Text

Amends 133 & 72 to Licenses DPR-67 & NPF-16,respectively, Implementing GL 93-05 Items 5.8,6.1,7.1 & 7.5
	ML17228B008
Person / Time
Site:	Saint Lucie
Issue date:	02/09/1995
From:	Matthews D; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML17228B009	List: ML17228B008; ML17228B010;
References
	NUDOCS 9502140227
	Download: ML17228B008 (24)
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0M1 FLORIDA POWER

& LIGHT COMPANY DOCKET NO. 50-335 ST.

LUCIE PLANT UNIT NO.

1 MENDMENT TO FACILITY OPERATING LICENSE Amendment No. 133 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 5, Light Company, et al. (the licensee),

dated July 25, 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.

9502140227 950209 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)

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

as revised through Amendment No. 133, 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.

FOR THE NUCLEAR REGULATORY COHHISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

February 9,

1995 David

. Hatthews, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

ATTACHMENT TO LICENSE AMENDMENT NO.

133 TO FACILITY OPERATING 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.

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

Remove Pa es 3/4 3-25 3/4 4-14a 3/4 5-2 3/4 5-4 Insert Pa es 3/4 3-25 3/4 4-14a 3/4 5-2

.3/4 5-4

INSTRUMENTATION INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The incore detection system shall be OPERABLE with:

a.

At least 75K of all incore detector locations, and b.

A minimum of two quadrant symmetric incore detector locations per core quadrant.

An OPERABLE incore detector location shall consist of a fuel assembly contain-ing a fixed detector string with a minimum of three OPERABLE rhodium detectors.

APPLICABILITY:

When the incore detection system is used for:

a.

Recalibration of the excore axial flux offset detection

system, b.

Monitoring the AZIMUTHAL POWER TILT, c.

Calibration of the power level neutron flux channels, or d.

Monitoring the linear heat rate.

ACTION:

With the incore detection system inoperable, do not use the system for the above applicable monitoring or calibration functions.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3.2 The incore detection system shall be demonstrated OPERABLE:

a.

By performance of a CHANNEL CHECK within 7 days prior to its use when required for:

1.

Recalibration of the excore axial flux offset detection

system, 2.

Monitoring the linear heat rate pursuant to Specification 4.2.1.3, ST LUGIE - UNIT 1

3/4 3-25 Amendment No. gl', goal

~

INSTRUMENTATION SURVEILLANCE RE UIREMENTS Continued 3.

Monitoring the AZIMUTHAL POWER TILT, or 4.

Calibration of the Power Level Neutron Flux Channels.

b.

At least once per 18 months by performance of a CHANNEL CALI-BRATION operation which exempts the neutron detectors but in-cludes all electronic components.

The neutron detectors shall be calibrated prior to installation in the reactor core.

ST.

LUCIE - UNIT 1

3/4 3-26

REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM LEAKAGE SURVEILLANCE RE UIREMENTS Continued b.

Monitoring the containment sump inventory and discharge at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , c.

Performance of a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months during steady state operation except when operating in the shutdown cooling mode, d.

Monitoring the reactor head flange leakoff system at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and e.

Verifying each Reactor Coolant System Pressure Isolation Valve leakage (Table 3.4.6-1)"to be within limits:

1.

Prior to entering MODE 2 after refueling, 2.

Prior to entering MODE 2, whenever the plant has been in COLD SHUTDOWN for 7 days or more and if leakage, testing has not been performed in the previous 9 months, 3.

Prior to returning the valve to service following maintenance, repair or replacement work on the valve.

4.

The provision of Specification 4.0.4 is not applicable for entry into MODE 3 or 4.

f.

Whenever integrity of a pressure isolation valve listed in Table 3.4.6-1 cannot be demonstrated the integrity of the remaining check valve in each high pressure line having a

leaking valve shall be determined and recorded daily.

In addition, the position of one other valve located in each high pressure line having a leaking valve shall be recorded daily.

ST LUCIE - UNIT 1

3/4 4-14a Amendment No.

133

TABLE 3.4.6-1 PRIMARY COOLANT SYSTEM PRESSURE ISOLATION VALVES Check Valve No.

