ML17328A390

Responds to NRC 900720 Ltr Re Violations Noted in Onsite Audit of Spds.Corrective Actions:Apparent Disparity in Selection of Reactor Trip & Sys Capacity or Anticipatory Values Rectified

ML17328A390
Person / Time
Site:	Cook
Issue date:	08/17/1990
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AEP:NRC:0773AI, AEP:NRC:773AI, NUDOCS 9008270136
Download: ML17328A390 (7)

Text

ACCELERATED DI TRIBUTION DEMONST TION SYSTEM REGULATORY INFORMATION DXS RIBUTION SYSTEM (RIDS)

ACCESSION NBR:9008270136 DOC.DATE: 90/08/17 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana & 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana & 05000316 AUTH. NAME AUTHOR AFFILIATION ALEXICH,M.P. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECIPIENT AFFILXATION MURLEY,T.E. Document Control Branch (Document Control Desk)

SUBJECT:

Submits info to closeout corrective actions for SPDS,in l

.II response to NRC 900720 ltr.

DISTRIBUTION CODE: A003D COPIES RECEIVED:LTR ENCL 6 SIZE: 3 TITLE: OR/Licensing Submittal: Suppl 1 to NUREG-0737(Generic Ltr 82-33)

NOTES:

RECIPIENT COPXES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA PD3-1 PD R,

COLBURN,T.

INTERNAL: NRRJ DLPQ/LHFB11 OCgjLFMB 01 RES/DS IR/EIB EXTERNAL: LPDR NR PDR NSIC NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED! j TOTAL NUMBER OF COPIES REQUIRED: LTTR 11 ENCL

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Indiana Michigan I

Power Company P.O. Box 16631 Columbus, OH 43216 AEP:NRC:0773AI Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 COOK NUCLEAR PLANT SAFETY PARAMETER DISPLAY SYSTEM (SPDS) CORRECTIVE ACTION CLOSE OUT U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Attn: T. E. Murley August 17, 1990

Dear Dr. Murley:

This letter responds to your July 20, 1990, letter and provides confirmation that corrective action in response to the findings resulting from the on-site audit of the SPDS has been taken and the items are closed. The specific findings and our confirmation of close-out are given below.

SPDS Is Not Continuous o The SPDS monitor does not provide any visual or audible cues to alert operators to a change in status for the five plant-specific safety functions on displays other than the two, top level iconic displays.

R~es ense The modification to limit the keyboard functions available on one of the control room TSC computer terminals and provide a dedicated display of the SPDS iconic was completed on July 2, 1990, for both Units 1 and 2. The software modification prevents a user from accessing any displays other than the iconic displays from the SPDS-dedicated terminal. A long range solution is also being investigated that would permit a user to access other displays on the SPDS dedicated terminal while still being aware if any adverse changes to the ICONIC Displays'rocess variables. If this alternative solution is found to be practical it will be implemented.

SPDS Is Not Desi ned to Incor orate Acce ted Human Factors Princi les o Numerical values for the high and low level alarm setpoints 0"OG~

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PDR ADOCK 05000315 P PDC y

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s Dr. T. E. Murley AEP:NRC:0773AI on each safety function "spoke" of the narrow- and wide-range iconic displays were not identified. Some alarm setpoints were reactor trip values and others were either anticipatory values or system capacity values. In addition, the Unit 2 SPDS steam generator low level reactor trip setpoint, 21%,

was incorrectly set at the Unit 1 value of 17%. In another case, the Unit 1 SPDS high Tavg alarm setpoint on the SPDS had not been changed to reflect the amended Technical Specification value.

R~es onse The apparent disparity in the selection of reactor trip

'alues, system capacity values, or anticipatory values has been rectified.

The narrow-range steam generator level low limit on the Unit 2 narrow-range iconic display was changed to the correct reactor trip setpoint. The RCS average temperature high limit on the Unit 1 narrow-range iconic display has been changed to the correct value corresponding to the amended Technical Specification limiting condition for operation requirement.

0 erator Trainin With SPDS Was Not Satisfactor o Control room did not know, in all instances, what the numerical values were for the high and low level alarm setpoints for each safety function on the SPDS narrow- and wide-range iconic displays.

~Res onse Numerical values for the alarm limits on the iconic display have been incorporated into the Plant Operators technical data reference. The general philosophy on how these values were selected was incorporated into the operator requalification training beginning in the third quarter of 1990.

This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.

Sincerely, M. P. Ale ch Vice President

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Dr. T. E. Murley AEP:NRC:0773AI eh cc: D. H. Williams, Jr.

A. A. Blind - Bridgman J. R. Padgett G. Charnoff NFEM Section Chief A. B. Davis - Region III-NRC Resident Inspector Bridgman

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