Text

Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
	ML14077A265
Person / Time
Site:	Saint Lucie
Issue date:	02/26/2014
From:	Jensen J; Florida Power & Light Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	L-2013-233
	Download: ML14077A265 (149)
	v • d • e

0FPL.

February 26, 2014 L-2013-233 10 CFR 50.90 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Re:

St. Lucie Units I and 2 Docket Nos. 50-335 and 50-389 Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process In accordance with the provisions of 10 CFR 50.90, Florida Power & Light Company (FPL) is submitting a request for an amendment to the technical specifications (TS) for St. Lucie Unit I and St. Lucie Unit 2.

The proposed amendment would modify TS requirements for mode change limitations in LCO 3.0.4 and SR 4.0.4. provides a description of the proposed change (including tables of affected TS with a brief descriptor of the change), the requested confirmation of applicability, and plant-specific verifications. Attachment 2 provides the existing TS pages marked up to show the proposed changes. Attachment 3 provides revised (clean) TS pages. Attachment 4 provides a summary of the regulatory commitments made in this submittal. Attachment 5 provides the existing TS Bases pages marked up to show the proposed change.

FPL requests that the proposed License Amendment be processed normally and that the amendment be effective on the date of issuance with implementation within 60 days.

This license amendment proposed by FPL has been reviewed by the St. Lucie Plant Onsite Review Group. In accordance with 10 CFR 50.91(b)(1), a copy of this application, with attachments, is being provided to the designated Florida State Official.

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

L-2013-233 Page 2 1 declare Linder penalty of perjury that the foregoing is true and correct.

Executed on

%Lt, FaIJo 2.olq If you should have any questions regarding this submittal, please contact Mr. Eric Katzman, Licensing Manager at 772-467-7734.

Sincerely,

""Jseph Jensen Site Vice President St. Lucie Plant Attachments: 1. Description and Assessment

2. Proposed Technical Specification Changes

3. Revised Technical Specification Pages

4. Regulatory Commitments

5. Proposed Technical Specification Bases Changes cc:

Ms. Cynthia Becker, Florida Department of Health

St. Lucie Units 1 and 2 L-2013-233 Docket Nos. 50-335 and 50-389 Page 1 of 5 ATTACHMENT 1 DESCRIPTION AND ASSESSMENT

1.0 DESCRIPTION

The proposed amendment would modify technical specifications (TS) requirements for mode change limitations in LCO 3.0.4 and SR 4.0.4.

The changes are consistent with Nuclear Regulatory Commission (NRC) approved Industry /

Technical Specification Task Force (TSTF) STS change TSTF-359, Revision 9. On April 4, 2003, the NRC published the Notice of Availability for TSTF-359, Revision 8 in Federal Register Notice 68 FR 16585. That Federal Register Notice announced the availability of this TS improvement through the consolidated line item improvement process (CLIIP). The NRC subsequently made two modifications in response to comments, as well as one editorial change, which have been incorporated into TSTF-359, Rev. 9. The changes proposed in this submittal are; therefore, based. on TSTF-359, Rev. 9.

2.0 ASSESSMENT

2.1 Applicability of Published Safety Evaluation FPL has reviewed the safety evaluation published in Federal Register Notice 68 FR 16585, dated April 4, 2003, which supports the CLIIP. This review included a review of the NRC staff s evaluation, as well as supporting information provided to support TSTF-359, Revision 8 (and subsequently, Revision 9 to TSTF-359). FPL has concluded that the justifications presented in the TSTF proposal and the safety evaluation prepared by the NRC staff are applicable to St. Lucie Unit 1 and St. Lucie Unit 2 and justify this amendment for incorporation of the changes into the St. Lucie Unit 1 and St. Lucie Unit 2 TS.

2.2 Optional Changes and Variations Insofar as the TS for St. Lucie Unit 1 and St. Lucie Unit 2 are custom TS, FPL is not proposing any substantive changes or variations from the TS changes described in TSTF-3 59, Revision 9 and the NRC staffs model safety evaluation dated April 4, 2003.

Additional information related to each affected St. Lucie Unit 1 and St. Lucie Unit 2 TS is provided in the following tables.

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2013-233 Page 2 of 5 St. Lucie Unit 1 The following Technical Specifications are changed to conform to TSTF-359, Revision 9.

TS No.

Title Page 3.0.4 APPLICABILITY - LIMITING CONDITION FOR OPERATION 3/4 0-1 4.0.4 APPLICABILITY - SURVEILLANCE REQUIREMENTS 3/4 0-2 3.4.8 SPECIFIC ACTIVITY 3/4 4-17 3.4.13 POWER OPERATED RELIEF VALVES 3/4 4-59 3.5.3 ECCS SUBSYSTEMS - SHUTDOWN 3/4 5-7 3.7.1.2 AUXILIARY FEEDWATER SYSTEM 3/4 7-4 3.8.1.1 A.C. SOURCES - OPERATING 3/4 8-3 The following Technical Specifications have pre-existing LCO 3.0.4 exceptions. TSTF-359, Revision 9 removes all existing LCO 3.0.4 exceptions; therefore, these exceptions are being removed.

TS No.

Title Page(s)

Table REACTOR PROTECTIVE INSTRUMENTATION 3/4 3-2 3.3-1 3/4 3-3 3/4 3-4 Table ENGINEERED SAFETY FEATURE ACTUATION SYSTEM 3/4 3-10 3.3-3 INSTRUMENTATION 3/4 3-11 3/43-12 3.3.3.1 RADIATION MONITORING INSTRUMENTATION 3/4 3-21 3.3.3.8 ACCIDENT MONITORING INSTRUMENTATION 3/4 3-41 3.4.6.1 REACTOR COOLANT SYSTEM LEAKAGE DETECTION 3/4 4-12 SYSTEMS 3.6.1.3 CONTAINMENT AIR LOCKS 3/4 6-10 3.7.1.1 TURBINE CYCLE SAFETY VALVES 3/4 7-1 3.7.1.5 MAIN STEAM LINE ISOLATION VALVES 3/4 7-9 3.7.5.1 ULTIMATE HEAT SINK 3/4 7-18 3.7.9.1 SEALED SOURCE CONTAMINATION 3/4 7-27 3.9.12 FUEL POOL VENTILATION SYSTEM - FUEL STORAGE 3/4 9-12 3.11.2.5 EXPLOSIVE GAS MIXTURE 3/4 11-14 3.11.2.6 1 GAS STORAGE TANKS 3/4 11-15

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2013-233 Page 3 of 5 St. Lucie Unit 2 The following Technical Specifications are changed to conform to TSTF-359, Revision 9.

TS No.

Title Page 3.0.4 APPLICABILITY - LIMITING CONDITION FOR OPERATION 3/4 0-1 4.0.4 APPLICABILITY - SURVEILLANCE REQUIREMENTS 3/4 0-2 3.4.8 SPECIFIC ACTIVITY 3/4 4-25 3.4.9.3 OVERPRESSURE PROTECTION SYSTEMS 3/4 4-36 3.5.3 ECCS SUBSYSTEMS - SHUTDOWN 3/4 5-7 3.7.1.2 AUXILIARY FEEDWATER SYSTEM 3/4 7-4 3.8.1.1 A.C. SOURCES - OPERATING 3/4 8-3 The following Technical Specifications have pre-existing LCO 3.0.4 exceptions. TSTF-359, Revision 9 removes all existing LCO 3.0.4 exceptions; therefore, these exceptions are being removed.

TS No.

Title Page Table REACTOR PROTECTIVE INSTRUMENTATION 3/4 3-2 3.3-1 3/4 3-3 Table ENGINEERED SAFETY FEATURES ACTUATION SYSTEM 3/4 3-12 3.3-3 INSTRUMENTATION 3/4 3-13 3/43-14 3/4 3-15 3.3.3.1 RADIATION MONITORING INSTRUMENTATION 3/4 3-24 3.3.3.5 REMOTE SHUTDOWN SYSTEM INSTRUMENTATION 3/4 3-38 3.3.3.6 ACCIDENT MONITORING INSTRUMENTATION 3/4 3-41 3.4.4 PORV BLOCK VALVES 3/44-10 3.4.6.1 REACTOR COOLANT SYSTEM LEAKAGE DETECTION 3/4 4-18 SYSTEMS 3.6.1.3 CONTAINMENT AIR LOCKS 3/4 6-9 3.7.1.1 TURBINE CYCLE SAFETY VALVES 3/4 7-1 3.7.1.5 MAIN STEAM LINE ISOLATION VALVES 3/4 7-9 3.7.5.1 ULTIMATE HEAT SINK 3/4 7-15 3.7.10 SEALED SOURCE CONTAMINATION 3/4 7-28 3.11.2.5 EXPLOSIVE GAS MIXTURE 3/4 11-14 3.11.2.6 GAS STORAGE TANKS 3/4 11-15

St. Lucie Units 1 and 2 L-2013-233 Docket Nos. 50-335 and 50-389 Page 4 of 5

3.0 REGULATORY ANALYSIS

3.1 No Significant Hazards Consideration Determination FPL has reviewed the proposed no significant hazards consideration determination (NSHCD) published in the Federal Register as part of the CLIIP. FPL has concluded that the proposed NSHCD presented in the Federal Register notice is applicable to St. Lucie Unit 1 and St. Lucie Unit 2 and is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91(a).

3.2 Verification and Commitments As discussed in the notice of availability published in the Federal Register on April 4, 2003 for this TS improvement, plant-specific verifications were performed as follows:

FPL has established TS Bases for LCO 3.0.4 and SR 4.0.4 which state that use of the TS mode change limitation flexibility established by LCO 3.0.4 and SR 4.0.4 is not to be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to operable status before entering an associated mode or other specified condition in the TS Applicability.

The modification also includes changes to the bases for LCO 3.0.4 and SR 4.0.4 that provide details on how to implement the new requirements. The bases changes provide guidance for changing Modes or other specified conditions in the Applicability when an LCO is not met. The bases changes describe in detail how: LCO 3.0.4.a allows entry into a MODE or other specified condition in the Applicability with the LCO not met when the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time; LCO 3.0.4.b allows entry into a MODE or other specified condition in the Applicability with the LCO not met after performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate; and LCO 3.0.4.c allows entry into a MODE or other specified condition in the Applicability with the LCO not met based on a Note in the Specification, which is typically applied to Specifications which describe values and parameters (e.g., Containment Air Temperature, Containment Pressure, MCPR, Moderator Temperature Coefficient), though it may be applied to other Specifications based on NRC plant-specific approval.. The bases also state that any risk impact should be managed through the program in place to implement 10 CFR 50.65(a)(4) and its implementation guidance, NRC Regulatory Guide 1.182. "Assessing and Managing Risks Before Maintenance Activities at Nuclear Power Plants," and that the results of the risk assessment shall be considered in determining the acceptability of entering the MODE or other specified condition in the Applicability, and any corresponding risk management actions. In addition, the bases state that upon entry into a Mode or other specified condition in the Applicability with the LCO not met, LCO 3.0.1 and LCO 3.0.2 require entry in to the applicable ACTIONS until the condition is resolved, until the LCO is met, or until the unit is not within the Applicability of the TS.

The

St. Lucie Units 1 and 2 L-2013-233 Docket Nos. 50-335 and 50-389 Page 5 of 5 bases also state that SR 4.0.4 does not restrict changing MODES or other specified conditions of the Applicability when a Surveillance has not been performed within the specified Frequency, provided the requirement to declare the LCO not met has been delayed in accordance with SR 4.0.3. Finally, FPL has a bases control program consistent with Section 5.5 of the STS, and the equivalent of STS SR 3.0.1 and associated bases.

4.0 ENVIRONMENTAL EVALUATION FPL has reviewed the environmental evaluation included in the model safety evaluation dated April 4, 2003 as part of the CLIIP. FPL has concluded that the staff's findings presented in that evaluation are applicable to St. Lucie Unit 1 and St. Lucie Unit 2 and the evaluation is hereby incorporated by reference for this application.

St. Lucie Units I and 2 Docket Nos. 50-335 and 50-389 L-2013-233 Page 1 of 54 ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATION CHANGES (MARK-UP)

L-2013-233 Page 2 of 54 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY LIMITING CONDITiON FOR OPERATION 3.0.1 Compliance with the Limiting Conditions -for Operation. (LCO) contained.in the succeeding. specifications is required during the OPERATIONAL MODES or other conditions specified therein; except that upon:failure to meet the Limiting Conditions for Operation, the associated ACTION :requirements shall be met.

3.0.2 Noncompliance with a specification shall exist when the requirements of the Limiting Condition for Operation (LCO) and associated ACTION requirements are not.met within the:specified time intervalsi If the Limiting Condition for Operation is restored prior to expiration.ofthe specified time intervals, completion of the ACTION requirements is not required.

3.0.3 When aLimiting Condition for Operation (LCO) is not met, except as provided in the associated ACTION requirements, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months action shall be initiated to place the unit in a MODE in which specification does not apply by placing it,. as: applicable in:

1..

At.. ieast.HOT STANDBY within the neXt 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .,

2.

At::least HOT SHUTDOWN within the following, 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and

3.

At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Where corrective measures are completed that permit.operationwunder the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the.LCO. Exceptions

'to these requiremen.ts. are stated in. the individual specifications.

This specification is not applicable in MODES.5 or 6.

8..4E n~try in to a n O P E R A T IO N A L M O D E o r o t hle r s p e c liie d "ia p p ic a

.bil.itY c o n d itio n "

hal o t be made when the conditions of.the..L imi~ting. Condition for. Operation.

are not met and the associated ACTION requires a~shutdown if they Are not met wihnaspecified timne interval. En~try into an OPERATIONAL MODE or specified l,

.ondiiomay be made in accordance with ACTION reu-r~mnt whe coformane..

to them permits continued operation of.the facility for an unli~m ited.

period....

of;time.. This provision.shall not.prevent passage through or to OPERATIONAL MODEs as-required. to comply with ACTION:statements. Exceptions to these,

.: tq uirements are stated in.the individual. specifications..

.j,.

7_

7 ST. LUCIE -:UNIT 1 3/40o-1 Amendment No. 40, 08,103

L-2013-233 Page 3 of 54 INSERT I (LCO 3.0.4)

When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made:

a. When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time;

b. After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate; exceptions to this Specification are stated in the individual Specifications, or

c. When an allowance is stated in the individual value, parameter, or other Specification.

L-2013-233 Page 4 of 54 APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be applicable. during the OPERATIONAL MODES. or other conditions specified forindividual.Limiting Conditions.for Operation unless otherwise stated in an individual Surveillance Requirement. Failure to perform :a Surveillance Requirement within the allowed surveillance interval, defined by Specification 4,0.2i shall constitute.noncompliance With the OPERABILITY requirements for a Limiting. Condition for Operation. Surveillance Requirements do not have'to be: performed on inoperable equipment.

4.0.2 Each Surveillance Requirement shall be performed within the specified surveillancb.e interval with a.maximum allowable extension. not to exceed 25% of the specified surveillance interval.

4.0.ý3 If it is.discovered that a Surveillance was not performed within its specified frequency, then compliance with the requirement to declare the Limiting Condition for Operation not met may be delayed,: from the time of discovery, up to 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s: or up to the limit.6f the specified frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. A risk. evaluation shall be performed for any Surveillance delayed greater than 24.hours and the risk impact shall be managed.

If the Surveillance is not performed Within the delay period, the Limiting Condition for Operation must immediately be declared not met, and the applicable ACTION(s) must be:

taken.

When the Surveillance is performed within the delay period and the Surveillance is not met, the Limiting Condition for Operation must immediately be declared not met,. andthe applicable ACTION(s) must be taken.

.. 4C.

4.0.4. Entryinto an OPERATIONAL MODE or other specified applicability condition sallýnotbe mad :e.un~less the.Surveillance.Requirement(s) associated with the Limiting Condition for :

Op rain ha e been performed within: the stated surveillance interval. or as otherwise )

E/pddiid. This provisoi. shall not predVet passage thro)ugh~ or46t OPERATIONAiL/,,

MODSasrqitedt t'Comply: with.ACTION requirements.

/

4.0.5 Surveillance Requirements for inservice inspection of ASME Code Class 1, 2 and 3 componhents shall be applicable:.as follows:

a.. Inservice inspection of ASME Code Class 1, 2 and 3 components shall be performed in accordance with.Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as. required.by 1t0.CFR 50, Section 50.55a(g),.extept.where:sp.ecific.written relief has been granted by the Commission purisuant to 1.0 CFR.50,:.Section 50.55a(g) (6) (i).

b.

deleted ST. LUCIE-.- UNIT 1 314 0-2 Amendment No 26,40,00, g 408, 463, 18.6

L-2013-233 Page 5 of 54 INSERT 2 (SR 4.0.4)

Entry into a MODE or other specified condition in the Applicability of a Limiting Condition for Operation (LCO) shall only be made when the LCO's Surveillances have been met within their specified frequency, except as provided by Surveillance Requirement 4.0.3. When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4.

This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

TABLE 3.3-1 REACTOR PROTECTIVE INSTRUMENTATION

.FUNCTIONAL: UNIT

1.

Man.ual Reactor Trip

2.

Power Level'- High

.3.

Reactor Coolant Flow - Low

4.

Pressurizer Pressure - High

5.

Containment.Pressure - High

6.

Steam Generator Pressure - Low

7.

Steam Generator Water Level - Low

8.

Local Power Density - High

9.

Thermal Margin/Low Pressure 9a. Steam Generator?.PressUre:

Difference -High

10. Loss of Turbine - Hydraulic Fluid Pressure -..Low TOTAL NO.

OF CHANNELS 4

,4/SG:

4 4

4/S:G 4/SG CHANNELS TO TRIP 1

.2(a) 2(a)/SG 2

2 2(b)/SG.

2/SG MINIMUM CHANNELS OPERABLE 2:

3(T) 3/SG 3

3

.3/SG 3/SG APPLICABLE MODES 1, 2.and*

1, 2 (e) 1,2 1.,2 1,:2' 1,.2 ACTION 1

2B 4

4 4

4.

.2(c)

.2(a) 2(a) 3 3

3

,3 1

1, ::2 (e) 1,2. (e) 1 2(c)

>~

ST. LUCIE - UNIT 1

-3/4 3-2 Amendment No. 445,43

TABLE 3.3-1 (Continued)

REACTOR PROTECTIVE, INSTRUMENTATION TOTAL NO.

OF CHANNELS CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE FUNCTIONAL UNIT

11. Wide.Range LogarithmicNeutron Flux Monitor

a. Startup and Operating -

Rate of.Change of Power -

High

b. Shutdown 1.2.. Reactor'Protection System Logic 1:3. Reacto.r Trip.Breakers APPLICABLE MODES ACTION 4

4 4

4

2(d) 0 2

2 3

2 4

4 1, 2 and*

3, 4,.5 1, 2*

1., :2*

3 4

4

-U>

0, CD, ST. LUCIE - UNIT 1 314 3-3

U3Amendment No...45 27

L-2013-233 Page 8 of 54 TABLE 3.3-1. (Continued)

TABLE NOTATION

With the protective system trip breakers 6n the closed position and the CEA&drive system capable:

of CEA withdrawal.

-#-T-he-previsionsf-Speeif4eat4eno-..O4-afre9otapplioable,----

(a)

Trip may be bypassed below 1% of RATED THERMAL POWER; bypass shall be automatically removed when Wide Range Logarithmic Neutron Flux power is> 1% of RATED THERMAL POWER; (b)

Trip may be manually bypassed below 685 psig; bypass shall be automatically removed at or above 685 psig.

(c).

Trip may be bypassed below 15% of RATED THERMAL POWER; bypass shall be automatically removed when Power Range Neutron Flux power is> 15% of RATED THERMAL POWER.

(d)

Trip may be6bypassed beloW: 104%.and :above 15% of RATED THERMAL.POWER; bypass shall be automatically removed when Wide Range Logari.thmic Neutron Flux power is > 10"4%'

and Power Range Neutron Flux power < 15% of RATED THERMAL POWER:..

(e)

Deleted.

(f)

There shall be at least two decades of overlap between the Wide Range Logarithmic Neutron Flux Monitoring Channels and the Power Range Neutron Flux.Monitoring Channels.

ACTION STATEMENTS ACTION 1 With the number of channels OPERABLE one less than required by the Minimum Channels.OPERABLE requirement, restore the inoperable channelItoOPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the protective system trip breakers.

ACTION 2: -

With the number of OPERABLE channels one less than the Total. Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a.

The..inoperable channel is placed in.either the bypassed or tripped condition within 1.hour. For the purposes of testing and maintenance, the inoperable channel may be bypassed for up to.48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months from time of initial loss of OPERABILITY; however, the inoperable channel shall then be either restored. to OPERABLE status or placed, in the tripped condition.

ST..LUCIE - UNIT 1 3/43.-4 Amendment No. 46, 27, 45, 402,159:

TABLE"3.3-3 "ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TOTAL. NO.

OF CVANNELS CHANNELS' TO TRIP MINIMUM CHANNELS OPERABLE FUNCTIONAL UNIT I.

I, SAFETY INJECTION (SIAS).

a. Manual (Trip Buttons)

b. Containment Pressure -

High

c. Pressurizer Pressure -

Low

2.

CONTAINMENT SPRAY (CSAS).

a. Manual: (Trip. Buttons) b.. Containment Pressure -

High-High

3.

CONTAINMENT ISOLATION, (CIS) a...Manual. (Trip. Buttons)

b.. Containment Pressu-re -

High

,.c, Containment Radiation -

High

d.

SIAS

4.

M.AN STEAM LINE ISOLATION (MSIS)

a. Manua.l.rip Buttons)

b. Steam Generator Pressure.- Low APPLICABLE MODES ACTION 2

4 4

2

.4 2

.4.

1 2.

2, 1

2(b) 2 2

3 3

2 3:

.2 3

%1,2., 3,4 1,2,3 1,2, 3(a)

!,2,3,4 1,2,3 1,2,3,4.

8

.8 10a, 1.0bf. 10c 8

1, 2,3

.4 2

3 1,2,3,4 9*

(S e e F u n ctio n a l U nit.1 a b o v e ) ----

2/steam 1/steam 2/operating generator generator steam

'generator 4/steam 2/steam

.3/steam

.generator generator generator 1, 2, 3j 4 1, 2, 3(c) 8 Co CD 0

Amendment No..-4., -3,, 188 0

0 LO ST. LUCIE.-.UNIT 1

3/4..3-10

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY.FEATURE ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT

.5.

CONTAINMENT SUMP RECIRCULATION (RAS)

a. Manual RAS (Trip Buttonss) b, RefUeling Water Tank - Low

6.

LOSS OF POWER

a. 4.16 kv Emergency Bus Under-

.voltage (Loss.of Voltage).

b. :4.16 kv. Emergency Bus Under-voltage (Degraded Voltage)

c. 480 V Emergency: Bus Under-voltage.(Degraded Voltage) 7..

AUXILIARY FEEDWATER (AFAS)

a. Manual (Trip Buttons)

b. Automatic Actuation Logic

c. SG.Level (1A/1B) -.Low

.8..

AUXILIARY FEEDWATER]ISOLATION

a. SG 1A-SG iB;Differential Pressure:

b. Feedwater Header 1A:-,.1 B Differential Pressure TOTAL NO,.

OF CHANNELS CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE MODES 2

.4" 1

.2

.2:

3 1, 2,3, 4 1,2, 3 2/Bus 2/Bus 2/Bus 4/SG

.4/SG

.4/SG 4/SG 4/SG

2/Bus 2/Bus 2/Bus 2/SG

.21SG 2/SG

.2JSG 2/SG 1/Bus 1/Buls 1/Bus 4/SG 3/SG 3/SG 3/SG 3/SG 1,2,3

1, 2, 3 1,2,3 1,2, 3 1.,2,3 1.,.2,..3 1,.2, 3 ACTION.

8 13 12 12 12 11 11 14a§ 14bc 14C 14ag, 14c

-D o0 0J 0*

ST. LUCIE - UNIT I 3/4 3-11.

.Amendment No.. 4-,6 74, 4, 188

L-2013-233 Page 11 of 54 TABIE 3.3-3 (continued)

TABLE NOTATION (a)

Trip funclion.may be bypassed in this MODE when pressurizer pressure is 1725 psia; bypassshall be automnatically removed when pressurizer pressure.is > 1725 psia.

(b)

An SIAS signal is first necessary to enable CSAS logic.

(c)

Trip function may be bypassed in this MODE beloW 685 psig; bypass shall be automatically removed.at or above 685 psig.

ACTION STATEMENTS ACTION 8 With'the.number of. OPERABLE channels:one less than the Total. Number Of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 9 With the number of OPERABLE channels.one less than.the.

Total.Number of Channels, operation rmay proceed.provided the following conditions are satisfied:.

a.

The.inoperable channel is placed in either thie bypassed or tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . For the purposes *of testing andmaintenance, the inoperable channel may be. bypassed for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months from time of:initial loss of OPERABILITY; however, the inoperable channel shall then be either restored to OPERABLE status or placed in the'tripped~condition.

b.

