ML17228A994

Amend 132 to License DPR-67,revising TS 3/4.4.13 to Incorporate LTOP Requirements

ML17228A994
Person / Time
Site:	Saint Lucie
Issue date:	01/27/1995
From:	Matthews D Office of Nuclear Reactor Regulation
To:
Shared Package
ML17228A995	List: ML17228A994 ML17228A996
References
NUDOCS 9502010278
Download: ML17228A994 (6)

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205554001 LORIDA POMER

& LIGHT COMPANY DOCKET NO. 50-335 ST.

LUCIE PLANT UNIT NO.

1 M NDMENT TO FACILITY OPERATING LICENSE Amendment No. 132 License No.

DPR-67 The Nuclear Regulatory Commission (the Commission) has found that:

A.

B.

C.

D.

E.

The application for amendment by Florida Power

& Light Company, et al. (the licensee),

dated July 28,

1994, 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 facility will operate 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; 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 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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PDR ADOCK 05000335 P

PDR

2.

3.

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) echnical S ecifications The Technical Specifications contained in Appendices A and B,

as revised through Amendment No. 132, 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 the date of its issuance and shall be implemented within 60 days.

FOR THE NUCLEAR REGULATORY COMMISSION Attachment Changes to the Technical Specifications

~

Dav d B. Matthews, Director Proj t Directorate II-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Date of Issuance:

January 27, 1995

TTACHME T TO LICENSE AMENDME T 0.

132 0 FACILI Y OPE TING LIC NSE NO.

OPR-67

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0. 5 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 overleaf pages are also provided to maintain document completeness.

~P 3/4 4-59 B 3/4 4-15 3/4 4-59 B 3/4 4-15

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R P R4T 3.4. 13 Two power operated relief valves (PORVs) shall be OPERABLE, with their setpoints selected to the low temperature mode of operation as follows:

a.

A setpoint of less than or equal to 350 psia shall be selected:

1.

During cooldown when the temperature of any RCS cold leg is less than or equal to 215'F and 2.

During heatup and isothermal conditions when the temperature of any RCS cold leg is less than or equal to 193'F.

b.

A setpoint of less than or equal to 530 psia shall be selected:

1.

During cooldown when the temperature of any RCS cold leg is greater than 215'F and less than or equal to 281'F

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2.

During heatup and isothermal conditions when the temperature of any RCS cold leg is greater than or equal to 193'F and less than or equal to 304'F.

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'r equal to 304'F, HOOE 5, and HOOE 6 when the head is on the reactor vessel; and the RCS is not vented through greater than a 1.75 square inch vent.

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With one PORV inoperable in HOOE 4, restore the inoperable PORV to OPERABLE status within 7 days; or depressurize and vent the RCS through greater than a 1.75 square inch vent within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

b.

With one PORV inoperable in NODES 5 or 6, either (1) restore the inoperable PORV to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or (2) complete depressurization and venting of the RCS through greater than a 1.75 square inch vent within a total of 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />.

c.

With both PORVs inoperable, rest'ore at least one PORV to operable status or complete depressurization and venting of the RCS through greater than a 1.75 square inch vent within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

d.

e.

With the RCS vented per ACTIONS a, b, or c, verify the vent pathway at least once per 31 days when the pathway is provided by a valve(s) that is locked,

sealed, or otherwise secured in the open position; otherwise, verify the vent pathway every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

In the event either the PORVs or the RCS vent(s) are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Coaeission. pursuant to Specification 6.9.2 within 30 days.

The report shall describe the circumstances initiating the transient, the effect of the PORVs or RCS vent(s) on the transient, and any corrective action necessary to prevent recurrence.

f.

The provisions of Specification 3.0.4 are not applicable.

4.4. 13 Each PORV shall be demonstrated OPERABLE by:

a.

Verifying the PORV isolation valve is open at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; and b.

Performance of a CHANNEL FUNCTION TEST, but excluding valve operation, at least once per 31 days; and c,

Performance of a CHANNEL CALIBRATION at least once per 18 months.

ST.

LUCIE - UNIT 1 3/4 4-59 Amendment ~61;~, l 32

REACTOR COOLANT SYSTEM REACTOR COOLANT PUMP - STARTING LIMITING CONDITION FOR OPERATION 3.4.14 If the steam generator temperature exceeds the primary temperature by more than 30'F, the first idle reactor coolant pump shall not be started.

APPLICABILITY:

MODES 4" and 5.

ACTION:

If a reactor coolant pump is started when the steam generator temperature exceeds primary temperature by more than 30'F, evaluate the subsequent transient to determine compliance with Specification 3.4.9.1.

SURVEILLANCE RE UIREMENTS 4.4.14 Prior to starting a reactor coolant pump, verify that the steam generator temperature does not exceed primary temperature by more than 30'F.

8Reactor Coolant System Cold Leg Temperature is less than 304'F.

ST.

LUGIE - UNIT 1 3/4 4-60 Amendment No. gggg, lOg

REACTOR COOLANT SYSTEM BASES 3 4.

. 13 POWER OPERATED RELIEF VALVES and 3 4.4. 14 REACTOR COOLANT PUMP-

~STA TING The low temperature overpressure protection system (LTOP) is designed to prevent RCS overpressurization above the 10 CFR Appendix G operating limit curves (Figures 3.4-2a and 3.4-2b) at RCS temperatures at or below 304'F during heatup and 281'F during cooldown.

The LTOP system is based on the use of the pressurizer power-operated relief valves (PORVs) and the implementation of administrative and operational controls.

The PORVs aligned to the RCS with the low pressure setpoints of 350 and 530 psia, restrictions on RCP starts, limitations on heatup and cooldown rates, and disabling of non-essential components provide assurance that Appendix G

P/T limits will not be exceeded during normal operation or design basis overpressurization events due to mass or energy addition to the RCS.

The LTOP system APPLICABILITY, ACTIONS, and SURVEILLANCE REQUIREMENTS are consistent with the resolution of Generic Issue 94, "Additional Low-Temperature Overpressure Protection for Light-Water Reactors,"

pursuant to Generic Letter 90-06.

3 4.4. 15 R ACTOR COOLANT SYSTEM VENTS Reactor Coolant System vents are provided to exhaust noncondensible gases and/or steam from the primary system that could inhibit natural circulation core cooling.

The OPERABILITY of at.least one Reactor Coolant System vent path from the reactor vessel head and the pressurizer steam space ensures the capability exists to perform this function.

The redundancy design of the Reactor Coolant System vent systems serves to minimize the probability of inadvertent or irreversible actuation while ensuring that a single failure of a vent valve, power supply, or control system does not prevent isolation of the vent path.

The function, capabilities, and testing requirements of the Reactor Coolant System vent system are consistent with the requirements of Item II.b. 1 of NUREG-0737, "Clarification of TMI Action Plan Requirements,"

November 1980.

ST.

LUCIE UNIT 1

B 3/4 4-15 Amendment No. ~,68;&, R%, 132