ML15198A030

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Proposed TS Changes for TSTF-523 LAR Incorporating Approved TSTF-425 LAR
ML15198A030
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 06/30/2015
From: Costanzo C
Florida Power & Light Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2015-180
Download: ML15198A030 (35)


Text

...

June 30, 2015 L-201 5-180 10 CFR: 50.90 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 Re:

St. Lucie Nuclear Plant, Units I and 2 Docket Nos. 50-335 Docket Nos. 50-335 and 50-389and 50-389 Proposed TS Changes for TSTF-523 LAR Incorporating Approved TSTF-425 LAR

References:

1. Florida Power & Light Company letter L-2014-029 date July 14, 2014, "License Amendment Request, Application to Revise Technical Specification to Adapt Technical Specifications Task Force (TSTF) Traveler-523, "Generic Letter 200801, Manage Gas Accumulation," Using the Consolidated Line Item Improvement Process," Accession No. ML14198A074.
2. NRC Letter dated June 22, 2015, "St. Lucie Plant, Unit Nos. 1 and 2 - Issuance of Amendments Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program (TAC Nos.

MF3495 AND MF3496)," Accession No. ML15127A066.

In Reference 1, Florida Power & Light Company (FPL) submitted a request for an amendment to the Technical Specifications (TS) for St. Lucie Units 1 and 2. This amendment would incorporate TSTF-523 as the means for satisfying gas management Technical Specification requirements as required by Generic Letter 2008-01. Although the license amendment request

([AR) was developed with the surveillance frequencies embedded in the associated TS surveillance requirements, the TSTF also allowed relocation of the surveillance frequency requirements into a Surveillance Frequency Control Program (SFCP) for licensees with that program.

In Reference 2, the NRC approved TS amendments 223 and 173 (St. Lucie Units I and 2, respectively) that allows St. Lucie to implement a SFCP. The approved changes were consistent with U.S. Nuclear Regulatory Commission (NRC)-approved TS Task Force Standard TS change TSTF-425, "Relocate Surveillance Frequencies to Licensee Control - RITSTF [Risk-Informed TS Task Force] Initiative Sb," Revision 3.

This letter provides new TS markups and justification for the TSFT-523 LAR utilizing the SFCP TS surveillance requirement option that was approved by the NRC in Reference.2. The no significant hazards consideration conclusion in Reference 1 bounds the changes. Although not provided in this correspondence, the.TS Bases for the associated TSs will be revised to include the use of the.SFCP.

FPL requests a 120 day implementation period for this [AR. This letter contains no new.

regulatory commitments and does not modify any existing commitments.

Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957

? exL& (CCQ.O*.

i J

L-201 5-1 80 Page 2 This letter contains no new regulatory commitments and does not modify any existing commitments.

Should you have any questions regarding this submittal, please contact Mr. Eric Katzman, Licensing Manager, at (772) 467-7734.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on *',,*,.

30:

,2015.

Sincerely, Christopher R. Costanzo Site Vice President St. Lucia Nuclear Plant Attachments cc:

NRC Regional Administrator, Region I!

NRC Senior Resident Inspector, St. Lucie Units 1 and 2 Ms. Cindy Becker, Florida Department of Health

St. Lucie Units 1 and 2 L-201 5-180 Docket Nos. 50-335 and 50-389 ATTACHMENT 1 Justification for the Chanqie TSTF-425 allowed licensees to relocate surveillance frequencies to the Surveillance Frequency Control Program (SFCP). TSTF-523 provided an option to relocate the gas accumulation surveillance frequencies into the SFCP. The use of the SFCP was approved subsequent to the submittal of this TSTF-523 LAR.

The provided markups simply replaced any referenced TS surveillance requirement frequency (e.g., "every 31 days," etc.) with the phrase "in accordance with the Surveillance Frequency Control Program," as allowed by TSTF-523. Any differences between the TSTF and FPL's proposed wording and format are due to the custom nature of the St. Lucie's TSs. Therefore, the intent of TSTF-523 is met and these proposed changes are administrative in nature.

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-201 5-180 Page 1 of 8 ATTACHMENT 2 St. Lucie Unit 1 Markups of the Technical Specifications 3/4 4-ic 3/4 4-id 3/4 4-ie 3/4 5-4 3/4 6-i5a 3/4 9-8 3/4 9-8a

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-201 5-1 80 Page 2 of 8 RECORSCOTOLANTSTE HOT SHUTDOWN SURVEILLANCE REQUIREMENTS 4.4.1.3.1 The required reactor~coolant pump(s), if not in operation, shallbe determined to be OPERABLE in accordance with the Surveillance Frequency Control Program by verifying correct breaker alignments and indicated power availability.

4.4.1.3.2 The required steam generator(s) shall be determined OPERABLE by verifying the secondary side water level to be>* 10% of narrow range indication in accordance with the Surveillance Frequency Control Program.

4.4.1.3.3. At least one reactorcoolant or shutdown cooling loop shall be verified to be in operation and circulating reactor coolant in accordance with the Surveillance Frequency Control Program.

I ST. LUCIE - UNIT 1 314 4-1c ST.LUCE

-UNI 1 14.lcAmendment No...55,-23

St. Lucie Units 1 and 2 L-201 5-180 Docket Nos. 50-335 and 50-389 Page 3 of 8 REACTOR COOLANT SYSTEM COLD SHUTDOWN - LOOPS FILLED LIMITING CONDITION FOROQPERATION 3.4.1.4,1 At least one shutdown cooling loop shall be OPERABLE and in operation* and either:

a.