V3227 V3123 V3217 V3113 V3237 V3133 V3247 V3143 V3124 V3114 V3134 V3144 NOTES (a)

Maximum Allowable Leakage (each valve):

1.

Leakage rates less than or equal to 1.0 gpm are acceptable.

2.

Leakage rates gr eater than 1.0 gpm but less than or equal to 5.0 gpm are acceptable if the latest measured rate has not exceeded the rate determined by the previous test by an amount that reduces the margin between previous measured leakage rate and the maximum permissible rate of 5.0 gpm by 505 or greater.

3.

Leakage rates greater than 1.0 gpm but less than or equal to 5.0 gpm are unacceptable if the latest measured rate exceeded the rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the maximum permissible rate of 5.0 gpm by 50% or greater.

4.

Leakage rates greater than 5.0 gpm are unacceptable.

(b)

To satisy ALARA requirements, leakage may be measured indirectly (as from the performance of pressure indicators) if accomplished in accordance with approved procedures and supported by computations showing that the method is capable of demonstrating valve compliance with the leakage criteria.

(c)

Mimimum test differential pressure shall not be less than 150 psid.

ST LUCIE - UNIT 1

3/4 4-14b Order dated 4/20/B]

~

3/4.5 EMERGENCY CORE COOLING SYSTEMS ECCS SAFETY INJECTION TANKS LIMITING CONDITION FOR OPERATION 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:

a.

With one safety injection tank inoperable, except as a result of a closed isolation valve, restore the inoperable tank to OPERABLE status within one hour or be in HOT SHUTDOWN within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

b.

With one safety injection tank inoperable due to the isolation valve being closed, either immediately open the isolation valve or be in HOT STANDBY within one hour and be in HOT-SHUTDOWN within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

SURVEILLANCE RE UIREMENTS 4.5.1 Each safety injection tank shall be demonstrated OPERABLE:

a.

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

l.

Verifying the water level and nitrogen cover-pressure in the tanks, and 2.

Verifying that each safety injection tank isolation valve is open.

With pressurizer pressure

> 1750 psia.

ST.

LUGI E - UNIT 1

3/4 5-1

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS Continued b.

At least once per 31 days and within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after each solution volume increase of > 1$ of tank volume by verifying the boron concentration of the safety injection tank solution.

This 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 injec-tion tank isolation valve opens automatically under each of the following conditions make it:

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 halo.

133

EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - T

) 325'F LIMITING CONDITION FOR OPERATION 3.5.2 Two independent ECCS subsystems shall be OPERABLE with each sub-system comprised of:

a.

One OPERABLE high-pressure safety injection (HPSI) pump (one ECCS subsystem shall include HPSI pump A and the second ECCS subsystem shall include either HPSI pump B or C),

b.

One OPERABLE low-pressure safety injection pump, and c.

An independent OPERABLE flow path capable of taking suction from the refueling water tank on a Safety Injection Actuation Signal and automatically transferring suction to the containment sump on a Recirculation Actuation Signal.

APPLICABILITY:

MODES 1, 2 and 3".

ACTION:

a

~

With one ECCS subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90. days describing the circumstances of the actuation and the total accumulated actuation cycles to date.

Wit pressur>zer pressure

> 1750 psia.

ST

~ LUCIE - UNIT 1 3/4 5-3 Amendment No.

28

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIPEMENTS J

4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:

a.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the following valves are in the indicated positions with power to the valve operators removed:

Valve Number

1. V-3659 ve Function

1. Mini-flow isolation lve Pos tion

l. Open

2. V-3660

2. Mini-flow isolation 2.

Open b.

At least once per 31 days by:

l.

Verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

c.

By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions.

This visual inspection shall be performed:

d.

1.

For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and 2.

At least once daily of the areas affected within containment by the containment entry and during the final entry when CONTAINMENT INTEGRITY is established.

At least once per 18 months by:

l.

Verifying proper operation of the open permissive interlock (OPI) and the valve open/high SDCS pressure alarms for isolation valves

V3651, V3652, V3480, V3481.

2.

A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks,

screens, etc.)

show no evidence of structural distress or corrosion.

ST.

