ML20210B409

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Amend 107 to License DPR-46,stating That Main Steam Drain Header Primary Containment Isolation Valves Normally Open
ML20210B409
Person / Time
Site: Cooper Entergy icon.png
Issue date: 02/03/1987
From: Muller D
Office of Nuclear Reactor Regulation
To:
Nebraska Public Power District (NPPD)
Shared Package
ML20210B412 List:
References
DPR-46-A-107, TAC 63580 NUDOCS 8702090151
Download: ML20210B409 (4)


Text

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UNITED 8TATES g

NUCLEAR REGULATORY COMMISSION

E WASHINGTON, D. C. 20665 g

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NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 l

COOPER NUCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.107 License No. DPR-46 L

i 1.

The Nuclear degulatory Commission (the Comission) has found that:

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A.

The application for amendment by Nebraska Public Power District g

(thelicensee)datedNovember6,1986,complieswiththestandards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I;

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B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; i

C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health j

and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; r

i 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 I

E.

The issuance of this amendment is in accordance with 10 CFR Part l

51 of the Comission's regulations and all applicable requirements I

have been satisfied.

2.

Accordingly, the licensee is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-46 is hereby amended to read as follows:

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I 8702090151 870203 PDR ADOCK 0500 8

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(2) Technical Specification The Technical Specifications contained in Appendix A, as revised through Amendment No.107, 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 its date of issuance.

FOR THE NUCLEAR REGULATORY CONtISS ON

/

Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing 4

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Attachment:

Changes to the Technical l

Specifications Date of Issuance: February 3,1987

4 ATTACHMENT TO LICENSE AMENDMENT NO.107 FACILITY OPERATING LICENSE NO. DPR-46 DOCKET NO. 50-298 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indiciated by marginal lines.

Pages 168 9

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I COOPER NUCLEAR STATION

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3 TABLE 3.7.1-(Page 1)

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PRIMARY CONTAINMENT ISOI.ATION VALVES

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l Number of Power Maximum Action On Operated Valves

. Operating Normal

. initiating

]

Valve & Steam Inboard outboard Time (Sec) (1)

Position (2)

Signal (3)

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Main Steam Isolation Valves I

MS-AO A.B.C

& D 4

3<T<5 0

GC i

MS-AO A.B.C. & D.=

4 3<T<5 0

CC 1

j Drywell Floor Drain Iso.. Valves 1

1 15 0

GC RW-AO-82 RW-AC-83 Drywell Equipment Drain 1

1 15 0

-CC Iso. Valves RW-AO-94 RW-AO-95 j'

Main Steam Line Drain I

1 30 0

'cc

-l l

Valves MS-MO-74, MS-MO-77 i

j Reactor Water Sample Valves 1

1.

15 0

CC i

RRV-740AV, RRV-741AV i

Reactor Water Cleanup System 1

1 60 0

CC l

!so. Valves RWCU-MO-15, RWCU-MO-18

]

RilR Reactor llead Spray 1

I' 60

.C SC j

1so. Valves kilR-MO-32, RHR-MO-33 1,

i RilR Suction Cooling Iso.

1 1

.40 C

SC j

Valve RilR-MO-17. RHR-MO-18 i

l RIIR Discharge to Radwaste 1

1 20 C

'SC j

iso. Valves RilR-MO-57, RiiR-MO-67 t

l Suppression Chamber Purge &

2 15

.C SC.

1 Vent PC-24'.;AV, PC-230MV I

Suppression Cliamber N, Supply 2

15

.C

-SC

]

PC-237AV, l'C-233MV

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