ML17221A437

Amend 23 to License NPF-16,reducing Steam Generator Water Level Setpoints for Reactor Trip & Auxiliary Feedwater Initiation

ML17221A437
Person / Time
Site:	Saint Lucie
Issue date:	09/24/1987
From:	Berkow H Office of Nuclear Reactor Regulation
To:
Shared Package
ML17221A438	List: ML17221A437 ML17221A439
References
NUDOCS 8710080262
Download: ML17221A437 (12)

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 FLORIDA POWER 5 LIGHT COMPANY ORLANDO UTILITIES COMMISSION OF THE CITY OF ORLANDO, FLORIDA AND FLORIDA MUNICIPAL POWER AGENCY DOCKET NO. 50-389 ST.

LUCIE PLANT UNIT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment Xo. 23 License No. NPF-16 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Florida Power It Light Company, et al. (the licensee),

dated December 2, 1986, as supplemented February 3, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comnission; 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 ComIission's regulations; D.

The issuance of this amendment will not be inimical to the colon 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 Comission's regulations and all applicable requirements have been satisfied.

8710080262 870924 PDR PDR ADOCg 05000389

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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 ~ollows:

2.

Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 23

, are hereby incorporated in the license.

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

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY CONISSION

Attachment:

Changes to the Technical Specifications Berber N. Her w,

re6tor Prefect Dfrectbrate 1-2 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation Date of Issuance:

September 24* 1987

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ATTACHMENT TO LICENSE AMENDMENT NO. 23 TO FACILITY OPERATING L'ICENSK NO. NPF-16 DOCKET NO. 50-389 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.

The corresponding oyerleaf pages are also provided to maintain document completeness.

Remove Pa es

. 2-4 3/4 3-18 82-5 t

Insert Pa es 2-4 3/4 3-18 B?-5

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SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS BASES Containment Pressure-Hi h

The Containment Pressure-High trip provides assurance that a reactor trip is initiated prior to or concurrently with a safety infection (SIAS).

This also provides assurance that a reactor trip is initiated prior to or concurrently with an MSIS.

Steam Generator Pressure-Low The Steam Generator Pressure-Low trip provides protection against an excessive rate of heat extraction from the.steam generators and subsequent cooldown of the reactor coolant.

The setpoint of 620 psia is sufficiently below the full load operating point of approximately 885 psia so as not to interfere with normal operation, but still high enough to provide the required protection in the event of excessively high steam flow.

This setting was u'sed with an uncertainty factor of 30 psi in the sifety analyses.

Steam Generator Level-Low The Steam Generator Level-Low trip provides protection against a loss of feedwater Flow incident and assures that the design pressure of the Reactor Coolant System will not be exceeded due to loss of the steam generator heat sink.

This specified setpoint provides allowance that there will be sufficient water'inventory in the steam generator at the time of the trip to provide a

margin of at least 10 minutes before auxiliary feedwater is required.

This trip also protects against violation of the specified acceptable fuel design limits (SAFDL) for DNBR, offsite dose and the loss of shutdown margin for asymmetric steam generator transients such as the opening of a main steam safety valve or atmospheric dump valve.

Local Power Densit -Hi h

,The Local".Power Density-High trip, functioning from AXIAL SHAPE 'INDEX monitoring, is provided to ensure that the peak local power density in the fuel which corresponds to fuel centerline melting will not occur as a

consequence of axial power maldistributions.

A reactor trip.is initiated whenever the AXIAL SHAPE INDEX exceeds the allowable limits of Figure 2.2-2.

The AXIAL SHAPE '.INDEX is calculated from the upper and lower excore neutron detector'hannels.

The calculated setpoints are generated as a function of THERMAL POWER level with the allowed CEA group positiion being inferred from the THERMAL POWER level.

The trip is automatically bypassed below 15% power.

The maximum AZIMUTHAL POWER TIL'T and maximum CEA misalignment permitted for continuous operation are assumed in generation of the setpoints.

In

addition, CEA group sequencing in accordance with the Specifications 3.1.3.5 and 3.1.3.6 is assumed.

Finally, the maximum insertion of CEA banks which can occur during any anticipated operational occurrence prior to a Power Level-High trip is assumed.

ST.

LUCIE - UNIT 2 B 2-5 Amendment No. 23

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SAFETY LIMITS AND LIMITING.SAFETY SYSTEM SETTINGS BASES RCP Loss of Com onent Coolin Mater A loss of component cooling water to the reactor coolant pumps causes a

delayed reactor trip.

This trip provides protection to the reactor coolant pumps by ensuring that plant operation is not continued without cooling water available.

The trip is delayed 10 minutes following a reduction in flow to below the tl'ip setpoint and the trip does not occur if flow is restored before IO minutes elapses.

No credit was taken for this trip in the safety analysis.

'Its functional capability at the specified trip setting is required to enhance the overall reliability of the Reactor Protective System.

Rate of Chan e of Power-Hi h

The Rate of Change of Power-High trip is provided to protect the core during startup operations and its use serves as a backup to the administra-tively enforced startup rate limit. Its trip setpoint does not correspond to a Safety Limit and no credit was taken in the safety analyses for operation of this trip.

Its functional capability at the specified trip setting is required to enhance the overall reliability of the Reactor Protection System.

Reactor Coolant Flow -

Low The Reactor Coolant Flow - Low trip provides protection against a reactor coolant pump sheared shaft event and a two pump opposite loop flow coastdown event.

A trip is initiated when the pressure differential across the primary side of either steam generator decreases below a variable setpoint.