LUGIE - UNIT 1

3/4 5-4 Amendment No. W, fZgf 133

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UNITED STATES NUCLEAR REGULATORY COMMISSlON WASHINGTON, D.C. 20555<001 FLORIDA POWER 81 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 No. 72 License No.

NPF-16 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 25,

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.

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 3.

The Technical Specifications contained in Appendices A and B,

as revised through Amendment No. 72

, 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.

FOR THE NUCLEAR REGULATORY COMMISSION

~

David B. Matthews, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

February 9,

1995

ATTACHMENT TO LICENSE AMENDMENT NO.

72 TO FACILITY OPERATING LICENSE 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 over leaf pages are also provided to maintain document completeness.

Remove Pa es 3/4 3-30 3/4 4-20 3/4 5-2 3/4 5-4 Insert Pa es 3/4 3-30 3/4 4-20 3/4 5-2 3/4 5-4

INSTRUMENTATION INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The incore detection system shall be OPERABLE with:

a.

At least 75K of all incore detector locations, and b.

A minimum of two quadrant symmetric incore detector locations per core quadrant.

An OPERABLE incore detector location shall consist of a fuel assembly containing a fixed detector string with a minimum of three OPERABLE rhodium detectors'PPLICABILITY:

When the incore detection system is used for:

a 0 b.

C.

Recalibration of the excore axial flux offset detection

system, Monitoring the AZIMUTHAL POWER TILT, Calibration of the power level neutron flux channels, or d.

Monitoring the linear heat rate.

ACTION:

a.

With the incore detection system inoperable, do not use the system for the above applicable monitoring or calibration functions.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3.2 The incore detection system shall be demonstrated OPERABLE:

a.

By performance of a CHANNEL CHECK within 7 days prior to its use when required for:

1.

Recalibration of the excore axial flux offset detection

system, 2.

Monitoring the linear heat rate pursuant to Specification 4.2.1.3, ST.

LUCIE - UNIT 2 3/4 3"30 Amendment No.

OI$. "2

REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.6.2

'a 0 b.

C.

d.

e.'eactor Coolant System leakage shall be limited to:

No PRESSURE BOUNDARY LEAKAGE, 1 gpm UNIDENTIFIED LEAKAGE, 1 gpm total primary-to-secondary leakage through all steam generators and 720 gallons per day through any one steam generator, 10 gpm IDENTIFIED LEAKAGE from the, Reactor Coolant System, and 1 gpm leakage (except as noted in Table 3.4-1) at a Reactor Coolant System pressure of 2235

+ 20 psig from any Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1.

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

ACTION:

a.

C.

d.

With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

With any Reactor Coolant System leakage greater than any one of the limits, excluding PRESSURE BOUNDARY LEAKAGE and leakage from Reactor Coolant System Pressure Isolation Valves, reduce the leakage rate to within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

With any Reactor Coolant System Pressure Isolation Valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least two closed manual or deactivated automatic valves, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

With RCS leakage alarmed and confirmed in a flow path with no flow indication, commence an RCS water inventory balance within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to determine the leak rate.

SURVEILLANCE RE UIREMENTS 4.4.6.2. 1 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by:

a.

Monitoring the containment atmosphere gaseous and particulate radioactivity monitor at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

Monitoring the containment sump inventory and discharge at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ST.

LUCIE - UNIT 2 3/4 4-19

REACTOR COOLANT SYSTEM SURVEILLANCE RE UIREMENTS Continued c.

Performance of 'a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

d.

Monitoring the reactor head flange leakoff system at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.4.6.2.2 Each Reactor Coolant System Pressure Isolation Valve check valve specified in Table 3.4-1 shall be demonstrated OPERABLE by verifying leakage to be within its limit:

a.

At least once per 18 months, b.

. Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 7 days or more and if leakage testing has not been performed in the previous 9 months, c.

Prior to returning the valve to service following maintenance, repair or replacement work on the valve, d.

Following valve actuation due to automatic or manual action or flow through the valve:

1.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying valve closure, and 2.

Within 31 days by verifying leakage rate.

4. 4.6.2.3 Each Reactor Coolant System Pressure Isolation Valve motor-operated valve specified in Table 3.4-1 shall be demonstrated OPERABLE by verifying leakage to be within its limit; a.

At least once per 18 months, and b.

