ML19347D891
| ML19347D891 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/09/1981 |
| From: | Baynard P FLORIDA POWER CORP. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| 3--3-A-3, 3-0-3-A-3, TAC-11009, NUDOCS 8104140407 | |
| Download: ML19347D891 (2) | |
Text
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. '"l Mr. John F. Stolz, Chief Operating Reactor Branch #4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Revised RPS Instrument Accuracies
Dear Mr. Stolz:
Babcock and Wilcox originally qualified the RPS instrumentation during the 1960's and early 1970's and documented the qualification tests in a report BAW-10003, approved in 1975.
Recently, Babcock and Wilcox has completed additional qualification testing which showed increases in module errors, beyond the original values.
These increases in instrument errors are a result of: reassessment of the magnitude of process errors; inclusion of calibration and setability inaccuracies; inclusion of functional gains and reassessment of flow normalization.
Babcock and Wilcox has performed a series of generic analyses to evaluate significa.nce of these increased errors.
This generic work shows that, for specif>ic plants, these errors could cause some technical specification limits to be exceeded.
Florida Power Corporation has requested Babcock and Wilcox perform a plant specific error analysis for Crystal River Unit 3 to determine if the instru-ment errors could cause any technical specification limits to be exceeded.
Florida Power Corporation and Babcock and Wilcox have determined that the trip setpoints currently listed in the approved Crystal River Unit 3 techni-cal specifications provide adequate margin to accommodate the effects of
/i increased instrument errors during the present cycle of operation provided
/,0 07 the power level is limited to 2452 MWt.
.5 Power upgrade to 2544 MWt would require additional analysis to confirm or jg revise the technical specifications that Florida Power Corporation has sub-mitted to the NRC in support of this upgrade.
Florida Power Corporation will have the additional analysis performed and will revise the technical specification, as required.
810.4140'/07 j#
General Office 320i Tn.rty-fourtn street souin. P O Scx 14042. st Peters 0urg F!orica 33733 813 - 866-5151
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a Mr. John F. Stolz Page Two April 9, 1981 As an interim measure to support the power upgrade, Florida Power Corpora-tion proposes to install a power to pump monitor trip.
This trip will cause a reactor trip on loss of any one of the four reactor coolant pumps at all power levels (> 0% FP).
The technical specifications will also include the following rcvisions.
Two pump or three pump operation will not be allowed at any power level.
The high power trip setpoint will be 104.9% FP.
The high temperature setpoint will be 618 F.
These changes to the technical specification supporting the 2544 MWt power level will provide protection of the reactor during most normal plant operating conditions.
The effects of the locked rotor transient have not been evaluated and adjustments to the power / imbalance / flow envelope have not been made. The effects of the locked rotor transient will be evaluated.
Very truly yours, FLORIDA POWER CORPORATION
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