W.thih one hour, all functional units receiving an input from the inoperable channel are also bypassed or tripped..

c.

The Minimum Channels OPERABLEirequirement. is rnet; however, one additional channel may be bypassed for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months while performing tests and maintenance on that channel provided the other inoperable channel is placed in the tripped condition.

.ST. LUCIE-ý.UNIT1l 314.3-12 Amendment No. 4-5, i45,202

L-2013-233 Page 12 of 54 IN5,TPI 'MENTATION 314.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING LIMITING CONDITION FOR OPERATION 3.S.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shail be OPERABLE with their alarm/trip Setpbints within the specified limits.

APPLICABILITY: As shown: in Table,3.3-6.

ACTION:.

a.

With a radiation monitoring channel alarm/trip setpoint exceeding the value shown in Table 3.3-6, adjust the setpoint to within the limit within 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months s:or declare the. channel inoperable.

b.

With one or more radiation monitoring channels inoperable, take:the ACTION shown in Table 3.3M6.

c.

The provisions of Specification\\ 3.0.3 efid&94 are not applicable.,

SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the.CHANNEL CHECK, CHANNEL CALIBRATION and. CHANNEL FUNCTIONAiL TEST operations during the modes and at the frequencies shown in. Table 4,.3-3.

4.3.3.2 At lease once per 18months, each Control. Room Isolation radiation monitoring instrumentation channel shall be demnonstrated OPERABLE by verifying that the response time of the channel:is within limits.

.ST. LUCIE - UNIT I 314 3-21 Amendment No. 40, 4-7 206

L-2013-233 Page 13 of 54 INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION LM1ITGQN DTJ NREQRPRATION 3.3.3.8 The accident monitoring instrumentation channels shown in Table 3.3-11 shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a.

Actions per Table 3.3-11.

,.b.---T-ho-provisions-ofSpeification_3OA-are-not-applicable.....'-

SURVEILLANCE REQUIREMENTS 4.3.3.8 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL.CALIBRATION operations at the frequencies shown in Table 4.3-7.,

S.Tý LUCIE - UNIT 1 3/4 3-41 Amendment No. 3, 118

L-2013-233 Page 14 of 54 REACTOR COOLANT SYSTEM W34.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS

.LIMITING *ONDITION

.OROPERfTItN 3.486:1 The following RCS leakage detection systems will be: OPERABILE:

a.

The reactor cavity sump inlet flow. monitoring.system; and

.b:

One containment atmosphere radioactivity monitor (gaseous. or particulate).

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

.ACTION:.

a.

With the reactor cavity sunmp inlet flow monitoring system inoperable with :an operable containment particulate radioactivity monitor, perform a RCS water inventory balance at least once per 24* hours and restore.the :sump inlet flow monitoring.systemf to OPERABLE status within 30 days; otherwise, be in.at least HOT STANDBY within the next&6 hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With the reactor cavity sump inlet flow monitoring system inoperable with only the:

co.ntainment gaseous radioactivity monitor operable, perform an RCS water inventory balance at least once per 24* hours and analyze grab samples 0f the containment atmosphere at least once per 1.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ; and either restore the sump inlet flow monitoring: system to OPERABLE status within 7 days or restore the containment particulate radioactivity monitor to OPERABLE status within 7 days and enter action a. above with the time.in this action applied against the allowed outage time of action a.'; otherwise, be in at least"HOT"STANDBY~within the next 6: hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c.

With the required radioactivity monitor inoperable, analyze grab samples of the containment atmosphere or perform.a RCS water inventory balance at least.once per 24*hours, and restore the required.radioactivity monitor to OPERABLE'status

-within 30 days;. otherwise, :be inat least HOT STANDBY within the.next 6.hours and in COLD.SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

d.

With all.required monitors inoperable, enter LCO3.0.3 immediately.

-Riobor "c " ~A SURVEILLANCE REQUIREMENTS 4.4.6.1 The RCS leakage detection.:instruments shall be demonstrated OPERABLE by:

a.

Pe.rfrmance.of t.he CHANNEL.CHECK, CHANNEL FUNCTIONAL TEST, and, CHANNEL CALIBRATION of the'required containment atmosphere radioactivity monitor atthe frequencies specified in Table 4.3-3.

b:

Performance of the CHANNEL CALIBRATION of the reactor cavity sump inlet flow.

monitoring system.at least once per 18 months..

t Not required to be performed until 12. hours after establishment of steady state operation.

ST., LUCIE - UNIT I.

3/4.41-12 SAmendment No. 4.44*.4, Z..212

L-2013-233 RFACTOP rO.

ANT SYSTEM Page 15 of 54 SPECIFIC ACTIVITY LIMITING CONDITION" FOROPERATION 3.4.8 The specific activityof the primary coolant shall be limited to:.

a. < 1.0 piCi/gram DOSE EQUIVALENT 1-13.1, and

b. < 518.9 pCi/gram DOSE EQUIVALENT XE 133..

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

ACTION:1

a.

With.the.specific activity of the primary coolant >1.0 pCilgram DOSE.

EQUIVALENT 1-131, verify DOSE EQUIVALENT I-131. is '60.0 pCi/gram once per four hours.

b.

With the. specific activity of the. 'primary coolant > 11.0. *.Ci/gram DOSE EQUIVALENT 1-131., but.<60.0 pCi/g.ram DOSE EQUIVALENT 1-.131, operation may. continue for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months while efforts are made to restore DOSE EQUIVALENT 1-131 to within.the 1.0 [lCi/gram limit. Speciftation-3.--4-i~s-.

e o -abi..,.O i3

c.

With the specific :a.ctivity of the primary coolant > 1.0 pCi'gram DOSE EQUIVALENT 1-1.31 for greater than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time.

interval, or > 60.0 pCi/gram DOSE EQUIVALENT 1-131, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following30.hours.

d.,

With the specific activity of the primary coolant > 518.9 p.Ci/gram:DOSE EQUIVALENT XE-i33, operation maycontintue for' up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months while efforts.

are made to restore DOSE.EQUIVALENT XE-1 33 to within the.518g9 itCi/gram DOSE EQUIVALENT XE-1 33 limit.

L.,peefi

-e-.'s a1lisale. Lo-O 3.0.4.

e.

With the specific:activity of the primary coolant.> 518.9 jtCi/granm DOSE EQUIVALENT XE-133 for greatefrthan 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time..

interval, be in HOT STANDBY Within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the folloWing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.4.8 The specific, activity of the primary coolant shall be determined to be within the limits by performance Of the sampling and analysis pro-g arafn of:Table 4.4-4.

S.T. LUCIE - UNIT 1

3/4 4-17 Amendment No. 69, 40-;, 213

L-2013-233 REACTOR COOLANT SYSTEM Page 16 of 54 POWER OPERATED RELIEF VALVES UIMIIIL

_N.DJTOfN FOR OPERATION 34.13 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 during heatup, cooldown and isothermal conditions when the temperature of any RCS cold leg is less than or equal to 2000F.

.b.

A setpoint of less than or equal to.530 psia shal.be selected during heatupý..cooldown and isothermal conditions. when. the temperature of any RCS cold leg isgreater than 200OF and less than or equal to 300°F.

APPLICABILITY:

MODE 4 when the temperature of any:RCS cold leg is:less than or equal to 3001F, MODE.5, and MODE 6 When the head is on the reactor vessel;

and the RCS is not veihted through greater than a 1.75 square inch vent,

ACTION:

a..

With ohe PORV inoperable in MODE 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

b..

With one PO.RV inoperable, in MODES: 5 or 6, either (1) restore the.

inoperable PORV to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; or (2), complete

,depressurization and venting of.the RC.S through. greater than a 1.75 square inch vent within a total of 32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months .

c.

With both PORVs inoperable, restore at least one PORV to operable status or complete dePressurizatio'nand venting of the. RCS through greater than a 1.75 squareinch vent within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

d.

With the RCS vented. per ACTIONS a,. b,. orc, 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 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s*.

e.

.In the:event.either'the PORVs or the RCS.vent(s) are used to mitigate an RCS pressure transient, :a speial Report shall be prepared and submitted to the: Commission 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.

hp i

LC 3.,,

4 46ppt~ecz,6t0

+c-POR\\Js. Win"b elle4.h SURVEILLANCE: REQUIREMENTS 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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; 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.

3V4 4-59 Amendment. No. 60, 84,i404, 432, 213

L-2013-233 Page 17 of 54 EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:

a.

In MODES,3* and 4#:, one EGGS subsystem composed of one OPERABLE. high pressure safety injection pump and one OPERABLE flow path capable of taking suction fiom the. refueling water storage tank on a safety injection actuationrsignal and automnaticallyitransferring suction to the containment sump On a sump recirculation actuation signal.

b.

Prior to decreasing the reactor coolant system temperature below 270°F a maximum..of only one high pressuresafety injection pump shall be OPERABLE withits associated header stop valve open.

c.

Prior to decreasing the reactor coolant system temperature below 236*F.all high pressure safety. injection pumps :shall be disabled and their associated header stop valves closed except as allowed by:Specifications 3.1.2.1 and 3.1.2.3.

APPLICABILITY: MODES 3* and 4.

MODES 5 and 6 when the Pressurizer manway cover is in place and.

the reactor vessel head is: on.

ACTION:

a.

'With no EGCS subsystems OPERABLE in MODES 3* and 4., immediately restore one ECCS subsystem' to OPERABLE status or be in COLD SHUTDOWN within 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .

b.

With RCS temperature below. 2700F and'with more than the allowed high pressure safety injection pump OPERABLE or injection valves: ahd header isolation valves open, immediately disable the high pressure safety injection pump(s) or close the header isolation valves.

c.

In the event the ECCS is actuated and :injects water into the Reactor Coolant System, a Special Reportshall 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.

L L..O3.6.4..A at$

"i4~Pel 4'"1

.6 ODS.V11 Pvelsuiv6

~kAIei~

8dSYjS41 eý+AODC~ 4.

SURVEILLANCE R~I1 EMENTS' 4.5.3.1 The ECCS subsystem shall be demnibstrated OPERABLE per the applicable Surveillance Requirements of 4.5.2.

4.5.3.?

The high pressure safetyinjection pumps shall be verified inoperable and the associated header stop valves closed prior to decreasing below the above. specified Reactor Coolant System temiperature and once per month when the Reactor Coolant.System is at refueling temperatures.

With.pressusrizer pressure < 1750 psia.

REACTOR COQLANT SYSTEM'cold leg temperature above 2500F.

%ST. LUCIE -.UNIT 1 3/4 5-7 Amendmen.N0..28:60, 84-,

404, 443. 177

L-2013-233 Page 18 of 54 CONTAINMENT SYSTEMS:

CONTAINMENT AIR LOCKS LIMITING.CONNDITION FOR OPERATION

.3.6.1.3 Each.containmeint air lock shall be. OPERABLE with:

a, Both doors closed except when the air lock is being used forrnormal transit entry and exit through thie. containment, then at least: one air lock door shall be closed., and

b.

An overall air lock leakage rate in accordance with the Containment Leakage Rate Testing Program.

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

ACTION:

a.

With one containment air lock door inoperable*'

1.

Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status within 24. hours or lock the OPERABLE air lock door closed.

2' Operation may then continue until performance of the next required overall air lock. leakage test provided that the. OPERABLE, air lock door is verified to be closed at least* once per 31 days.

3.

Otherwise, 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 .

b..

With the containment air lockinopefable, except as:the result of an inoperable air lock.door,. maintain at least one air lock door closed; restore the inoperable air lock to.OPERABLE status within-24 hours or be in-atleast 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 .

.SURVEILLANCE REQUIREMENTS,

.4.6.1.3 Each: containment air lock shall be. demonstrated OPERABLE:

If the inner air lock dooris inoperable, passage through the. OPERABLE outerair lock door is permitted to effect, repairs to the inoperable inner air. lock door. No mhore than one airlock door shall be.open at-an.ytime.

ST. LUCIEý-:UNIT*!

3/4 6A 10 Amendment No. 85, 149.

L-2013-233 3/4.7 PLANT SYSTEMS Page 19 of 54 3.4.7,1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1,1 All main steam line Code safety Valves shall be OPERABLE with lift settings as specified in'Table 4.7-1.

APPLICABILITY: MODES 1, 2 and.3.

ACTION:

a.

With boih reactor coolant loops and associated steam generators in operation:and with one or more main steam line code safety valves inoperable, operation in MODES 1, 2 and 3 may proceed provided that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ,. either the inoperable

.valve is restored to OPERABLE status. or the Power Level-High trip. setpoint, is reduced per Table 3.7-1; otherwise, be in at least HOT STANDBY within the next 6:.hours and in COLD. SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

,.-b.----T-he-povisions-ofS'pecifieation-3.-.4-are:not -applicable...

_(.

SURVEILLANCE REQUIREMENTS 4.7.1.1 Verify each main steam lin.e.. code safety valve is OPERABLE in accordance with the Inservice Tessting Program. Following testing, as-left lift settings shall be within +1-1/0 of 1000 psia for Valves 8201 through 8208, and-within +/- 1% of 1040 psia for Valves 8209 through 8216 specified in Table 4.7-1.

ST., LUCIE.-..UNIT1.!

3/4 7:1 Amendmnent No. 90,453,166

L-2013-233 PLANT SYSTEMS Page 2(

AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7. 1.2 At least three independent steam generator.auxiliary feedwater pumps and associated flow paths shall beOPERABLE with:

a.

Two motor driven feedwater pumps, and

b.

One feedwater pump capable of being powered from an OPERABLE steam supply system.

APPLICABILITY: MODES 1,.2 and 3.

ACTION:

o.. With one auxiliary feedwater pump inoperable, restore at least three auxiliary feedwater pumps (two motor driven pumps and one capable of being powered by an OPERABLE steam supply system) 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 .

6b. LCO 3.O04.._ 6

,IS,+

I Ica I6..

SURVEILLANCE REQUIREMENTS 4.7.1.2 Each: auxiliary feedwater pump shall be demonstrated OPERABLE:

a.

At least once per 31 days by:

) of 54 I

ST. LUCIE - UNIT I

3M4 7-4 Amendment No. 35, 90i 199

L-2013-233 Antachnment 2 Page 21 of 54 PLANT SYSTEMS MAIN STEAM LINE ISOLATION VALVES LIMIIN3 CNDITION FOR OPERATION 3.7.1.5

.Each main steam line isolation valve shall be OPERABLE.

APPLICABILITY: MODES 1:,.2 and 3.

ACTION:

MODE I With one main steam line isolation valve inoperable, POWER OPERATION may continue. provided the inoperable valve is either restored to OPERABLE~status or closed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; :otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ..

MODES 2 -

and 3 With one or both main steamiso!atioh valve(s) inoperable, subsequent operation in MODES 2 or 3 may proceed provided the.isolation valve(s) is (are) maintained closed' Otherwise, 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 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

,,-4previs* oS-,.p~eeifieatortra, e~tap~li*ablae~

_S_3ELL

__I*E.BEOUIREMENTS 4.7.1.5 Each main steam line isolation valve that is open shall.be demonstrated OPERABLE by Verifying full closure Within 6.0 seconds when tested pursuant to the I nservice Testing Program.

.ST. LUCIE.- UNIT'!

"3/4 7-9 Amendment. No. 69,.444, 153

L-2013-233 PLANT SYSTEMS 314.7.5 ULTIMATE HEAT SINK Page 22 of 54 LIMITING CONDITION FOR OPERATION0.

3.7.5.1 The ultimate heat sink shall be OPERABLE with::

a Cooling water Ifrom the Atlantic Ocean providing a water level above

-10.5 feet elevation, Mean Low Water,..at.theplant intake structure, and

b.

Two OPERABLE valves in the barrier dam between Big.Mud Creek and.

the intake structure.

APPLICABILITY: At all times.

ACTION:

a.

With the water: level requirement of the above Specification not satisfied, be in at least HOT STANDBY within six hours and provide cooling water from Big Mud Creek within the next 12. hours.

b.

With one isolation valve in the barrier dam between Big Mud Creek

.and the intake structure inoperable, restore the inoperable valve.

to.OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . or, within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

install a temporary flow barrier, and open the barrier damn isola-tion valve. The availability of-the onsite equipment capable of removing the barrier shall be verified at least once per seven days thereafter.

c..

With both of the isolation valves in the barrier dam between. the in-take*structure.and Big.Mud Creek inoperable, within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months either:

1.)

Install both temporary flow barriers and manually open both barrier dam isolation valves. The availability of.the onsite equipment capable of removing the barriers. shall be verified at least once per seven days thereafter, or

2)

Be in at least HOT STANDBY within.the. next 6.hours.and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

d~hepvei~i~s-f-Beifpa'tierow-4)are-rnot-applieableý..

SURVEILLANCE REQUIREMENTS!

4.7.5.1.1 The ultimate heat sink shall be determined OPERABLE at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the average water level to be within the limits, J.

4.7.5.1.2 The isolation valves in the barrier dam between the intake structure and Big Mud Creek shall be demonstrated OPERABLE at least once per six months%

by cycling each valve.,through, at leastoe.necomplete cycle of full. travel.

.ST. LUCIE - UNIT'1

.3/4 7o.18 Amendment No. 54

L-2013-233 Attachrnent 2 PLANT SYSTEMS Page 23 of 54 314.7.9 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATLON 3.7,9.1 Each sealed source containing.radioactive material either in ex)cess of 100 microcuries :of beta;and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of > 0.005 microcu-ries of removable. contamination.

APPLICABiLITY: At all timeS..

ACTION:

a.

Each sealed source with removable contamination in excess of the above limit shall be immediately withdrawn from use and:

1.

Either decontaminated and repaired, or

2.

Disposed of inaccordance with Commission Regulations.

b.

The provisions ofSpecificationk..3.0.3"ai-3.-4 are not applicable.

.SURVEILLANCE RE.QUIREMENS 4.7.9.1.1 Test Requirements -.. Each.sealed source shall be tested for leakage and/or contamination by.:

a. The licensee, or

b. Other perso ns.specifically..authorized by the Commission or an Agreement State.

Theltest. method shall have ad.etection sensitivity of at.least 0.005 microcuries per test sample.

4.7.9.1.2 Test Frequencies.- Each.category of:sealed sources shall be tested at the frequencies described belOw.

a.

Sources in use (excludingq startup sources previously subjected toWcore, flux) - At least once per six.months forall sealed

.sources containipng.radioactive material:.

ST. LUCIE - UNIT I 3141 7-27

L-2013-233 Page 24 of 54 ELECTRICAL POWER SYSTEMS ACTION (continued)

e.

With two of the above required diesel generators inoperable, demonstrate the OPERABILITY of two offsite.A.C. circuits by performing Surveillance.

Requirement 4.8.1.1.1.a within 1. hour and at least once: per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; restore.one of thelinoperable.diesel generators. to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in the 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 . Following restoration of.one diesel generator unit, follow ACTION Statement b, with the time requirement of that ACTION Statement:based on the time of initial loss of the remaining inoperable diesel. generator.

f.

With one Unit 1 startup transformer (MA.or I B) inoperable and with %a Unit 2 startup transformer (2A or 28) connected to the same A or B offsite power circuit and administratively available to both units, then should. Unit 2 require the use of the startup transformer administratively available to both units,. Unit 1 shalldemonstrate the OPERABILITY of the remaining A.C. :surces by performing Surveillance Requirement 4.8.1.1.1.a..within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.. Restore the inoperable startup transformer 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

LCO 3.0.4..:b.

.s MA poCae dsg SURVELLLANCE REQUIREMENTS 4.8.1.1.1 Each of the above required independent:.circuits between the offsite.transmission network and the onsite Class 1 E distribution system shall be:

a.

Determined OPERABLE at least once per 7 days by verifying correct breaker alignments, indicated power availability;.and

b.

Demonstrated OPERABLE at least once per 18 months by transferring (manually and automatically) unit power supply from the auxiliary transformer to the startup transfoi mer.

4.8.1.1.2% Each diesel generator shall be demonstrated OPERABLE-.

a.

At least once per 31 days on. a STAGGERED TEST BASIS. by:.

1.

V.erifying fuel level in the engine-mounted fuel tank,

2.

Verifying the fuel level in the fuel storage tank, 3.. Verifying the fuel transfer pump can be started and transfers fuel from the

.storage system to the engine-mounted tank, S,.I4:UCIE.- U.NIT1 3/4 8-3; TNAmendment No. 4N3,442. 138

L-2013-233 REFUELING OPERATIONS, Page 25 of 54 FUEL POOL VENTILATION SYSTEM - FUEL STORAGE LIMITJNG CONDITION FOR OPERATION 3.9.12 At least one fuelpool Ventilation system sshall be OPERABLE.

APPLICABILITY: Whenever recently irradiated fuel is in the spent fuel pooi.

ACTION:

a.,

With.no fuel pool ventilation system OPERABLE, suspend. all operations involving mrovement of recently irradiated fuel Within the spent fuel pool or crane operation with loads over the recently irradiated spent.fuel until at least one fuel pool.Ventilation. system is restored to OPERABLE status.

b.

The provisions of Specification)V 3.0.3,ad,-4O ll are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.12 The ýabove required fuel pool ventilation system.shall be demonstrated OPERABLE:

a..

At least once per 31. days by initiating flow through the HEPA filter and charcoal adsorber train.and verifying that the train operates for atleast 15 minutes.

b.

At least once per 18 months or (1).after any structural maintenance

.on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the:system by:'

ST.. LUCIE - UNIT *1.,

3/4 9-12, Amendment No. 184

L-2013-233 Page 26 of 54 RADIOACTIVE EFFLUENTS EXPLOSIVE. GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.:2.5 The concentration of oxygen in the waste gas decay tanks shall be limited to. less than or equal to 2% by volume whenever the hydrogen concentration exceeds 4%.by volume.

APPLICABILITY: At all times.

ACTION:

a.

With the concentration of oxygen in the waste gas decay tank greater than 2% by volume but less.than or equal to 4 % :by volume, reduce the oxygen concentration to the above limits within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

b.

With the concentration of oxygen in the waste gas decay tank greater than 4% by volume and the hydrogen concentration greater than 2% by Volume, immediately suspend all: additions of Waste gases to the system and immediately commence reduction of the concentration of oxygen to less than or equal to 2% by volume.

c.

The provisions of. Specificationý 3.0.3end-8-0-Ware not applicable.

SURVEILLANCE REQUIREMENTS 4.11. 2.5.1 The concentration of oxygen in the waste: gas decay tank shall be determined to be within theabove limits by continuously*,monitoring the waste gases: in the on service waste gas decay. tank.

4.11.2..5.2 With theoxygen concentration in the on service waste gas.decay tank greater than.2% by volume.as determihed by Specification 4.11.2.5.1, the concentration of hydrogen in the waste gas decay tank shall be determined to be within the above limits by gaspartitioner sample at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

When continuous monitoring capability is: inoperable, waste gases shall be: monitored in accordance with the actions specified for the:Waste"Gas Decay Tanks ExplosiVe Gas: Monitoring System i.n:Chapter 13 of the Updated Final Safety Analysis Report..

ST. LUCIE'- UNIT i

3/4 11-14 Amendment..No. 69,446, 4-52.156,

L-2013-233 Page 27 of 54 RADIOACTIVE EFFLUENTS GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity.contained in each gas storage.tank shall be limited to less than orequal to 1.65,090 curies noble gases (considered asXe-133).

APPLICABILITY: At all-times.

ACTION.:

a.

With the quantity of radioactive material in any gas storage tank exceeding-.

the above limit, immediately suspend all additions of radioactive material to the tank,

b.

The provisions of SpecificatioriN 3.0.3 e."d44are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas storage tank shall be determined tobe within.the above limit at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when radioactive materials are being added to the tank-when reactor coolaht system activity exceeds

,518.9 jtCi/grarn DOSE EQUIVALENT XE-1 33.

S*T. ILUCIE -" UNIT"I.

3/4 11-15 Amendment No. 5.,.69,.213

L-2013-233 Page 28 of 54 314 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 314.0 APPLICABILITY LIMITING cONDITION FOR OPERATION 3.0.1 Compliance with the Limiting Conditions for Operation.contained in the.

succeeding specifications is required during the OPERATIONAL MODES or other conditions specified therein;, except:that upon failure to meet the Limitirig Conditions for Operation, the associated ACTION. requirerments.shall be met.

3.0.2 Noncompliance with a specification shall exist when the requirements of the Limiting Condition for Operation and/or associated ACTION requirements are not met within the specifiedtime intervals. If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the ACTION requirements.is not required.

3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, within 1.hour, action shall be initiated to place the unit in -a MODE in which specificati~on does.not apply by placing it, as applicable,. in:

1.

At least.HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

2.

At least. HOT SHUTDOWN within the. following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and

3.

At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Where corrective measures are-completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation. Exceptions to these requirements are stated in the.individual.

.specifi -cations '..

This specification is not applicable in MODE'5 or 6.

