ML20004G113

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Submits Summary of Items Discussed During 810219 Telcon Re Response to IE Bulletin 80-06, Engineered Safety Feature (ESF) Reset Controls. Plant Sys Serving safety-related Functions Have Been Tested
ML20004G113
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 06/22/1981
From: Shimshak R
DAIRYLAND POWER COOPERATIVE
To: James Shea
Office of Nuclear Reactor Regulation
References
IEB-80-06, IEB-80-6, LAC-7618, NUDOCS 8106290214
Download: ML20004G113 (2)


Text

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DlDA/RYLAND

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COOPERAT/VE Po BOX 817 2615 EAST AV SOUTH = LA CROSSE. WISCONSIN 54601 (608) 788 4 000 June 22, 1981 In reply, please a

refer to LAC-7618 DOCKET NO. 50-409 Director of Nuclear Reactor Regulation

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ATTN:

Mr. James J. Shea, Project Manager

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Operating Reactors Branch No. 5

U Division of Operating Reactors

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U. SJ Nuclear Regulatory Commission

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Washington, D. C.

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SUBJECT:

DAIRYLAND POWER COOPERATIVE pg

Il LA CROSSE BOILING WATER REACTOR (LACDWR) x-PROVISIONAL OPERATING LICENSE NO. DPR-45 N

e, IE BULLETIN NO. 80 ENGINEERED SAFETY (ESF q

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RFSET CONTROLS

References:

(1)

NRC Letter, Keppler to Linder, dated March 13, 1980.

(2)

DPC Letter, Linder to Keppler, LAC-6987, dated June 20, 1980.

Dear Mr. Shea:

Pursuant to the telephone conference held February 19 between DPC, you, and EG&G, we are hereby submitting a summary of the items discussed and our response to them.

In paragraph 2 of Reference 2, the question was raised of how the actuating signal is removed.

Our response was that the signals refaxed to here are trip signals from various reactor plant parameters and that the trip signal is removed when the parameter was restored to less than tha trip value.

A question was raised relative to whether all systems serving safety-related functions have been tested in response to Bulletion No.

80-06.

Our response was yes, and we have on file records to that effect.

A question was asked as to why we are not modifying those devices that do not remain in emergency. mode upon reset of an; actuating signal.

This refeasd to items 3 and 5 of Appendix A of Reference 2.

Our response was that since reference was submitted, that both devices' circuit has been modified to add a manual reset function.

Therefore, all safety related equipment now remains in its emergency mode upon reset of a safety actuation signal. l

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,,. g; Mr. James J. Shea, Project Manager IAC-7618 Operating Reactors Branch No. 5 June 22, 1981 The last. item asked for a description of all proposed or implemented modificai.2ons.

IACBWR.has implemented all necessary modifications.

The type of change effected for all the modifications consisted of adding a contact in series with the parameter trip coil.

This contact would remain open after the trip signal until reset by a momentary pushbutton or key switch.

If you have any more questions, please contact us.

Very truly yours, DAIRYLAND POWER COOPERATIVE ff h. -

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R. E. Shimshak LACBWR Plant Superintendent RES: HAT:af cc:

J. Keppler, Reg. Dir., NRC-DRO III NRC Resident Inspectors

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