ML17229A884

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Amends 157 & 96 to Licenses DPR-67 & NPF-16,respectively, Revising TS Action Statements & Certain SRs of TS 3/4.5.1, Sits
ML17229A884
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 10/16/1998
From: Hebdon F
NRC (Affiliation Not Assigned)
To:
Shared Package
ML17229A885 List:
References
NUDOCS 9810210278
Download: ML17229A884 (16)
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UNITED STATES NUCLEAR REGULATORY COMIVIISSION WASHINGTON> D.C. 2055&0001 LO IDA OWE

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LUCIE PLANT UNIT 0 ENDMEN T FACI I

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Amendment No. 157 License No. DPR-67 The Nuclear Regulatory Commission (the Commission) has found that:

A.

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

dated June 21, 1995, 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; The facilitywilloperate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; D.

There is reasonable assurance (i) that the activities authoiized 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; 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.

98i02i0278 98iOi6 PDR ADQCK 05000335 P,

PDR 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).

T chni alS ecifica ions The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 157, 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 its date of issuance and shall be implemented within 30 days of receipt.

FOR THE NUCLEAR REGULATORY COMMISSION Frederick J. Hebdo, 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:

October 16, 1998

TTACH E

T LI NSE MENDMEN NO F

CI ERATI G LICENSE NO DP

-6 D

T

- 3 Replace the following page of the Appendix "A"Technical Specifications with the enclosed page.

The revised page is identified by amendment number and contains vertical lines indicating the area of change.

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

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3/4 5-1 3/4 5-2 B 3/4 5-1

~se Parcae 3/4 5-1 3/4 5-2 B 3/4 5-1

/4.5 EMERGENCY CORE COOLING SYSTEMS ECCS

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SAFETY INJECTION TANKS SIT 3.5.1 Each reactor coolant system safety injection tank shall be OPERABLE with:

a.

The isolation valve open, b.

Between 1090 and 1170 cubic feet of borated water, c.

A minimum boron concentration of 1720 PPM, and d.

A nitrogen cover-pressure of between 200 and 250 psig.

APPLICABILITY: MODES 1, 2 and 3.*

ACTION:

With one SIT inoperable due to boron concentration not within limits, or due to an inabilityto verify the required water volume or nitrogen cover-pressure, restore the inoperable SIT to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; otherwise, be in at least 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 in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b.

With one SIT inoperable due to reasons other than those stated in ACTION-a, restore the inoperable SIT to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; otherwise, be in at least 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 in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

4.5.1 Each safety injection tank shall be demonstrated OPERABLE:

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by:

Verifying that the borated water volume and nitrogen cover-pressure in the tanks are within their limits, and 2.

Verifying that each safety injection tank isolation valve is open.

With pressurizer pressure a 1750 psia.

ST. LUCIE-UNIT 1 3/4 5-1 Amendment No. 1/7

0 EMERGENCY CORE COOLING SYSTEMS b.

At least once per 31 days and once within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after each solution volume increase of a 1% of tank volume by verifying the boron concentration of the safety injection tank solution. This latter surveillance is not required when the volume increase makeup source is the RWT and the RWT has not been diluted since verifying that the RWT boron concentration is equal to or greater than the safety injection tank boron concentration limit.

c.

At least once per 31 days when the RCS pressure is above 1750 psia, by verifying that power to the isolation valve operator is removed by maintaining the breaker open under administrative control.

d.

At least once per 18 months by verifying that each safety injection tank isolation valve opens automatically under each of the following conditions:

1.

When the RCS pressure exceeds 350 psia, and 2.

Upon receipt of a safety injection test signal.

ST. LUCIE-UNIT 1 3/4 5-2 Amendment No.~, 157

3/4.5 EMERGENCY CORE COOLING SYSTEMS ECCS 3/4.5.1 SAFETY INJECTION TANKS The OPERABILITYof each of the RCS safety injection tanks ensures that a sufficient volume of borated water willbe immediately forced into the reactor core through each of the cold legs in the event the RCS pressure falls below the pressure of the safety injection tanks. This initial surge of water into the core provides the initial cooling mechanism during large RCS pipe ruptures.

The limits on safety injection tank volume, boron concentration and pressure ensure that the assumptions used for safety injection tank injection in the accident analysis are met.

The limitof 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for operation with an SIT that is inoperable due to boron concentration not within limits, or due to the inabilityto verify liquid volume or cover-pressure, considers that the volume of the SIT is still available for injection in the event of a LOCA. Ifone SIT is inoperable for other reasons, the SIT may be unable to perform its safety function and, based on probability risk assessment, operation in this condition is limited to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS The OPERABILITYof two separate and independent ECCS subsystems ensures that sufficient emergency core cooling capability willbe available in the event of a LOCA assuming the loss of one subsystem through any single failure consideration.

Either subsystem operating in conjunction with the safety injection tanks is capable of supplying'sufficient core cooling to limitthe peak cladding temperatures within acceptable limits for all postulated break sizes ranging from the double ended break of the largest RCS cold leg pipe downward.

In addition, each ECCS subsystem provides long term core cooling capability in the recirculation mode during the accident recovery period.

The Surveillance Requirements provided to ensure OPERABILITYof each component ensure that at a minimum, the assumptions used in the accident analyses are met and that subsystem OPERABILITYis maintained.

The limitations on HPSI pump operability when the RCS temperature is s 270'F and s 236'F, and the associated Surveillance Requirements provide additional administrative assurance that the pressure/temperature limits (Figures 3.4-2a and 3.4-2b) willnot be exceeded during a mass addition transient mitigated by a single PORV. A limiton the maximum number of operable HPSI pumps is not necessary when the pressurizer manway cover or the reactor vessel head is removed.

