ML20246A453
| ML20246A453 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/18/1989 |
| From: | Loflin L CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20246A457 | List: |
| References | |
| NLS-89-236, NUDOCS 8908220467 | |
| Download: ML20246A453 (3) | |
Text
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'Y.
Carolina Power & Light Company L
. AUS 181989 L
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-SERIAL: NLS-89-236
-United States. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington,'.DC 20555 BRUNSWICK STEAM ELECTRIC PIANT, UNIT NO.1
-DOCKET NO. 325/ LICENSE NO. DPR-71 TRANSMITTAL OF CORE OPERATING LIMITS REPORT Gentlemen:
In accordance with Technical Specification 6.9.3.4 for the Brunswick Steam Electric Plant, Unit 1, Carolina Power & Light Company herewith submits a copy of the Core Operating Limits Report, Revision 2, August 1989 for Brunswick-
' Unit 1, Cycle 7.
This revision'is being made to establish the option of providing power for the reactor' recirculation system pumps from either the unit auxiliary transformer (UAT) or the start-up auxiliary transformer (SAT).
Since 1984, plant procedures have restricted the power source for the recirculation pumps to the SAT.
Reload licensing analyses performed between 1984 and 1988 have-been prepared using the SAT as the only power source for the recirculation pumps.
For some analyzed events, including the generator load rejection without bypass event, an increase in recirculation pump speed is possible when the pumps are powered from the UAT and may impact the transient CPR thermal limit performance.
For the current operating cycle for Brunswick Unit 1, the generator load rejection without bypass transient is the most liraiting event.
Supplemental analyses have been completed-for Brunswick Unit 1 Cycle 7 to evaluate any impact on operating MCPR limits as a result of powering the recirculation pumps from the UAT.
The results of these analyses indicate small changes in CPR performance of less than 0.01.
Due to the round off technique applied to the results for reporting the MCPR thermal limits in the l:
Core Operating Limits Report and the Supplemental Reload Licensing Report, only the ODYN Option B MCPR limits at the middle of cycle exposure conditions have been changed by the 0.01 value.
0 411 Fayettevihe Street
- P. O Box 1551
- Raleigh. N C. 27602 8908220467 890818 PDR ADOCK 05000325 P
. PDC
l.
l
'Ddcumsnt. Control Desk NLS-89-236 / Page 2-i i
Please refer any questions regarding this submittal.to Mr. William R. Murray at (919) 546-4661.
Yours very truly,
/h.
h't.6sso-.
Leonard I. Loflin Manager Nuclear Licensing Section SC/WRM/wrm (\\cor\\ulcolrr2)
Enclosure cc:
Mr. S. D. Ebneter Mr.
W. H. Ruland Mr. E.
G. Tourigny
t ENCLOSURE 1 CORE OPERATING LIMITS REPORT, REVISION 2, AUGUST 1989 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1
..