One additional shutdown cooling loop shall be OPERABLE¶, or

b.

The secondary side water level of at least two steam generators shall be greater than 10% of narrow range indication.

APPLICABILITY: MODE 5 with reactor coolant loops filled##.

ACTION:

a.

With less than the above required loops OPERABLE or with less than the required steam generator level, within one (1) hour initiate corrective action to return the required loops to OPERABLE status or to restore the required level.

b.

With no shutdown cooling loop in operation, suspend operations that would cause introduction into the ROSS coolant with boron concentration less than required to meet SHUTDOWN MARGIN of Technical Specification 3.1.1.2 and within one (1) hour initiate corrective action to return the required shutdown loop to operation.

SURVEILLANCE REQUIREMENTS 4.4.1.4.1.1 The secondary side water level of at least two steam generators when required shall be determined to be within limits in accordance with the Surveillance Frequency Control Program.I 4.4.1.4.1.2 At least one shutdown cooling loop shall be determined to be in operation and circulating reactor coolant in accordance with the Surveillance Frequency Control Program.I One shutdown cooling loop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing provided the other shutdown cooling loop is OPERABLE and in operation.

    1. A reactor coolant pump shall not be started with two idle loops unless the secondary water temperature of each steam generator is less than 30°F above each of the Reactor Coolant System cold leg temperatures.

ST. LUCIE - UNIT 1 314 4-id Amendment No.,56, 841, 4l03, 9,

St. Lucie Units 1 and 2 L-2015-180 Docket Nos. 50-335 and 50-389 Page 4 of 8 REACTOR COOLANT SYSTEM COLD SHUTDOWN - LOOPS NOT FILLED LIIIN ONDITION FOR OPERATION 3.4.1.4.2 Two shutdown cooling loops shall be OPERABLE# and at least one shutdown cooling loop shall be in operation*.

APPLICABILITY: MODE 5 with reactor coolant loops not filled.

ACTION:

a.

With less than the above required loops OPERABLE, within one (1) hour initiate corrective action to return the required loops to OPERABLE status.

b.

With no shutdown cooling loop in operation, suspend operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet SHUTDOWN MARGIN of Technical Specification 3.1.1.2 and within one (1) hour initiate corrective action to return the required shutdown cooling loop to operation.

S*URVEILLANCE RQ U IRE ME NTS 4.4.1.4.2 At least one shutdown cooling loop shall be determined to be in operation and circulating reactor coolant in accordance with the Surveillance Frequency Control Program.t One shutdown cooling loop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing provided the other shutdown cooling loop is OPERABLE and in operation.

The shutdown cooling pump may be de-energized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided 1) no operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SHUTDOWN MARGIN of Technical Specification 3.1.1.2 and 2) core outlet temperature is maintained at least 10°F below saturation temperature.

ST, LUClE - UNIT 1 3;4 4-1e ST.

UCI

- NITI 34 41 eAmendment No. *6,.10a, 4.t-9,223

St. Lucie Units 1 and 2 L-2015-180 Docket Nos. 50-335 and 50-389 Page 5 of 8 EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:.

a.

In accordance with the Surveillance Frequency Control Program by verifying

  • that the following valves are in the indicated positions with power to the valve operators removed:

Valve Number Valve Function Valve Position

1.

V-3659

1.

Mini-flow

1.

Open isolation

2.

V-3660

2.

Mini-flow

2.

Open isolation

b.

In accordance with the Surveillance Frequency Control Program by:

1.

Verifying that each valve.(manual, power operated or automatic) in the flow path that is not locked, sealec*'

otherwise secured in position, is in its correct position."j 5

c.

iy 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:

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.

In accordance with the Surveillance Frequency Control Program by:

1.

Verifying proper operation of the =open permissive interlock (OP) ad te lveopn/hgh DCSpr Amuendlamen for 0 40

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-201 5-180 Page 6 of 8 SURVEILLANCE REOUIREMENTS 4.62,21 Each containment spray system shall be demonstrated OPERABLE:.

a.

In accordance with the Surveillance Frequency Control Program by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed,.or otherwise secUred in poiion, Hightstsitinq*(ttk sutin-ro the RWT on a Containment Pressure -- Hoightigh, test psitin*Ot~k scioJfo

b.

By verifying that each spray pump develops the specified discharge pressure when tested pursuant to the Inservice Testing Program.

ST. LUCIE - UNIT 1 3/4 6-15a ST.LUCE UNT 13/ 8-5aAmendment No. 4*3-I, 45, 4.94,

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2015-180 Page 7 of 8 REFUELING OPERATIONS SHUTDOWN COOLING AND COOLANT CIRCULATION HIGH WATER LEVEL LIIIGCONDITION FOR OPERATION 3.9.8.1 At least one shutdown cooling loop shall be OPERABLE and in operation*.

APPLICABILITY:

MODE 6 when the water level above the top of irradiated fuel assemblies seated within the reactor pressure vessel is greater than or equal to 23 feet.

ACTION:

a.

With less than one shutdown cooling loop in operation, suspend all operations involving an increase in reactor decay heat load or operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of Technical Specification 3.9.1.

Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANC.EREQUIREMENTS 4.9.8.1 At least one shutdown cooling loop shall be verified to be in operation and Circulating reactor coolant at a flowrate of greater than or equal to per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the performance of CORE ALTERATIONS in the vicinity of reactor pressure vessel hot legs, provided no operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required.to meet the SH-UTDOWN MARGIN of Technical Specification 3.9.1.

ST, LUClE-UNIT 1 3/'4 g-8 ST.

UCI

- UIT 3/49-8Amendment No. *5, 7-9, 223L

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2015-180 Page 8 of 8 REFUELING OPERATIONS LOW WATER LEVEL LIIIGCNIINFROPERATION 3.9.8.2 Two independent shutdown cooling loops shall be OPERABLE and at least one shutdown cooling loop shall be in operation.*

APPLICABILITY:

MODE 6 when the water level above the top of irradiated fuel assemblies seated within the reactor pressure vessel is less than 23 feet.

ACTION:

a.

With less than the required shutdown cooling loops OPERABLE, within one (1) hour 1) initiate corrective action to return the required loops to OPERABLE status, or 2) establish greater than or equal to 23 feet of water above irradiated fuel assemblies seated within the reactor pressure vessel.

b.

With no shutdown cooling loop in operation, suspend operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of Technical Specification 3.9.1. and within one (1) hour initiate corrective action to return the required shutdown cooling loop to operation. Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.8.2 At least one shutdown cooling loop shall be verified to be in opera-tion and circulating reactor coolant at a flow rate of greater than or equal to 3000 gpm in accordance with the Surveillance Frequency Control Program.

  • One required shutdown cooling loop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing, provided that the other shutdown cooling loop is OPERABLE and in operation.

ST. LUCIE - UNIT 1 3f4 9-8a ST.LUIEUNTI3/

98aAmendment No. 56, -403, 7-, 4-9,2

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-201 5-180 Page 1 of 8 ATTACHMENT 3 St. Lucie Unit 2 Markups of the Technical Specifications Technical Specifications 3/4 4-4 3/4 4-5 3/4 4-6 3/4 5-4 3/4 6-1.5a 3/4 9-8 3/4 9-9

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-201 5-180 Page 2 of 8 REACTOR COOLANT SYSTEM HOT SHUTDOWN SURVEILLANCE REQUIREMENTS 4.4.1.3.1 The required Reactor Coolant pump(s), if not in operation, shall be determined to be OPERABLE in accordance with the Surveillance Frequency Control Program by.

verifying correct breaker alignments and indicated power availability.

4.4,1.3.2 The.required steam generator(s) :shall.be.determined OPERA8LE by verifying the secondary side water level to be_> 10% iindicated narrow range level :in accordance with the Surveillance Frequency Control Program.

4.4.1.3.3 At least one Reactor Coolant or shutdown cooling loop shall be verified to be in operation and circulating Reactor Coolant in accordance withl the Surveillance Frequency Control Program.

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 4.

ST. LUCIE -UNIT 2 3444Aed~n o

7 3/4 4-4 Amendment'No.,173

St. Lucie Units 1 and 2 L-2015-180 Docket Nos. 50-335 and 50-389 Page 3 of 8 REACTOR COOLANT SYSTEM COLD SHUTDOWN - LOOPS FILLED LIMITING CONDITION FOR OPERATION 3.4.1.4.1 At least one shutdown cooling loop shall be OPERABLE and in operation*, and either:

a.

One additional shutdown cooling loop shall be OPERABLE#, or

b.

The secondary side water level of at least two steam generators shall be greater than 10% indicated narrow range level.

APPLICABILITY: MODE 5 with Reactor Coolant loops filled##.

ACTION:

a.

With one of the shutdown cooling loops inoperable and with less than the required steam generator level, immediately initiate corrective action to return the inoperable shutdown cooling loop to OPERABLE status or to restore the required steam generator level as soon as possible.

b.

With no shutdown cooling loop in operation, suspend operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet SHUTDOWN MARGIN of Technical Specification 3.1.1.2 and immediately initiate corrective action to return the required shutdown cooling loop to operation.

SURVEILLANCE REOUIREMENTS 4.4.1.4.1.1 The secondary side water level of at least two steam generators when required shall be determined to be within limits in accordance with the Surveillance Frequency control Program.

4.4,1.4.1.2 At least one shutdown cooling loop shall be determined to be in operation and circulating reactor coolant in accordance with the Surveillance Frequency Control

=Program.I saturation temperature.

One shutdown cooling loop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing provided.the other shutdown cooling loop is OPERABLE and in operation.

1# A Reactor Coolant pump shall not be started with two idle loops unless the secondary water temperature of each steam generator is less than 40°F above each of the Reactor Coolant System cold leg temperatures.

ST. LUClE - UNIT 2 3!4 4-5 ST.

UCI

- UIT 3/44-5Amendment No. 46. 24, 48, 42-2 473

St. Lucie Units 1 and 2 L-2015-180 Docket Nos. 50-335 and 50-389 Page 4 of 8 REACTOR COOLANT SYSTEM COLD SHUTDOWN - LOOPS NOT FILLED LIIIGCNITION FOR OPERATION 3.4.1.4.2 Two shutdown cooling loops shall be OPERABLE# and at least one shutdown cooling loop shall be in operation.*

APPLICABILITY: MODE 5 with reactor coolant loops not filled.

