ML17261A930

Responds to NRC Bulletin 89-003 Re Potential Loss of Shutdown Margin During Refueling Operations.Option to Use Listed Assembly Configurations During Refueling,Including Temporary Storage in Baffle Locations,Will Be Retained

ML17261A930
Person / Time
Site:	Ginna
Issue date:	01/25/1990
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
IEB-89-003, IEB-89-3, NUDOCS 9002060325
Download: ML17261A930 (3)

Text

ACCELERATED DI UTION DEMON 4TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9002060325 DOC.DATE: 90/01/25 NOTARIZED: YES DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas & Electric Corp.

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

SUBJECT:

Responds to NRC Bulletin 89-003, "Potential Loss of Shutdown Margin During Refueling Operations."

DISTRIBUTION CODE: IE29D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: Bulletin 89-03,Potential Loss of Required Shutdown Margin During Refu 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 PDl-3 LA PD1-3 PD ~ 1 JOHNSON,A INTERNAL: AEOD/DOA AEOD/DS P/TPAB KOPP, LARRY LABARGE,DAVE NRR/DET/ECMB 9H NRR/DET/EMEB9H3 NRR/DOEA/OEAB11 NRR/DOEA/OGCB11 NRR/DREP/PEP B9 D NRR/DST 8E2 NRR/PMAS/I LRB1 2 NUDOCS-ABSTRACT RES/DSIR/EIB GN1 FILE 01 EXTERNAL: LPDR NRC PDR NSIC go 7

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASfEI CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISIRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL

~p yoaa E>>

r $ 1A1C ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 January 25, 1990 AREA 7 C t. C 0 tc 0 N C cooc 7I6 546.2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson Project Directorate I-3 Washington, D.C. 20555

Subject:

Response to NRC Bulletin 89-03; Potential Loss of Shutdown Margin During Refueling Operations R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Johnson:

NRC Bulletin 89-03 requires each licensee to notify the NRC by letter whether they have taken or will take the actions specified in this Bulletin. The purpose of this correspondence is to inform the NRC of Rochester Gas and Electric Corporation's (RG&E) plans to address the actions specified in NRC Bulletin 89-03.

RG&E will retain the option to use the following intermediate fuel assembly configuration during refueling:

1) temporary storage of fuel assemblies in baffle locations.

2) constructing "boxes" to load difficult assemblies.

These configurations could result in achieving a more reactive core configuration than that analyzed in the core safety analysis.

In order to assure adequate shutdown margin when using these intermediate core configurations, RG&E incorporated into its fuel assembly movement sequence procedure, in March of 1989, the requirement that any assembly temporarily stored in a baffle location will have at least one open core location between stored the baffle. In addition, it and will any other assembly on RG&E add, prior .to the'next core reload in April 1990, the following requirements for constructing temporary boxes. If in any boxing its final configuration uses an assembly which is not configuration, then one of the assemblies making up the box must have a face adjacent to an open location or the baffle. Any fresh assembly not in its final configuration which is loaded face-adjacent to another fresh assembly must have at least one face adjacent to an open core location or the baffle. Assembly faces constituting the box should not be considered in fulfillingwill the open location requirement. Following these requirements assure that the shutdown margin as defined in Technical Specifications is maintained during refueling operations.

i>~7~5~ ( i+0()c wp.

0'$(~i j)C> . q z>

F Xl(

I)n

To place a fuel assembly in an intermediate location, the PORC approved fuel assembly movement sequence procedure must be changed.

This requires approval of the reactor engineer and the shift supervisor. By requiring strict adherence to its procedures and the procedure change process, RG&E is assured that these intermediate core configuration requirements will be followed.

To ensure the responsible personnel are informed on this issue, the reactor engineers and all the licensed operators will be trained, prior to the next core reload in April 1990, on the restrictions imposed on intermediate fuel assembly configurations and the consequences of violating these restrictions.

By incorporating these requirements and training the appropriate personnel, RG&E will continue to assure adequate shutdown margin during all refueling operations.

Very truly yours,

')

C,>e.

Robert C. Mecre y General Manager Nuclear Production Subscribed and sworn to before me on this 25th day of January, 1990. SAMUEL R BAOWNE NTARYPUBUC, Stae d Now Yetk egistaten Ne. 4917041 QggiglinMenee Cy.IWepo~

py Setwissbn Eqiies Dec.28, 19~/

RWEN078 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 I