-. 4 t y i n o nO D or o th e r s p e.c ifie d c o n d i tio n s h a ll.not

( 7 m d - h n t e c n ii n ft e L m t n ondition forO peration are :not e a dt ea s cae AC I Nrequires a shutdown.;if".they are not Met

-within...

a s e i i c t i m i t r a. E r y n o an.O

.P.E R A T IO N A L M O D E o r s p e c ifi e d c o~

n d it io n l

a~ b ma ei.a co'-~ t ih AT.ON.

requirements: when conformance to them

- .or n !*imitdpri.0d of time, this provision shall not prevent passage through or to OPERATIONAL MODES as req d t mements.

Exceptions.tothese requirements

L are state~d: .in: the individ~ual.:s ecifications,.

thes n

ST. LUCIE -,:UNIT 2 3/4 0-*1 Amendment No. 33 corrected

L-2013-233 Page 29 of 54 INSERT I (LCO 3.0.4)

When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made:

a. When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time;

b. After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate; exceptions to this Specification are stated in the individual Specifications, or

c. When an allowance is stated in the individual value, parameter, or other Specification.

L-2013-233 Page 30 of 54

.APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement. Failure to perform a Surveillance Requirement within the allowable surveillance interval, defined.by **Specification 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a Limiting Condition for Operation. Surveillance Requirements do hot have to be performed on inoperable equipment.

4.0.2 Each Surveillance Requirement shall be. performed within the. specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

4.0.3 Ifit is discovered that. a Surveillance was.not performed within its specified frequency, then compliance with the requirement to declare the Limiting Condition for Operation not met may be. delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified frequency, whichever is greater. This delay period is permitted. to allow performance. of the Surveillance. A risk evaluation shall. be performed for any Survefilance delayed greater than.24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the :risk impact.shall be managed.

If the:Surveillance is not performed within the delay period, the Limiting Condition.for Operation must immediately be declared not met,.and. the-applicable ACTION(s) must be taken.

When the Surveillance is performed within the delay period.and the Surveillance is not met, the Limiting: Condition for Operation must immediately be declared not met, and the applicable ACTION(s)must be taken..

S,..+/-._a_:;-;.

4.0.4 n ry into an. OPERATIONAL MODE or other specified applicability conditioifshall not be, made unless the Surveillance Requirement(s):associated with the Limiting Condition.for Operation have been performed within the stated surveillance interval or asotherwise:

specified. This provision shall not prevent passage through.orto :OPERATIONAL MODES as required to comply with ACTION requirements..

4.0.5 Surveillance Requirements.for ihservice inspection of ASME Code Class 1, 2 and 3 components shall be applica.ble as. follows.:

a..

Inservice inspection of ASME Code Class.1, 2.and:.3 components shall be performed in accordance with Section Xl of the.ASME Boiler and Pressure Vessel Code and applicable Addenda as required. by 10 CFR 50P Section 50:55a(g), except where specific written relief has been granted.by the Commission pursuant to 10 CFR 50, Section 50.55a(g) (6) (i).

b.

deleted c..

deleted

St. LUCIE.-;UNIT2 8/4 0-2*

Amendment No. 33,.48, 94, 129

L-2013-233 Page 31 of 54 INSERT 2 (SR 4.0.4)

Entry into a MODE or other specified condition in the Applicability of a Limiting Condition for Operation (LCO) shall only be made when the LCO's Surveillances have been met within their specified frequency, except as provided by Surveillance Requirement 4.0.3. When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4.

This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

TABLE 3.3-1 REACTOR PROTECTIVE INSTRUMENTATION FUNCTIONAL UNIT

1.

Manual Reactor Trip

2.

Variable Power Level -

High

3.

Pressurizer Pressure -

High

4.

Thermal Margin/Low. Pressure

5.

Containment. Pressure - High

6.

Steam. Generator Pressure - Low

7.

Steam GeneratorPressure Difference - High

8.

Steam Generator*Level - Low

9.

Local Power Density-High

10. Loss of Component Cooling Water to Reactor Coolant Pumps

11. Reactor Protection System Logic

12. Reactor Trip Breakers, 1.3. Wide Range Logarithmic Neutron Flux.Monitor.

a. Startup and Operating -

Rate of Change of Power -

High

b. Shutdown

14. Reactor Coolant Flow - Low TOTAL NO.

OF CHANNELS 4

4 4;

4:

4 4.

41SG.

4 4/SG 4

4 4.

4 CHANNELS TO TRIP 2

2 2(a) (d) 2 2(a) (d) 2 2/SG(b) 2(a):(d) 2/SG 2(c) (d) 2 2

MINIMUM.

CHANNELS OPERABLE 4

4 3

3 3

3 3/SG 3

3 3

4 APPLICABLE MODES 1,2 3*, 4*", 5*

11.2 1,2 1,2 1,2 1,2 1,2 112 1

1,2 1,2

3*, 4*, 5*

1,.2 3*, 4* ;5*

ACTION 1.5 4

5 4

4 4/SG' 4

2(e) (g) 0 2/SG(a)(d)

.2(c).

3 2

3/SG 3

1,2 3,4, 5 1,2 3

15.. Loss of Load (Turbine Hydraulic Fluid Pressure -"Low) 1

>.L~

ST. LUCIE -.UNIT 2 W/4 3w2 Amendment No.. 60

L-2013-233 Page 33 of 54 TABLE 3.3-1 (Continued)..

TABLE NOTATION

With the protective system trip breakers.in the closed position, the CEA drive system capable of CEA withdrawal, and fuel in the reactor vessel.

(a)

Trip may be manually bypassed below 0.5% of RATED THERMAL POWER in conjunction with (d) below; bypass shall be automatically removed when Wide Range Logarithmic Neutron Flux power isigreater than or equal to 0.5% of RATED THERMAL POWER.

(b)

Trip may be manually bypassed below 705 psig; bypass shall be automatically removed at or above 705 psig.

(c)

Trip may be bypassed below 15% of RATED THERMAL PPOWER; bypass shall be automatically removed when Power Range Neutron Flux power' is greaterthan or equal to 15% of RATED THERMAL POWER.

(d)

Trip may be bypassed during testing pursuant to Special Test.Exception 3.10.3.1 (e)

Trip may be bypassed below 1 0-4% anhd above 15% of RATED THERMAL POWER; bypass shall be automatically removed when Wide Range Logarithmic Neutron Flux power is> 10%

and Power Range Neutron Flux power < 1.5% of RATED THERMAL POWER.

(f):

Each: channel shall be comprised.of two trip breakers; actual trip logicdshall be one-out-of-two taken twice.

(g)

There shall be: at least two decades of overlap between the Wide Range Logarithmic. Neutron.

Flux Monitoring Channels and the Power.Ranrge Neutron Flux Moni.toring Channels.

ACTION STATEMENTS ACTION i With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to.OPERABLE status Within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-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/or open the protective.sys-te.m. trip breakers.

ST. LUCIE - UNIT.23 3/43.-3 Amendment'No. 98

TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABL FUNCTIONAL UNIT

1.

SAFETY INJECTION (SIAS)

a. Manual (Trip Buttons)

b. Containment Pressure -

High

c. Pressurizer Pressure -

Low

d. Automatic Actuation -

Logic

2.

CONTAINMENT SPRAY (CSAS)

a. Manual (Trip Buttons)

b. Containment Pressure -

High-High

c. Automatic Actuation Logic

3.

CONTAINMENT ISOLATION (CIAS)

a. Manual CIAS (Trip Buttons)

b. Safety Injection (SIAS)

c. Containment Pressure -

High

d. Containment Radiation -

High

e. Automatic Actuation Logic OF CHANNELS TO TRIP OPERABLE MODES E

2 4

4 2

2 4

2 1

2 2

1 1

2 2

3 3

2 2

3 2

1,2,3,4, 1,2,3 1,2, 3(a) 1,2,3,4 1,2,3,4 1(b), 2(b), 3Jb) 1,2,3,4 ACTION 12 1§, 14 1,14 12 12 18, 18, 18c 12 2

1 See Functional and Requirements 4

2 2

1,2,3,4 12 Unit 1 for all Safety Injection Initiating Functions 3

1,2,3 1 P, 14 3

1,2,3 1* 14 2

1,2,3,4 12 4

2 2

1 CD ~

ST. LUCIE - UNIT 2 3/4 3-12 Amendment No. 132

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT

4.

MAIN STEAM LINE ISOLATION (MSIS)

a. Manual (Trip Buttons)

b. Steam Generator Pressure - Low

c. Containment Pressure -

High

d. Automatic Actuation Logic

5.

CONTAINMENT SUMP RECIRCULATION (RAS)

a. Manual RAS (Trip Buttons)

b. Refueling Water Storage Tank-Low

c. Automatic Actuation Logic TOTAL NO.

OF CHANNELS 2

4/steam generator 4

2 2

4 2

CHANNELS TO TRIP 1

2/steam generator 2

1 1

2 1

MINIMUM CHANNELS OPERABLE 2

3/steam generator 3

2 2

3 2

APPLICABLE MODES 1,2,3 1, 2, 3(c) 1,2,3 1,2,3 1,2,3,4 1,2,3 1,2,3 ACTION 16 1A 14 1A 14 12 12 19 12 Q 0 ST. LUCIE - UNIT 2 3/4 3-13 Amendment No. 69, 132

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

6.

LOSS OF POWER (LOV)

a. (1) 4.16 kV Emergency Bus Undervoltage (Loss of Voltage) 2/Bus 2/Bus 1/Bus 1, 2,3 17 (2) 480 V Emergency Bus Undervoltage (Loss of Voltage) 3/Bus 2/Bus 2/Bus 1, 2, 3 17

b. (1) 4.16 kV Emergency Bus Undervoltage (Degraded Voltage)

(2) 480 V Emergency Bus 3/Bus 2/Bus 2/Bus 1,2,3 17 Undervoltage (Degraded Voltage)

7.

AUXILIARY FEEDWATER (AFAS)

a. Manual (Trip Buttons) 4/SG 2ISG 4/SG 1, 2, 3 15

b. Automatic Actuation Logic 4/SG 2/SG 3/SG 1, 2, 3 15

c. SG Level (2A/2B) - Low 4/SG 2/SG 3/SG 1, 2, 3 20aQ, 20bg, 20c

8.

AUXILIARY FEEDWATER ISOLATION

a. SG 2A - SG 2B Differential Pressure 4/SG 2/SG 3/SG 1,2, 3 20af, 201:,

20c

b. Feedwater Header 2A - 2B 4/SG 2/SG 3/SG 20a, 20c Differential Pressure 1,2, 3 ST. LUCIE - UNIT 2 3/4 3-14 Amendment No. 28, -, 132

L-2013-233 Page 37 of 54 TABLE 3.3*f (gContinuedJ TABLE: NOTATION (a)

Trip function may be bypassed in this MODE.wlhen pressurizer pressure is less than 1836 psia;.bypass* shall be automiatically removed When pressurizer pressure.is greaterthan or equal to 1836 psia.

(b)

An SIAS signal is first necessary to enable CSAS logic.

(c)

Trip function may be bypassed in this MODE below 700.psia.; bypass shall be automatically removed at or above 700 psia&

ie-ovis ion s-ofýificatioTr-ý4are-nOt-aFSTAT bleME ACTION OF STATEMENTS ACTION 12 -

ACTION 13 With the number of OPERABLE channels one less:than the.Total.

Number of Channels, restore the inoperable channel.to.OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be. in. at least.HOT STANDBY within the next 6: hours and in COLD.SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

With the number-of channels OPERABLE one less:than the Total Number of Channels, STARTUP and/or POWER.. OPERATION maycontinuie provided the inoperable channel! is placed in the bypassed or tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . :The channel.shall be returned to OPERABLE status no later than during the next COLD SHUTDOWN.

With a channel process measurement circuit that~affects multiple: functional units inoperable or in test,. bypass or trip all associated functional units :as listed below.

Process Measurement Circuit

1. Containment. Pressure.

2. Steam Generator Pressure -

3. Steam Generator Level -

4. Pressurizer Pressure -

Functional Unit Bypassed Containment Pressure7-High (SIAS, CIAS, CSAS)

Containment Presstlre.- High (RPS)

Steam Generator Pressure - Lows (MS.IS)

AFAS-1 and AFAS-2 (AFAS).

Thermal Margin/Low Pressure (RPS)

Steam Generator Pressure.- Low (RPS)

Steam Generator Level - Low (R.PS)

If SG-2A, then.AFAS-1 (AFAS) if SG-2B, then AFAS-2 (AFAS).

Pressurizer Pressure - High (RPS)

Pressurizer Pressure =..Low (SIAS)

Thermal Margin/Low"Pressure (RPS)

ST. LUCIE.7 UNIT 2 "3/4 '315 Amendment NO :8, 2.3,1 49

L-2013-233 INSTRUMENTATION Page 38 of 54 314.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION

323.3 1 The radiation moniloring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their ala.rm/trip setpoints within the specified limits.

APPLICABILITY-As shown in Table 3.3-6.

ACTION:

a.

With a radiation monitoring channel alarm/trip setpoint..exceeding the value shown in Table 3..3-6, adjust the setpoint to within the limit.within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or d.eclare the channel inoperable.

bl With one or more radiation monitoring channels. inoperable, take the ACTION shown. in Table 3.3-6.

c.

The provisions. of Specification\\ 3.03 eaod

.4are not applicable.*

SURVEILLANCE REQUIREMENTS 433.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the..CHANNEL.CHECK, CHANNEL CALIBRATION and CHANNEL. FUNCTIONAL TEST operations for the MODES and at the:

frequencies shown in Table 4.3-3.

4.3.3.2 At least-onceper 18 months, each Control Room. Isolation radi ation monitoring instrumentation channel shall.be demonstrated OPERABLE.by verifying that. the response. time of the channel is within limits..,

ST. LUCIE -**UNIT 2.

3/4 3ý24 Arnendment.No." 4412, 1.59

L-2013-233 INSTRUMENTATION Page 39 of 54 REMOTE SHUTDOWN SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.5 The remote shutdown system transfer switches, control and.

instrumientation channels shown. in Table 33-9[shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a.

With the number of OPERABLE: renote shutdown channels less than the Required Number of Channels shown in Table 3:3-9,:either restore the inoperable, channel to OPERABLE:status within 30 days or be in HOT:

SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

With the number of OPERABLE remote shutdown channels less than the Mihimum Channels OPERABLE requirements of Table 3.3-9, either restore the inoperable channel to OPERABLE statusý within 7 days,: or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4 h

iof pl

.URVEILLANCE REQUIREMENTS 4.3.3.5.1 Each remote shutdown monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies.shown in Table 4.3-6.

4.3.3.5.2 Each remote shutdown system instrumentation transfer switch and control circuit shall be demonstrated.OPERABLE by verifying its capability to performrits intended function(s) at least once per 18 months...

ST. LUCIE - UNIT 2.

-3/4 3-38

L-2013-233 Page 40 of 54 INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.6 The accident' monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a.,*

With the number:of OPERABLE accident monitoring channels less than the Required: Number.of'Channels shown in Table 3.3-10, either restore the inoperable channel. to-OPERABLE status Within 7 days,..or be. in HOT STANDBY in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and. HOT SHUTDOWN in.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.*

With the number of OPERABLE accident.monitOring channels less-than the Minimum.Channels.OPERABLE requirements of Table 3.3-10, either restore the inoperable channels to OPERABLE status within 48. h1ours or be: in HOT STANDBY in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and HOT SHUTDOWN in. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

6."

With the number of OPERABLE Channels.one.less than the Total Number

.of.Channels shown,in Table 3.3-10, either restore the inoperable channel to OPERABLE status within 7 days if repairs are feasible Without shutting down or prepare and submit.a.SpecialReport to the Commission.pursuant: to..Specification 6.9.2;within 30 days. following the event o.utlining the action 1taken, the cause of the inoperability

.and the plans and schedule for restoring the system to OPERABLE status.

d.** With the number of OPERABLE Channels less than the Minimum Channels OPERABLE requirements of Table 3.3-10, eitherrestore the inoperable channel(s) to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months if repairs are feasible without shutting down or:

1.

Initiate an alternate method of monitoring the reactor Vessel inventory; and 2..

Prepare and submit a Special Reportto..the Commission pursuant to.Specification 6.9.2 within 30 days followingjthe event out-lining the action taken, the cause of the inoperability anpd the plans and.schedule for restoring :the-system to OPERABLE status, and

3.

Restore the Channel to OPERABLE status at th.e.next scheduled.

refueling.

Action statements, do not apply to.Reactor Vessel Level Monitoring System,

.Con 'tainment Sump Water Level (narrow range) and. Containment Sump Water Leve-l(wide range) instruments.

Action statements apply only to Reactor Vessel Level Monitoring System, Containrmient.Sump, Water Level (narrow range) and Containment Sump Water Level (wide range). instruments.

ST. LUCIE - UNIT 2 3/4 3A.1 SIAmendment No. 4.-, 45, 159

L-2013-233 REACTOR COOLANT.SYSTEM Page 41 of 54 314.4.4 PORV 'BLOCK VALVES LTINGCONDM2_IILONf QFROPERATION 3.4.4 Each Power Operated Relief Valve (PORV) Block valve shall be OPERABLE.

No more than one block valve shall be open at any one time.

APPLICABILITY: MODES: 1, 2 and 3.

ACTION:

a.

With one or more block valve(s) inoperabie, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ei-ther restore..the block valve(s) to OPERABLE. status or close the block valve(s) and remove power.from the. block valve(s); otherwise, be in at least HOT STANDBY within thenext 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 .

b.

With both block valves open, close one block valve within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , otherwise be in at least HOT: STANDBY withinithe.next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .and in COLD SHUTDOWN Within the followi.ng 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.4.4 Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed with. power removed in order:to meet the requirements.of Action a. or b. above.

ST. LQJC.E, --UNIT 2 3.144-10.

Amendmhent No. 34-46

L-2013-233 REACTOP COOI.ANT SYSTEM Page 42 of 54 3W4.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMMUG-CONDITJON FOR OPERATION 3.4.6.1 The following.RCS.:.leakage detection..systems wilIlbe.OPERABLE:

a.

The reactor cavity sump inlet flowmonitoring system; and

b.

One contaicinment.atmrospherle, ra.dioat:tivity: monitor (gaýeous or particulate).

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

ACTION:

a.

With the reactor: cavity sump inlet flow monitor ing system inoperable with an operable containment particulate radioactivity monitor, perform a RCS water.

inventory balance at least once per 24* hours and restore the sump inlet flow monitoring systernto OPERABLE.status within 30 days; othierwise, 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: hours.

b..

With the reactor cavity sump in!et flow monitoring system inoperable with only the containment gaseous radioaclivity monitor operable, perform an RCS water inventory. balance at least once per 24*.hours and analyze grab samples of the containment atmosphere at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and either restore the sump inlet flow monitoring: system to OPERABLE:status within 7 daysorrestore the:

containment particulate radioactivity monitor to OPERABLE status within 7 days and enter action a. above with the time in this action applied against the allowed outage time of:.action.a:; otherwise,. bein~at least HOT STANDBY within the next6 hours and in COLD SHUTDOWN within the following.30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c.

With the required radioactivity monitor inoperable, analyze grab samples of the containment atmosphere or: perform a RCS water inventory balance at least once per 24* hours, and restore the, required radioactivity monitor to OPERABLE status within 30 days; otherwise; be in at least HOT STANDBY within the6next 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 .

d.

With al :required monitors inoperable, enter LCO 3.0.3 immediately.

~I SLIRVEILLANCE REQUIREMENTS 4A4.6.1 The RCS leakage detection instruments shall be demonstrated OPERABLE by:.

a.

Performance of'the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and.

CHANNEL CALIBRATION of the required containment atmosphere radioactivity monitor at the frequencies, specified in Table 4.3-3.

b.

Performance of the CHANNEL CALIBRATION of the reactor cavity sump inlet flow monitoring. system at leastl once per 1&8 months.

Not required to be perfOrmed until 1.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after establishrment..of steady state-operation.

S.S] LUCIE - UNIT 2 3/4 4-18 Amendment No. 84, 447, 161

L-2013-233 Page 43 of 54 REACTOR COOLANT SYSTEM 314.4.8 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant shall be limited to:.

a. Less than or equal to 1.0. microcurie/gram DOSE EQUIVALENT 1-131, and b.. Less than or equal to 518.9 microcuries/gram DOSE EQUIVALENT XE-133..

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

a.

With the specific activity of the primary coolant >. 1.0 pCi/gram DOSE EQUIVALENT 1-131, verify DOSE EQUIVALENT 1-131. is 5 6.00 pCi/gram once per four hours.

b.

With the specific activity of the primary coolant > 1.0 pCi/gram DOSE EQUIVALENT [.131, but*. 60.0 pCi/gram DOSE EQUIVALENT. 17131, operation may cor.ntinue for up to 4.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months while efforts are made to restore DOSE EQUIVALENT 1-131 to within the 1.0 pCi/gram limit.,fecifcatiei4.

tnet-C. With the specific activity of the primary coolant:>1..0 pCi/gram DOSE EQUIVALENT -131 for greater than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval, or.> 60.0 pCi/gram DOSE EQUIVALENT [k131, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

.d..

With the specific activity of the primary coolant > 518.9 pCi/gram DOSE EQUIVALENT XE-1 33, operation may continue for up to, 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months while efforts are made to restore DOSE EQUIVALENT XE-1 33 to within the 518.9 pCi/gram DOSE EQUIVALENT XE-133 limit.

1flatio f

.u.- is-ot Pcatr=eN... LCO 3.C.-4.

e.

With the specific activity of. the primary coolant,>518.9 pCi/gram DOSE EQ0IUVALENTXE-1 33 for greater than 48 hhours during one continuous time interval, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWNwithin the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 44.8 The specific..activity of the primary coolant. shall.be determined to be within the.limits by performance of the sampling and analysis program of Table 4.4-4..

ST. LUCIE - UNIT 2.

3/4 4-25.

Amendment No, 44, 163

L-2013-233 REACTOR COOi.ANT SYSTEM Page 44 of 54 OVERPRESSURE PROTECTION SYSTEMS LIMITING: CONDITION FOR OPERATION ACTION:. (Continued)

c.

In the event either the PORVs, SDCRVs or the RCS vent(s) are used to mitigate a:

RCS pressUre transient, a.Special Report shall.be. prepared and submnitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient,: the effect of the PORVs, SDCRVs or ven t(s) on the: transient and any corrective action necessary to prevent recurrence.

d..

T-h

,3-pe0f ieato

-e4.t-applieab,.

j..

4.

I>

i,-apppt6oL&,e6t,

+6 IRVs e,,4e*[i MODE 4-.

SURVEILLANCE REQUIREMENTS 4.4.9.3.1 Each PORV shall be demonstrated OPERABLE by:

a.

In addition to the requirements of the Inservice Testing Program, operating the PORV through one complete cycle of full travel at least once per 18 months.

ST, ILUCIE.- UNIT 2, 3/4 4-36 Amendment No. 46.1, 91

L-2013-233 Page 45 of 54

.EMERGENCY CORE. COOLING SYSTEMS 3/4.5.3 ECCS SUBSYSTEMS - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.5*.3 As.a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:

a.

One QPERABLE. high-pressure safety. injection pump, and

b.

An. 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 Sump Recirculation Actuation Signal.

APPLICABILITY: MODES 3*.and Footnote # shall remain applicable in.: MODES.5 and 6 when the

.Pressurizer manway cover is in place and.the.reactor vessel head is on.

ACTION:

a.

With. no. ECCS subsystems OPERABLE, restore at least one ECCS subsystem to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .

b.

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

c

.3..4.b ECCS Hto 'P tie.e Sd~.+

e~~+o SaEy 4 J whkODE 4..

SURVEILLANCE REOUiEMENTS 4.5.3 The ECCS subsystem shall be demonstrated OPERABLE per the applicable Surveillance. Requirements of 4.5.2.

With pressurizer pressure. less than 1750 psia.

One HPSl shall be rendered inoperable prior to entering MODE 5.

ST. LUCIE - UNIT:2

,3/4 5m7 Amendment No. 46, 8,, 119

L-2013-233 CONTAINMENT -SYSTEMS Page 46 of 54 CONTAINMENT AIR'LOCKS

,.LIMITING CONDITION FOR OPERATION 3.6.1.3 Each containment air lock:.shall be OPERABLE with:

a.

Both doors closed except when the air lock is being. used for normal transit entry and exit through the containment then at least one air lock door shall be closed, and.

b.

An overall air lock leakage rate in accordance with the Containment Leakage Rate Testing Program.

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

.ACTION::

a, With one containment air lock door inoperable*:

1..

Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or: lock, the OPERABLE air lock door closed.

2.

Operation may then continue until performance Of the next required overall air lock leakagetest provided, that the OPERABLE air lock door is verified to be locked closed at least once per 31 days.

3..

Otherwise, be in at least HOT STANDBY withiin 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 ..

b, With the containment air lock inoperable,. except as the resultof an ihoperable air..lock door, maintain at least one air lock door closed; restore the inoperable.air lock to OPERABLE'status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-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. hours..

