ML20030D357

From kanterella
Jump to navigation Jump to search
Supplies Addl Info & Comment to NRC 810702 Evaluation of SEP Topic VI-4, Override of Containment Purge Isolation & Other ESF Actuation Signals
ML20030D357
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 08/26/1981
From: Linder F
DAIRYLAND POWER COOPERATIVE
To: Crutchfield D
Office of Nuclear Reactor Regulation
References
TASK-06-04, TASK-6-4, TASK-RR LAC-7761, NUDOCS 8109010235
Download: ML20030D357 (2)


Text

-

O B

C64//?PZs4/b27 h

[k COOPERAT/VE PO BOX 817 2615 EAST AV SOUTH LA CROSSE. WISCONSIN 54601 (608) 7R84000 August 26, 1981 In reply, please refer to LAC-7761 3

yM9 DOCg\\ g

'N.

Director of Nuclear Reactor Regulation 5 x b

7

/4 Attn:

Mr. Dennis M. Crutchfield, Chief 2

Operating Reactors Branch No. 5 Division of Opera *ing Reactors

~C

\\p, q.

7 U.

S.

Nuclear Ru ttory Commission 9

eE (1

V s_

Washington, D.

C.

20555 V,,.

j(s e,

-ce

@\\ \\

SUBJECT:

DAIRYLAND POWER COOPERATIVE O

LA CROSSE BOILING WATER REACTOR (LACBWR)

PROVISIONAL OPERATING LICENSE NO. DPR-45 SEP TOPIC VI-4, OVERRIDE OF CONTAINMENT PURGE ISOLATION AND OTHER ESF ACTUATION SIGNALS (LA CROSSE)

REFERENCE:

(1)

NRC Letter, Crutchfield to Linder, i

Dated July 2, 1981

Dear Mr. Crutchfield:

Reference (1) enclosed a copy of your current evaluation of the electrical rortion of generic activity B-24 for La Crosse.

The assessment compared our facility, as described in Docket No. 50-409, with the criteria currently used by the regulatory staff for licensing new facilities.

You asked us to inform you if our as-built facility differs from the licensing basis assumed in the assessment with thirty (30) days upon receipt of Reference (1).

We have reviewed the evaluations and would like to supply the I

following additional information and comments:

~

In Section 1.0, Introduction; the last line in the first paragraph should refer to LACBWR, not Millstone Unit 1.

In Section 2.2, Containment Ventilation Isolation Circuits Design Description; the first line of the second paragraph should be revised to read; "The four-inch vent header valve will also close on all of the above signals."

The high l

radiation signal for closure was added this year.

In Section 2.2, Containuent Ventilation Isolation Circuits Design Description; the last paragraph should be revised to read, "The high primary system pressure signal can be bypassed y l

/Q 8109010235 810826 DR ADOCK 05000409

  • DR

,_. - - - ~ _

Mr. Dennis M.

Crutchfield, Chief LAC-7761 i

U.

S.

Nuclear Regulatory Commission August 26, 1981 for calibration by means of a test switch on the front of the amplifier drawer for each chaanel.

The amplifier drawers are located in the vertical contril panel in the control room.

If both drawer test switches are in the " Test" position at the same time a reactor scram will result.

The scram signal from each drawer cannot be bypassed at the same time.

The ut, of either the drawer test switch or the key-operated scram bypass switch is annunciated."

In Section 2.3, Containment Ventilation 1sulation System Design Evaluation; in the second paragraph, the last line should be changed to read, "Dr.iryland Power Cooperative installed a l

locked cover over all reset switches that are not key-operated."

4 In Section 2.3, Containment Ventilation Isolation System Design Evaluation; in the fourth paragraph, delete the third and fourth sentences as Dairyland Power Cooperative has installed a high radiation signal closure on all CVI valves / dampers.

If you have any further comments, please contact us.

4 Very truly yours, DAIRYLAND PO ER COOPERATIVE

[

}

(

Mw Frank Linder, General Manager FL: HAT:eme cc:

J.

G.

Keppler, Director, NRC-DRO III NRC Resident Inspectors l

i

-