ACTION:

a.

With less than the above required loops OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate corrective action to return the required loops to OPERABLE status as soon as possible.

b.

With no shutdown cooling loop in operation, suspend operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet SHUTDOWN MARGIN of Technical Specification 3,1.1,2 and within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate corrective action to return the required shutdown cooling loop to operation.

SURVEILLANCE REQUIREMENTS 4.4.1.4.2 At least one shutdown cooling loop shall be determined to be in operation and One shutdown cooling loop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing provided the other shutdown cooling loop is OPERABLE and in operation.

  • The shutdown cooling pump may be deenergized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided (1) no operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SHUTDOWN MARGIN of Technical Specification 3.1.1.2 and (2) core outlet temperature is maintained at least 100F below saturation temperature.

ST, LUClE - UNIT 2 3/4 4-6 ST.

UCI

- UIT 3144.6Amendment No. -422, 473

St. Lucie Units 1 and 2 L-2015-180 Docket Nos. 50-335 and 50-389 Page 5 of 8 EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:

a.

In accordance with the Surveillance Frequency Control Program by verifying that the following valves are in the indicated positions with power to the valve operators removed:

Valve Number Valve Function Valve Position

a.

V3733

a. SIT Vent Valves
a. Locked Closed V3734
b.

V3735

b. SIT Vent Valves
b. Locked Closed V3736 V3738 In acodnewthteSrellneFeuncy Control V373g 9 Prormb etigECSlctosssetible to gas
b.

In accordance w e*

-3trlP~r--*~if'"v l

that each valve (maul oe-prtdo uoai) in the flow path t~'

not locked, sealed, or otherwise secured in position, is in its correct positi***

c. Byvcifia ha tc CS ion-isfllofwacrb,cti~ h ocsczzblbc piping high points follwn ancnancc, shutdown
d.

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:

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.

In accordance with the Surveillance Frequency Control Program by:

1.

Verifying automatic isolation and interlock action of the shutdown cooling system from 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

St. Lucie Units 1 and 2 L-201 5-1 80 Docket Nos. 50-335 and 50-389 Page 6 of 8 SURVEILLANCE REOUIREMENTS' 4.6:2,1 Each containment spray system shall be demonstrated OPERABLE:

a.

In accordance with.the Surveillance.Frequency Control Program 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 positione~T~Ie suction from the RWT on a containment Pressure*-- High-High test sign*.* --

b.

By verifying that each spray pump develops :the specified discharge.pressure when tested purSuant to the Inservice Testing Program,

c.

In accordance with the Surveillance Frequency Control Program, during shutdown,.

by:

1.

Verifying that each automatic valve in the flow path actuates to its correct position on a CSAS test signal.

2.

Verifying that upon a Recirculation Actuation Test Signal (RAS), the containment sump isolation valves open and that a recirculation mode flow path via an OPERABLE shutdown cooling heatrexchanger is established.

o eurdt emtfrsstmvn lwptsoee ne ST. LUCIE-UNIT 2

3/4 6;15a ST.LUIE-UNT 231 6-~aAmendment:

No..70,94.,4-16,. 11T

St. Lucie Units 1 and 2 L-2015-180 Docket Nos. 50-335 and 50-389 Page 7 of 8 REFUELING OPERATIONS 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION HIGH WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.1 At least one shutdown cooling loop shall be OPERABLE and in operation.*

APPLICABILITY: MODE 6 when the water level above the top of the reactor pressure vessel flange is greater than or equal to 23 feet.

ACTION:

With no shutdown cooling ioop OPERABLE and in operation, suspend all operations involving an inorease in reactor decay heat load or operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of Technical Specification 3.9.1 and within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate corrective action to return the required shutdown cooling loop to OPERABLE and operating status as soon as possible. Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.9.8.1 In accordance with the Surveillance Frequency Control Program:

a.

At least one shutdown cooling loop shall be verified to be in operation

b.

The total flow rate of reactor coolant to the reactor pressure vessel shall be verified to be greater than or equal to 3000 gpm.**

    • The reactor coolant flow rate requirement may be reduced to 1850 gpm if the following conditions are satisfied before the reduced requirement is implemented: the reactor has been determined to have been subcritical for at least 125 hours0.00145 days <br />0.0347 hours <br />2.066799e-4 weeks <br />4.75625e-5 months <br />, the maximum RCS temperature is <_ 11 70 F, and the temperature of CCW to the shutdown cooling heat exchanger is _<87 0 F.

ST. LUClE - UNIT 2 3/4 9-8 ST.

ucl

- uIT 3/49-8Amendment No. -7, -422,.7*

St. Lucie Units 1 and 2 L-201 5-1 80 Docket Nos. 50-335 and 50-389 Page 8 of 8 REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDITION FORO OPERATION 3.9.8.2 Two independent shutdown cooling loops shall be OPERABLE and at least one shutdown cooling loop shall be in operation.**

APPLICABILITY: MODE 6 when the water level above the top of the reactor pressure vessel flange is less than 23 feet.

ACTION:

a.

With less than the required shutdown cooling loops OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate corrective action to return the required loops to OPERABLE status, or to establish greater than or equal to 23 feet of water above the reactor pressure vessel flange, as soon as possible.

b.

