ML20092A502
| ML20092A502 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 02/05/1992 |
| From: | Vaughn G CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLS-91-348, NUDOCS 9202100135 | |
| Download: ML20092A502 (3) | |
Text
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Carolina Power & Light Company _
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- NWh. N C 270o2 SERIAL N13-91-348 tr-EB 051992 n a=+
Vice Presemt i#
Nurtear Services Depaw United States Nuclear Regulatory Commission ATTENTION:
Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLAN' UNIT NOS. 1 AND 2 DOCKET NOS. 50 325 AND 50 324/ LICENSE NOS. DPR-71 AND DPR-62 SIMUTATOR CERTIFICATION SCHEDULE CHANGE Gentlemen:
The purpose of this letter is to inform the Nuclear Regulatory Commission of a change in the simulator modification schedule provided in the certification package for the Brunswick Plant Reference Simulator.
Replacement of the process computer as modeled by the simulator was scheduled to be complete by December 31, 1991.
Installation of the Brunswick Unit 2 process computer, which is the unit the simulator models, has been rrscheduled to take place during the spring 1993 Brunswick Unit 2 refueling outage rather than the fall 1991 Unit 2 outage.
Consequently, implementation of the new process computer on the simulator has been deferred to June 1993.
Operator requalification training will be adjusted to accommodate the revised schedule. provides the revised certification report page for your use.
Should you have questions regarding this issue, please contact Mr.
S. D. Floyd at (919) 546-6154.
Yours very truly,
/,5 m/
C. E. Vaughn DBB/jbv (1451CLU)
Enclosure cc:
Mr. S. D. Ebneter Mr. N. B. Le Mr. J. E. Tedrow
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Certification Test Deficiencies Revised Schedule - Plant Process Computer for Brunswick Steam Electric Plant INITIAL CERTIFICATION POSITION:
Numerous problems exist ~with the current Process Computer.
Specifics identified in PTA SS-001, PTA SS 002, PTA MV 601, PTA MV 605, and PTA MV 705.
Additional problems have been identified during the training program.
The plant and simulator are in the process of replacing existing systems. The simulator upgrade is scheduled to lead the plant; implementation is scheduled for December 1991.
SSk 90 189 REVISED IMPLEMENTATION SCHEDULE:
The deficiencies noted will be corrected by upgrading the plant-and simulator Process Computers. Delays in installation of the new Process Computers in Y.:e control room have postponed installation of the system in the simulator.
Installation of the new Process Computer in the simulator is now scheduled for June 1993.
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APPENDIX E DUMMARY OF CERTIFICATION TEST DEFICIENCIES tiectrical 89 120 -
~ Too many loads were lost when metfunction activated. DC Distribution upgrade, expected correction 12/91. PIA MA 033 91 071 -
Upgrade DC Model. DC Upgrade, expected correction 12/91. PTA MA 033 90 137 -
Incoerect DC distribution to transmitters. DC Upgrade, expected correction 12/91.
PIA MA 033 90 261 -
APRM Power supply not mdeled correctly. To be corrected by 12/91.
89 244 -
Radiation Monitor has incorrect power surply. 10 be corrected by 12/91 Plant Process Conputer The deficiencies noted will be corrected by upgrading the plant and simulator Process Conputers.
Delays in installation of the new Process Conputers in the control room have postponed installation of the system in the simulator. Installation of the raw Process Conputer in the simulator is now scheduled for June 1993.
HVAC and Radjetton Monitoring 89-120 Radiation Monitor rioes not activate when required 90 037 CB HVAC air supply is incorrectly modeled 90 254 Stock Radiation Monitor reading high 90 067 RCIC Steam Line Break does not cause tenverature or radiation indlcation. P1A-MA 006 9P065 Upgrade HVAC Models 91 067 Upgrade Radiation Monitoring system The HVAC and Radiation Monitoring Systems are currently being upgraded. Madel ir.tegration is scheduled for the third quarter of 1991. Integration into the training program will be e furction of the Configuration Control Board, Condensate Feed, Off Gas, and SJAE 90 087 -
The 28 Feedwater Heater tube leak does not give a correct. indication. To be corrected by 12/91.
91 055 -
Vacwm will not decrease on a loss of $JAE. PTA MA 059. Correction ple d by 12/92.91-058 -
Feedwater control responds too quickly. PTA 1N 008 and PTA MA 074 To be corrected by 12/91 91 109 -
A0G system model becomes unreliable during LOCAs. Problem is not repeatable or consistent. To be corrected by 12/92.
91 050 -
Booster pwp discharge pressure remains high when pwps are secured. PTA MV 400.
To be corrected by 12/91.
91 056 *
$JAE did not warm-up correctly. PTA MV 300. To be corrected by 12/92.
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