ML040710582

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Revision No. 44 to Procedure No. EI-1, Emergency Classification and Actions.
ML040710582
Person / Time
Site: Palisades Entergy icon.png
Issue date: 03/03/2004
From: Brott N
Nuclear Management Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
260249 EI-1, Rev 44
Download: ML040710582 (3)


Text

Date Entered: Mar 03, 2004 TO: USNRCIWASHINGTON JMCKNIGHT Copy Number: 145

<TRANSMITAL NUMBER: 260249 H PROCEDURE NUMBER: El-1 TITLE: EMERGENCY CLASSIFICATION AND ACTIONS TRANSMITTAL: LISTED BELOW ARE NEW/REVISED PROCEDURES WHICH MUST BE IMMEDIATELY INSERTED INTO OR DISCARDED FROM YOUR PROCEDURE MANUAL.

Action Required Section or Description REMOVE AND DESTROY El-1, R/44, COVERSHEET AND ATTACHMENT 1, PAGE 4 OF 26 REPLACE WITH El-1, R/44, COVERSHEET AND ATTACHMENT 1, PAGE 4 OF 26 EDITORIAL SIGN, DATE, AND RETURN THEACKNOWLEDGEMENTFORM WITHIN 10 DAYS TO THE PALISADES PLANT DOCUMENT CONTROL SIGNATURE OR INITIALS DATE If applicable, REMOVE ALL travelers and marked up pages in front of this procedure.

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  • Procedure No El-1 Revision 44 Effective Date 313104 PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: EMERGENCY CLASSIFICATION AND ACTIONS Approved: NKBrott I 312/04 Procedure Sponsor Date New Procedure/Revision Summary:

Editorial change to Revision 44 Specific Changes

C7 C Proc No El-1

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Attachment I Revision 44 SITE EMERGENCY PLAN CLASSIFICATION Page 4 of 26 ENGINEERED SAFETY FEATURES CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS UNUSUAL EVENT Inability to reach a required mode within Technical Plant is not brought to required Mandatory: 1, 4, 5, 7, 8 Specification limits. operating mode within Technical Specifications LCO Action Statement Subsequent: 15, 22 Limit.

If Needed: None ALERT Failure of the Reactor Protection System to initiate An RPS setpoint exceeded AND the Mandatory: 1, 2, 3, 4, 5, 7, 8, 9, 10, and complete a trip AND the Reactor is not sub Automatic RPS actuation did NOT 11 critical. occur AND Manual Reactor Trip from C-02 or C-06 was successful. Subsequent: 15,21,22 Complete loss of any functions needed for cold Both S/Gs are not available for PCS shutdown. heat removal AND uncontrolled PCS If Needed: 12, 19 heatup is in progress.

SITE AREA Complete loss of any function needed for hot All AFW pumps/trains not available for Mandatory: 1, 2, 3, 4, 5, 7, 8, 9, 10, EMERGENCY shutdown. less than 30 minutesAND Main 11, 14, 15 Feedwater/Condensate NOT feeding steam generators when required by Subsequent: 17, 21, 22, 23

__ __ _ __ __ __ _ __ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ap plicable EO P .

Transient requiring operation of shutdown systems An RPS setpoint exceeded AND the If Needed: 12, 13, 19, 20 with failure to trip (continued power generation, Automatic RPS actuation did NOT but no core damage immediately evident). occur AND Manual Reactor Trip (was NOT successful (C-02/C-06)).

GENERAL EMERGENCY Transient requiring operation of shutdown system Rx Trip initiated AND any full length Mandatory: 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, with failure to trip, which results in core damage, CRD NOT inserted AND Rx power 11, 13, 14, 15 or additional failure of core cooling and makeup increasing or stable AND Rx power systems (which could lead to core melt). greater than 1%AND either of the Subsequent: 17,19, 21, 22, 23 following:

LESS THAN 250F subcooled If Needed: 12, 20 OR failed fuel confirmed by sample

.___ analysis.

Transient initiated by loss of Feedwater and All AFW pumps/trains not available for Condensate System (principal heat removal greater than 30 minutes AND Main system), followed by failure of Auxiliary Feedwater Feedwater/Condensate NOT feeding System for an extended period. Core melting steam generators when required by

_ possible in several hours. applicable EOP.