ML17264B033

Forwards LAR Which Proposes to Revise TS to Change Allowable Value for High Steam Flow Input Into LCO Table 3.3.2-1, Function 4d (Main Steam Isolation)

ML17264B033
Person / Time
Site:	Ginna
Issue date:	09/29/1997
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17264B034	List: ML17264B033 ML17264B038 ML17264B039
References
NUDOCS 9710020014
Download: ML17264B033 (6)

Text

CATEGORY 1 r

REGULAT i INFORMATION DISTRIBUTIO STEM (RIDS)

ACCESSION NBR:9710020014 DOC.DATE: 97/09/29 NOTARIZED: NO DOCKET

'FACIL:50=244 Robert Emmet Ginna Nuclear Plant, Unit 1,. Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY-,R.C. 'Rochester Gas 6 Electric Corp.

RECIP.NAME- RECIPIENT AFFILIATION VISSING,G.S.

SUBJECT:

Forwards LAR which proposes to revise TS to change allowable value for high steam flow input into LCO Table 3.3.2-1, Function 4d (main steam isolation).

DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ( ENCL ( SIZE:

TITLE: OR Submittal: General Distribution T NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-1 LA 1 1 PD1-1 PD 1 1 0 VISSING,G. 1 1 INTERNA . FILE CEbg 1 1 1 NRR/DE/ECGB/A 1 1 EMCB 1 1 NRR/DRCH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0

,EXTERNAL: NOAC 1 1 NRC PDR 1 1 D

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NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 41S-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL 12

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AHD ROCHESTER GAS AND ELECWIC CORPORATION ~ 89 EASTAVENUEi ROCHESTER, N.Y. Id6d9-0001 AREA CODE7I6 546-2700 ROBERT C. MECREDY Vice President Hvcieor operations September 29, 1997 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555

Subject:

Application for Amendment to Facility Operating License Change to Main Steam Isolation Setpoint (LCO Table 3.3.2-1, Function 4.d)

Rochester Gas & Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Vissing,

The enclosed license amendment request (LAR) proposes to revise the Ginna Station Technical Specifications to change the Allowable Value for the high steam flow input into LCO Table 3.3.2-1, Function 4.d (main steam isolation). This change is necessary due to setpoint analyses which determined that the current specified Allowable Value can only be met with an extremely low Trip Setpoint (i.e., below the re-set value of the installed bistables). Consequently, to meet the specified Allowable Value, the bistables for high steam flow input into LCO Table 3.3.2-1, Function 4.d would have to be lowered to a point at which they would never clear or re-set once the Trip Setpoint had been reached (which normally occurs at approximately 10% RTP).

RG&E has determined that the existing Allowable Value for this function was inadvertently not revised during a power uprate from 1300 MWt to 1520 MWt in the early 1970s. Implementation of the proposed new Allowable Value corrects this error while allowing use of the existing Trip Setpoint for this function which is above the bistable re-set value. A minor clarification is also made to the Trip Setpoint. Consequently, no plant modifications would have to occur as a result of this LAR.

,, 97i00200i4 i,'s PDR.

970929 ADQCK 05000244 P PDR

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RG&E is currently operating with the bistables for the high steam flow input in the tripped condition in order to meet technical specification requirements for operability of LCO Table 3.3.2-1, Function 4.d. This is considered acceptable since the remaining inputs into LCO Table 3.3.2-1, Function 4.d (i.e., coincident safety injection and low T,Q are not met and the bistables are normally tripped once above 10% RTP. However, to help prevent an inadvertent actuation of main steam isolation during startup and shutdown activities when the bistables are normally not tripped, RGB'equests a high NRC priority for review and approval of this LAR. Please allow RG8.E 30 days for implementation of this LAR upon NRC approval.

Very truly yours, Robert C. Mecr dy MDF$939 Attachments U.S. Nuclear Regulatory Commission Mr. Guy Vissing (Mail Stop 14B2)

PWR Project Directorate I-1 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector Mr. F. William Valentino, President New York State Energy, Research, and Development Authority Empire State Plaza Albany, NY 12223-1253

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