I If the inner air l.ockdoor is inoperable, passage*throughthe OPERABLE outer air lock door.is permitted to effect repairs to the inoperable inner air lock door. No: more than one airlock door shall be openi, at any time.

ST..I-UCIE.- UNIT 2 3/4.6ý9

.Amendment No..36, 88

L-2013-233 3/4.7 PLANT SYSTEMS Page 47 of 54 314.7.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam line code safety valves shall be OPERABLE with lift settings as shown in Table 3.7-2.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a.

With.both reactor coolant loops and associated steam generators in. operation and with one or more main steamr line code safety valves: inoperable, operation. in MODES 1, 2 and. 3 may proceed provided that, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either the inoperable valve is restored to OPERABLE status or the Power Level-High trip setpoint: is reduced per Table 3.7-1; otherwise, 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 .

b-,.JThe-provisions-of:specification-3-.0;4a'are-not-applicable.....

SURVEILLANCE REQUIREMENTS 4.7.1.1 Verify each main steam.line code safety valve is OPERABLE in accordance with the Inservice Testing Program. Following testing, as-left lift settings shall be within +1-1%.of 1000 psia for valves 8201 through 8208, and.within +1. 1 %.of.1040 psia for valves 8209 through 8216 specified in Table 3.7-2.

ST. LUCIE"-UNIT 2:

'3147-1 Amendment No. 8, 68,

-94

,110

L-2013-233 Page 48 of 54 PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:

a.

Two feedwater pumps, each capable of being powered from separate OPERABLE emergendy buisses, and

b.

One feedwaterpump capable of being powered from an OPERABLE steam supply system.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

'a.

With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps 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 .

b.

W ith two auxiliary feedwater pumps inoperable 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restoreat least one auxiliary feedwater pump to OPERABLE status.

SýLCO*...6..

4 SURVEILLANCE REOUi:QjANTS 4.7.1:2 Each auxiliary feedwaiter pump 'shai,be demonstrated OPERABLE:

a.

At least once per 31: daysby:

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.

ST. LUCIE'- UNIT 2 3/4 7A4 ArS4endment No. 2-,. 146

L-2013-233 Page 49 of 54 P! ANT SYSTEMS MAIN STEAM LINE ISOLATION VALVES LIMTIN CNDITION EOR OPERATION____________

3.7.1.5 Each:.main steam line isolation valve shall!be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

MODE 1 With one main steam line isolation valve inoperable but open, POWER

.OPERATION may continue providedthe inoperablevalve is restored: t.o OPERABLE status within. 4. hours*' otherwise, be in at least HOT STANDBY within the next 6. hours,

.MODES 2,j.

3, and 4 With one or both main steam isolation valve(s) inoperable, subsequent operation in..MODES 2,; 3: or 4 may proceed provided the isolation valve(s). is.(are)

maintained closed. Otherwise, be in at least HOT STANDBY within :the next

6. hours and: in COLD SHUTDOWN *within the.following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ...

'T he-provisirns-of-Speeifieationr.

G4-afe-fnet-applieable-

.SUJRVELL ANCE REQUIREMENTS 4.7.1.5 Each Main steam lirie.isolation valve shall be.demonstrated 0PERABLE by-verifying full closure within 6.75 seconds;when tested pursuant.to the Inservice Testing Program.

ST. LUICIE.*UNIT2.

3/4.7-9:

Amendment No. 35, 62, 91

L-2013-233 PLANT SYSTEMS Page 50 of 54 314.7.5 ULTIMATE HEAT SINK LMI_.NGO LQ Nf_ EORO PERATION 3.7.5.1 The ultimate heat sink shall be OPERABLE with:

a.

Cooling.water from the.AtlanticOcean providing a.water level: above.

-10:5 feet. elevation,. Mean LowWater, at the plant intake structure, and

b.

Two OPERABLE valves.:in the barrier dam between Big Mud: Creek and the intake structure, APPLICABILITY: At all times.

ACTION:

a.

With the water level requirement of the above specification not satisfied, be in at least HOT STANDBY within 6..hurs and provide cooling water. from Big Mud Creek within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

With one isolation.valve in the.barrier dam between Big Mud Creek and the intake structure inoperable, restore the inoperable valve.

to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or within.the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , install a temporary flow barrier and open the barrier dam isola-tion valve. The availability of the onsite equipment capable of.

removing theabarrier shall be.verified at least once per 7 days thereafter.

c.

With both of the isolation valves in the barrier'dam between the in-take*structure and Big Mud Creek inoperable, within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , either:

1..

Install both temporary flow barriers and manually open both barrier dam isolation valves. The availability of the 6nsite equipment capable of removing the barriers shall be verified at.least once per 7 days thereafter., or

2.

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.hours.

SURVEiLLANCE REQUIREMENTS 4.7.5.1.1 'The ultirmateheat sink shall be determined OPERABLE at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the average water level to be within the. limits...

4.7.5.1.2 The isolation valves in the barrier dam between the intake structure and Big Mud Creek shall be demonstrated OPERABLE at.least once: per six months by cycling each valVe through at leastone Complete cycle of full travel.

ST. LUCIE: - UNIT 2 314 7-15,

L-2013-233 PLANT SYSTEMS Page 51 of 54 314.7.10 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.10 Each sealed source containingradioactive material either in excess.of 1:00 microcuries of beta.a.nd/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of. greater than or equal to 0.005 microcuries of removable contamination.

APPLICABILITY: At all times.

ACTION:

a.

With a sealed source, having removable contamination in excess of the above limit, immediately withdraw the sealed source from use and. either:.

1.

Decontaminate and repair the sealed source,. or

2.

Dispose of the sealed..source in accordance with Commission

.Regulations.

b.

The provisions of Specificatidn\\*3.0.3 and-3,"

are not:applicable:

SURVEILLANCE REQUIREMENTS 4.7.10.1 Test Requirements - Each sealed source shall be tested for, leakage.

ahd/or cdntamination by:,

a.

The licensee, or

b.

Other persons specifically authorized. by the Commission or an Agree*ennt State.

The test method shall be a..detection sensitivity of at least.

0,005 microcuries per test sample.

4.7.10.2 Test Frequencies - Each categry of sealed sources (excluding startup sources a.nd'fission detectors previously subjected to core flux) shall be tested at. the frequencies described below.

a..

Sources in use -At least once per 6 months for all sealed.sources containing radioactive material.

1 With a half-life greater than 30.days (excluding Hydrogen.3),

and

2.

In 'any form other than gas.

ST. LUCIE - UNIT 2 1314:7-28

L-2013-233 Page 52 of 54 ELECTRICAL POWER SYSTEMS ACTION: (Continued)

d.

With two of the required offsite A;C. circuits inoperable, restore one of the inoperable offsite sources to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-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 . Following restoration of one offsite source, follow ACTION Statement a. with the time requirement of that.

ACTION Statement based on the time of the initial loss of the remaining inoperable.

offsite. A.C.. circuit.

e.;

With two of the above required diesel generators inoperable, demonstrate the OPERABILITY of two offsite.A.C. circuits by performing Surveillance Requirement 4.8.1 1.1..a within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; restore one of the inoperable diesel generators to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in the 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 . Following.restorationof one. diesel generator unit, follow ACTION Statement b. with the time requirement of that ACTION Statement based on the time of initial'loss of the remaining inoperable dieslel!generator.

f.

With one Unit 2 startup transformer (2A or 2B) inoperable and With a Unit 1 startup transformer (IA or 1 B) connected to the same A or B offsite power circuit.and administratively available to both units, then should Unit 1 require.

the use of the startup transformer:administratively available to both units, Unit 2 shall demonstrate the operability of the remaining A.C. sources by performing Surveillance Requirement 4.8.i. 1.1 a. within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter. Restore.the:inoperable startup transformer. 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Lto 6i6 3

.:61

'is",nio cppftcmzd@ý

+, d~eseJ e-a 4oS SURVEILLANCE REQUIREMENTS:

4.8.1.1.1 Each of the above required independent circuits between the offsite transmission, network:and. the:onsite Class 1. E distribution system shall be:

a..

Determined OPERABLE at least once per 7 days by verifying. correct breaker alignments, indicated power availability; and

b.

Demonstrated OPERABLE at least once per 18 months.by transferring (manually and automatically) unit power supply from the normal circuit: totiie alternate circuit.

4.8.1.1.2 Each diesel generator shall be demonstrated. OPERABLE:

a.

At least.once per.31 days on a STAGGERED TEST BASIS BY:

ST. L:UCIE -UNIT 2.

.3/4 8-3 Amendment No. 39, 43, 78

L-2013-233 Page 53 of 54 RADIOACTIVE EFFLUENTS.

EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the waste gas decay tanks shallbe limited to less than or equal.to 2% by volume whenever the hydrogen: concentration exceeds.4% by volume, APPLICABILITY: At alltimes.

ACTION:

a.

With the concentration of oxygen. in the waste gas decay tank greater than 2% by volume but less than or :equal to 4% by *volume, reduce the oxygen concentration to the above limitswithin 48.hours.

b.

With the concentration of oxygen in the waste gas decay tank greater than 4% by volume and the hydrogen concentration greater than 2% by volume, immediately suspend all!additions of waste gases to the system and immediately commence reduction of the concentration of oxygen to less than or equal. to 2% by Volume.

C...

The provisions of Specificationk 3.0.3 -and4-& are. not applicable

SURVEILLANCE REQUIREMENTS

4.11 i.2.5.1 The concentration of oxygen in the waste gas. decay tank; shall be deternmined to be Within the above limits by continuously" monitoring the waste gases in.the.on service waste gas decay tank.

4.11.2.5.2 With the oxygen concentration.in.the..on service waste gas decay tank greaterthan 2% by volume as determined by Specification,.4.11.2..5.1,. the: concentration of hydrogen. in the was te:gas decay tank shall be determined to. be within the above irnmits by gas partitioner samPle.at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

When continuous monitoring capability is inoperable, waste gases shall be monitored in accordance with the actions specified for the Waste Gas..Decay Tanks:. Explosive Gas Monitoring System in. Chapter. 13 of the Updated Final.Safety Analysis Report.

ST. LUCE*-.UNIT 2.

314 1 -14 Amendment No.:57-89,.94

L-2013-233 Page 54 of 54 RADIOACTIVE EFFLUENTS GAS.STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 The quant!ity. of radioactivity contained in each gas storage. tank..

shall be limited.to less than or equal to 165,000 curies noble gases (considered as Xe-1.33).

APPLICABILITY: At all times.

ACTION:

a.

With the quantity of radioactive material -in any gas storage tank exceeding the above limit, immediately Suspend.all additions of radioactive materialto the tank.

b.

The provisions of Specificatiorni 3.0.3 sR4_.

are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each.gas storage tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when radioactive, materials are being added.to the tank. when reactor coolant~system activity exceeds 518.9 pCi/gram..DOSE EQUIVALENT XE-1 33.

.STAUWIE - ONIT'2 3/4 11-15 STAmendment No. 43,163

L-2013-233 Word-Processed Technical Specification Pages Unit 1 Unit 2 3/4 0-1 3/4 0-1 3/4 0-2 3/4 0-2 3/4 3-2 3/4 3-2 3/4 3-3 3/4 3-3 3/4 3-4 3/4 3-12 3/4 3-10 3/4 3-13 3/43-11 3/4 3-14 3/4 3-12 3/4 3-15 3/4 3-21 3/4 3-24 3/4 3-41 3/4 3-38 3/4 4-12 3/4 3-41 3/4 4-17 3/4 4-10 3/4 4-59 3/4 4-18 3/4 5-7 3/4 4-25 3/4 6-10 3/4 4-36 3/4 7-1 3/4 5-7 3/4 7-4 3/4 6-9 3/4 7-9 3/4 7-1 3/4 7-18 3/4 7-4 3/4 7-27 3/4 7-9 3/4 8-3 3/4 7-15 3/4 9-12 3/4 7-28 3/4 11-14 3/4 8-3 3/4 11-15 3/4 11-14 3/4 11-15 consists of 50 pages including this cover page.

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 314.0 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.1 Compliance with the Limiting Conditions for Operation (LCO) contained.in the succeeding specifications is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met.

3.0.2 Noncompliance with a specification shall exist when the requirements of

-the Limiting Condition for Operation (LCO) and associated ACTION requirements are not met within the specified time intervals. If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.

3.0.3 When a Limiting Condition for Operation (LCO) is not met, except as provided in the associated ACTION requirements, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months action shall be initiated to place the unit in a MODE in which specification does not apply by placing it, as applicable in:

1.

At least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

2.

At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and

3.

At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the LCO. Exceptions to these requirements are stated in the individual specifications.

This specification is not applicable in MODES 5 or 6.

3.0.4 When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made:

a.

When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time;

b.

After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate; exceptions to this Specification are stated in the individual Specifications, or

c.

When an allowance is stated in the individual value, parameter, or other Specification.

ST. LUCIE - UNIT 1

.3/4 0-1 Amendment No. 40, 98, 4-0,

APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement. Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Specification 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a Limiting Condition for Operation. Surveillance Requirements do not have to be performed on inoperable equipment.

4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

4.0.3 If it is discovered that a Surveillance was not performed within its specified frequency, then compliance with the requirement to declare the Limiting Condition for Operation not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified frequency, whichever is greater. This delay period is permitted to.allow performance of the Surveillance. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the risk impact shall be managed.

If the Surveillance is not performed within the delay period, the Limiting Condition for Operation must immediately be declared not met, and the applicable ACTION(s) must be taken.

When the Surveillance is performed within the delay period and the Surveillance is not met, the Limiting Condition for Operation must immediately be declared not met, and the applicable ACTION(s) must be taken.

4.0.4 Entry into a MODE or other specified condition in the Applicability of a Limiting Condition for Operation (LCO) shall only be made when the LCO's Surveillances have been met within their specified frequency, except as provided by Surveillance Requirement 4.0.3. When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4.

This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

4.0.5 Surveillance Requirements for inservice inspection of ASME Code Class 1, 2 and 3 components shall be applicable as follows:

a.

Inservice inspection of ASME Code Class 1, 2 and 3 components shall be performed in accordance with Section Xl of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g) (6) (i).

b.

deleted ST. LUCIE - UNIT 1 3/4 0-2 Amendment No. 2-, 40, 9G, 98, 408, 4ý5, 486

TABLE 3.3-1 REACTOR PROTECTIVE INSTRUMENTATION FUNCTIONAL UNIT

1.

Manual Reactor Trip

2.

Power Level - High.

3.

Reactor Coolant Flow - Low

4.

Pressurizer Pressure - High

5.

Containment Pressure - High

6.

Steam Generator Pressure - Low

7.

Steam Generator Water Level - Low

8.

Local Power Density - High

9.

Thermal Margin/Low Pressure 9a. Steam Generator Pressure Difference - High

10. Loss of Turbine - Hydraulic Fluid Pressure - Low TOTAL NO.

OF CHANNELS 2

4 4/SG 4

4 4/SG 4/SG CHANNELS TO TRIP 1

2(a) 2(a)/SG 2

2 2(b)/SG 2/SG MINIMUM CHANNELS OPERABLE 2

3(f) 3/SG 3

3 3/SG 3/SG APPLICABLE MODES 1, 2 and*

1,2 1, 2 (e) 1,2 1,2 1,2 1,2 ACTION 1

2 2

4 4

2(c) 2(a) 2(a) 2(c) 3 3

3 3

1 1, 2 (e) 1,2 (e) 1 ST. LUCIE - UNIT 1 3/4 3-2 Amendment No. 4-1, 43

TABLE 3.3-1 (Continued)

REACTOR PROTECTIVE INSTRUMENTATION TOTAL NO.

FUNCTIONAL UNIT OF CHANNELS CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE MODES ACTION

11. Wide Range Logarithmic Neutron Flux Monitor

a. Startup and Operating --

Rate of Change of Power -

High

b.

Shutdown

12. Reactor Protection System Logic

13. Reactor Trip Breakers.

4 4

2(d) 0 2

2 3

2 4

4 1,2 and

3,4,5 1,2*

1,2*

2 3

4 4

ST. LUCIE - UNIT 1 3/4 3-3 Amendment No. 45, 2-7

TABLE 3.3-1 (Continued)

TABLE NOTATION

With the protective system trip breakers in the closed position and the CEA drive system capable of CEA withdrawal.

(a)

Trip may be bypassed below 1% of RATED THERMAL POWER; bypass shall be automatically removed when Wide Range Logarithmic Neutron Flux power is > 1% of RATED THERMAL POWER.

(b)

Trip may be manually bypassed below 685 psig; bypass shall be automatically removed at or above 685 psig.

(c)

Trip may be bypassed below 15% of RATED THERMAL POWER; bypass shall be automatically removed when Power Range Neutron Flux power is > 15% of RATED THERMAL POWER.

(d)

Trip may be bypassed below 10-4% and above 15% of RATED THERMAL POWER; bypass shall be automatically removed when Wide Range Logarithmic Neutron Flux power is > 10-4%

and Power Range Neutron Flux power < 15% of RATED THERMAL POWER.

(e)

Deleted.

(f)

There shall be at least two decades of overlap between the Wide Range Logarithmic Neutron Flux Monitoring Channels and the Power Range Neutron Flux Monitoring Channels.

ACTION STATEMENTS ACTION 1 -

ACTION 2 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the protective system trip breakers.

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a.

The inoperable channel is placed in either the bypassed or tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . For the purposes of testing and maintenance, the inoperable channel may be bypassed for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months from time of initial loss of OPERABILITY; however, the inoperable channel shall then be either restored to OPERABLE status or placed in the tripped condition.

JNIT 1 3/4 3-4 Amendment No. 4-5, 2-7, 45, 4-02, 459 ST. LUCIE - U

TABLE 3.3-3 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TOTAL NO.

OF FUNCTIONAL UNIT CHANNELS CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE MODES ACTION

1.

SAFETY INJECTION (SIAS)

a. Manual'(Trip Buttons)

b. Containment Pressure -

High

c. Pressurizer Pressure-Low

2.

CONTAINMENT SPRAY (CSAS)

a. Manual (Trip Buttons)

b. Containment Pressure -

High-High

3.

CONTAINMENT ISOLATION (CIS)

a. Manual (Trip Buttons)

b. Containment Pressure -

High

c. Containment Radiation -

High

d.

SIAS

4.

MAIN STEAM LINE ISOLATION (MSIS)

a. Manual (Trip Buttons)

b. Steam Generator Pressure - Low 2

4 4

2 4

4 1

2 2

1 2(b) 2 3

3 2

3 1,2,3,4 1,2,3 1,2, 3(a) 1,2,3,4 8

9 9

I 8

10a, 10b, 10c 1,2,3 1

2

-(See 1,2,3,4 1,2,3 8

9 3

1,2,3,4 9

Functional Unit 1 above) 2/steam 1/steam 2/operating generator generator steam generator 4/steam 2/steam 3/steam generator generator generator 1,2,3,4 1,2, 3(c) 8 9

ST. LUCIE - UNIT 1 3/4 3-10 Amendment No. 41-, 37, 4-88

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT

5.

CONTAINMENT SUMP RECIRCULATION (RAS)

a. Manual RAS (Trip Buttons)

b. Refueling Water Tank - Low

6.

LOSS OF POWER

a. 4.16 kv Emergency Bus Under-voltage (Loss of Voltage)

b. 4.16 kv Emergency Bus Under-voltage (Degraded Voltage)

c. 480 V Emergency Bus Under-voltage (Degraded Voltage)

7.

AUXILIARY FEEDWATER (AFAS)

a. Manual (Trip Buttons)

b. Automatic Actuation Logic

c. SG Level (1A/1B) - Low

8.

AUXILIARY FEEDWATER ISOLATION

a. SG 1A-SG 1B Differential Pressure

b. Feedwater Header 1A-1B Differential Pressure TOTAL NO.

OF CHANNELS CHANNELS TO TRIP

-MINIMUM CHANNELS OPERABLE APPLICABLE MODES ACTION 2

4 1

2 2

3 1,2,3,4 1,2,3 8

13 2/Bus 2/Bus 2/Bus 4/SG 4/SG 4/SG 4/SG 4/SG 2/Bus 2/Bus 2/Bus 2/SG 2/SG 2/SG 2/SG 2/SG 1/Bus 1/Bus 1/Bus 4/SG 3/SG 3/SG 3/SG 3/SG 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 12 12 12 11 11 14a, 14b, 14c 14a, 14b, 14c 14a, 14c ST. LUCIE - UNIT 1 3/4 3-11 Amendment No. 46, 5-, 78, 402, 4-24, -I88

TABLE 3.3-3 (Continued)

TABLE NOTATION (a)

Trip function may be bypassed in this MODE when pressurizer pressure is < 1725 psia; bypass shall be automatically removed when pressurizer pressure is > 1725 psia.

(b)

An SIAS signal is first necessary to enable CSAS logic.

(c)

Trip function may be bypassed in this MODE below 685 psig; bypass shall be automatically removed at or above 685 psig.

ACTION STATEMENTS ACTION 8 -

ACTION9 With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the following conditions are satisfied:

a.

The inoperable channel is placed in either the bypassed or tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . For the purposes of testing and maintenance, the inoperable channel may be bypassed for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months from time of initial loss of OPERABILITY; however, the inoperable channel shall then be either restored to OPERABLE status or placed in the tripped condition.

b.

Within one hour, all functional units receiving an input from the inoperable channel are also bypassed or tripped.

c.

The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months while performing tests and maintenance on that channel provided the other inoperable channel is placed in the tripped condition.

ST. LUCIE - UNIT 1 3/4 3-12 Amendment No. 1-5, 45, 202

INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm/trip setpoints within the specified limits.

APPLICABILITY: As shown in Table 3.3-6.

ACTION:

a.

With a radiation monitoring channel alarm/trip setpoint exceeding the value shown in Table 3.3-6, adjust the setpoint to within the limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or declare the channel inoperable.

b.

With one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6.

c.

The provisions of Specification 3.0.3 is not applicable.

SURVEILLANCE REOUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the modes and at the frequencies shown in Table 4.3-3.

4.3.3.2 At lease once per 18 months, each Control Room Isolation radiation monitoring instrumentation channel shall be demonstrated OPERABLE by verifying that the response time of the channel is within limits.

ST. LUCIE - UNIT 1 3/4 3-21 Amendment No. 40, 4-7, 206

INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 The accident monitoring instrumentation channels shown in Table 3.3-11 shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a.

Actions per Table 3.3-11.

SURVEILLANCE REQUIREMENTS 4.3.3.8 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-7.

Sf LUCIE - UNIT 1 3/4 3-41 Amendment No. 37, 4-1-8

REACTOR COOLANT SYSTEM 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.6.1 The following RCS leakage detection systems will be OPERABLE:

a.

The reactor cavity sump inlet flow monitoring system; and

b.

One containment atmosphere radioactivity monitor (gaseous or particulate).

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

ACTION:

a.

With the reactor cavity sump inlet flow monitoring system inoperable with an operable containment particulate radioactivity monitor, perform a RCS water inventory balance at least once per 24* hours and restore the sump inlet flow monitoring system to OPERABLE status within 30 days; otherwise, 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 .

b.

With the reactor cavity sump inlet flow monitoring system inoperable with only the containment gaseous radioactivity monitor operable, perform an RCS water inventory balance at least once per 24* hours and analyze grab samples of the containment atmosphere at least once per 12. hours, and either restore the sump inlet flow monitoring system to OPERABLE status within 7 days or restore the containment particulate radioactivity monitor to OPERABLE status within 7 days and enter action a. above with the time in this action applied against the allowed outage time of action a.; otherwise, 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 .

c.

With the required radioactivity monitor inoperable, analyze grab samples of the containment atmosphere or perform a RCS water inventory balance at least once per 24* hours, and restore the required radioactivity monitor to OPERABLE status within 30 days; otherwise, 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 .

d.

With all required monitors inoperable, enter LCO 3.0.3 immediately.

SURVEILLANCE REQUIREMENTS 4.4.6.1 The RCS leakage detection instruments shall be demonstrated OPERABLE by:

a.

Performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION of the required containment atmosphere radioactivity monitor at the frequencies specified in Table 4.3-3.

b.

Performance of the CHANNEL CALIBRATION of the reactor cavity sump inlet flow monitoring system at least once per 18 months.

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation.

ST. LUCIE - UNIT 1 3/4 4-12 Amendment No. 444, 200, 2-142

REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant shall be limited to:

a. < 1.0 iCi/gram DOSE EQUIVALENT 1-131, and

b.

< 518.9 liCi/gram DOSE EQUIVALENT XE-133.

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

ACTION:

a.

With the specific activity of the primary coolant >1.0 pCi/gram DOSE EQUIVALENT 1-131, verify DOSE EQUIVALENT 1-131 is < 60.0 jiCi/gram once per four hours.

b.

With the specific activity of the primary coolant > 1.0 p.Ci/gram DOSE EQUIVALENT 1-131, but < 60.0 jLCi/gram DOSE EQUIVALENT 1-131, operation may continue for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months while efforts are made to restore DOSE EQUIVALENT 1-131 to within the 1.0 I.LCi/gram limit. LCO 3.0.4.c is applicable.

c.

