ML20248F819
| ML20248F819 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/04/1989 |
| From: | Loflin L CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-88-16, NLS-89-083, NLS-89-83, NUDOCS 8904130208 | |
| Download: ML20248F819 (2) | |
Text
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se' Carolina Power & Light Company APR 0 41989 SERIAL:
NLS-89-083 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 1 DOCKET No. 50-3'c3/ LICENSE NO. DPR-71 ERRONEOUS APLHCR LIMIT VALUE IN CYCLE 7 RELOAD Gentlemen:
On February 6,.1989, the NRC issued Amendment No. 124 to the Operating License for the Brunswick Steam Electric Plant, Unit 1.
This amendment incorporated revised fuel parameters for Cycle 7 operation into the Technical Specifications.
During generation and review of the Unit 1 process computer databank for Cycle 7, a' discrepancy was identified in the APLHGR limit at 45,000 MWE/ST for the P8DRB284H fuel type. The Supplemental Reload
. Licensing Report indicates the correct APLHCR value for 45,000 MWD /ST exposure is 8.5 kW/ft; Figure 3.2.1-1 incorrectly specifies the APLHGR limit at.45,000 MWD /ST as 8.6 kW/ft. The error was introduced during preparation of the amendment request due to the poor legibility of the Supplemental Reload Licensing Report.
The Cycle 7 operational projections indicate that the maximum average planar exposure for the P8DRB284H fuel type will not exceed 40,000 MWD /ST.
Figure 3.2.1-1 is correct up to 40,000 MWD /ST. Therefore, the incorrect APLHGR value on the figure will have no affect on thermal limit monitoring during Cycle 7 operation. However, to ensure that the thermal limits are not exceeded, the Company has verified that the correct APLHGR value has been entered into the plant process computer for use in monitoring the APLHGR limits. The Company will monitor the maximum average planar exposure of the P8DRB284H fuel type with the process cc.cputer and ensure that this fuel type is not operated beyond an average planar exposure of 40,000 MWD /ST until the Technical Specification figure is corrected.
The Company submitted a license amendment request on September 4, 1987 to remove cycle-specific parameters from the Technical Specifications.
Supplemental requests were submitted on February 6, 1989 and March 20, 1989 to address the guidance of Generic Letter 88-16 and Staff comments.
A copy of the Core Operating Limits Report (COLR) for Unit 1, Cycle 7 was provided with the March 20, 1989 submittal.
Because the Unit 1 COLR already contains the corrected APLHGR value of 8.5 kW/ft at 45,000 MWD /ST exposure, approval of the request to remove cycle-specific goal 411 Fayetteville Street
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I parameters will obviate the need for the NRC to process another, separate license amendment request to correct the APLHGR value.
The Company'is preparing a request for license amendment to correct the APLHGR value on Figure 3.2.1-1.
Based on the low safety significance of this item, the Company plans to submit this request to the NRC by June 30, 1989_unless the request to remove cycle-specific parameters has been approved.
The Company requests the Staff notify us if this schedule is not acceptable.
Please refer any questions regarding this submittal to Mr. Stephen D.
Floyd at (919) 546-6901.
Yours very truly,
_f?
- ? ^
l Leonar
.L lin Manager Nuclear Licensi g Section WRM/wrm
(\\cor\\ulap1hgr) cc:
Mr. S. D. Ebneter Mr. W. H.'Ruland Mr. ?
G. Tourigny l
.