ML17261B061

Advises of Changes to 890201 Commitments Made Under Programmed Enhancement Response to Generic Ltr 88-17.Changes Will Not Reduce Capability to Operate Safely in Reduced Inventory Condition or Scope of Programmed Enhancements

ML17261B061
Person / Time
Site:	Ginna
Issue date:	04/26/1990
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Andrea Johnson Office of Nuclear Reactor Regulation
References
GL-88-17, NUDOCS 9005040045
Download: ML17261B061 (5)

Text

ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY XNFORMATXON DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9005040045 DOC.DATE: 90/04/26 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATXON MECREDY,R.C. Rochester Gas 6 Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R. Project Directorate I-3 R

SUBJECT:

Advises of changes to 890201 commitments made under programmed enhancement, response to GL 88-17.

9 DISTRIBUTION CODE: AO61D TITLE: OR/Licensing Submittal: Loss COPIES RECEIVED:LTR g ENCL 0 SIZE:

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8. ill ijriiSir7 ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.K 14649-0001 A'pril 26, 1990 TCLCPHONC AREA COOE 7le 546-2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson Project Directorate I-3 Washington, D.C. 20555

Subject:

Loss of Decay Heat Removal While Operating in the Reduced Inventory Condition (GL 88-17)

R.E. Ginna Nuclear Power Plant Docket No. 50-244

Reference:

(a) Letter from R.C. Mecredy (RG&E) to Carl Stahle (NRC), Loss of Decay Heat Removal (GL 88-17), dated January 4, 1989 (b) Letter from R.C. Mecredy (RG&E) to Carl Stahle (NRC), same subject, dated February 1, 1989

Dear Mr. Johnson:

RG&E responded to Generic Letter 88-17 in References (a) and (b). Two commitments made under our Programmed Enhancement response in Reference (b) have been changed as noted herein.

Neither of these changes results in a reduction in the capability to operate safely while in the reduced. inventory condition nor the overall scope of our programmed enhancements.

Item 1 In our Programmed Enhancement response, Reference (b), Attachment 1, page 2; RG&E stated that the reference leg for the (original)

Loop "B" level transmitter would be relocated to the pressurizer.

The basis for this action was an attempt to reduce loop level error should a difference between containment pressure and RCS pressure occur. It was determined during the modification process that such a condition would not occur during reduced inventory operation, because the RCS is provided. with a sufficiently large vent path through either the pressurizer or other analyzed vent paths which will prevent pressurization. This is implemented through the operating procedure during reduced inventory. Eductor operations are no longer conducted while in the reduced inventory condition thereby eliminating this as a concern relative to inducing a pressure differential. Therefore, since an improvement in loop level accuracy would not be expected from such a modification, this relocation was deleted from the overall work scope of providing enhanced loop level indication.

9005040045 900426 PDR ADOCK 05000244 P PDC

Item 2 In our Programmed Enhancement response, Reference (b), Attachment 1, page 4, RG&E stated that in order to enhance the monitoring of the state of the RHRS and RCS during reduced inventory conditions, several plant modifications are being developed for implementation during the 1990 refueling outage: 1) RHR pump suction pressure monitoring, 2) RHR motor current monitoring, and 3) RHR NPSH monitoring. One of the inputs to the NPSH instrumentation is RHR suction fluid temperature. 'pproximately a month delay in the receipt of the new temperature detectors has occurred with the result that the NPSH monitoring instrumentation will not be available for use until after our anticipated return to full power in early May 1990. Based on a 4/30/90 receipt of the new detectors, installation and turnover is expected'y the end of May 1990 which is long before the next scheduled. reduced inventory will notify you.'ery condition. Should a significant change in this schedule occur, we truly yours, Robert C. M credy Division Manager Nuclear Production GAHK100 xc: Mr. Allen R. Johnson (Mail Stop 14D1)

Project Directorate I-3 Washington, D.C." 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector

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