With the specific activity of the primary coolant > 1.0 [tCi/gram DOSE EQUIVALENT 1-131 for greater than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval, or > 60.0 pCi/gram DOSE EQUIVALENT 1-131, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

d.

With the specific activity of the primary coolant > 518.9.tCi/gram DOSE EQUIVALENT XE-1 33, operation may continue for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months while efforts are made to restore DOSE EQUIVALENT XE-1 33 to within the 518.9 llCi/gram DOSE EQUIVALENT XE-1 33 limit. LCO 3.0.4.c is applicable.

e.

With the specific activity of the primary coolant > 518.9 PtCi/gram DOSE EQUIVALENT XE-1 33 for greater than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval; be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.4.8 The specific activity of the primary coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-4.

ST. LUCIE - UNIT 1 3/4 4-17 Amendment No. 69, 4-4, 2-42

REACTOR COOLANT SYSTEM POWER OPERATED RELIEF VALVES LIMITING CONDITION FOR OPERATION 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 during heatup, cooldown and isothermal conditions when the temperature of any RCS cold leg is less than or equal to 2000F.

b.

A setpoint of less than or equal to 530 psia shall be selected during heatup, cooldown and isothermal conditions when the temperature of any RCS cold leg is greater than 200°F and less than or equal to 3000F.

,APPLICABILITY:

MODE 4 when the temperature of any RCS cold leg is less than or equal to 3000F, MODE 5, and MODE 6 when the head is on the reactor vessel; and the RCS is not vented through greater than a 1.75 square inch vent.

ACTION:

a.

With one PORV inoperable in MODE 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

b.

With one PORV inoperable in MODES 5 or 6, either (1) restore the inoperable PORV to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , 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 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months .

c.

With both PORVs inoperable, restore 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

d.

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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

e.

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 Commission 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.

LCO 3.0.4.b is not applicable to PORVs when entering MODE 4.

SURVEILLANCE REQUIREMENTS 4.4.13 Each PORV shall be demonstrated OPERABLE by:

a.

Verifying the PORV isolation valve is open at least once per 72

hours; 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 No. 60, 84, 404, 432, 24-3

EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:

a.

In MODES 3* and 4 one ECCS subsystem composed of one OPERABLE high pressure safety injection pump and one OPERABLE flow path capable of taking suction from the refueling water storage tank on a safety injection actuation signal and automatically transferring suction to the containment sump on a sump recirculation actuation signal.

b.

Prior to decreasing the reactor coolant system temperature below 270°F a maximum of only one high pressure safety injection pump shall be OPERABLE with its associated header stop valve open.

c.

Prior to decreasing the reactor coolant system temperature below 2360 F all high pressure safety injection pumps shall be disabled and their associated header stop valves closed except as allowed by Specifications 3.1.2.1 and 3.1.2.3.

APPLICABILITY: MODES 3* and 4.

MODES 5 and 6 when the Pressurizer manway cover is in place and the reactor vessel head is on.

ACTION:

a.

With no ECCS subsystems OPERABLE in MODES 3* and 4#, immediately restore one ECCS subsystem to OPERABLE status or be in COLD SHUTDOWN within 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .

b.

With RCS temperature below 270°F and with more than the allowed high pressure safety injection pump OPERABLE or injection valves and header isolation valves open, immediately disable the high pressure safety injection pump(s) or close the header isolation valves.

c.

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.

d.

LCO 3.0.4.b is not applicable to ECCS High Pressure Safety Injection subsystem when entering MODE 4.

SURVEILLANCE REQUIREMENTS 4.5.3.1 The EGGS subsystem shall be demonstrated OPERABLE per the applicable Surveillance Requirements of 4.5.2.

4.5.3.2 The high pressure safety injection pumps shall be verified inoperable and the associated header stop valves closed prior to decreasing below the above specified Reactor Coolant System temperature and once per month when the Reactor Coolant System is at refueling temperatures.

With pressurizer pressure < 1750 psia.

REACTOR COOLANT SYSTEM cold leg temperature above 2500 F.

ST. LUCIE - UNIT 1 3/4 5-7 Amendment No. 2-, 60, 84, 404, 14a, 4-7-7

CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 Each containment air lock shall be OPERABLE with:

a.

Both doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed, and

b.

An overall air lock leakage rate in accordance with the Containment Leakage Rate Testing Program.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

a.

With one containment air lock door inoperable*:

1.

Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or lock the OPERABLE air lock door closed.

2.

Operation may then continue until performance of the next required overall air lock leakage test provided that the OPERABLE air lock door is verified to be closed at least once per 31 days.

3.

Otherwise, 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 .

b.

With the containment air lock inoperable, except as the result of an inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-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 .

SURVEILLANCE REQUIREMENTS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:

If the inner air lock door is inoperable, passage through the OPERABLE outer air lock door is permitted to effect repairs to the inoperable inner air lock door. No more than one airlock door shall be open at any time.

ST. LUCIE - UNIT 1 3/4 6-10 Amendment No. 85,449

3/4.7 PLANT SYSTEMS 3.4.7.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam line code safety valves shall be OPERABLE with lift settings as specified in Table 4.7-1.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a.

With both reactor coolant loops and associated steam generators in operation and with one or more main steam line code safety valves inoperable, operation in MODES 1, 2 and 3 may proceed provided that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either the inoperable valve is restored to OPERABLE status or the Power Level-High trip setpoint is reduced per Table 3.7-1; otherwise, 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 .

SURVEILLANCE REQUIREMENTS 4.7.1.1 Verify each main steam line code safety valve is OPERABLE in accordance with the Inservice Testing Program. Following testing, as-left lift settings shall be within +/- 1% of 1000 psia for valves 8201 through 8208, and within +/- 1% of 1040 psia for valves 8209 through 8216 specified in Table 4.7-1.

ST. LUCIE - UNIT 1 3/4 7-1 Amendment No. 90, 43, 466

PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:

a.

Two motor driven feedwater pumps, and

b.

One feedwater pump capable of being powered from an OPERABLE steam supply system.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a.

With one auxiliary feedwater pump inoperable, restore at least three auxiliary feedwater pumps (two motor driven pumps and one capable of being powered by an OPERABLE steam supply system) 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 .

b.

LCO 3.0.4.b is not applicable.

SURVEILLANCE REQUIREMENTS 4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE:

a.

At least once per 31 days by:

ST. LUCIE - UNIT 1 3/4 7-4 Amendment No. -,8, 99, 4-99

PLANT SYSTEMS MAIN STEAM LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.7.1.5 Each main steam line isolation valve shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

MODE 1 With one main steam line isolation valve inoperable, POWER OPERATION may continue provided the inoperable valve is either restored to OPERABLE status or closed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

MODES 2 With one or both main steam isolation valve(s) inoperable, subsequent operation in and 3 MODES 2 or 3 may proceed provided the isolation valve(s) is (are) maintained closed. Otherwise, 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 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.7.1.5 Each main steam line isolation valve that is open shall be demonstrated OPERABLE by verifying full closure within 6.0 seconds when tested pursuant to the Inservice Testing Program.

ST. LUCIE - UNIT I 3/4 7-9 Amendment No. G9, 1-44, 1-5

PLANT SYSTEMS 3/4.7.5 ULTIMATE HEAT SINK LIMITING CONDITION FOR OPERATION 3.7.5.1 The ultimate heat sink shall be OPERABLE with:

a.

Cooling water from the Atlantic Ocean providing a water level above

-10.5 feet elevation, Mean Low Water, at the plant intake structure, and

b.

Two OPERABLE valves in the barrier dam between Big Mud Creek and the intake structure.

APPLICABILITY: At all times.

ACTION:

a.

With the water level requirement of the above Specification not satisfied, be in at least HOT STANDBY within six hours and provide cooling water from Big Mud Creek within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

With one isolation valve in the barrier dam between Big Mud Creek and the intake structure inoperable, restore the inoperable valve to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or, within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , install a temporary flow barrier and open the barrier dam isola-tion valve. The availability of the onsite equipment capable of removing the barrier shall be verified at least once per seven days thereafter.

c.

With both of the isolation valves in the barrier dam between the in-take structure and Big Mud Creek inoperable, within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months either:

1)

Install both temporaryflow barriers and manually open both barrier dam isolation Valves. The availability of the onsite equipment capable of removing the barriers shall be verified at least once per seven days thereafter, or

2)

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 .

SURVEILLANCE REQUIREMENTS 4.7.5.1.1 The ultimate heat sink shall be determined OPERABLE at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the average water level to be within the limits.

4.7.5.1.2 The isolation valves in the barrier dam between the intake structure and Big Mud Creek shall be demonstrated OPERABLE at least once per six months by cycling each valve through at least one complete cycle of full travel.

ST. LUCIE - UNIT 1 3/4 7-18 Amendment No. 6*4

PLANT SYSTEMS 314.7.9 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.9.1 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of > 0.005 microcu-ries of removable contamination.

APPLICABILITY: At all times.

ACTION:

a.

Each sealed source with removable contamination in excess of the above limit shall be immediately withdrawn from use and:

1.

Either decontaminated and repaired, or

2.

Disposed of in accordance with Commission Regulations.

b.

The provisions of Specification 3.0.3 is not applicable.

SURVEILLANCE REQUIREMENTS 4.7.9.1.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:

a. The licensee, or

b. Other persons specifically authorized by the Commission or an Agreement State.

The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.

4.7.9.1.2 Test Frequencies - Each category of sealed sources shall be tested at the frequencies described below.

a.

Sources in use (excluding startup sources previously subiected to core flux) - At least once per six months for all sealed sources containing radioactive material:

ST. LUCIE - UNIT 1 3/4 7-27

ELECTRICAL POWER SYSTEMS ACTION (continued)

e.

With two of the above required diesel generators inoperable, demonstrate the OPERABILITY of two offsite A.C. circuits by performing Surveillance Requirement 4.8.1.1.1.a within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; restore one of the inoperable diesel generators to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in the 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 . Following restoration of one diesel generator unit, follow ACTION Statement b. with the time requirement of that ACTION Statement based on the time of initial loss of the remaining inoperable diesel generator.

f.

With one Unit 1 startup transformer (1A or 1 B) inoperable and with a Unit 2 startup transformer (2A or 2B) connected to the same A or B offsite power circuit and administratively available to both units, then should Unit 2 require the use of the startup transformer administratively available to both units, Unit 1 shall demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirement 4.8.1.1.1.a within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter. Restore the inoperable startup transformer 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

g.

LCO 3.0.4.b is not applicable to diesel generators.

SURVEILLANCE REQUIREMENTS 4.8.1.1.1 Each of the above required independent circuits between the offsite transmission network and the onsite Class 1 E distribution system shall be:

a.

Determined OPERABLE at least once per 7 days by verifying correct breaker alignments, indicated power availability; and

b.

Demonstrated OPERABLE at least once per 18 months by transferring (manually and automatically) unit power supply from the auxiliary transformer to the startup transformer.

4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:

a.

At least once per 31 days on a STAGGERED TEST BASIS by:

1.

Verifying fuel level in the engine-mounted fuel tank,

2.

Verifying the fuel level in the fuel storage tank,

3.

Verifying the fuel transfer pump can be started and transfers fuel from the storage system to the engine-mounted tank, ST. LUCIE - UNIT 1 3/4 8-3 Amendment No. 4, 4-1-2, 438

REFUELING OPERATIONS FUEL POOL VENTILATION SYSTEM - FUEL STORAGE LIMITING CONDITION FOR OPERATION 3.9.12 At least one fuel pool ventilation system shall be OPERABLE.

APPLICABILITY: Whenever recently irradiated fuel is in the spent fuel pool.

ACTION:

a.

With no fuel pool ventilation system OPERABLE, suspend all operations involving movement of recently irradiated fuel within the spent fuel pool or crane operation with loads over the recently irradiated spent fuel until at least one fuel pool ventilation system is restored to OPERABLE status.

b.

The provisions of Specification 3.0.3 is not applicable.

SURVEILLANCE REQUIREMENTS 4.9.12 The above required fuel pool ventilation system shall be demonstrated OPERABLE:

a.

At least once per 31 days by initiating flow through the HEPA filter and charcoal adsorber train and verifying that the train operates for at least 15 minutes.

b.

At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system by:

ST. LUCIE - UNIT I 3/4 9-12 Amendment No. 484

RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the waste gas decay tanks shall be limited to less than or equal to 2% by volume whenever the hydrogen concentration exceeds 4% by volume.

APPLICABILITY: At all times.

ACTION:

a.

With the concentration of oxygen in the waste gas decay tank greater than 2% by volume but less than or equal to 4% by volume, reduce the oxygen concentration to the above limits within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

b.

With the concentration of oxygen in the waste gas decay tank greater than 4% by volume and the hydrogen concentration greater than 2% by volume, immediately suspend all additions of waste gases to the system and immediately commence reduction of the concentration of oxygen to less than or equal to 2% by volume.

c.

The provisions of Specification 3.0.3 is not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.5.1 The concentration of oxygen in the waste gas decay tank shall be determined to be within the above limits by continuously* monitoring the waste gases in the on service waste gas decay tank.

4.11.2.5.2 With the oxygen concentration in the on service waste gas decay tank greater than 2% by volume as determined by Specification 4.11.2.5.1, the concentration of hydrogen in the waste gas decay tank shall be determined to be within the above limits by gas partitioner sample at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

When continuous monitoring capability is inoperable, waste gases shall be monitored in accordance with the actions specified for the Waste Gas Decay Tanks Explosive Gas Monitoring System in Chapter 13 of the Updated Final Safety Analysis Report.

ST. LUCIE - UNIT 1 3/4 11-14 Amendment No. 69, -46, 4-,1, 41

RADIOACTIVE EFFLUENTS GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 165,000 curies noble gases (considered as Xe-1 33).

APPLICABILITY: At all times.

ACTION:

a.

With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank.

b.

The provisions of Specification 3.0.3 is not applicable.

SURVEILLANCE REOUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when radioactive materials are being added to the tank when reactor coolant system activity exceeds 518.9 IiCi/gram DOSE EQUIVALENT XE-133.

ST. LUCIE - UNIT 1 3/4 11-15 Amendment No. 69, 69, 24-,

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.1 Compliance with the Limiting Conditions for Operation contained inthe succeeding specifications is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met.

3.0.2 Noncompliance with a specification shall exist when the requirements of the Limiting Condition for Operation and/or associated ACTION requirements are not met within the specified time intervals. If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.

3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION, requirements, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , action shall be initiated to place the unit in a MODE in which specification does not apply by placing it, as applicable, in:

1.

At least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

2.

At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and

3.

At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation. Exceptions to these requirements are stated in the individual specifications.

This specification is not applicable in MODE 5 or 6.

3.0.4 When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made:

a.

When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time;

b.

After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate; exceptions to this Specification are stated in the individual Specifications, or

c.

When an allowance is stated in the individual value, parameter, or other Specification.

ST. LUCIE - UNIT 2 3/4 0-1 Amendment No.,,3-ee3-eeted

APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement. Failure to perform a Surveillance Requirement within the allowable surveillance interval, defined by Specification 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a Limiting Condition for Operation. Surveillance Requirements do not have to be performed on inoperable equipment.

4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

4.0.3 If it is discovered that a Surveillance was not performed within its specified frequency, then compliance with the requirement to declare the Limiting Condition for Operation not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the risk impact shall be managed.

If the Surveillance is not performed within the delay period, the Limiting Condition for Operation must immediately be declared not met, and the applicable ACTION(s) must be taken.

When the Surveillance is performed within the delay period and the Surveillance is not met, the Limiting Condition for Operation must immediately be declared not met, and the applicable ACTION(s) must be taken.

4.0.4 Entry into a MODE or other specified condition in the Applicability of a Limiting Condition for Operation (LCO) shall only be made when the LCO's Surveillances have been met within their specified frequency, except as provided by Surveillance Requirement 4.0.3. When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4.

This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

4.0.5 Surveillance Requirements for inservice inspection of ASME Code Class 1, 2 and 3 components shall be applicable as follows:

a.

Inservice inspection of ASME Code Class 1, 2 and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g) (6) (i).

b.

deleted

c.

deleted ST. LUCIE - UNIT 2 3/4 0-2 Amendment No. 33, 48, 94-, 429

TABLE 3.3-1 REACTOR PROTECTIVE INSTRUMENTATION FUNCTIONAL UNIT

1.

Manual Reactor Trip

2.

Variable Power Level - High

3.

Pressurizer Pressure - High

4.

Thermal Margin/Low Pressure

5.

Containment Pressure - High

6.

Steam Generator Pressure - Low

7.

Steam Generator Pressure Difference - High

8.

Steam Generator Level-- Low

9.

Local Power Density - High

10. Loss of Component Cooling Water to Reactor Coolant Pumps

11. Reactor Protection System Logic TOTAL NO.

OF CHANNELS 4

4 4

4 4/SG 4

CHANNELS TO TRIP 2

2 2(a)(d) 2 2(a)(d) 2 2/SG(b) 2(a)(d) 2/SG 2(c)(d) 2 2

2(f)

MINIMUM CHANNELS OPERABLE 4

4 3

3 3

3 3/SG 3

3/SG 3

3 3

4 APPLICABLE MODES 1,2 3*, 4*, 5*

1,2 1,2 1,2 1,2 1,2 1,2 1,2 1

1,2 1,2 3*, 4*, 5*

1,2 3*, 4*, 5*

ACTION 1

5 2

2 2

2 5

4 5

4/SG 4

4 4

12. Reactor Trip Breakers 4

13. Wide Range Logarithmic Neutron Flux Monitor

a. Startup and Operating -

Rate of Change of Power -

High

b. Shutdown

14. Reactor Coolant Flow - Low

15. Loss of Load (Turbine Hydraulic Fluid Pressure - Low) 4 4

4/SG 4

2(e)(g) 0 2/SG(a)(d) 2(c) 3 2

3/SG 3

1,2 3,4,5 1,2 2

3 2

2 1

ST. LUCIE - UNIT 2 3/4 3-2 Amendment No. 60

TABLE 3.3-1 (Continued)

TABLE NOTATION

With the protective system trip breakers in the closed position, the CEA drive system capable of CEA withdrawal, and fuel in the reactor vessel.

(a)

Trip may be manually bypassed below 0.5% of RATED THERMAL POWER in conjunction with (d) below; bypass shall be automatically removed when Wide Range Logarithmic Neutron Flux power is greater than or equal to 0.5% of RATED THERMAL POWER.

(b)

Trip may be manually bypassed below 705 psig; bypass shall be automatically removed at or above 705 psig.

(c)

Trip may be bypassed below 15% of RATED THERMAL POWER; bypass shall be automatically removed when Power Range Neutron Flux power is greater than or equal to 15% of RATED THERMAL POWER.

(d)

Trip may be bypassed during testing pursuant to Special Test Exception 3.10.3.

(e)

Trip may be bypassed below 10-4% and above 15% of RATED THERMAL POWER; bypass shall be automatically removed when Wide Range Logarithmic Neutron Flux power is > 1 0 -%

and Power Range Neutron Flux power < 15% of RATED THERMAL POWER.

(f)

Each channel shall be comprised of two trip breakers; actual trip logic shall be one-out-of-two taken twice.

(g)

There shall be at least two decades of overlap between the Wide Range Logarithmic Neutron Flux Monitoring Channels and the Power Range Neutron Flux Monitoring Channels.

ACTION STATEMENTS ACTION 1 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-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/or open the protective system trip breakers.

ST. LUCIE - UNIT 2 3/4 3-3 Amendment No. 98

TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLI FUNCTIONAL UNIT

1.

SAFETY INJECTION (SIAS)

a. Manual (Trip Buttons)

b.

Containment Pressure -

High

c.

Pressurizer Pressure -

Low

d. Automatic Actuation -

Logic

2.

CONTAINMENT SPRAY (CSAS)

a. Manual (Trip Buttons)

b. Containment Pressure -

High-High

c. Automatic Actuation Logic

3.

CONTAINMENT ISOLATION (CIAS)

a. Manual CIAS (Trip Buttons)

b. Safety Injection (SIAS)

c.

Containment Pressure -

High

d.

Containment Radiation -

High

e. Automatic Actuation Logic OF CHANNELS TO TRIP OPERABLE MODES E

2 4

4 2

2 4

2 1,

2 2

1 1

2 3

3 2

2 3

2 1,2,3,4 1,2,3 1,2, 3(a) 1,2,3,4 1,2,3,4 1(b), 2(b), 3(b) 1,2,3,4 ACTION 12 13, 14 13, 14 12 12 18a, 18b, 18c 12 2

1 See Functional and Requirements 4

2 2

1,2,3,4 12 Unit 1 for all Safety Injection Initiating Functions 3

1,2,3 13, 14 3

1,2,3 13, 14 2

1,2,3,4 12 4

2 2

1 ST. LUCIE - UNIT 2 3/4 3-12 Amendment No. 4-32

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT

4.

MAIN STEAM LINE ISOLATION (MSIS)

a. Manual (Trip Buttons)

b. Steam Generator Pressure - Low

c. Containment Pressure -

High

d. Automatic Actuation Logic

5.

CONTAINMENT SUMP RECIRCULATION (RAS)

a. Manual RAS (Trip Buttons)

b. Refueling Water Storage Tank - Low

c. Automatic Actuation Logic TOTAL NO.

OF CHANNELS 2

4/steam generator 4

2 2

4 2

CHANNELS TO TRIP 1

2/steam generator 2

1 1

2 1

MINIMUM CHANNELS OPERABLE 2

3/steam generator 3

2 3

2 APPLICABLE MODES 1,2,3 1, 2, 3(c) 1,2,3 1,2,3 1,2,3,4 1,2,3 1,2,3 ACTION 16 13, 14 13, 14 12 12 19 12 ST. LUCIE - UNIT 2 3/4 3-13 Amendment No. 60, 432

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

6.

LOSS OF POWER (LOV)

a. (1) 4.16 kV Emergency Bus Undervoltage (Loss of Voltage) 2/Bus 2/Bus 1/Bus 1, 2, 3 17 (2) 480 V Emergency Bus 3/Bus 2/Bus 2/Bus 1,2,3 17 Undervoltage (Loss of Voltage)

b. (1) 4.16 kV Emergency Bus 17 Undervoltage (Degraded Voltage)

(2) 480 V Emergency Bus 3/Bus 2/Bus 2/Bus 1,2,3.

17 Undervoltage (Degraded Voltage)

7.

AUXILIARY FEEDWATER (AFAS)

a. Manual (Trip Buttons) 4/SG 2/SG 4/SG 1,2,3 15

b. Automatic Actuation Logic 4/SG 2/SG 3/SG 1, 2, 3 15

c. SG Level (2A/2B) - Low 4/SG 2/SG 3/SG 1, 2, 3 20a, 20b, 20c

8.

AUXILIARY FEEDWATER ISOLATION

a. SG 2A - SG 2B Differential Pressure 4/SG 2/SG 3/SG 1, 2, 3 20a, 20b, 20c

b. Feedwater Header 2A - 2B 4/SG 2/SG 3/SG 1, 2, 3 20a, 20c Differential Pressure ST. LUCIE - UNIT 2 3/4 3-14 Amendment No. 2-8, 7-9, 432

TABLE 3.3-3 (Continued)

TABLE NOTATION (a)

Trip function may be bypassed in this MODE when pressurizer pressure is less than 1836 psia; bypass shall be automatically removed when pressurizer pressure is greater than or equal to 1.836 psia.

(b)

An SIAS signal is first necessary to enable CSAS logic.

(c)

Trip function may be bypassed in this MODE below 700 psia; bypass shall be automatically removed at or above 700 psia.

ACTION OF STATEMENTS ACTION 12 -

ACTION 13 -

With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

With the number of channels OPERABLE one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may continue provided the inoperable channel is placed in the bypassed or tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . The channel shall be returned to OPERABLE status no later than during the next COLD SHUTDOWN.

With a channel process measurement circuit that affects multiple functional units inoperable or in test, bypass or trip all associated functional units as listed below.

Process Measurement Circuit

1. Containment Pressure -

2. Steam Generator Pressure -

3. Steam Generator Level -

4. Pressurizer Pressure -

Functional Unit Bypassed Containment Pressure - High (SIAS, CIAS, CSAS)

Containment Pressure - High (RPS)

Steam Generator Pressure - Low (MSIS)

AFAS-1 and AFAS-2 (AFAS)

Thermal Margin/Low Pressure (RPS)

Steam Generator Pressure - Low (RPS)

Steam Generator Level - Low (RPS)

If SG-2A, then AFAS-1 (AFAS)

If SG-2B, then AFAS-2 (AFAS)

Pressurizer Pressure - High (RPS)

Pressurizer Pressure - Low (SIAS)

Thermal Margin/Low Pressure (RPS)

ST. LUCIE - UNIT 2 3/4 3-15 Amendment No. 28, 73, 449

INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm/trip setpoints within the specified limits.

APPLICABILITY: As shown in Table 3.3-6.