With no shutdown cooling loop in operation, suspend operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of Technical Specification 3.9.1 and within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate corrective action to return the required shutdown cooling loop to operation, close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.9.8.2 In accordance with the Surveillance Frequency control Program:

a.

At least one shutdown cooling loop shall be verified to be in operation.

b.

The total flow rate of reactor coolant to the reactor pressure vessel shall be verified to be greater than or equal to 3000 gpm.*

  • The reactor coolant flow rate requirement may be reduced to 1860 gpm if the following conditions are satisfied before the reduced requirement is implemented: the reactor has been determined to have been subcritical for at least 125 hours0.00145 days <br />0.0347 hours <br />2.066799e-4 weeks <br />4.75625e-5 months <br />, the maximum RCS temperature is _< 1170F, and the temperature of CCW to the shutdown cooling heat exchanger is < 870F.
    • One required shutdown cooling loop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing, provided that the other shutdown cooling loop is OPERABLE and in operation.

ST. LUCIE - UNIT 2 314 9-9 Amendment No. 4, 60, :76, 4I2.2, 4.39.

-I-,,,73

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-201 5-180 Page 1 of 8 St. Lucie Unit 1 Word Processed Technical Specifications 3/4 4-ic 3/4 4-id 3/4 4-1e 3/4 5-4 3/4 6-i5a 3/4 9-8 3/4 9-8a

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-201 5-180 Page 2 of 8 REACTOR COOLANT SYSTEM HOT SHUTDOWN SUVILIANCE REOUIREMENTS 4.4.1.3.1 The required reactor coolant pump(s), if not in operation, shall be determined to be OPERABLE in accordance with the Surveillance Frequency Control Program by verifying correct breaker alignments and indicated power availability.

4.4.1.3.2 The required steam generator(s) shall be determined OPERABLE by verifying the secondary side water level to be_> 10% of narrow range indication in accordance with the Surveillance Frequency Control Program.

4.4.1.3.3 At least one reactor coolant or shutdown cooling loop shall be verified to be in operation and circulating reactor coolant in accordance with the Surveillance Frequency Control Program.

4.4.1.3.4 Verify required shutdown cooling train locations susceptible to gas accumulation are sufficiently filled with water in accordance with the Surveillance Frequency Control Program.*

- Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 4.

ST. LUCIE - UNIT 1 3/4 4-1c ST.

UCI

- UIT 3/4-IcAmendment No.-6, 22,3

St. Lucie Units 1 and 2 L-201 5-180 Docket Nos. 50-335 and 50-389 Page 3 of 8 REACTOR COOLANT SYSTEM COLD SHUTDOWN - LOOPS FILLED LIMITING CONDITION FOR OPERATION 3.4.1.4.1 At least one shutdown cooling loop shall be OPERABLE and in operation* and either:

a.

One additional shutdown cooling loop shall be OPERABLE#, or

b.

The secondary side water level of at least two steam generators shall be greater than 10% of narrow range indication.

APPLICABILITY: MODE 5 with reactor coolant loops filled.

ACTION:

a.

With less than the above required loops OPERABLE or with less than the required steam generator level, within one (1) hour initiate corrective action to return the required loops to OPERABLE status or to restore the required level.

b.

With no shutdown cooling loop in operation, suspend operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet SHUTDOWN MARGIN of Technical Specification 3.1.1.2 and within one (1) hour initiate corrective action to return the required shutdown loop to operation.

SURVEILLANCE REQUIREME=NTS; 4.4.1.4.1.1 The secondary side water level of at least two steam generators when required shall be determined to be within limits in accordance with the Surveillance Frequency Control Program.

4.4.1.4.1.2 At least one shutdown cooling loop shall be determined to be in operation and circulating reactor coolant in accordance with the Surveillance Frequency Control Program.

4.4.1.4.1.3 Verify required shutdown cooling train locations susceptible to gas accumulation are sufficiently filled with water in accordance with the Surveillance Frequency Control Program.

  • The shutdown cooling pump may be de-energized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided 1) no operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SHUTDOWN MARGIN of Technical Specification 3.1.1.2 and
2) core outlet temperature is maintained at least 10°F below saturation temperature.

One shutdown cooling loop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing provided the other shutdown cooling loop is OPERABLE and in operation.

A reactor coolant pump shall not be started with two idle loops unless the secondary water temperature of each steam generator is less than 30°F above each of the Reactor Coolant System cold leg temperatures.

ST. LUCIE - UNIT 1 3(4 4-id Amendment No. 56, 84-, -403, 4-79, 497,222,

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 REACTOR COOLANT SYSTEM L-201 5-1 80 Page 4 of 8 COLD SHUTDOWN - LOOPS NOT FILLED LIIIN ODITION FOR OPERATION 3.4.1.4.2 Two shutdown cooling loops shall be OPERABLE# and at least one shutdown cooling loop shall be in operation*.

APPLICABILITY: MODE 5 with reactor coolant loops not filled.

ACTION:

a.

With less than the above required loops OPERABLE, within one (1) hour initiate corrective action to return the required loops to OPERABLE status.

b.

With no shutdown cooling loop in operation, suspend operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet SHUTDOWN MARGIN of Technical Specification 3.1.1.2 and within one (1) hour initiate corrective action to return the required shutdown cooling loop to operation.

