ML20214E118

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Provides Addl Response to Generic Ltr 83-28 Re Reactor Trip Breaker Automatic Shunt Trip Actuation.Confirmation That Shunt Trip Components Have Been Seismically Qualified Per Reg Guide 1.100,Rev 1 Addressed
ML20214E118
Person / Time
Site: Point Beach  
Issue date: 05/13/1987
From: Fay C
WISCONSIN ELECTRIC POWER CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
CON-NRC-87-51, RTR-REGGD-01.100, RTR-REGGD-1.100 GL-83-28, TAC-53186, TAC-53187, VPNPD-87-203, NUDOCS 8705210664
Download: ML20214E118 (2)


Text

d lMsconsm Electnc ma coww 231 W MICHIGAN,P o. BOX 2046, MILWAUKEE,Wi53201 (414)221 2345 VPNPD-87-203 NRC-87-51 May 13, 1987 U. S. NUCLEAR REGULATORY COMMISSION Document Control Desk Washington, D. C.

20555 Gontlomont DOCKETS 50-266 AND 50-301 ADDITIONAL RESPONSE TO GENERIC LETTER 83-28 REACTOR TRIP BREAKER AUTOMATIC SHUNT TRIP ACTUATION POINT DEACH NUCLEAR PLANT, UNITS 1 AND 2 In your letter dated September 26, 1984, the NRC provided a Safety Evaluation Report (SER) on our responso to Itom 4.3 of Gonoric Lottor 83-28, "Roactor Trip Breaker Automatic Shunt Trip."

The SER was conditioned upon four items requiring additional information and/or confirmation by Wisconsin Electric.

Information allowing disposition of throo of the four items was provided in our letters dated February 26 and August 8, 1985.

The remaining itom to be addressed by this lettor is confirmation that the shunt trip compononts have boon soismically qualified in accordance with the provisions of Regulatory Guido 1.100, Revision 1, which ondornos IEEE Standard 344.

In April 1986, Wostinghouso Electric Corporation completed the successful gonoric qualification testing of tho shunt trip ccmpononta.

Wo have sinco verified that the genoric soismic, environmental, and lifo cyclo testing of tho shunt trip compononts is applicable to the Point Beach installations.

Survoillanco of the shunt trip attachmonto and automatic shunt trip panols will bo provided to assuro that qualification will bo maintained throughout the installed life of the components.

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NRC Document Control Desk April 13, 1987 Page 2 Should you have any further questions or need additional details, please contact us.

Very truly yours, 6EvSy C. W./ ay Vice President Nuclear Power Copies to NRC Regional Administrator, Region III NRC Resident Inspector l

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