ACTION:

a.

With a radiation monitoring channel alarm/trip setpoint exceeding the value shown in Table 3.3-6, adjust the setpoint to within the limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or declare the channel inoperable.

b.

With one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6.

c.

The provisions of Specification 3.0.3 is not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-3.

4.3.3.2 At least once per 18 months, each Control Room Isolation radiation monitoring instrumentation channel shall be demonstrated OPERABLE by verifying that the response time of the channel is within limits.

ST. LUCIE - UNIT 2 3/4 3-24 Amendment No. -Q, 4--9

INSTRUMENTATION REMOTE SHUTDOWN SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.5 The remote shutdown system transfer switches, control and instrumentation channels shown in Table 3.3-9 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a.

With the number of OPERABLE remote shutdown channels less than the Required Number of Channels shown in Table 3.3-9, either restore the inoperable channel to OPERABLE status within 30 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

With the number of OPERABLE remote shutdown channels less than the Minimum Channels OPERABLE requirements of Table 3.3-9, either restore the inoperable channel to OPERABLE status within 7 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.3.3.5.1 Each remote shutdown monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-6.

4.3.3.5.2 Each remote shutdown system instrumentation transfer switch and control circuit shall be demonstrated OPERABLE by verifying its capability to perform its intended function(s) at least once per 18 months.

ST. LUCIE - UNIT 2 3/4 3-38

INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.6 The accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a.*

With the number of OPERABLE accident monitoring channels less than the Required Number of Channels shown in Table 3.3-10, either restore the inoperable channel to OPERABLE status within 7 days, or be in HOT STANDBY in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and HOT SHUTDOWN in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.*

With the number of OPERABLE accident monitoring channels less than the Minimum Channels OPERABLE requirements of Table 3.3-10, either restore the inoperable channels to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and HOT SHUTDOWN in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c.** With the number of OPERABLE Channels one less than the Total Number of Channels shown in Table 3.3-10, either restore the inoperable channel to OPERABLE status within 7 days if repairs are feasible without shutting down or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

d.** With the number of OPERABLE Channels less than the Minimum Channels OPERABLE requirements of Table 3.3-10, either restore the inoperable channel(s) to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months if repairs are feasible without shutting down or:

1.

Initiate an alternate method of monitoring the reactor vessel inventory; and

2.

Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event out-lining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status, and

3.

Restore the Channel to OPERABLE status at the next scheduled refueling.

Action statements do not apply to Reactor Vessel Level Monitoring System, Containment Sump Water Level (narrow range) and Containment Sump Water Level (wide range) instruments.

- Action statements apply only to Reactor Vessel Level Monitoring System, Containment Sump Water Level (narrow range) and Containment Sump Water Level (wide range) instruments.

.ST. LUCIE - UNIT 2 3/4 3-41 Amendment No. 1-9, 46, 469

REACTOR COOLANT SYSTEM 3/4.4.4 PORV BLOCK VALVES LIMITING CONDITION FOR OPERATION 3.4.4 Each Power Operated Relief Valve (PORV) Block valve shall be OPERABLE.

No more than one block valve shall be open at any one time.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a.

With one or more block valve(s) inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the block valve(s) to OPERABLE status or close the block valve(s) and remove power from the block valve(s); otherwise, 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 .

b.

With both block valves open, close one block valve within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , otherwise 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 .

SURVEILLANCE REQUIREMENTS 4.4.4 Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed with power removed in order to meet the requirements of Action a. or b. above.

ST. LUCIE - UNIT 2 3/4 4-10 Amendment No. 3-, 46

REACTOR COOLANT SYSTEM 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.6.1 The following RCS leakage detection systems will be OPERABLE:

a.

The reactor cavity sump inlet flow monitoring system; and

b.

One containment atmosphere radioactivity monitor (gaseous or particulate).

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

ACTION:

a.

With the reactor cavity sump inlet flow monitoring system inoperable with an operable containment particulate radioactivity monitor, perform a RCS water inventory balance at least once per 24* hours and restore the sump inlet flow monitoring system to OPERABLE status within 30 days; otherwise, 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 .

b.

With the reactor cavity sump inlet flow monitoring system inoperable with only the containment gaseous radioactivity monitor operable, perform an RCS water inventory balance at least once per 24* hours and analyze grab samples of the containment atmosphere at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and either restore the sump inlet flow monitoring system to OPERABLE status within 7 days or restore the containment particulate radioactivity monitor to OPERABLE status within 7 days and enter action a. above with the time in this action applied against the allowed outage time of action a.; otherwise, 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 .

c.

With the required radioactivity monitor inoperable, analyze grab samples of the containment atmosphere or perform a RCS water inventory balance at least once per 24* hours, and restore the required radioactivity monitor to OPERABLE status within 30 days; otherwise, 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 .

d.

With all required monitors inoperable, enter LCO 3.0.3 immediately.

SURVEILLANCE REQUIREMENTS 4.4.6.1 The RCS leakage detection instruments shall be demonstrated OPERABLE by:

a.

Performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION of the required containment atmosphere radioactivity monitor at the frequencies specified in Table 4.3-3.

b.

Performance of the CHANNEL CALIBRATION of the reactor cavity sump inlet flow monitoring system at least once per 18 months.

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation.

ST. LUCIE - UNIT 2 3/4 4-18 Amendment No. 84, 447-, 46 REACTOR COOLANT SYSTEM 3/4.4.8 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant shall be limited to:

a. Less than or equal to 1.0 microcurie/gram DOSE EQUIVALENT 1-131, and

b. Less than or equal to 518.9 microcuries/gram DOSE EQUIVALENT XE-133.

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

a.

With the specific activity of the primary coolant > 1.0 pCi/gram DOSE EQUIVALENT 1-131, verify DOSE EQUIVALENT 1-131 is <60.0 pCi/gram once per four hours.

b.

With the specific activity of the primary coolant > 1.0 pCi/gram DOSE EQUIVALENT 1-131, but <60.0 pCi/gram DOSE EQUIVALENT 1-131, operation may continue for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months while efforts are made to restore DOSE EQUIVALENT 1-131 to within the 1.0 pCi/gram limit. LCO 3.0.4.c is applicable.

c.

With the specific activity of the primary coolant > 1.0 pCi/gram DOSE EQUIVALENT 1-131 for greater than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval, or > 60.0 pCi/gram DOSE EQUIVALENT 1-131, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

d.

With the specific activity of the primary coolant > 518.9 pCi/gram DOSE EQUIVALENT XE-1 33, operation may continue for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months while efforts are made to restore DOSE EQUIVALENT XE-1 33 to within the 518.9 pCi/gram DOSE EQUIVALENT XE-1 33 limit. LCO 3.0.4.c is applicable.

e.

With the specific activity of the primary coolant > 518.9 pCi/gram DOSE EQUIVALENT XE-1 33 for greater than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.4.8 The specific activity of the primary coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-4.

ST. LUCIE - UNIT 2 3/4 4-25 Amendment No. 44, 46

REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION ACTION: (Continued)

c.

In the event either the PORVs, SDCRVs or the RCS vent(s) are used to mitigate a RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs, SDCRVs or vent(s) on the transient and any corrective action necessary to prevent recurrence.

d.

LCO 3.0.4.b is not applicable to PORVs when entering MODE 4.

SURVEILLANCE REQUIREMENTS 4.4.9.3.1 Each PORV shall be demonstrated OPERABLE by:

a.

In addition to the requirements of the Inservice Testing Program, operating the PORV through one complete cycle of full travel at least once per 18 months.

ST. LUCIE - UNIT 2 3/4 4-36 Amendment No. 46, 34, 94

EMERGENCY CORE COOLING SYSTEMS 3/4.5.3 ECCS SUBSYSTEMS - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:

a.

One OPERABLE high-pressure safety injection pump, and

b.

An 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 Sump Recirculation Actuation Signal.

APPLICABILITY: MODES 3* and 4 Footnote # shall remain applicable in MODES 5 and 6 when the Pressurizer manway cover is in place and the reactor vessel head is on.

ACTION:

a.

With no ECCS subsystems OPERABLE, restore at least one EGOS subsystem to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .

b.

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

c.

LCO 3.0.4.b is not applicable to ECCS High Pressure Safety Injection subsystem when entering MODE 4.

SURVEILLANCE REQUIREMENTS 4.5.3 The ECCS subsystem shall be demonstrated OPERABLE per the applicable Surveillance Requirements of 4.5.2.

With pressurizer pressure less than 1750 psia.

One HPSI shall be rendered inoperable prior to entering MODE 5.

ST. LUCIE - UNIT 2 3/4 5-7 Amendment No. 4-6, 83, 44-9

CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 Each containment air lock shall be OPERABLE with:

a.

Both doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed, and

b.

An overall air lock leakage rate in accordance with the Containment Leakage Rate Testing Program.

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

ACTION:

a.

With one containment air lock door inoperable*:

1.

Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or lock the OPERABLE air lock door closed.

2.

Operation may then continue until performance of the next required overall air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed at least once per 31 days.

3.

Otherwise, 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 .

b.

With the containment air lock inoperable, except as the result of an inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-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 .

If the inner air lock door is inoperable, passage through the OPERABLE outer air lock door is permitted to effect repairs to the inoperable inner air lock door. No more than one airlock door shall be open at any time.

ST. LUCIE - UNIT 2 3/4 6-9 Amendment No. 36, 88

314.7 PLANT SYSTEMS 314.7.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam line code safety valves shall be OPERABLE with lift settings as shown in Table 3.7-2.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a.

With both reactor coolant loops and associated steam generators in operation and with one or more main steam line code safety valves inoperable, operation in MODES 1, 2 and 3 may proceed provided that, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either the inoperable valve is restored to OPERABLE status or the Power Level-High trip setpoint is reduced per Table 3.7-1; otherwise, 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 .

SURVEILLANCE REQUIREMENTS 4.7.1.1 Verify each main steam line code safety valve is OPERABLE in accordance with the Inservice Testing Program. Following testing, as-left lift settings shall be within +/- 1% of 1000 psia for valves 8201 through 8208, and within +/- 1% of 1040 psia for valves 8209 through 8216 specified in Table 3.7-2.

ST. LUCIE - UNIT 2 3/4 7-1 Amendment No. 8, 68, 94, 44-G-

PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:

a.

Two feedwater pumps, each capable of being powered from separate OPERABLE emergency busses, and

b.

One feedwater pump capable of being powered from an OPERABLE steam supply system.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a.

With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps 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 .

b.

With two auxiliary feedwater pumps inoperable 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status.

d.

LCO 3.0.4.b is not applicable.

SURVEILLANCE REQUIREMENTS 4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE:

a.

At least once per 31 days 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.

ST. LUCIE - UNIT 2 3/4 7-4 Amendment No. 2-, 446

PLANT SYSTEMS.

MAIN STEAM LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.7.1.5 Each main steam line isolation valve shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

MODE I With one main steam line isolation valve inoperable but open, POWER OPERATION may continue provided the inoperable valve is restored to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; otherwise, 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 .

MODES 2, 3 and 4 With one or both main steam isolation valve(s) inoperable, subsequent operation in MODES 2, 3 or 4 may proceed provided the isolation valve(s) is (are) maintained closed. Otherwise, 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 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.7.1.5 Each main steam line isolation valve shall be demonstrated OPERABLE by verifying full closure within 6.75 seconds when tested pursuant to the Inservice Testing Program.

ST. LUCIE - UNIT 2 3/4 7-9 Amendment No. 3', 62, 94

PLANT SYSTEMS 3/4.7.5 ULTIMATE HEAT SINK LIMITING CONDITION FOR OPERATION 3.7.5.1 The ultimate heat sink shall be OPERABLE with:

a.

Cooling water from the Atlantic Ocean providing a water level above

-10.5 feet elevation, Mean Low Water, at the plant intake structure, and

b.

Two OPERABLE valves in the barrier dam between Big Mud Creek and the intake structure.

APPLICABILITY: At all times.

ACTION:

a.

With the water level requirement of the above specification not satisfied, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and provide cooling water from Big Mud Creek within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

With one isolation valve in the barrier dam between Big Mud Creek and the intake structure inoperable, restore the inoperable valve to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , install a temporary flow barrier and open the barrier dam isola-tion valve. The availability of the onsite equipment capable of removing the barrier shall be verified at least once per 7 days thereafter.

c.

With both of the isolation valves in the barrier dam between the in-take structure and Big Mud Creek inoperable, within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , either:

1.

Install both temporary flow barriers and manually open both barrier dam isolation valves. The availability of the onsite equipment capable of removing the barriers shall be verified at least once per 7 days thereafter, or

2.

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 .

SURVEILLANCE REQUIREMENTS 4.7.5.1.1 The ultimate heat sink shall be determined OPERABLE at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the average water level to be within the limits.

4.7.5.1.2 The isolation valves in the barrier dam between the intake structure and Big Mud Creek shall be demonstrated OPERABLE at least once per six months by cycling each valve through at least one complete cycle of full travel.

ST. LUCIE - UNIT 2 3/4 7-i5

PLANT SYSTEMS 314.7.10 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.10 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of greater than or equal to 0.005 microcuries of removable contamination.

APPLICABILITY: At all times.

ACTION:

a.

With a sealed source having removable contamination in excess of the above limit, immediately withdraw the sealed source from use and either:

1.

Decontaminate and repair the sealed source, or

2.

Dispose of the sealed source in accordance with Commission Regulations.

b.

The provisions of Specification 3.0.3 is not applicable.

SURVEILLANCE REQUIREMENTS 4.7.10.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:

a.

The licensee, or

b.

Other persons specifically authorized by the Commission or an Agreement State.

The test method shall be a detection sensitivity of at least 0.005 microcuries per test sample.

4.7.10.2 Test Frequencies - Each category of sealed sources (excluding startup sources and fission detectors previously subjected to core flux) shall be tested at the frequencies described below.

a.

Sources in use - At least once per 6 months for all sealed sources containing radioactive material:

1.

With a half-life greater than 30 days (excluding Hydrogen 3),

and

2.

In any form other than gas.

ST. LUCIE - UNIT 2 3/4 7-28

ELECTRICAL POWER SYSTEMS ACTION: (Continued)

d.

With two of the required offsite A.C. circuits inoperable, restore one of the inoperable offsite sources to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-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 . Following restoration of one offsite source, follow ACTION Statement a. with the time requirement of that ACTION Statement based on the time of the initial loss of the remaining inoperable offsite A.C. circuit.

e.

With two of the above required diesel generators inoperable, demonstrate the OPERABILITY of two offsite A.C. circuits by performing Surveillance Requirement 4.8.1.1.1.a within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; restore one of the inoperable diesel generators to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in the 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 . Following restoration of one diesel generator unit, follow ACTION Statement b. with the time requirement of that ACTION Statement based on the time of initial loss of the remaining inoperable diesel generator.

f.

With one Unit 2 startup transformer (2A or 2B) inoperable and with a Unit 1 startup transformer (1A or 1 B) connected to the same A or B offsite power circuit and administratively available to both units, then should Unit 1 require the use of the startup transformer administratively available to both units, Unit 2 shall demonstrate the operability, of the remaining A.C. sources by performing Surveillance Requirement 4.8.1.1.la. within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter. Restore the inoperable startup transformer 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

g.

LCO 3.0.4.b is not applicable to diesel generators:

SURVEILLANCE REQUIREMENTS 4.8.1.1.1 Each of the above required independent circuits between the offsite transmission network and the onsite Class 1 E distribution system shall be:

a.

Determined OPERABLE at least once per 7 days by verifying correct breaker alignments, indicated power availability; and

b.

Demonstrated OPERABLE at least once per 18 months by transferring (manually and automatically) unit power supply from the normal circuit to the alternate circuit.

4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:

a.

At least once per 31 days on a STAGGERED TEST BASIS BY:

ST. LUCIE - UNIT 2 3/4 8-3 Amendment No. 39, 43, 78

RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the waste gas decay tanks shall be limited to less than or equal to 2% by volume whenever the hydrogen concentration exceeds 4% by volume.

APPLICABILITY: At all times.

ACTION:

a.

With the concentration of oxygen in the waste gas decay tank greater than 2% by volume but less than or equal to 4% by volume, reduce the oxygen concentration to the above limits within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

b.

With the concentration of oxygen in the waste gas decay tank greater than 4% by volume and the hydrogen concentration greater than 2% by volume, immediately suspend all additions of waste gases to the system and immediately commence reduction of the concentration of oxygen to less than or equal to 2% by volume.

c.

The provisions of Specification 3.0.3 is not applicable SURVEILLANCE REQUIREMENTS 4.11.2.5.1 The concentration of oxygen in the waste gas decay tank shall be determined to be within the above limits by continuously* monitoring the waste gases in the on service waste gas decay tank.

4.11.2.5.2 With the oxygen concentration in the on service waste gas decay tank greater than 2% by volume as determined by Specification 4.11.2.5.1, the concentration of hydrogen in the waste gas decay tank shall be determined to be within the above limits by gas partitioner sample at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

When continuous monitoring capability is inoperable, waste gases shall be monitored in accordance with the actions specified for the Waste Gas Decay Tanks Explosive Gas Monitoring System in Chapter 13 of the Updated Final'Safety Analysis Report.

ST. LUCIE - UNIT 2 3/4 11-14 Amendment No.

7., 89, 94

RADIOACTIVE EFFLUENTS GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 165,000 curies noble gases (considered as Xe-133).

APPLICABILITY: At all times.

ACTION:

a.

With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank.

b.

The provisions of Specification 3.0.3 is not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when radioactive materials are being added to the tank when reactor coolant system activity exceeds 518.9 pCi/gram DOSE EQUIVALENT XE-133.

ST. LUCIE - UNIT 2 3/4 11-15 Amendment No. 13, 463

St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2013-233 ATTACHMENT 4 LIST OF REGULATORY COMMITMENTS The following table identifies those actions committed to by FPL in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments. Please direct questions regarding these commitments to Mr. Eric Katzman, Licensing Manager at 772-467-7734.

Regulatory Commitment Due Date/Event FPL will establish the Technical Specification Bases for LCO To be implemented 3.0.4 and SR 4.0.4 as adopted with this license amendment with the Technical request.

Specification amendment

St. Lucie Units I and 2 Docket Nos. 50-335 and 50-389 L-2013-233 Page 1 of 37 ATTACHMENT 5 PROPOSED CHANGES TO TECHNICAL SPECIFICATION BASES PAGES

L-2013-233 Page 2 of 37 SECT!ON NO.:

TITLE:

TECHNICAL SPECIFICATIONS.

PAG.

3.0 &.4.0 BASES ATTACHMENT 2 OF ADM-25.04 7 of REVISION NO.:

LIMITING CONDITIONS FOR-OPERATION 7

AND SURVEILLANCE REQUIREMENTS

[7 ST. LUCIE UNIT 11 3/4.0 APPLICABILITY (continued)

BASES (continued) 3.0.4 This specification establishes limitations on MODE changes when a Limiting Condition for Operation is not met. It precludes placing the facility in a higher MODE of operation when the requirements for a Limiting Condition for Operation are not met and continued noncompliance to these conditions would result in. a shutdown to comply with the ACTION. requirements if a Change in MODES were permitted. The purpose of this specification is to ensure that facility operation is not initiated or that higher MODES of operation are not entered when corrective action is being taken to obtain compliance with a specification by restoring equipment to OPERABLE. status or parameters to specified limits. Compliance with ACTION requirements that permit continued operation of the facility for an unlimited period of time provides an accept-able level of safety for continued operation without regard to the status of the plant before or after a MODE change. Therefore, in this case, entry into an OPERATIONAL MODE or other specified. condition may be made in accordance with the provisions.of the ACTION requirements. The provisions of this specification should not, however, be interpreted as endorsing the failure to exercise good practice in restoring systems or components to OPERABLE status before plant startup.

When a shutdown is required to comply with the ACTION requirements, the provisions of Specification 3.0.4 do not apply because they would delay placing the facility in a lower MODE of operation.

Exceptions to this* provision have been provided.for a limited number of specifications when* startup with inoperable equipment would not affect plant safety. These exceptions are stated-in the ACTION statements of the appropriate specifications.

The specifications of this section establish the general requirements applicable to Surveillance Requirements. These requirements are based on the Surveillance Requirements stated in the Code of Federal Regulations, 10 CFR 50.36(c)(3):

'Surveillance requirements are requirements relating to test, calibration, or inspection to ensure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the

.limiting conditions of operation will be met."

o~e

%Nth h sley+

3

L-2013-233 Page 3 of 37 INSERT 3 (BASES 3.0.4)

LCO 3:0'.4 establishes limitations on changes in MODES or other specified conditions in the Applicability when an LCO is not met. It allows placing the unit in a MODE or other specified condition stated in that Applicability (e.g., the Applicability desired to be entered) when unit conditions are such that the requirements of the LCO would not be met, in accordance with LCO 3.0.4.a, LCO 3.0,4.b, or LCO 3.0.4.c.

LCO 3.0.4.a allows entry into a MODE or other specified condition in the Applicability with the LCO not met when the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time. Compliance with required Actions that permit continued operation of the unit for an unlimited period of time in a MODE or other specified condition provides an acceptable level of safety for continued operation. This is without regard to the status of the unit before or after the MODE change. Therefore, in such cases, entry into a MODE or other specified condition in the Applicability may be made in accordance with the provisions of the required Actions.

LCO 3.0.4.b allows entry into a MODE or other specified condition in the Applicability with the LCO not met after performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate.

The risk assessment may use quantitative, qualitative, or blended approaches, and the risk assessment will be conducted using the plant program, procedures, and criteria in place to implement 10 CFR 50.65(a)(4), which requires that risk impacts of maintenance activities to be assessed and managed. The risk assessment for the purposes of LCO 3.0.4.b, must take into account all inoperable Technical Specification equipment regardless of whether the equipment is included in the normal 10 CFR 50.65(a)(4) risk assessment scope.

The risk assessments will be conducted using the procedures and guidance endorsed by Regulatory Guide 1.182, "Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants." Regulatory Guide 1.182 endorses the guidance in Section 11 of NUMARC 93-01, "Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants." These documents address general guidance for conduct of the risk assessment, quantitative and qualitative guidelines for establishing risk management actions, and example risk management actions. These include actions to plan and conduct other activities in a manner that controls overall risk, increased risk awareness by shift and management personnel, actions to reduce the duration of the condition, actions to minimize the magnitude of risk increases (establishment of backup success paths or compensatory measures), and determination that the

L-2013-233 Page 4 of 37 proposed MODE change is acceptable. Consideration should also be given to the probability of completing restoration such that the requirements of the LCO would be met prior to the expiration of ACTIONS completion times that would require exiting the Applicability.

LCO 3.0.4.b may be used with single or multiple systems and components unavailable. NUMARC 93-01 provides guidance relative to consideration of simultaneous unavailability of multiple systems and components.

The results of the risk assessment shall be considered in determining the.

acceptability of entering the MODE or other specified condition in the Applicability, and any corresponding risk management actions. The LCO 3.0.4.b risk assessments do not have to be documented.

The Technical Specifications allow continued operation with equipment unavailable in MODE 1 for the duration of the completion time. Since this is allowable, and since in general the risk impact in that particular MODE bounds the risk of transitioning into and through the applicable MODES or other specified conditions in the Applicability of the LCO, the use of the LCO 3.0.4.b allowance should be generally acceptable, as long as the risk is assessed and managed as stated above. However, there is a small subset of systems and components that have been determined to be more important to risk and use of the LCO 3.0.4.b allowance is prohibited. The LCOs governing these systems and components contain notes prohibiting the use of LCO 3.0.4.b by stating LCO 3.0.4.b is not applicable.

LCO 3.0.4.c allows entry into a MODE or other specified condition in the Applicability with the LCO not met based on a note in the Specification which states LCO 3.0.4.c is applicable. These specific allowances permit entry into MODES or other specified conditions in the Applicability when the associated ACTIONS to be entered do not provide for continued operation for an unlimited period of time and a risk assessment has not been performed. This allowance may apply to all the ACTIONS or to a specific required Action of a Specification.

The risk assessments performed to justify the use of LCO 3.0.4.b usually only consider systems and components. For this reason, LCO 3.0.4.c is typically applied to Specifications which describe values and parameters (e.g., Reactor Coolant System Specific Activity), and may be applied to other Specifications based on NRC plant-specific approval.

The provisions of this Specification should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before entering an associated MODE or other specified condition in the Applicability.

The provisions of LCO 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with

L-2013-233 Page 5 of 37 ACTIONS. In addition, the provisions of LCO 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown. In this context, a unit shutdown is defined as a change in MODE or other specified condition in the Applicability associated with transitioning from MODE 1 to MODE 2, MODE 2 to MODE 3, MODE 3 to MODE 4, and MODE 4 to MODE 5.

Upon entry into a MODE or other specified condition in the Applicability with the LCO not met, LCO 3.0.1 and LCO 3.0.2 require entry into the applicable Conditions and Required Actions until the Condition is resolved, until the LCO is met, or until the unit is not within the Applicability of the Technical Specification.

