentation Isolation Valves NA Division I:

E41-F401'b' T50- F412A"

E41-F400 x

Division II:

E41-F403(b)

T' T50-F412B"

k$

E41-F402

{

24.

EECW Supply to Drywell Eauipment Isolation Valves NA Division I:

P44-F606A l

Division II:

P44-F6068 l[

25.

EECW Return from Drywell Eauipment Isolation Valves NA s

l EI Division I:

P44-F607A l

l E[

P44-F616

[

f EI Division II:

P44-F607B

[,

P44-F615 CD f

i i

L t