Prior to returning the valve to service following maintenance,

repair, or replacement work on the valve.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4.

ST.

LUCIE - UNIT 2 3/4 4-20 Amendment No.

72

3/4.5 EMERGENCY CORE COOLING SYSTEMS ECCS 3/4. 5.1 SAFETY INJECTION TANKS LIMITING CONDITION FOR OPERATION 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 l, 2, 3", and 4".

ACTEQN:

With one safety injection tank inoperable, except as a result of a closed isolation valve, restore the inoperable tank to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With one safety injection tank inoperable due to the isolation valve being closed, either immediately open the isolation valve or be in at least HOT STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE RE UIREMENTS 4.5. l. 1 Each safety injection tank shall be demonstrated OPERABLE:

4 a.

At least once per l2 hours by:

1, Verifying (by the absence of alarms) the contained borated water volume and nitrogen cover-pressure in the tanks, and 2.

Verifying that each safety injection tank isolation valve is open.

With pressurizer pressure greater than or equal to 1750 psia.'hen pressur-izer 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.

LUGIE - UNIT 2 3/4 5"1 Amendment No.)P, 58,

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS Continued) b.

At least once per 31 days and within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after each solution volume increase of greater than or equal to IX of tank volume by verifying the boron concentration of the safety injection tank solution.

This 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 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 ps ia, and 2.

Upon receipt of 4.5.1.2 Each safety. injection demonstrated OPERABLE:

a safety injection test signal.

tank water level and pressure channel shall be a.

At least once per 31 days by the performance of a CHANNEL FUNCTIONAL TEST.

I b.

At least once per 18 months by the performance of a CHANNEL CALIBRATION.

ST.

LUCIE - UNIT 2 3/4 5-2 Amendment No.

72

EMERGENCY CORE COOLING SYSTEMS 3I4.5.2 ECCS SUBSYSTEMS -.T GREATER THAN OR E UAL TO 325 F

'v LIMITING CONDITION FOR OPERATION 3.5.2 Two independent Emergency Core Cooling System (ECCS) subsystems shall be OPERABLE with each subsystem comprised of:

a.

One OPERABLE high pressure safety injection pump, b.

One OPERABLE low pressure safety injection pump, and C.

An independent OPERABLE flow path capable of taking suction from the refueling water tank on a Safety Injection Actuation Signal and automatically transferring suction to the containment sump on a Recirculation Actuation Signal, and d.

One OPERABLE charging pump.

APPLICABILITY:

MODES 1, 2, and 3".

ACTION:

a 0 b.

With one ECCS subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9 '

within 90 days des-crib'ing the circumstances of the actuation and the total accumulated actuation cycles to date.

The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report wheneve~ its value exceeds 0.70.

With pressurizer pressure greater than or equal to 1750 psia.

ST.'UCIE - UNIT 2 3/4 5-3

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:

a 0 At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the following valves are in the indicated positions with power to the valve operators removed:

b.

C.

d.

Valve Function a.

SIT Vent Valves b.

Locked Closed Valve Number a.

V3733 a.

Locked Closed V3734 b.

V3735 V3736 c.

V3737 c.

SIT Vent Valves c.

Locked Closed V3738 V3739 V3740 At least once per 31 days by verifying that each valve (manual, power-operated or automatic) in the flow path that. is not locked,

sealed, or otherwise secured in position, is in its correct position.

By verifying that the ECCS piping is full of water by venting the accessible piping high points following maintenance, shutdown cooling system operation and/or any other activity which could cause the introduction of air into the system.

By a visual inspection which verifies that no loose debris flags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions.

This visual inspection shall be performed:

1.

For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and 2.

At least once daily of the areas affected within containment by the containment entry and during the final entry when CONTAINMENT INTEGRITY is established.

e.

At least once per 18 months by:

l.

Verifying automatic isolation and interlock action of the shutdown cooling system from the Reactor Coolant System when RCS pressure (actual or simulated) is greater than or equal to 515 psia, and that the interlocks prevent opening the shutdown cooling system isolation valves when RCS pressure (actual or simulated) is greater than or equal to 276 psia.

ST.

LUCIE - UNIT 2 3/4 5-4 Amendment No. 72

ML17228B008

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