This variable setpoint stays a set amount below the pressure differential unless limited by a set maximum decrease rate or a set minimum value.

The specified setpoint ensures that a reactoi trip occurs to prevent violation of local power density or DNBR safety limits under the stated conditions.

ST.

LUCIE - UNIT 2 B 2-6

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FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES TABLE 3.3-4 ENGINEEREO SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES C

M tO CO 04I Co Containment Pressure - High d.

Contaiment Radiation - High e.

Automatic Actuation Logic 4.

MAIN STEN LiNE ISOLATION a.

Manual (Trip Buttons) b.

Steam Generator Pressure - Low c.

Containment Pressure - High d.

Automatic Actuation Logic SAFETY INJECTION (SIAS) a.

Manual (Trip Buttons) b.

Containment Pressure - High c.

Pressurizer Pressure - Los d.

Automatic Actuation Logic 2.

CONTAINMENT SPIIAY (CSAS) a.

Manual (Trip Buttons) b.

Containment Pressure High-High c.

Automatic Actuation Logic 3.

CONTAINMENT ISOLATION (CIAS) a.

Manual CIAS (Trip Buttons) b.

Safety Injection (SIAS)

Hot Applicable

< 3.5 psig

> 1736 psia Hot Applicable Hot Applicable

< 5.40 psig Not Applicable Not Applicable Not Applicable

< 3.5 psig

< 10 R/hr Not Applicable Hot Applicable

> 600 psia

< 3.5 psig Not Applicable Not Applicable

< 3.6 psig

> 1728 psia Hot Applicable Not Applicable

< 5 50 Psig Hot Applicable Not Applicable Hot Applicable

< 3-6 psig

< 10 R/hr Hot Applicable Not Applicable

> 567 psia

< 3.6 psig, Not Applicable

TABLE 3.3-4 Continued ENGINEEREO SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES nM FUNCTIONAL UNIT 5.

CONTAINMENT SUMP RECIRCULATION (RAS) a.

Manual RAS (Trip Buttons) b.

Refue)ing Mater Storage Tank - Low c.

Automatic Actuation Logic TRIP VALUE

'ot Applicable 5.67 feet above tank bottom Not Applicable ALLOWABLE VALUES Not Applicable 4.62 feet to 6.24 feet above tank bottom Not Applicable Cu I

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LOSS OF POWER a.

(1) 4.16 kV Emergency Bus Undervoltage (Loss of Voltage)

(2) 480 V Emergency Bus Undervoltage (Loss of Voltage) b.

(1) 4.16 kV Emergency Bus Undervoltage (Oe'graded Voltage)

(2) 480 V Emergency Bus Undervoltage (Oegraded Voltage) 7; AUXILIARYFEEOWATER (AFAS) a.

Manual (Trip Buttons)

- b.

hutoeatic Actuation Logic c.

Steam Generator hP-High

d. 'G 2M2B Level Low e.

Feedwater Header High hP

> 3120 volts

> 360 volts

> 3848 volts with a 10-second time delay

> 432 volts Not Applicable Not Applicable

< 180.0 psid

> 19.0X

< 100.0 psid

> 3120 volts

> 360 volts

> 3848 volts with a 10-second time delay

> 432 volts Not Applicable Not Applicable

< 187.5 psid

> 18.0X

< 107.5 psid

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UNACCEPTABLE OPE RATION LIHITS CONTAIN NO ALLOWANCE FOR INSTRUMENT ERROR OR FLUCTUATIONS VALID FOR AXIAL SHAPES AND INTEGRATED ROD RADIAL PEAKINC FACTORS LESS THAN OR EQUAL TO THOSE ON FIGURE B 2.1-1 ACCEPTABLE OPERATION REACTOR OPERATION LIMITED TO LESS THAN 580 F BY ACTUATION OF THE SECONDARY SAFETY VAI VES Cll Cl}

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2. 20 FRACTION OF RATED THERMAL POWER

, ~ was, ~ ra ys n Ir.r ~ r ~ TASLE 2.2-,1,) <i;; REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIHITS I C M m I FUNCTIONAL UNIT 1. Hanual Reactor Trip 2. Variable Power Level - High Four Reactor Coolant Pumps Operating 3. Pressurizer Pressure - High TRIP SETPOINT Not Applicable < 9.61'bove THERMAL PNER, with a minimum setpoint of '5K of RATED THERMA

POWER, and a maximum of < 107.0X of RATED THERMAL POMER.

<.2370 psia ALLOWABLE VALUES Not Applicable < 9.61X above THERMAL POMER, and a minimum setpoint of 15K of RATED THERMAL POHER and a maximum ~ of < 107.0X of RATED THERMAL POWER. < 2374 psia 4. Thermal Hargin/Low Pressure I Four Reactor Coolant Pumps Operating ~ 5. Containment Pressure - High 6. 'Steam Generator Pressure - Low 7. Steae Generator Pressure I Difference - High (Logic in TH/LP Trip Unit) Trip setpoint adjusted to not exceed the limit lines of Figures 2.2-3 and 2.2-4. Minimum value of 1900 psia. 3.0 Psig > 626.0 psia (2) < 120.0 psid Trip setpoint adjusted to not exceed the limit lines of Figures 2.2-3 and 2.2-4. Minimum value of 1900 psia. < 3.l Psig > 621.0 psia (2) < 132.0 psid . O 8. Steam Generator Level - Low > 20.5X (3) > 19.5X (3)}}