SURVEILLANCE REOUIREMENTS 4.4.1.4.2 At least one shutdown cooling loop shall be determined to be in operation and circulating reactor coolant in accordance with the Surveillance Frequency Control Program.

4.4.1.4.2.1 Verify shutdown cooling train locations susceptible to gas accumulation are sufficiently filled with water in accordance with the Surveillance Frequency Control Program.

One shutdown cooling loop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing provided the other shutdown cooling loop is OPERABLE and in operation.

The shutdown cooling pump may be de-energized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided 1) no operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SHUTDOWN MARGIN of Technical Specification 3.1.1.2 and 2) core outlet temperature is maintained at least 1Q0 F below saturation temperature.

ST. LUCIE - UNIT 1 3/4 4-le Amendment No. SG. 40,3, -140,

St. Lucie Units 1 and 2 L-2015-1 80 Docket Nos. 50-335 and 50-389 Page 5 of 8 EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:

a.

In accordance with the Surveillance Frequency Control Program by verifying that the following valves are in the indicated positions with power to the valve operators removed:

Valve Number Valve Function Valve Position

1.

V-3659

1.

Mini-flow

1.

Open isolation

2.

V-3660

2.

Mini-flow

2.

Open isolation

b.

In accordance with the Surveillance Frequency Control Program by:

1.

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.*

2.

Verifying ECCS train locations susceptible to gas accumulation are sufficiently filled with water.

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:

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.

d.

In accordance with the Surveillance Frequency Control Program by:

1.

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.

  • Not required to be met for system vent flow paths opened under administrative control.

ST. LUClE - UNIT 1 3/4 5-4 Amendment No. 90, 420, m3,=2

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-201 5-180 Page 6 of 8 SURVEILLANCE REQUIREMENTS 4.6.2.1 Each containment spray system shall be demonstrated OPERABLE:

a.

In accordance with the Surveillance Frequency Control Program 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 positioned to take suction from the RW-I on a Containment Pressure -- High High test signal.*

b.

By verifying that each spray pump develops the specified discharge pressure when tested pursuant to the Inservice Testing Program.

c.

In accordance with the Surveillance Frequency control Program by verifying containment spray system locations susceptible to gas accumulation are sufficiently filled with water.

  • Not required to be met for system vent flow paths opened under administrative control.

ST. LUCIE - UNIT 1 3/4 6-15a Amendment No. 4341, 45,3, 4-94,

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2015-1 80 Page 7 of 8 REFUELING OPERATIONS SHUTDOWN COOLING AND COOLANT CIRCULATION HIGH WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.1 At least one shutdown cooling ioop shall be OPERABLE and in operation*.

APPLICABILITY: MODE 6 when the water level above the top of irradiated fuel assemblies seated within the reactor pressure vessel is greater than or equal to 23 feet.

ACTION:

a.

With less than one shutdown cooling loop in operation, suspend all operations involving an increase in reactor decay heat load or operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of Technical Specification 3.9.1.

Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.8.1 At least one shutdown cooling ioop shall be verified to be in operation and circulating reactor coolant at a flow rate of greater than or equal to 3000 gpm in accordance with the Surveillance Frequency Control Program.

4.9.8.1.1 Verify required shutdown cooling loop locations susceptible to gas accumulation are sufficiently filled with water in accordance with the Surveillance Frequency Control Program.

  • The shutdown cooling loop may be removed from operation for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the performance of CORE ALTERATIONS in the vicinity of reactor pressure vessel hot legs, provided no operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SHUTDOWN MARGIN of Technical Specification 3.9.1.

ST. LUCIE - UNIT 1 3/4 9-8 ST.LUCE

-UNI I

/4 -8Amendment No. 56, 4-7-, 223

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-201 5-180 Page 8 of 8 REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.2 Two independent shutdown cooling loops shall be OPERABLE and at least one shutdown cooling loop shall be in operation.*

APPLICABILITY:

MODE 6 when the water level above the top of irradiated fuel assemblies seated within the reactor pressure vessel is less than 23 feet.

ACTION:

a.

With less than the required shutdown cooling loops OPERABLE, within one (1) hour 1) initiate corrective action to return the required loops to OPERABLE status, or 2) establish greater than or equal to 23 feet of water above irradiated fuel assemblies seated within the reactor pressure vessel.

b.

With no shutdown cooling loop in operation, suspend operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of Technical Specification 3.9.1. and within one (1) hour initiate corrective action to return the required shutdown cooling loop to operation, Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.8.2 At least one shutdown cooling ioop shall be verified to be in operation and circulating reactor coolant at a flow rate of greater than or equal to 3000 gpm in accordance with the Surveillance Frequency Control Program.

4.9.8.2.1 Verify shutdown cooling loop locations susceptible to gas accumulation are sufficiently filled with water in accordance with the Surveillance Frequency Control Program.

  • One required shutdown cooling loop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing, provided that the other shutdown cooling loop is OPERABLE and in operation.

ST. LUClE -UNIT 1 3/4 9-8a Amendment No. *6, 4O3, 4-79, -19g,

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-201 5-180 Page 1 of 8 St. Lucie Unit 2 Word Processed Technical Specifications 3/4 4-4 3/4 4-5 3/4 4-6 3/4 5-4 3/4 6-15a 3/4 9-8 3/4 9-9

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-201 5-1 80 Page 2 of 8 REACTOR COOLANT SYSTEM HOT SHUTDOWN S;URVEILLANCE REQUIREMENTS 4.4.1.3.1 The required Reactor Coolant pump(s), if not in operation, shall be determined to be OPERABLE in accordance with the Surveillance Frequency Control Program by verifying correct breaker alignments and indicated power availability.

