ML17261A442

Informs That Modified Emergency Operating Procedures Containing Reactor Vessel Level Indication Sys Cannot Be Fully Implemented in Mar 1987,per 840807 Requirement. Implementation Will Be Completed by Jul 1987

ML17261A442
Person / Time
Site:	Ginna
Issue date:	03/18/1987
From:	Kober R ROCHESTER GAS & ELECTRIC CORP.
To:	Lear G NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM NUDOCS 8703260576
Download: ML17261A442 (5)

Text

RECULATORY .ORNATION DISTRIBUTION SYFN (RIDE)

ACCESSIQN 'NBR: 8703260576 DOC. DATF: 87/03/18 NOTARl ZED: NO DOCKET 0 FACIL: 50-244 Robert Emmet Qinna Nuclear Plant Unit 1> RochesteT 0 a5aOO244 I

AUTH. NAt tE AUTHOR AFFILIATION KQBER. R. N: Rochester Gas 8( Electric Corp.

RECIP. NANE RECIPIENT AFFILIATION LEARNS Q. E. Division of Boiling Water Reactor (BNR) Licensing

SUBJECT:

Informs that modified" emergency operating procedures containing reactor vessel level indication sg5 cannot be fully implemented in Nar 198'er 870807 r'equirement.

Implementation mill be completed bg Jul 1987.

DISTRIBUTION CODE'OOSD COPIES RECEIVED; LTR l ENCL 0 SIZE; TITLE: QR Submittal: Inadequate Core Cool ing ( Item II. F. 2) CL 82-28 NOTES: License Exp date in accordance with 10CFR2I 2. 109(9/19/72). o5oao244 RECIPIENT I COP ES RECIPIENT COP IES ID CODE/MANE LTTR ENCL ID CODE/NANE LTTR ENCL p NR-A PDi LA NRR SHEA> J PNR-A PD1 PD STAHLEi C PNR-A RSB V INTERNAL ADN/LFMB NRR BWR DIR 1 NRR BWR PD1 NRR PNR-A DIR 1 NRR PNR-B DIR I ENR T 1 N RR/DSRO/RSI 8 EQ F E 01, 1 EXTERNAL LPDR NRC PDR NSIC TOTAL NUBBER QF COPIES REQUIRED: LTTR 18 ENCL

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'Iltllilkl~~~zieii~i 55AlC ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649-pppI ROGER W. KOBER TCLCRHOHC vie RResloe155 ARcA cooc 716 546.2700 CLecCRlc pRoovcnoN March 18, 1987 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Mr. George E. Lear, Chief PWR Project Directorate No. 1 Washington, D.C. 20555

Subject:

Inadequate Core Cooling Instrumentation Implementation Schedule Rev1s1on NUREG-0737 I Item II.F. 2 R. E. Ginna Nuclear Power Plant Docket No. 50-244

Reference:

1. RGGE Letter from R.W. Kober to Attention of W.A.

Paulsoni NRRI Dated August 7c 1984

2. RGGE Letter from R.W. Kober to Attention of G.W.

Lear> NRRc Dated December 22I 1986

Dear Mr. Lear:

Reference 1 provided a schedule for implementation of the Reactor Vessel Level Indication System (RVLIS) at R.E. Ginna. The schedule called for installation of RVLIS by the end of the 1986 refueling outage and implementation of modified procedures one year later with intermediate milestones between installation and implementation.

The RVLISI as described in Reference 2I was installed in March 1986. The RVLIS is available for operator use and is noted in emergency procedures. In addition> following functional testing and calibrationi preliminary setpoints were generated to provide more detailed guidance in the Emergency Operating Pro-cedures (EOPs). During the implementation process apparent that the original RVLIS estimated worst case uncer-it became tainties were larger than was judged acceptable for use in detection and mitigation of degraded core cooling. Thereforer the RVLIS algorithms have been modifiedi major sources of channel uncertainty have been determined> and an evaluation is in progress to reduce the channel uncertainties. The objective is to improve the RVLIS accuracy so that RVLIS can better aid in the detection and mitigation of inadequate core cooling.

8703260576 8703l8 PDR ADOCK 05000244 PDR

The dominant source of channel uncertainty has been deter-mined to be associated with the reactor vessel differential pressure transmitter. A detailed evaluation of transmitter errors from qualification tests and how they are applied to the RVLIS is in progress. Preliminary results indicate thar the estimated RVLIS accuracy during adverse containment conditions can be improved. However> since this evaluation has not been completed>

the modified EOPs containing RVLIS cannot be fully implemented in Narch 1987 as required by Reference 1. If the final evaluation yields acceptable results< draft EOPs containing the RVLIS setpoints will be implemented by mid June 1987 for operator training and validation and verification. Final approved EOPs will be implemented by the end of July 1987.

Currently> the RVLIS is operating and is available to the operators as additional guidance in responding to transient events. Our current EOPs note that it may be used for indication but do not require that any specific action be taken based on RVLIS. Other indicators< including core exit thermocouple temperatures> are used to assure an appropriate response to emergency conditions based on a validated non-RVLIS version of EOPs derived from the Westinghouse Owners Group Emergency Response Guidelines. Prior to revising the EOPs from the current version to include actions based on RVLIS< it is important to assure that the modified actions will improve upon the emergency response.

If the final evaluation indicates that hardware modifications are required< we will notify you by mid June 1987 and propose an implementation schedule. If hardware modifications are berequired<

the earliest possible time for these modifications will the spring 1988 refueling.

Very truly yours>

Roger W. Kober