ST. LUCIE-UNIT1 B 3/4 5-1 Amendment No. 26, N, 404,y57 443

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON( D C 2055&4001 FLORID WE 8

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L C E PLANT UNIT 0 CY END ENT TO F CILITYOPERATIN LI EN Amendment No. 96 License No. NPF-16 The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Florida Power 8 Light Company, et al. (the licensee), dated June 21, 1995, 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; 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.

0 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.

echnical ec' i

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

96, 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 its date of issuance and shall be implemented within 30 days of receipt.

FOR THE NUCLEAR REGULATORYCOMMISSION Frederick J. Hebdon, 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:

October 16, 1998

'I

ACHMENTTO LI E

SE AMENDMENTNO 96 0FA OPERATING ICEN D

C E

0 0-3 PF-1 Replace the following page of the Appendix "A"Technical Specifications with the enclosed page.

The revised page is identified by aniendment number and contains vertical lines indicating the area of change.

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

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3/4 5-1 3/4 5-2 8 3/4 5-1

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e 3/4 5-1 3/4 5-2 B 3/4 5-1

3/4.5 EMERGENCY CORE COOLING SYSTEMS ECCS 3/4.5'.1 SAFETY INJECTION TANKS SIT 3.5.1 Each Reactor Coolant System safety injection tank shall be OPERABLE with:

a.

The isolation valve open, b;

A contained borated water volume of between 1420 and 1556 cubic feet, c.

A'boron concentration of between 1720 and 2100 ppm of boron, and d.

A nitrogen cover-pressure of between 500 and 650 psig.

APPLICABILITY: MODES 1, 2, 3*, and 4*.

ACTION:

'a With one SIT inoperable due to boron concentration not within limits, or due to an inabilityto verify the required water volume or nitrogen cover-pressure, restore the inoperable SIT to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; otherwise, be in at least 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 in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b.

With one SIT inoperable due to reasons other than those stated in ACTION-a, restore the inoperable SIT to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; otherwise, be in at least 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 in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

4.5.1

~ 1 Each safety injection tank shall be demonstrated OPERABLE:

a.

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by:

1.

Verifying that the contained borated water volume and nitrogen cover-pressure in the tanks are within their limits, and 2.

Verifying that each safety injection tank isolation valve is open.

With.pressurizer pressure greater than or equal to 1750 psia. When pressurizer pressure is less than 1750 psia, at least three safety injection tanks shall be OPERABLE, each with a minimum pressure of 235 psig and a maximum pressure of 650 psig and a contained water volume of between 1250 and 1556 cubic feet with a boron concentration of between 1720 and 2100 ppm of boron. With all four safety injection tanks OPERABLE, each tank shall have a minimum pressure of 235 psig and a maximum pressure of 650 psig and a contained water volume of between 833 and 1556 cubic feet with a boron concentration of between 1720 and 2100 ppm of boron.

In MODE 4 with pressurizer pressure less than 276 psia, the safety injection tanks may be isolated.

ST. LUCIE-UNIT2 3/4 5-1 Amendment No.40,58, 96

EME GE CY CO E COOL G S STE S

b.

C.

At least once per 31 days and once within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after each solution volume increase of greater than or equal to 1% of tank volume by verifying the boron concentration. of the safety injection tank solution. This latter surveillance is not required when the volume increase makeup source is the RWT and the RWT has not been diluted since verifying that the RWT boron concentration is equal to or greater than the safety injection tank boron concentration limit.

At least once per 31 days when the RCS pressure is above 700 psia, by verifying

~

that power to the isolation valve operator is disconnected by maintaining the breaker open by administrative controls.

d.

At least once per 18 months by verifying that each safety injection tank isolation valve opens automatically under each of the following conditions:

1.

When an actual or simulated RCS pressure signal exceeds 515 psia, and 2.

Upon receipt of a safety injection test signal.

ST. LUCIE-UNIT2 3/4 &2 Amendment No.~ 96

3/4.5

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EMERGENCY CORE COOLING SYSTEMS ECCS 3/4.5.1 SAFETY INJECTION TANKS The OPERABILITYof each of the Reactor Coolant System (RCS) safety injection tanks ensures that a sufficient volume of borated water willbe immediately forced into the reactor core through each of the cold legs in the event the RCS pressure falls below the pressure of the safety injection tanks.

This initial surge ofwater into the core provides the initial cooling mechanism during large RCS pipe ruptures.

The limits on safety injection tank volume, boron concentration, and pressure ensure that the assumptions used for safety injection tank injection in the safety analysis are met.

The safety injection tank power-operated isolation valves are considered to be "operating bypasses" in the context of IEEE Std. 279-1971, which requires that bypasses of a protective function be removed automatically whenever permissive conditions are not met.

In addition, as these safety injection tank isolation valves fail to meet single failure criteria, removal of power to the valves is required.

The limitof 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for operation with an SIT that is inoperable due to boron concentration not within limits, or due to the inabilityto verify liquid volume or cover-pressure, considers that the volume of the SIT is still available for injection in the event of a LOCA. Ifone SIT is inoperable for other reasons, the SIT may be unable to perform its safety function and, based on probability risk assessment, operation in this condition is limited to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS The OPERABILITYof two separate and independent ECCS subsystems ensures that sufficient emergency core cooling capability willbe available in the event of a LOCA assuming the loss of one subsystem through any single failure consideration.

Either subsystem operating in conjunction with the safety injection tanks is capable of supplying sufficient core cooling to limitthe peak cladding temperatures within acceptable limits for all postulated break sizes ranging from the double-ended break of the largest RCS hot leg pipe downward.

In addition, each ECCS subsystem provides long-term core cooling capability in the recirculation mode during the accident recovery period.

ST. LUCIE-UNIT2 B 3/4 5-1 Amendment No. 96

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