4.4.1.3.2 The required steam generator(s) shall be determined OPERABLE by verifying the secondary side water level to be_> 10% indicated narrow range level in accordance with the Surveillance Frequency Control Program.

4.4.1.3.3 At least one Reactor Coolant or shutdown cooling loop shall be verified to be in operation and circulating Reactor Coolant in accordance with the Surveillance Frequency Control Program.

4.4.1.3.4 Verify required shutdown cooling trains locations susceptible to gas accumulation are sufficiently filled with water in accordance with the Surveillance Frequency Control Program.*

  • Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 4.

ST. LUCIE - UNIT 2 3/4 4-4 ST.

UCI

- UIT 3/44-4Amendment No. 4-73

St. Lucie Units 1 and 2 L-2015-180 Docket Nos. 50-335 and 50-389 Page 3 of 8 REACTOR COOLANT SYSTEM COLD SHUTDOWN - LOOPS FILLED LIMITING CONDITION FOR OPERATION 3.4.1.4.1 At least one shutdown cooling loop shall be OPERABLE and in operation*, and either:

a.

One additional shutdown cooling loop shall be OPERABLE

, or

b.

The secondary side water level of at least two steam generators shall be greater than 10% indicated narrow range level.

APPLICABILITY: MODE 5 with Reactor Coolant loops filled##

ACTION:

a.

With one of the shutdown cooling loops inoperable and with less than the required steam generator level, immediately initiate corrective action to return the inoperable shutdown cooling loop to OPERABLE status or to restore the required steam generator level as soon as possible.

b.

With no shutdown cooling loop in operation, suspend operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet SHUTDOWN MARGIN of Technical Specification 3.1.1.2 and immediately initiate corrective action to return the required shutdown cooling loop to operation.

SURVEILLANCE REQUIREMENTS 4.4.1.4.1.1 The secondary side water level of at least two steam generators when required shall be determined to be within limits in accordance with the Surveillance Frequency Control Program.

4.4.1.4.1.2 At least one shutdown cooling loop shall be determined to be in operation and circulating reactor coolant in accordance with the Surveillance Frequency Control Program.

4.4.1.4.1.3 Verify required shutdown cooling trains locations susceptible to gas accumulation are sufficiently filled with water in accordance with the Surveillance Frequency Control Program.

  • The shutdown cooling pump may be de-energized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided
1) no operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SHUTDOWN MARGIN of Technical Specification 3.1.1.2 and 2) core outlet temperature is maintained at least 1 0°F below saturation temperature.

One shutdown cooling loop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing provided the other shutdown cooling loop is OPERABLE and in operation.

4# A Reactor Coolant pump shall not be started with two idle loops unless the secondary water temperature of each steam generator is less than 400 F above each of the Reactor Coolant System cold leg temperatures.

ST. LUCIE - UNIT 2 3/4 4-5 Amendment No. 4S, C4-, 46, -422, 4:3

St. Lucie Units 1 and 2 L-201 5-180 Docket Nos. 50-335 and 50-389 Page 4 of 8 REACTOR COOLANT SYSTEM COLD SHUTDOWN - LOOPS NOT FILLED LIMITING CONDITION FOR OPERATION 3.4.1.4.2 Two shutdown cooling loops shall be OPERABLE# and at least one shutdown cooling loop shall be in operation.*

APPLICABILITY: MODE 5 with reactor coolant loops not filled.

ACTION:

a.

With less than the above required loops OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate corrective action to return the required loops to OPERABLE status as soon as possible.

b.

With no shutdown cooling loop in operation, suspend operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet SHUTDOWN MARGIN of Technical Specification 3,1.1.2 and within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate corrective action to return the required shutdown cooling ioop to operation.

SURVEILLANCE REQUIREMENTS 4.4.1.4.2 At least one shutdown cooling loop shall be determined to be in operation and circulating reactor coolant in accordance with the Surveillance Frequency Control Program.

4.4.1.4.2.1 Verify shutdown cooling trains locations susceptible to gas accumulation are sufficiently filled with water in accordance with the Surveillance Frequency Control Program.

One shutdown cooling loop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing provided the other shutdown cooling loop is OPERABLE and in operation.

The shutdown cooling pump may be deenergized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided (1) no operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SHUTDOWN MARGIN of Technical Specification 3.1.1.2 and (2) core outlet temperature is maintained at least 1 0°F below saturation temperature.

ST. LUCIE - UNIT 2 3!4 4-6 ST.

UCI~

UIT 23/44.6Amendment No. 422,47-3

St. Lucie Units 1 and 2 L-201 5-180 Docket Nos. 50-335 and 50-389 Page 5 of 8 EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REOUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:

a.

In accordance with the Surveillance Frequency Control Program by verifying that the following valves are in the indicated positions with power to the valve operators removed:

Valve Number Valve Functien Valve Position

a.

V3733

a. SIT Vent Valves
a. Locked Closed V3734
b.

