ML19325C953

From kanterella
Jump to navigation Jump to search
Amend 163 to License DPR-49,revising Tech Spec Table 3.2.B to Reflect New Containment High Pressure Trip Level Setting & Mod Remarks Section Re New Trip Level Setting
ML19325C953
Person / Time
Site: Duane Arnold 
(DPR-49-A-163)
Issue date: 10/06/1989
From: Hannon J
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19325C954 List:
References
NUDOCS 8910180207
Download: ML19325C953 (4)


Text

..

p..,;, [;

i t

a

.a H !"

" } jp g,

.Y

'o UNITED STATES '

t y' i (i

[

' ~

^g g

NUCLEAR REGULATORY COMMISSION j

,g-

E WASHINGTON, D. C. 70555 g

October 6, 1989 j

-IOWA ELECTRIC LIGHT AND POWER COMPANY:

.CEU KAL IDWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE.

m

- J

' DOCKET NO. 50-331 DUANE' ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 163 License ~No. DPR-49 i

c1 1.

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

A.

The: application for amendment by Iowa Electric Light' and Power Company, et al. ; dated October 13, 1987 complies with the standards 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;

'B.,

The' facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the L

.Comission; K

C.

There is reasonable assurance-(i).that the activities authorized by this amendment can be conducted without endangering the health 1

and safety of'the public, and (ii):that-such activities will be conducted in compliance with the'Comission's regulations;1 i

i D.-

The issuance of this amendment will not be ~ inimical to the comon defense and security or to the health-and safety of the public; and:

L L

.E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all-applicable requirements have~been satisfied.

12.-

Accordingly, the license is amended by changes to the Technical Specifi-cations'as indicated in the attachment to this license amendment and q

paragraph 2.C.(2) of Facility Operating License No. DPR-49 is hereby L.

amended to read as follows:

L l

8910180207 891006 DR ADOCK 05000331 PNU p

^

...,,... _. ~. _ _... -.

_.... _... ~ ~..... _..... _.,.... _...

.)

l :. '.

b t

2=.

.v j

(2) Technical' Specifications

.The Technical Specifications contained in Appendix A, as revised through Amendment No.163, are hereby incorporated in-the license..The licensee shall operate the facility-in accordance with the Technical Specifications.

. 3.;

The license amendment,is. effective as.of-the date of. issuance and

'shall be implemented within 30 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION v

'.2 4 a. W John N. Hannon, Director H

Project Directorate-III-3 Division of Reactor Projects

III, IV, V and Special' Projects

-Office of Nuclear Reactor Regulation

Attachment:

' Changes to the Technical Specifications

.i i-Date of. Issuance: October 6,~1989 l

l L

i i

i

k.

) -

4 8

swp g -.

L,a i ATTACHMENT TO LICENSE-AMENDMENT NO. 163- -

FACILITY ~ OPERATING LICENSE NO. DPR ]

DOCKET NO. 50-331 Replacethe7following page of-the Appendix'A Technical Specifications with the enclosed page. The revised areas are indicated by marginal lines.

s 3.2-9; e

f l ':,

l( -

1 r1' h

0 b

I; I

f :-'

l e

~.

1 l.'

l'

.N -

1.

lv i

1 i

4 o

' y [.:;l_ll1 y

.7 -

j,

. TABLE '3 2-8 (Continued) j INSTRMNTATION THAT INITIATES OR CONTROLS THE CORE Als CONTAllOENT COOLIIS SYSTEMSL 2

Mirimun No.

~

of Operable Instrument flunber of I

Channels Per Instrument Channels-Trip System (1)

Trip Function-Trip Level Setting

Provided by Design ~

Remarks b

1 Reactor Low Level-

> + 305.5 in. above-

2. Instrument Channels : 'PreventsJinadvertent (inside shroud)

Vessel zero (2/3 core -

operation of contain 1 height) ment spray during _

i accident condition j

2 Containment High

> 2.0 psig 4 Instrument Channels Prevents-inadvertent 1

l Pressure operation of contain-'-

j ment spray during.

normal operation -

j w

7 1

Confirinatcry Low-

--< + 170 in. Indicated -

2 Instrument Channels - ADS Permissive 1

Level level (4) i 2

High Dryuell

--< 2.0 psig 4 HPCI Instrument Initiates Core" Spray LCPI and IFCI pumps.,.

Pressure Channels o

l In cog unction with 450 ps'g reactor p

operation.'init1stes pressure of LPCI and n,

j g.

core spray valves.-

2 Reactor Low i

Pressure

-- 450 psig 4 Instrument Channels ' Periaissive for Core Spray and i

Ilection valves.

(!1 gh dryuell pressure-l w

starts LPCI ans. Core-pumps).?In unction with 4

i 1

w tri le low water

~

i lev 1, cycles core ei spray and LPCI-

-injection valves open.

i i

i t

.;,.,_.1.

A.

,.r

_~

_.s,.

-