Surveillances do not have to be performed to be performed on the associated inoperable equipment (or on variables outside the specified limits), as permitted by SR 4.0.4 Therefore, utilizing LCO 3.0.4 is not a violation of SR 4.0.1 or SR 4.0.4 for any Surveillances that have not been performed on inoperable equipment. However, SRs must be met to ensure OPERABILITY prior to declaring the associated equipment OPERABLE (or variable within limits) and restoring compliance with the affected LCO.

L-2013-233 Page 6 of 37 SECTION NO.:

3.0 & 4.0 REVISION NO.:

2 TITLE:

TECHNICAL SPECIFICATIONS BASES ATTACHMENT 2 OF ADM-25.04 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS ST. LUCIE UNIT 1 PAGE;',

12 of 12 L. :'

3/4.0 APPLICABILITY (continued)

BASES (continued) 4.03 (continued)

If a SR is not completed within the allowed delay period, then the equipment is considered inoperable or the variable is considered outside the specified limits and the completion times of the required ACTION(s) for the applicable Limiting Condition for Operation begin immediately upon expiration of the delay period. If a surveillance is failed within the delay period, then the equipment is inoperable, or the variable is outside the specified limits and the completion times of the required ACTION(s) for-the applicable Limiting Condition for Operation begin immediately upon the failure of the surveillance.

Completion of the SR within the delay period allowed by this specification, or within the completion time of the ACTIONS, restores compliance with SR 4.01.

Re p ac*v,, i+/I

-+,

4-4.0.4'

'his specification establishes the requirement that alltpplicable surveillancesý must be met before entry into an OPERATIONAL MODE or other condition or operation specified in the Applicability statement. The purpose of this specification is to ensure that system and component OPERABILITY requirements or parameter limits are met before entry into a MODE or condition for which these systems and components ensure safe operation of the facility.

This provision, applies to changes in OPERATIONAL MODES or other specified conditions associated' with plant shutdown as well as startup.

Under the provisions of-this specification, the applicable Surveillance Requirements must be performed within the specified. surveillance interval to.

ensure that the Limiting Conditions for Operation are met during initial plant startup or following a plant outage.

When a shutdown is required to comply with ACTION requirements, the provisions of Specification 4.0.4 do-not apply because: this-would delay 4.0.5 This specification ensures that inservice inspection of ASME Code Class 1, 2 and.3 components will be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel: Code and Addenda as required by 10 CFR 50.55a. Relief from any of the above

.requirements has been provided in writing by the Commission and is not part of these Technical Specifications.

L-2013-233 Page 7 of 37 INSERT 4 (BASES SR 4.0.4)

SR 4.0.4 establishes the requirement that all applicable SRs must be met before entry into a MODE or other specified condition in the Applicability.

This Specification ensures that system and component OPERABILITY requirements and variable limits are met before entry into MODES or other specified conditions in the Applicability for which these systems and components ensure safe operation of the unit. The provisions of this Specification should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before entering an associated MODE or other specified condition in the Applicability.

A provision is included to allow entry into a MODE or other specified condition in the Applicability when an LCO is not met due to Surveillance not being met in accordance with LCO 3.0.4.

However, in certain circumstances, failing to meet an SR will not result in SR 4.0.4 restricting a MODE change or other specified condition change. When a system, subsystem, division, component, device, or variable is inoperable or outside its specified limits, the associated SR(s) are not required to be performed, per SR 4.0.1, which states that surveillances do not have to be performed on inoperable equipment. When equipment is inoperable, SR 4.0.4 does not apply to the associated SR(s) since the requirement for the SR(s) to be performed is removed. Therefore, failing to perform the Surveillance(s) within the specified frequency does not result in an SR 4.0.4 restriction to changing MODES or other specified conditions of the Applicability. However, since the LCO is not met in this instance, LCO 3.0.4 will govern any restrictions that may (or may not) apply to MODE or other specified condition changes. SR 4.0.4 does not restrict changing MODES or other specified conditions of the Applicability when a Surveillance has not been performed within the specified frequency, provided the requirement to declare the LCO not met has been delayed in accordance with SR 4.0.3.

The provisions of SR 4.0.4 shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS. In addition, the provisions of SR 4.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown. In this context, a unit shutdown is defined as a change in MODE or other specified condition in the Applicability associated with transitioning from MODE 1 to MODE 2, MODE 2 to MODE 3, MODE 3 to MODE 4, and MODE 4 to MODE 5.

L-2013-233 Page 8 of 37 SETINNO:PAGE:

SECTION.NO.:

TITLE:

TECHNICAL SPECIFICATIONS

-A...

3/4.4 BASES ATTACHMENT 6 OF ADM-25.04 of36 REVISION NO.:

REACTOR COOLANT SYSTEM 6

ST. LUCIE UNIT 1 3/4.4 REACTOR COOLANT SYSTEM (continued)

BASES (continued) 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE (continued) 314.4.6.1.

LEAKAGE DETECTION SYSTEMS (continued)

The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ' interval provides periodic information that is adequate to detect leakage. A Note is added allowing that the RCS water inventory balance is not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after-establishing steady state operation (stable temperature, power level, pressurizer and makeup tank levels, makeup and letdown, and RCP seal injection and return flows). The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months allowance provides sufficient time to collect and process all necessary data after stable plant conditions are established. The 30 day Completion Time recognizes at least one other form of leakage detection is available.

ACTION d If all required monitors are inoperable, no automatic means of monitoring leakage are available and immediate plantshutdown in accordance with LCO 3.0.3 is required.

isoeffN-e-SURVEILLANCE SR 4.4.6:1 REQUIREMENTS SR 4.4.6.1 requires the performance of CHANNEL CHECKs, CHANNEL FUNCTIONAL TESTs, and CHANNEL CALIBRATIONs of the required leakage detection monitors. These checks give reasonable confidence the channels are operating properly.

L-2013-233 Page 9 of 37 SECTION NO.:

TITLE:

3/4.4 REVISION NO.:

6 TECHNICAL SPECIFICATIONS BASES ATTACHMENT 6 OF ADM-25.04 REACTOR COOLANT SYSTEM ST. LUCIE UNIT 1 3/4.4 REACTOR COOLANT SYSTEM (continued).

-_7 BASES (continued) 3/4.4.7 CHEMISTRY The limitations on Reactor Coolant System chemistry ensure that corrosion of the Reactor Coolant System is minimized and reduce the potential for Reactor Coolant System leakage or failure due to stress corrosion. Maintaining the chemistry within the Steady State Limits provides adequate corrosion protection to ensure the structural integrity of the Reactor Coolant System over the life of the plant. The associated effects ofexceeding the oxygen, chloride and fluoride limits are time and temperature dependent. Corrosion studies show that operation may be continued with contaminant concentration levels in. excess of the Steady State Limits, up to the Transient Limits, for the specified limit time intervals without having a significant effect on the. structural integrity of the Reactor Coolant System. The time.interval permitting.continued operation within the restrictions of the Transient Limits provides time for taking corrective actions to restore the contaminant concentrations to within the Steady State. Limits.

The surveillance requirements' provide adequate assurance that.

concentrations in excess of the limits will be detected in sufficient time to take corrective action.

6t4^

3/4.4.8 SPECIFIC ACTIVITY e maximum allowable doses to an individual at the exclusion area boundary (EAB) distance for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . following an accident, or at the low population zone (LPZ) outer boundary distance for the radiological release duration, are specified in 10 CFR 50.67 for design basis. accidents using the alternative source term methodology and in Branch Technical Position 11-5 for the waste gas decay tank rupture accident. Dose limits to control room operators are given in 10 CFR 50.67 and in GDC 19.

0)

The RCS specific activity LCO limits the allowable concentration of radionuclides in the reactor coolant to ensure that the dose consequences of limiting accidents do not exceed appropriate regulatory offsite and control room dose acceptance criteria. The LCO contains specific activity limits for both DOSE EQUIVALENT (DE) 1-131 and DOSE EQUIVALENT (DE) XE-1 33.

L-2013-233 Page 10 of 37 SECTION NO.:

TITLE:

3/4.4 REVISION.NO.:

6 TECHNICAL SPECIFICATIONS BASES ATTACHMENT 6 OF ADM-25.04 REACTOR COOLANT SYSTEM ST. LUCIE UNIT 1 3/4.4 REACTOR COOLANT SYSTEM (continued)

+

0.66LaK BASES (continued) 3/44e8 PECIFIC ACTIVITY (continued) e radiological dose assessments assume the specific activity of the reactor coolant is at the LCO limits, and an existing reactor coolant steam generator tube leakage rate at the applicable Technical Specification limit.

The radiological dose assessments assume the specific activity of the secondary coolant is at its limit as specified in LCO 3.7.1.4, "Plant Systems - Activity."

The ACTIONS allow operation when DOSE EQUIVALENT-I-131 is greater than 1..0 pCi/gram and less than 60 pCi/gram. The ACTIONS, require.

samplinw*f, f

s and every four hours following to establish a trend. W s

One surveillance requires the determination of the DE XE-1 33 specific activity as a measure of noble gas specific activity of the.reactor coolant at least once per 7 days.

A second surveillance is performed to ensure that iodine-specific activity remains within the LCO limit once-per 1.4 days during normal operation and following rapid power changes when iodine spiking, is more apt to occur. The frequency between two and six hours after a power change of greater than 15% RATED THERMAL POWER within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period, is established because the iodine levels peak during this time following iodine spike initiation.

The RCS specific activity satisfies Criterion 2 of 10 CFR 50.36(c)(2)(ii).

3/4.4.9 PRESSURE/TEMPERATURE LIMITS All. components in the Reactor Coolant System are designed to withstand the effects of cyclic loads due to system temperature and pressure changes. These cyclic loads are introduced by normal load transients, reactor trips, and startup and shutdown operations, The various categories of load cycles used for design purposes are provided in Section 5.2.1 of the FSAR. During startup and shutdown, the rates of temperature and pressure changes are limited so that the maximum specified heatup and cooldown rates. are consistent with the design assumptions and satisfy the stress limits for cyclic operation.

L-2013-233 Page 11 of 37 INSERT 5 (BASES LCO 3.4.8)

A note permits the use of the provisions of LCO 3.0.4.c. This allowance permits entry into the applicable MODE(S) while relying on the ACTIONS. This allowance is acceptable due to the significant conservatism incorporated into the specific activity limit, the low probability of an event that is limiting due to exceeding this limit, and the ability to restore transient specific activity excursions while the plant remains at, or proceeds to power operations.

L-2013-233 Page 12 of 37 SECIO N

.:PAGE:-.,,

SECTION NO.:

TITLE:

TECHNICAL SPECIFICATIONS PAGE 3/464 BASES ATTACHMENT'6 OF ADM-25.04 35.of.36 35 of 3.6 REVISION NO.:

REACTOR COOLANT SYSTEM 6

ST. LUCIE UNIT 1 3/4.4 REACTOR COOLANT SYSTEM (continued)

BASES (continued) 3/4.4.11 DELETED 3/4.4.12 PORV BLOCK VALVES The opening of the Power Operating Relief Valves fulfills no safety related function. The electronic controls of the PORVs must be maintained OPERABLE to ensure satisfaction of Specifications 3.4.12 and 3.4.13.

Since it is impractical and undesirable to actually open the PORVs to demonstrate reclosing, it becomes necessary to verify operability of the PORV Block Valves to ensure the capability to isolate. a malfunctioning PORV.

3/4.4.13 POWER OPERATED RELIEF VALVES and 3/4.4.14 REACTOR COOLANT PUMP - STARTING The low temperature overpressure protection system (LTOP) is designed toprevent RCS overpressurization above the 10! CFR 50 Appendix G operating limit curves (Figures 3.4-2a and 3.4-2b) at RCS temperatures at or below 3000F. 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 andr 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.

L-2013-233 Page 13 of 37 INSERT 6 (BASES Unit 1 LCO 3.4.13)

LCO 3.4.13 Action f prohibits the application of LCO 3.0.4.b to inoperable PORVs used for LTOP. There is an increased risk associated with entering MODE 4 from MODE 5 with PORVs used for LTOP inoperable and the provisions of LCO 3.0.4.b, which allow entry into a MODE or other specified condition in the Applicability with the LCO not met after performance of a risk assessment addressing inoperable systems and components, should not be applied in this circumstance.

L-2013-233 Page 14 of 37 SECTION NO:..

TITLE:

TECHNICAL SPECIFICATIONS PG 3/4.5 BASES ATTACHMENT 7 OF ADM-25.04.

4 o REVISION NO.:

EMERGENCY CORE COOLING SYSTEMS (ECCS) 3 ST. LUCIE UNIT 1.

3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) (continued)

BASES (continued) 3/4Z5.2 and 3/4.5.3 ECCS SUBSYSTEMS The OPERABILITY of two separate and independent ECCS subsystems ensures that sufficient emergency core cooling capability will be available in the event of a LOCA assuming the loss of one subsystem. through any single failure consideration. Either subsystem operating in conjunction with the safety injection tanks is capable of supplying sufficient core cooling to limit the peak cladding temperatures within acceptable limits for all postulated break sizes ranging from the-double ended break of-the largest RCS cold leg pipe downward. In addition, each ECCS subsystem provides long term core cooling capability in the-recirculation mode during the accident recovery period'.

TS 35.2.c and 3.5.3.a require that, ECCS subsystem(s) have an independent OPERABLE flow path capable of automatically transferring suction to the containment sump on a Recirculation. Actuation Signal.

The containment sump is defined as the. area of containment below the minimum flood level in the vicinity of the containment sump strainers.

Therefore, the LCOs are satisfied when an independent OPERABLE flow.

path to the containment sump strainer is available.

TS 3.5.2.d requires that an ECOS subsystem(s) have OPERABLE charging pump and associated flow path from the BAMT(s). Reference to TS 3.1.2.2 requires that the Train A charging pump flowpath is from the BAMT(s) through the boric. acid makeup pump(s). The Train B charging pump flowpath is from.the BAMT(s) through the gravity feed valve(s).

TS 3.5.2, ACTION a.1. provides an allowed outage/action completion time (AOT) of up to 7 days from initial discovery of failure to meet the LCO provided the affected ECCS subsystem is inoperable only because its associated LPSI train is inoperable. This 7 day AOT is based on the findings of a deterministic and probabilistic safety analysis and is, referred to as a "risk-informed" AOT extension. Entry into this ACTION requires that a risk assessment be performed in accordance with the Configuration Risk Management Program (CRMP) which is described in the Administrative Procedure (ADM-1 7.08) that implements the Maintenance Rule pursuant to

. F Cae urve*iance Requirements provided to ensure OPERABILITY of each component ensure that at a minimum, the assumptions used in the accident analyses are met and that subsystem OPERABILITY is maintained.

L-2013-233 Page 15 of 37 INSERT 7 (BASES Unit I LCO 3.5.3)

LCO 3.5.3 Action d prohibits the application of LCO 3.0.4.b to inoperable ECCS High Pressure Safety Injection subsystem. There is an increased risk associated with entering MODE 4 from MODE 5 with an inoperable ECCS High Pressure Safety Injection subsystem and the provisions of LCO 3.0.4.b, which allow entry into a MODE or other specified condition in the Applicability with the LCO not met after performance of a risk assessment addressing inoperable systems and components, should not be applied in this circumstance.

L-2013-233 Page 16 of 37 SECTION NO.:

TITLE:

TECHNICAL SPECIFICATIONS PAGE' t,__

3/4.7 BASES ATTACHMENT 9 OF ADM-25.04 4.Of.13

~4 of 1:3 REVISION NO.:

PLANT SYSTEMS 4

ST. LUCIE UNIT 1 3/4.7 PLANT SYSTEMS (continued).

BASES (continued) 3/4.7'1 TURBINE CYCLE (continued) 106.5 =

Power Level-High Trip Setpoint for two loop operation X

= Total relieving capacity of all safety valves per steam line in lbs/hour (6.192 x 1 06 lbs/hr.)

Y

= Maximum relieving capacity of any one safety valve in lbs/hour (7.74.x 105 Ilbs/hr.).

Surveillance Requirement 4.7.1.1. verifies the OPERABILITY of the MSSVs by the verification of each MSSV lift setpoint..in. accordance with the Inservice Testing Program. The MSSV setpoints are 1000. psia +/-3%.

(4 valves each header) and 1040 psia +2/-3% (4 valves each header) for OPERABILITY; however, the valvesý are reset to 1000 psia +/-1% and 1040 psia +/- 1 %,, respectively, during the Surveillance to allow for drift.

The LCO is expressed in units of psig for consistency with implementing procedures.

Shpois-oT of Sufeio-.0 dr noapl

_Thbis iidws e~tyi4..

_a4eer~atie4re9&E-7b-tiu

,t

-If'rI I lt 1 ha-Svmei~kwG-..

~.ath M

Vs may De tested Underboteeed 3/4.7A1.2 AUXILIARY FEEDWATER PUMPS The OPERABILITY of the -auxiliary feedwater pumps ensures that the Reactor Coolant System can be cooled down to less than 325°F from normal operating conditions in the event of a total loss of off-site power.

Any two of the three auxiliary feedwater pumps have the required capacity to provide sufficient feedwater flow to remove reactor decay heat and reduce the RCS temperature to 325°F where the shutdown cooling be placed into operation for continued cooldown.

37ATE STORAGE TANKS The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water is available to maintain HOT STANDBY for one hour and then cooldown of the Reactor Coolant System to less than 3250F in the event of a total loss of off-site power.

The minimum water volume is sufficient to maintain the RCS at HOT STANDBY conditions for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months with steam discharge to atmosphere.

The minimum usable volume to satisfy the criteria stated above is 130,500 gallons, which is ensured by the LCO for the CST volume of 153,400 gallons.

L-2013-233 Page 17 of 37 INSERT 8 (BASES Unit I LCO 3.7.1.2)

Action b prohibits the application of LCO 3.0.4.b to an inoperable AFW train.

There is an increased risk associated with entering a MODE or other specified condition in the Applicability with an AFW train inoperable and the provisions of LCO 3.0.4.b, which allow entry into a MODE or other specified condition in the Applicability with the LCO not met after performance of a risk assessment addressing inoperable systems and components, should not be applied in this circumstance.

3/4J L-2013-233 Page 18 of 37 ION NO.:

TITLE:

TECHNICAL SPECIFICATIONS PAGE -

3/4.8 BASES ATTACHMENT 10 OF ADM-25.04

'4 of. 6 3ON NO::

ELECTRICAL POWER SYSTEMS 3

ST. LUCIE UNIT 1 ELECTRICAL POWER SYSTEMS (continued)

BASES (continued)

TS 3.8.1.1,. ACTION "b" provides an allowed outage/action completion time (AOT) of up to 14 days toto restore a single inoperable diesel generator to operable status. This AOT is based on the findings of a deterministic and probabilistic safety analysis and is referred to as a "risk-informed" AOT.

Entry into this action requires that a risk assessment be performed in accordance with the Configuration Risk Management Program (CRMP),.

which is described in the Administrative Procedure that implements the Maintenance Rule pursuant to 10 CFR 50.65.

All EDG inoperabilities must be investigated for common-cause failures regardless of how long the EDG inoperability persists. When one diesel generator is inoperable, required ACTIONS 3.8.1A..b and 3.8.1.1.c provide.

an allowance to avoid unnecessary testing of EDGs. If it can be determined that the cause of the inoperable EDG does not exist on the remaining OPERABLE EDG, then SR 4.8.1.1.2.a.4 does not have to be performed.

Eight (8) hours is reasonable to confirm that the OPERABLE EDG is not affected by the same problem as the inoperable EDG. If it cannot otherwise be determined that the cause of the initial inoperable EDG does not exist on the remaining EDG, then satisfactory performance of SR 4.8.1.1.2.a.4 suffices to provide assurance of continued OPERABILITY of that EDG.

If the cause of the initial inoperability exists on the remaining OPERABLE-EDG,, that EDG would also be declared inoperable upon discovery, and ACTION 3.8.1.1.e would be entered. Once the failure is repaired (on either E

Dthe common-cause failure no longer exists.

m conditions are the normal standby conditions for the diesel engines. Any normally running. warmup systems should be in service and operating, and manufacturer's recommendations for engine oil and water temperatures and other parameters should be followed.

The OPERABILITY of the minimum specified A.C. and D.C. power sources and associated distribution systems during shutdown and refueling ensures that 1) the facility can be maintained in the shutdown or refueling condition for extended time periods and 2) sufficient instrumentation and control capability is available for monitoring and maintaining the facility status.

L-2013-233 Page 19 of 37 INSERT 9 (BASES LCO 3.8.1.1)

Action g prohibits the application of LCO 3.0.4.b to an inoperable diesel generator. There is an increased risk associated with entering a MODE or other specified condition in the Applicability with an inoperable diesel generator and the provisions of LCO 3.0.4.b, which allow entry into a MODE or other specified condition in the Applicability with the LCO not met after performance of a risk assessment addressing inoperable systems and components, should not be applied in this circumstance.

L-2013-233 Page 20 of 37

'SECTION NO.:

TITLE:

TECHNICAL SPECIFICATIONS PAGr7E -

3.0 & 4.0 BASES ATTACHMENT 2 OF ADM-25.04 REVISION NO.:

LIMJTING CONDITIONS FOR OPERATION

,--,7 of 12T,:

AND SURVEILLANCE REQUIREMENTS 2

ST. LUCIE UNIT 2 F77; 3/4.0 APPLICABILITY (continued)

BASES (continued) 3.0.4 This specification establishes: limitations on MODE changes when a Limiting Condition for Operation is not met. It precludes placing the facility in a higher MODE of operation, when the requirements for a Limiting Condition for Operation are not.met and continued, noncompliance to these conditions would result in a shutdown to comply with the ACTION requirements if.a change in MODES were permitted. The purpose of this specification is to ensure that facility operation is not initiated or that higher MODES of operation are not entered when corrective action is being taken to obtain compliance with a specification by restoring equipment to. OPERABLE status or parameters to specified limits. Compliance with ACTION requirements that permit continued operation of the facility for an unlimited period of time provides an acceptable

.level of safety for continued.operation without regard to the status of the plant before or after a MODE change. Therefore, in this case, entry into an OPERATIONAL MODE or other specified condition may be made in accordance with the provisions of the ACTION requirements. The provisions of this specification should not, however, be interpreted as endorsing the failure, to exercise good practice in restoring systems or components to OPERABLE status before plant startup.

When a shutdown is required to. comply With the ACTION requirements, the provisions of Specification 3.0.4 do not apply because they would. delay placing the facility ih a lower MODE of operation.

Exceptions to this provision have been provided for a limited number of specifications when startup with inoperable equipment would rot affect plant safety. These exceptions are stated in the ACTION statements of the appropriate specifications.

The specifications of this section establish the general requirements applicable to Surveillance Requirements. These requirements are based on the Surveillance Requirements stated in the Code of Federal Regulations, 10 CFR 50.36(c)(3):

I "Surveillance requirements are requirements relating to test, calibration, or inspection to, ensure that the. necessary quality of systems and components maintained, that facility operation, will be within safety limits, and that the limiting conditions of operation will be met."

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~-4 3

L-2013-233 Page 21 of 37 INSERT 3 (BASES 3.0.4)

LCO 3.0.4 establishes limitations on changes in MODES or other specified conditions in the Applicability when an LCO is not met. It allows placing the unit in a MODE or other specified condition stated in that Applicability (e.g., the Applicability desired to be entered) when unit conditions are such that the requirements of the LCO would not be met, in accordance with LCO 3.0.4.a, LCO 3.0.4.b, or LCO 3.0.4.c.

LCO 3.0.4.a allows entry into a MODE or other specified condition in the Applicability with the LCO not met when the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time. Compliance with required Actions that permit continued operation of the unit for an unlimited period of time in a MODE or other specified condition provides an acceptable level of safety for continued operation. This is without regard to the status of the unit before or after the MODE change. Therefore, in such cases, entry into a MODE or other specified condition in the Applicability may be made in accordance with the provisions of the required Actions.

LCO 3.0.4.b allows entry into a MODE or other specified condition in the Applicability with the LCO not met after performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the. MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate.

The risk assessment may use quantitative, qualitative, or blended approaches, and the risk assessment will be conducted using the plantprogram, procedures, and criteria in place to implement 10 CFR 50.65(a)(4), which requires that risk impacts of maintenance activities to be assessed and managed. The risk assessment for the purposes of LCO 3.0.4.b, must take into account all inoperable Technical Specification equipment regardless of whether the equipment is included in the normal 10 CFR 50.65(a)(4) risk assessment scope.

The risk assessments will be conducted using the procedures and guidance endorsed by Regulatory Guide 1.182, "Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants." Regulatory Guide 1.182 endorses the guidance in Section 11 of NUMARC 93-01, "Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants." These documents address general guidance for conduct of the risk assessment, quantitative and qualitative guidelines for establishing risk management actions, and example risk management actions. These include actions to plan and conduct other activities in a manner that controls overall risk, increased risk awareness by shift and management personnel, actions to reduce the duration of the condition, actions to minimize the magnitude of risk increases (establishment of backup success paths or compensatory measures), and determination that the

L-2013-233 Page 22 of 37 proposed MODE change is acceptable. Consideration should also be given to the probability of completing restoration such that the requirements of the LCO would be met prior to the expiration of ACTIONS completion times that would require exiting the Applicability.

