ML17241A478

Amend 104 to License NPF-16,removing Redundant Boron Concentration Monitoring Requirements Specified for Modes 3-6 Contained in TS 3/4.1.2.9,accomplished by Deleting TS 3/4.1.2.9

ML17241A478
Person / Time
Site:	Saint Lucie
Issue date:	10/04/1999
From:	Peterson S NRC (Affiliation Not Assigned)
To:
Shared Package
ML17241A479	List: ML17241A478 ML17241A480
References
NUDOCS 9910080059
Download: ML17241A478 (7)

Text

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e UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20585-0001 FLORIDA POWER & LIGHTCOMPANY ORLANDO UTILITIESCOMMISSION OF THE CITYOF ORLANDO FLORIDA AND FLORIDA MUNICIPALPOWER AGENCY DOCKET NO. 50-389 ST. LUCIE PLANT UNIT NO. 2 AMENDMENTTO FACILITYOPERATING LICENSE Amendment No.

104 License No. NPF-16 The Nuclear Reguiatoiy Commission (the Commission) has found that:

The application for amendment by Florida Power & Light Company, et al. (the licensee), dated February 23, 1999, 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 willbe conducted in compliance with the Commission's regulations; D.

The issuance of this amendment willnot 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.

99i0080059 991004 PDR ADQCK 05000389 P

PDR

-2,-

2.

Accordingly, Facility Operating License No. NPF-16 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. y04, 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 60 days.

FOR THE NUCLEAR REGULATORYCOMMISSION Sheri R. Peterson, Chief, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: ~t:o~ 4. >999

ATTACHMENTTO LICENSE AM NDMENT NO. 104 TO FACILITYOPERATING LICENSE NO. NPF-16 DOCKET NO. 50-389 Replace the following pages of the Appendix "A"Technical Specifications with the attached pages.

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

Index page IV List of Tables page XXlll Page 3/4 1-16 Page 3/4 1-17 Page B 3/41-3 Index page IV List of Tables page XXIII Page 3/4 1-16 Page B 3/4 1-3

INDEX I

I LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCERE UIREMENTS SECTION 3/4.0 APPLICABILITY 3/4.1 REACTIVITYCONTROL SYSTEMS PAGE 3/4 0-1 3/4.1.1 3/4.1.2 BORATION CONTROL SHUTDOWN MARGIN T+vg ) 200 F,

SHUTDOWN MARGIN T<>g ( 200 F

~

BORON DILUTION..

MODERATOR TEMPERATURE COEFFICIENT MINIMUMTEMPERATURE FOR CRITICALITY BORATION SYSTEMS FLOW PATHS SHUTDOWN.

FLOW PATHS OPERATING.

CHARGING PUMPS SHUTDOWN CHARGING PUMPS OPERATING BORIC ACID MAKEUP PUMPS SHUTDOWN BORIC ACID MAKEUP PUMPS OPERATING BORATED WATER SOURCES SHUTDOWN.

BORATED WATER SOURCES OPERATING.

3/4 1-1 3/4 1-3 3/4 1-4 3/4 1-5 3/4 1-6 3/4 1-7 3/4 1-8 3/4 1-9 3/4 1-10 3/4 1-11 3/4 1-12 3/4 1-13 3/4 1-14 3/4.1.3 MOVABLECONTROL ASSEMBLIES CEA POSITION POSITION INDICATORCHANNELS OPERATING.

POSITION INDICATORCHANNELS SHUTDOWN

~

CEA DROP TIME SHUTDOWN CEA INSERTION LIMIT.

REGULATING CEA INSERTION LIMITS 3/4 1-18

. 3/4 1-21

. 3/4 1-23

. 3/4 1-24

. 3/4 1-25

. 3/4 1-26 ST. LUCIE - UNIT2 IV Amendment No.i'

INDEX LIST OF TABLES TABLE FREQUENCY NOTATION.

OPERATIONALMODES PAGE

. 1-8

. 1-9 2.2-1 REACTOR PROTECTIVE INSTRUMENTATIONTRIP SETPOINT LIMITS.... ~ ~..... 2-4 3.1-1 DELETED 3.2-1 DELETED.

3.2-2 DNB MARGIN LIMITS 3.3-1 REACTOR PROTECTIVE INSTRUMENTATION.

3.3-2 DELETED.

4.3-1 REACTOR PROTECTIVE INSTRUMENTATIONSURVEILLANCE REQUIREMENTS 3/4 2-1 1 3/4 2-15

. 3/4 3-2

. 3/4 3-8 3.3-3 3.3-4 3.3-5 ENGINEERED SAFETY FEATURES ACTUATIONSYSTEM INSTRUMENTATION.

ENGINEERED SAFETY FEATURES ACTUATIONSYSTEM INSTRUMENTATIONTRIP VALUES DELETED.

~.. 3/4 3-12 3/4 3-17 4.3-2 ENGINEERED SAFETY FEATURES ACTUATIONSYSTEM INSTRUMENTATIONSURVEILLANCEREQUIREMENTS 3.3-6 RADIATIONMONITORING INSTRUMENTATION.

3/4 3-22 3/4 3-25 4.3-3 3.3-8 4.3-5 RADIATIONMONITORING INSTRUMENTATIONSURVEILLANCE REQUIREMENTS DELETED.

DELETED.

3/4 3-28 ST. LUCIE-UNIT2 XXIII Amendment No. 6, i%, W, 66~

Page 3/4 1-17 (Amendment No. 8) has been deleted from the Technical Specifications.

The next page is 3/4 1-18.

ST. LUCIE - UNIT2 3/4 1-16 Amendment No. 104

REACTIVITYCONTROL SYSTEMS BASES The contained water volume limits includes allowance for water not available because of discharge line location and other physical characteristics.

The OPERABILITYof one boron injection system during REFUELING ensures that this system is available for reactivity control while in MODE 6.

The limits on contained water volume and boron concentration of the RWT also ensure a pH value. of between 7.0 and 8.0 for the solution recirculated within containment after a LOCA.

This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.

3/4.1.3 MOVABLECONTROL ASSEMBLIES The specifications of this section ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGINis maintained, and (3) the potential effects of CEA misalignments are limited to acceptable levels.,

The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original design criteria are met.

The ACTION statements applicable to a stuck or untrippable CEA, to two or more inoperable CEAs and to a large misalignment (greater than or equal to 15 inches) of two or more CEAs, require a prompt shutdown of the reactor since either of these conditions may be indicative of a possible loss of mechanical functional capability of the CEAs and in the event of a stuck or untrippable CEA, the loss of SHUTDOWN MARGIN.

For small misalignments (less than 15 inches) of the CEAs, there is (1) a small effect on the time-dependent long-term power distributions relative to those used in generating LCOs and LSSS setpoints, (2) a small effect on the available SHUTDQ~Vii MARGIN,and (3) a small effect on the ejected CEA worth used in the safety analysis.

Therefore, the ACTION statement associated with small misalignments of CEAs permits a 1-hour time interval during which attempts may be made to restore the CEA to within its alignment requirements.

The 1-hour time limitis sufficient to (1) identify causes of a misaligned CEA, (2) take appropriate corrective action to realign the CEAs, and (3) minimize the effects of xenon redistribution.

ST. LUCIE - UNIT2 B 3/4 1-3 Amendment No.49, 104