ML17229A979

Amend 159 to License DPR-67,revising Table 2.2-1 Notations in TS Section 2.2.1,Reactor Trip Setpoints

ML17229A979
Person / Time
Site:	Saint Lucie
Issue date:	01/05/1999
From:	Thomas C NRC (Affiliation Not Assigned)
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Shared Package
ML17229A980	List: ML17229A979
References
NUDOCS 9901110313
Download: ML17229A979 (9)

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 LO DA WE 8 LIG C

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LUC E PLANT UNIT NO END E TTO FACILITYOPE Amendment No. 159 License No. DPR-67 The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Florida Power 8 Light Company (the licensee),

dated October 29, 1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facilitywilloperate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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Accordingly, Facility Operating License No. DPR-67 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph 2.C.(2) to read as follows (2)

Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.159, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

This license amendment is effective as of its date of issuance and shall. be implemented within 30 days of receipt.

FOR THE NUCLEAR REGULATORYCOMMISSION Cecil O. Thomas, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

January 5

]999

ATTACHMENTTO LICENSE AMENDMENTNO. 159 TO FACILITYOPERATING LICENSE NO. DPR-67 DOCKET NO. 50-335 Replace the following pages of the Appendix "A"Technical Specifications with the enclosed pages.

The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

Remove Pa e

2-5 3/4 3-4

~Insert Pa e

2-5 3/4 3-4

TABLE2.2-1 (Continued)

REACTOR PROTECTIVE INSTRUMENTATIONTRIP SETPOINT LIMITS FUNCTIONALUNIT TRIP SETPOINT ALLOWABLEVALUES 9.

Thermal Margin/Low Pressure (1)

Four Reactor Coolant Pumps Operating Trip setpoint adjusted to not exceed the limit'ripsetpoint adjusted to not exceed the limit lines of Figures 2.2-3 and 2.2Q.

lines of Figures 2.2-3 and 2.2-4.

9a.

Steam Generator Pressure Difference High (1)

(logic in TM/LP) 10.

Loss of Turbine Hydraulic Fluid Pressure Low (3) 11.

Rate of Change of Power-High (4)

< 135 psid

> 800 psig

< 2.49 decades per minute

< 135 psid

> 800 psig

< 2.49 decades per minute TABLE NOTATION (1)

Trip may be bypassed below 1% of RATED THERMALPOWER; bypass shall be automatically removed when Wide Range Logarithmic Neutron Flux power is > 1% of RATED THERMALPOWER.

(2)

Trip may be manually bypassed below 685 psig; bypass shall be automatically removed at or above 685 psig.

(3)

Trip may be bypassedbelow 15% of RATED THERMALPOWER; bypass shall be automatically removed when Power Range Neutron Flux power is

> 15% of RATED THERMALPOWER.

(4)

Trip may be bypassed below 10 % and above 15% of RATED THERMALPOWER.

ST. LUCIE-UNIT 1 2-5 Amendment No. 97, 48, 45~ ~59

TABLE3.3-1 (Continued)

TABLE NOTATION

• With the protective system trip breakers in the closed position and the CEA drive system capable of CEA withdrawal.

¹ The provisions of Specification 3.0.4 are not applicable.

(a)

Trip may be bypassed below 1 /o of RATED THERMALPOWER; bypass shall be automatically removed when Wide Range Logarithmic Neutron Flux power is > 1'/o of RATED THERMAL POWER.

, (b) Trip may be manually bypassed below 685 psig; bypass shall be automatically removed at or above 685 psig.

(c)

Trip may be bypassed below 15/o of RATED THERMALPOWER; bypass shall be automatically removed when Power Range Neutron Flux power is > 15/0 of RATED THERMALPOWER.

(d)

Trip may be bypassed below 10

/o and above 15/o of RATED THERMALPOWER; bypass shall be automatically removed when Wide Range Logarithmic Neutron Flux power is > 10

/o and Power Range Neutron Flux power < 15/o of RATED THERMALPOWER.

(e)

Deleted.

(f)

There shall be at least two decades of overlap between the Wide Range Logarithmic Neutron Flux Monitoring Channels and the Power Range Neutron Flux Monitoring Channels.

ACTION STATEMENTS ACTION 1 With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STANDBYwithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the protective system trip breakers.-

ACTION 2 With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a0 The inoperable channel is placed in either. the bypassed or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. For the purposes of testing and maintenance, the inoperable channel may be bypassed for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> from time of initial loss of OPERABILITY;however, the inoperable channel shall then be either restored to OPERABLE status or placed in the tripped condition.

ST. LUCIE-UNIT 1 3/4 3-4 Amendment No. W, &7, 45p ~ 59

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