LCO 3.0.4.b may be used with single or multiple systems and components unavailable. NUMARC 93-01 provides guidance relative to consideration of simultaneous unavailability of multiple systems and components.

The results of the risk assessment shall be considered in determining the acceptability of entering the MODE or other specified condition in the Applicability, and any corresponding risk management actions. The LCO 3.0.4.b risk assessments do not have to be documented.

The Technical Specifications allow continued operation with equipment unavailable in MODE 1 for the duration of the completion time. Since this is allowable, and since in general the risk impact in that particular MODE bounds the risk of transitioning into and through the applicable MODES or other specified conditions in the Applicability of the LCO, the use of the LCO 3.0.4.b allowance should be generally acceptable, as long as the risk is assessed and managed as stated above. However, there is a small subset of systems and components that have been determined to be more important to risk and use of the LCO 3.0.4.b allowance is prohibited. The LCOs governing these systems and components contain notes prohibiting the use of LCO 3.0.4.b by stating LCO 3.0.4.b is not applicable.

LCO 3.0.4.c allows entry into a MODE or other specified condition in the Applicability with the LCO not met based on a note in the Specification which states LCO 3.0.4.c is applicable. These specific allowances permit entry into MODES or other specified conditions in the Applicability when the associated ACTIONS to be entered do not provide for continued operation for an unlimited period of time and a risk assessment has not been performed. This allowance may apply to all the ACTIONS or to a specific required Action of a Specification.

The risk assessments performed to justify the use of LCO 3.0.4.b usually only consider systems and components. For this reason, LCO 3.0.4.c is typically applied to Specifications which describe values and parameters (e.g., Reactor Coolant System Specific Activity), and may be applied to other Specifications based on NRC plant-specific approval.

The provisions of this Specification should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before entering an associated MODE or other specified condition in the Applicability.

The provisions of LCO 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with

L-2013-233 Page 23 of 37 ACTIONS. In addition, the provisions of LCO 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown. In this context, a unit shutdown is defined as a change in MODE or other specified condition in the Applicability associated with transitioning from MODE 1 to MODE 2, MODE 2 to MODE 3, MODE 3 to MODE 4, and MODE 4 to MODE 5.

Upon entry into a MODE or other specified condition in the Applicability with the LCO not met, LCO 3.0.1 and LCO 3.0.2 require entry into the applicable Conditions and Required Actions until the Condition is resolved, until the LCO is met, or until the unit is not within the Applicability of the Technical Specification.

Surveillances do not have to be performed to be performed on the associated inoperable equipment (or on variables outside the specified limits), as permitted by SR 4.0.4 Therefore, utilizing LCO 3.0.4 is not a violation of SR 4.0.1 or SR 4.0.4 for any Surveillances that have not been performed on inoperable equipment. However, SRs must be met to ensure OPERABILITY prior to declaring the associated equipment OPERABLE (or variable within limits) and restoring compliance with the affected LCO.

L-2013-233 Page 24 of 37 SECTION NO;:

TITLE:

TECHNICAL SPECIFICATIONS

PAGE, 3.0 & 4.0 BASES ATTACHMENT 2 OF ADM-25.04 REVISION NO.:

LIMITING CONDITIONS FOR OPERATION

',2 of 12.

AND SURVEILLANCE REQUIREMENTS ST. LUCIE UNIT 2 314.0 APPLICABILITY (continued)

BASES (continued) 4.03 (co.ntinued)

If a SR is not completed within the allowed delay period, then the equipment is considered inoperable or the variable is. considered outside the specified limits and the completion times of the required ACTION(s) for the applicable Limiting Condition for Operation begin immediately upon expiration of the delay period. If a surveillance is failed within the delay period, then the equipment is inoperable, or the variable is outside the specified limits. and the completion times of the required ACTION(s). for the applicable Limiting Condition for Operation begin immediately upon the failure of the surveillance.

Completion of the SR within the delay period. allowed by this specification, or within the completion time. of the ACTIONS, restores compliance with SR.

S 4.0,1..

"v-"4-4.0.4*

This specification establishes the requirement that all applicable surveillances

.must be met before entry into.an OPERATIONAL MODE* or other condition, or

.operation specified in the Applicability statement... The purpose of this

,specification is to -ensure that System and component OPERABILITY irequirements or parameter limits are met before entry into a MO DE or condition

'for which these systems and components ensure safe operation of the facility.

This provision applies to changes in OPERATIONAL MODES or other specified conditions associated with plant shutdown as. well as startup.

Under the provisions of this specification, the applicable Surveillance Requirements must be performed within the specified surveillance interval to ensure that the Limiting Conditions for Operation are met during initial plant startup or following a plant outage.

When a shutdown is required to comply with ACTION requirements, the 1

Sprovisions of Specification 4.0.A do not apply because this would delay placing the: facility in a lower MODE of oprtin 4.0.5 This specification ensures that inservice inspection of ASME Code Class 1, 2 and 3 components will be. performedin accordance with a periodically updated version of Section XI of the ASME. Boiler and Pressure Vessel Code and Addenda as, required by 10 CFR 50.55a. Relief from any of the above requirements.has been provided in writing by the Commission and is not part of these Technical Specifications.

L-2013-233 Page 25 of 37 INSERT 4 (BASES SR 4.0.4)

SR 4.0.4 establishes the requirement that all applicable SRs must be met before entry into a MODE or other specified condition in the Applicability.

This Specification ensures that system and component OPERABILITY requirements and variable limits are met before entry into MODES or other specified conditions in the Applicability for which these systems and components ensure safe operation of the unit. The provisions of this Specification should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before entering an associated MODE or other specified condition in the Applicability.

A provision is included to allow entry into a MODE or other specified condition in the Applicability when an LCO is not met due to Surveillance not being met in accordance with LCO 3.0.4.

However, in certain circumstances, failing to meet an SR will not result in SR 4.0.4 restricting a MODE change or other specified condition change. When a system, subsystem, division, component, device, or variable is inoperable or outside its specified limits, the associated SR(s) are not required to be performed, per SR 4.0.1, which states that surveillances do not have to be performed on inoperable equipment. When equipment is inoperable, SR 4.0.4 does not apply to the associated SR(s) since the requirement for the SR(s) to be performed is removed. Therefore, failing to perform the Surveillance(s) within the specified frequency does not result in an SR 4.0.4 restriction to changing MODES or other specified conditions of the Applicability. However, since the LCO is not met in this instance, LCO 3.0.4 will govern any restrictions that may (or may not) apply to MODE or other specified condition changes. SR 4.0.4 does not restrict changing MODES or other specified conditions of the Applicability when a Surveillance has not been performed within the specified frequency, provided the requirement to declare the LCO not met has been delayed in accordance with SR 4.0.3.

The provisions of SR 4.0.4 shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS. In addition, the provisions of SR 4.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown. In this context, a unit shutdown is defined as a change in MODE or other specified condition in the Applicability associated with transitioning from MODE 1 to MODE 2, MODE 2 to MODE 3, MODE 3 to MODE 4, and MODE 4 to MODE 5.

L-2013-233 Page 26 of 37 SECTION NO.:

PAGE',,

TITLE:

TECHNICAL SPECIFICATIONS 3/4.4 BASES. ATTACHMENT 6 OF ADM-25.04 21 of 37 REVISION NO.:

REACTOR COOLANT SYSTEMo 9

ST. LUCIE UNIT 2 3/4.4 REACTOR COOLANT SYSTEM (continued)

BASES (continued) 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE (continued) 3/4.4.6.1 LEAKAGE DETECTION SYSTEMS (continued)

ACTION c With both gaseous and particulate containment atmosphere radioactivity monitoring instrumentation channels inoperable, alternative action is required. Either grab samples of the containment atmosphere must be taken and analyzed, or water inventory balances, must be performed to provide alternate periodic information. With a sample obtained and analyzed or an inventory balance performed every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , the reactor may be operated for up to 30 days to allow restoration of at least one of the radioactivity monitors.

The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval-provides periodic information that is adequate to detect leakage.. A Note is added allowing that the RCS water inventory balance is not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishing steady state operation (stable temperature, power level, pressurizer and makeup tank levels, makeup and letdown, and RCP seal injection and return flows). The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months allowance provides sufficient time to collect and process all necessary data after stable plant conditions are established. The 30 day Completion Time recognizes at least one other form of leakage-detection is available.

ACTION d If all required monitors are inoperable, no automatic means of monitoring leakage are available and immediate plant shutdown in accordance with LCO 3.0.3 is required.

tt t*

-efT he--e.t0ed-m tr---.

.. s-epefar--le.

SURVEILLANCE SR 4.4.6.1 REQUIREMENTS SR 4.4.6.1 requires the performance of CHANNEL CHECKs, CHANNEL FUNCTIONAL TESTs, and CHANNEL CALIBRATIONs of the required leakage detection monitors, These checks give reasonable confidence the channels are operating properly.

L-201 3-23 3 Page 27 of 37 SECTION NO::;

TITLE:

TECHNICAL SPECIFICATIONS 3/4.4 BASESAATTACHMENT 6 OF ADM-25.04 REVISION NO.:

REACTOR COOLANT SYSTEM 9

ST. LUCIE UNIT 2 3/4.4 REACTOR COOLANT SYSTEM (continued)

BASES (continued) 3/4.4.8 SPECIFIC. ACTIVITY The maximum allowable doses to an individual at the exclusion area boundary. (EAB) distance for2 hours following an accident, or at the.low

.population zone (LPZ) outer boundary distance for the radiological release duration, are specified in 10 CFR.50.67 for design basis accidents using the alternative source term methodology and in Branch Technical Position 11-5 for the waste gas decay tank rupture accident. Dose limits to control. room operators are given in 10 CFR 50.67 and in GDC 19 The RCS specific activity LCO limits the allowable concentration of radionuclides in the reactor coolant to ensure that the dose consequences of limiting. accidents do not exceed appropriate regulatory offsite and Control room dose acceptance criteria. The LCO contains specific activity limits for both DOSE EQUIVALENT (DE) 1-131 and DOSE EQUIVALENT (DE) XE-1.33.

The radiological dose assessments assume the specific activity of the reactor coolant is at the LCO limits, and an existing reactor coolant steam generator tube leakage rate at the applicable Technical Specification limit. The radiological dose assessments, assume the specific activity of the secondary coolant is at its limit as specified in LCO 3.7.1.4, "Plant Systems - Activity."

The ACTIONS allow operation when DOSE EQUIVALENT 1-1.31 is greater than 1.0 pCi/gram and less than 60 pCi/gram. The ACTIONS require,ns1 within four hours and every four hours fdllowing to establish a trend.

se.r4 One surveillance requires the determination of the DE.XE-133 specific activity as a measure of noble gas. specific activity of the reactor coolant at least once per 7 days.

A second surveillance.is performed to ensure that iodine specific activity remains within the LCO limit once per 14 days during normal operation and following rapid power changes when iodine spiking is more apt to occur. The frequency between two and six hours after a power change of greater than 15% RATED THERMAL POWER within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period, is, established because the iodine levels peak during this time following iodine spike i.nitiation.

The RCS specific activity satisfies Criterion 2 of 1O.CFR 50.36(c)(2)(ii).

L-2013-233 Attachment 5

Page 27 of 37 CD

L-2013-233 Page 28 of 37 INSERT 5 (BASES LCO 3.4.8)

A note permits the use of the provisions of LCO 3.0.4.c. This allowance permits entry into the applicable MODE(S) while relying on the ACTIONS. This allowance is acceptable due to the significant conservatism incorporated into the specific activity limit, the low probability of an event that is limiting due to exceeding this limit, and the ability to restore transient specific activity excursions while the plant remains at, or proceeds to power operations.

L-2013-233 Page 29 of 37 SECTION NO;:

TITLE:

TECHNICAL SPECIFICATIONS' PAGE:,---'

3/4.4 BASES ATTACHMENT 6 OF ADM-25.04 35 of 37 REVISION NOý:

REACTOR COOLANT SYSTEM 9

ST. LUCIE UNIT 2 3/4.4 REACTOR COOLANT SYSTEM (continued)

BASES (continued) 3/4.4.9 PRESSUREITEMPERATURE LIMITS (continued)

The limitations imposed on the pressurizer heatup and cooldown rates and spray water temperature differential are provided to assure that the pressurizer is operated within the design criteria assumed for the fatigue analysis performed in accordance with the ASME Code requirements.

The.OPERABILITY of two PORVs, two SDCRVs or an RCS vent opening of greater than 3.58 square inches ensures that the RCS will be protected' from pressure transients which could exceed the liniits of Appendix G to 10 CFR Part 50 when one or more of the RCS cold leg temperatures are less than or equal to the LTOP temperatures. The Low Temperature Overpressure Protection System has adequate relieving capability to protect the RCS from overpressurization when the transient is limited to either (1) a safety injection actuation in a water-solid RCS with the pressurizer heaters energized or (2) the start of.an idle RCP with the secondary water temperature of the steam generator less than or equal to 40°F above the RCS cold leg temperatures

,._bý

ýizer water-solid.

3/4.4.10 ýXO

ýOLANT 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 ll.b.1 of NUREG-0737, "Clarification of TMI Action Plan Requirements," November 1980.

L-2013-233 Page 30 of 37 INSERT 6 (BASES Unit 2 LCO 3.4.9)

LCO 3.4.9.3 Action d prohibits the application of LCO 3.0.4.b to inoperable PORVs used for LTOP. There is an increased risk associated with entering MODE 4 from MODE 5 with PORVs used for LTOP inoperable and the provisions of LCO 3.0.4.b, which allow entry into a MODE or other specified condition in the Applicability with the LCO not met after performance of a risk assessment addressing inoperable systems and components, should not be applied in this circumstance.

L-2013-233 Page 31 of 37 SECTION NO.:

TITLE:

TECHNICAL SPECIFICATIONS PAGE" 3/4.5.

BASES ATTACHMENT 7 OF ADM-25.04

, of 7'. :

REVISION NO.:

EMERGENCY CORE COOLING SYSTEMS (ECCS).

2 ST. LUCIE UNIT 2 3/4.5 EMERGENCY-CORE COOLING SYSTEMS (ECCS) (continued)

BASES (continued) 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS The OPERABILITY of two separate and independent ECCS subsystems ensures that sufficient emergency core: cooling capability will be available in the event of a LOCA assuming the loss. of one subsystem through any single failure consideration. Either subsystem operating in conjunction with the safety injection tanks is capable of supplying sufficient core cooling to limit the. peak cladding temperatures within acceptable limits for all postulated break sizes ranging from the double-ended break of the largest RCS hot leg pipe downward. In addition, each ECCS subsystem provides long-term core cooling capability in the recirculation mode during the accident recovery period.

TS 3.5.2.c and 3.5.3 require that ECCS subsystem(s) have an independent OPERABLE flow path capable of'automatically transferring suction to the containment on a Recirculation Actuation Signal. The containment sump is defined as the area of Containment below the minimum flood level in the vicinity of the Containment sump strainers. Therefore, the LCOs are satisfied when an independent OPERABLE flow path to the containment sump strainer is available.

TS 3.5.2.d requires that an ECCS subsystem(s) have an OPERABLE charging pump and associated flow path from the BAMT(s). Reference to TS 3.1.2.2 requires that the one charging pump flow path is from the BAMT(s) through the boric acid makeup pump(s). The second charging pump flowpath is from the BAMT(s) through the gravity feed valves.

TS 3.5.2, ACTION a. 1. provides an allowed outage/action completion time (AOT) of up to 7 days from initial discovery of failure to meet the LCO provided the affected ECCS subsystem is inoperable only because its associated LPSI train is inoperable. This 7 day AOT is based on the findings of a deterministic and probabilistic safety analysis and is referred to as a "risk-informed" AOT extension. Entry into thisACTION requires that a.risk assessment be performed in accordance with the Configuration Risk Management Program (CRMP) which is described in the Administrative Procedure (ADM-17.08) that implements the Maintenance Rule pursuant to 10 CFR 50.65.

In Mode 3 with RCS pressure < 1750 psia and in. Mode 4, one OPERABLE ECCS subsystem is acceptable without single failure consideration on the basis of the stable reactivity Condition of the reactor and the limited core cooling requirements.

L-2013-233 Page 32 of 37 INSERT 7 (BASES Unit 2 LCO 3.5.3)

LCO 3.5.3 Action c prohibits the application of LCO 3.0.4.b to inoperable ECCS High Pressure Safety Injection subsystem. There is an increased risk associated with entering MODE 4 from MODE 5 with an inoperable ECCS High Pressure Safety Injection subsystem and the provisions of LCO 3.0.4.b, which allow entry into a MODE or other specified condition in the Applicability with the LCO not met after performance of a risk assessment addressing inoperable systems and components, should not be applied in this circumstance.

L-2013-233 Page 33 of 37 S

C INNO:PAGE".-:..

SECTION:NO.:

TITLE:

TECHNICAL SPECIFICATIONS GE 3/4.7 BASES ATTACHMENT 9 OF ADM-25.04 4 of 16""

REVISION NO.:

PLANT SYSTEMS 6

ST. LUCIE UNIT 2 3/4.7 PLANT SYSTEMS (continued)

BASES (continued) 3/4.7.1 TURBINE CYCLE (continued) 3/4.7.1.1 SAFETY VALVES (continued) 107.0 =

Power Level-High Trip Setpoint for two loop operation.

0.9 = Equipment processing uncertainty

.X = Total relieving capacity of all safety valves per steam line in lbs/hour (6.247 x 106 lbs/hr)

Y = Maximum relieving capacity of any one safety valve in lbs/hour (7.74 x 10 lbs/hr)

Surveillance Requirement 4.7.1.1 verifies the OPERABILITY of the MSSVs. by the. verification of each MSSV lift setpoint in accordance with the Inservice Testing Program. The MSSV setpoints are 1000 psia +/-3% (4 valves each header) and 1040 psia +2%/-3% (4 valves each header) for OPERABILITY; however, the. valves are reset to 1000 psia +/- 1 % and 1040 psia +/- 1 %,

respectively, during the Surveillance to allow for drift. The LCO is expressed in units of psig for consistency with implementing procedures,

_The-MSSVi mie er4e tndefrio ty-lhis'ttes-netryi.

s ereta,,ý m in-Mef* -'p-*

k toprerforrmie-n-:

em,* r t

3/4.7.1.2.

AUXILIARY FEEDWATER SYSTEM The Auxiliary Feedwater (AFW) System automatically supplies feedwater to the steam generators to remove decay heat from the Reactor Coolant. System upon the loss of normal feedwater supply. The AFW System consists of two motor driven AFW pumps and one steam turbine driven pump configured into three trains.

Each motor driven pump provides 100% of AFW flow capacity; the turbine*

driven pump provides 100%,of the required capacity to the steam, generators as assumed in the accident analysis. Each motor driven AFW pump is powered from an independent Class 1 E power supply and feeds one steam generator, although each pump has the capability to be-realigned from the control room to feed the other steam generator. One pump at full flow is sufficient to remove decay heat and cool the unit to Shutdown Cooling (SDC)

System entry conditions.

L-2013-233 Page 34 of 37 SECTION:NO.:

TITLE:

TECHNICAL SPECIFICATIONS PAGE.

3/4.7 BASES ATTACHMENT 9 OF ADM-25.04 5 of 16, REVISION NO.:

PLANT SYSTEMS 6

ST. LUCIE UNIT2 2 314.7 PLANT SYSTEMS (continued)

BASES (continued) 3/4.7.1 TURBINE CYCLE (continued) 3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM (continued)

The steam turbine-driven AFW pup receives steam from either main steam header upstream of the main steam, isolation valve. Each of the steam feed lines will supply 100% of the requirements of the turbine driven AFW pump.

The turbine driven AFW pump supplies a common header capable of feeding both steam generators, with DC powered control valves actuated to the appropriate steam generator by the Auxiliary Feedwater Actuation System (AFAS).

The. AFW System supplies feedwater to the steam generators during normal unit startup, shutdown, and hot standby conditions.

The: AFW System mitigates the consequences.of anyevent with a loss of normal feedwater. The limiting Design Basis Accidents and transients for the AFW System are as follows:

1.

Feedwater Line Break, and

,,of normal feedwater.

u equirement (SR) 4.7.1.2.d verifies that each AFW pump's developed head at the flow test point is greater than or equal to the required developed head ensures that AFW pump performance has not degraded during the cycle. Flow and differential head are normal tests of pump performance required by the ASME Code. Because it is. undesirable to introduce cold.AFW into the steam generators while they are operating, this testing is performed on recirculation flow. this test confirms one point on the pump design curve and is indicative of overall performance. Such inservice tests confirm component Operability, trend performance, and detect incipient failures by indicating abnormal performance. Performance of-inservice testing, discussed in the ASME Code, at 3 month intervals satisfies this requirement. This SR is modified to defer performance Until suitable test conditions are established for the steam turbine-driven AFW pump within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after entering Mode 3 and prior to entering Mode 2.

L-2013-233 Page 35 of 37 INSERT 8 (BASES Unit 2 LCO 3.7.1.2)

Action d prohibits the application of LCO 3.0.4.b to an inoperable AFW train.

There is an increased risk associated with entering a MODE or other specified condition in the Applicability with an AFW train inoperable and the provisions of LCO 3.0.4.b, which allow entry into a MODE or other specified condition in the Applicability with the LCO not met after performance of a risk assessment addressing inoperable systems and components, should not be applied in this circumstance.

L-2013-233 Page 36 of 37 SECTION NO.:

PG,---

TITLE:

TECHNICAL SPECIFICATIONS PAGEN-.

3/4.8 BASES ATTACHMENT 10 OF ADM-25.04 4 of 8 REVISIONNO,:

ELECTRICAL POWER SYSTEMS 3

ST. LUCIE UNIT 2 3/4.8 ELECTRICAL POWER SYSTEMS (continued)

BASES (continued) 3/4.81A, 3/4.8.2 and 3/4.8.3 A.C. SOURCES, D.C. SOURCES and ONSITE POWER DISTRIBUTION. SYSTEMS (continued)

The four hour completion time upon discovery that an opposite train required feature is inoperable is to provide assurance that a loss of offsite power, during the period that a EDG is inoperable, does not result in a complete loss of safety function of critical redundant required features.

The four-hour completion time allows the operator time to evaluate and repair any discovered inoperabilities. This completion time also allows for an exception to the normal "time zero" for beginning the allowed outage time "clock." The four hour completion time 0nly begins on discovery that both an inoperable EDG: exists and a required feature on the other train is inoperable.

TS:3.8.1.1, ACTION "b" provides an allowed outage/action. completion time (AOT) of up to 1.4 days to restore a single inoperable diesel generator to operable status. This AOT is based on the findings of a deterministic and probabilistic safety analysis and is referred to as a "risk-informed" AOT.

Entry into this action requires that a risk assessment be performed in accordance with the Configuration. Risk Management Program (CRMP),

which is described in the Administrative Procedure that implements the Maintenance Rule pursuant.to 1.0 CFR 50.65.

All EDG inoperabilities must be investigated for common-cause failures regardless of how long the EDG inoperability persists. When one diesel generator is inoperable, required ACTIONS 3.8.1.lb and 3.8.1.1.c provide

'an allowance to avoid unnecessary testing of EDGs. If it can be determined that the cause of the inoperable EDG does not exist on the remaining OPERABLE EDG, then SR 4.8.1.1.2.a.4 does not have to be performed. Eight (8) hours is reasonable to confirm that the OPERABLE EDG is not affected by the same problem as the inoperable.EDG. If it cannot otherwise be determined that the cause of the initial inoperable EDG does not exist on the remaining EDG, then satisfactory performance of SR 4.8.1.1.2.a.4 suffices to provide assurance of continued OPERABILITY of that EDG. If the cause of the initial inoperability exists on the remaining OPERABLE EDG, that EDG would also be declared inoperable upon discovery, and ACTION 3.8.1.1.e would be entered. Once the failure is repaired (on either EDG), the common-cause failure no longer exists.

D9

L-2013-233 Page 37 of 37 INSERT 9 (BASES LCO 3.8.1.1)

Action g prohibits the application of LCO 3.0.4.b to an inoperable diesel generator. There is an increased risk associated with entering a MODE or other specified condition in the Applicability with an inoperable diesel generator and the provisions of LCO 3.0.4.b, which allow entry into a MODE or other specified condition in the Applicability with the LCO not met after performance of a risk assessment addressing inoperable systems and components, should not be applied in this circumstance.

v t e Letter Sequence Request
TAC:MF3618, Increase Flexibility in Mode Restraints, TSTF-3 (Approved, Closed)
Initiation Request, Request Acceptance... Administration Questions Answers 29 May 2014 Results Approval Other:
MONTHYEAR2014-05-29 [Table View]

L-2013-233, Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process

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L-2013-233, Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process

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