V3735

b. SIT Vent Valves
b. Locked Closed V3736
c.

V3737

c. SIT Vent Valves
c. Locked Closed V3738 V3739 V3740
b.

In accordance with the Surveillance Frequency Control Program 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.*

c.

In accordance with the Surveillance Frequency Control Program by verifying ECCS locations susceptible to gas accumulation are sufficiently filled with water.

d.

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:

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.

In accordance with the Surveillance Frequency Control Program by:

1.

Verifying automatic isolation and interlock action of the shutdown cooling system from 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.

  • Not required to be met for system vent flow paths opened under administrative control.

I ST. LUCIE - UNIT 2 3/4 5-4 Amendment No. :*2.,

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-201 5-180 Page 6 of 8 SURVEILLANCE REOUIREMENTS 4.6.2.1 Each containment spray system shall be demonstrated OPERABLE:

a.

In accordance with the Surveillance Frequency Control Program 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 positioned to take suction from the Rw'r on a Containment Pressure - - High-High test signal.*

b.

By verifying that each spray pump develops the specified discharge pressure when tested pursuant to the Inservice Testing Program.

c.

In accordance with the Surveillance Frequency Control Program, during shutdown, by:

1.

Verifying that each automatic valve in the flow path actuates to its correct position on a CSAS test signal.

2.

Verifying that upon a Recirculation Actuation Test Signal (RAS), the containment sump isolation valves open and that a recirculation mode flow path via an OPERABLE shutdown cooling heat exchanger is established.

d.

In accordance with the Surveillance Frequency Control Program by verifying containment spray system locations susceptible to gas accumulation are sufficiently filled with water.

  • Not required to be met for system vent flow paths opened under administrative control.

ST. LUCIE - UNIT 2 3/4 6-15a ST.

UCI-UNT2 34 6155Amendment No..7.0, 04I, 4-38, 4~

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2015-180 Page 7 of 8 REFUELING OPERATIONS 314.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION HIGH WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.1 At least one shutdown cooling loop shall be OPERABLE and in operation.*

APPLICABILITY: MODE 6 when the water level above the top of the reactor pressure vessel flange is greater than or equal to 23 feet.

ACTION:

With no shutdown cooling loop OPERABLE and in operation, suspend all operations involving an increase in reactor decay heat load or operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of Technical Specification 3.9.1 and within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate corrective action to return the required shutdown cooling loop to OPERABLE and operating status as soon as possible. close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.9,8.1 In accordance with the Surveillance Frequency control Program:

a.

At least one shutdown cooling loop shall be verified to be in operation

b.

The total flow rate of reactor coolant to the reactor pressure vessel shall be verified to be greater than or equal to 3000 gpm.**

c.

Verify required shutdown cooling loop locations susceptible to gas accumulation are sufficiently filled with water.

The shutdown cooling loop may be removed from operation for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8-hour period during the performance of CORE ALTERATIONS in the vicinity of reactor pressure vessel hot legs, provided no operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SHUTDOWN MARGIN of Technical Specification 3.9.1.

    • The reactor coolant flow rate requirement may be reduced to 1850 gpm if the following conditions are satisfied before the reduced requirement is implemented: the reactor has been determined to have been subcritical for at least 125 hours0.00145 days <br />0.0347 hours <br />2.066799e-4 weeks <br />4.75625e-5 months <br />, the maximum RCS temperature is _< 11 70F, and the temperature of CCW to the shutdown cooling heat exchanger is <_ 870F.

ST. LUClE - UNIT 2 3/49-8 Amendment No..76, 422*, 473

St. Lucie Units 1 and 2 L-2015-1 80 Docket Nos. 50-335 and 50-389 Page 8 of 8 REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.2 Two independent shutdown cooling loops shall be OPERABLE and at least one shutdown cooling loop shall be in operation.**

APPLICABILITY:

MODE 8 when the water level above the top of the reactor pressure vessel flange is less than 23 feet.

ACTION:

a.

With less than the required shutdown cooling loops OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate corrective action to return the required loops to OPERABLE status, or to establish greeter than or equal to 23 feet of water above the reactor pressure vessel flange, as soon as possible.

b.

With no shutdown cooling loop in operation, suspend operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of Technical Specification 3.9.1 and within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate corrective action to return the required shutdown cooling loop to operation, Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.9.8.2 In accordance with the Surveillance Frequency Control Program:

a.

At least one shutdown cooling loop shall be verified to be in operation.

b.

The total flow rate of reactor coolant to the reactor pressure vessel shall be verified to be greater than or equal to 3000 gpm.*

c.

Verify shutdown cooling trains locations susceptible to gas accumulation are sufficiently filled with water.

The reactor coolant flow rate requirement may be reduced to 1850 gpm if the following conditions are satisfied before the reduced requirement is implemented: the reactor has been determined to have been subcritical for at least 125 hours0.00145 days <br />0.0347 hours <br />2.066799e-4 weeks <br />4.75625e-5 months <br />, the maximum ROS temperature is <_ 11 70F, and the temperature of CCW to the shutdown cooling heat exchanger is < 87°F.

One required shutdown cooling loop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing, provided that the other shutdown cooling loop is OPERABLE and in operation.

ST. LUCIE - UNIT 2 3/4 9-9 Amendment No. 48, 60, 76,4-22, 42=9,

-4A6, 472