ML17261A930
| 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 ID CODE/NAME PDl-3 LA JOHNSON,A INTERNAL: AEOD/DOA KOPP, LARRY NRR/DET/ECMB 9H NRR/DOEA/OEAB11 NRR/DREP/PEP B9 D NRR/PMAS/ILRB1 2 GN1 FILE 01 EXTERNAL: LPDR NSIC go 7
COPIES LTTR ENCL RECIPIENT ID CODE/NAME PD1-3 PD AEOD/DSP/TPAB LABARGE,DAVE NRR/DET/EMEB9H3 NRR/DOEA/OGCB11 NRR/DST 8E2 NUDOCS-ABSTRACT RES/DSIR/EIB NRC PDR COPIES LTTR ENCL
~ 1 NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASfEI CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAMEFROM DISIRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI TOTAL NUMBER OF COPIES REQUIRED:
LTTR 22 ENCL
ROCHESTER GAS AND ELECTRIC CORPORATION
~
~p yoaa E>>
r
$1A1C 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 January 25, 1990 7 C t. C0 tc0 N C AREA 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 it and any other assembly stored on the baffle.
In addition, RG&E will add, prior.to the'next core reload in April 1990, the following requirements for constructing temporary boxes.
If any boxing configuration uses an assembly which is not in its final 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 fulfilling the open location requirement.
Following these requirements will assure that the shutdown margin as defined in Technical Specifications is maintained during refueling operations.
i>~7~5~
( i+0()c wp.
0'$(~ij)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 NowYetk 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