Text

Amends 153 & 91 to Licenses DPR-67 & NPF-16,respectively, Relocating Inservice Testing Program Requirements from TS 4.0.5 to Administrative Controls Section in Units 1 & 2 TS
	ML17229A657
Person / Time
Site:	Saint Lucie
Issue date:	02/25/1998
From:	Hebdon F; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML17229A658	List: ML17229A657; ML17229A659;
References
	NUDOCS 9803110264
	Download: ML17229A657 (65)
	v • d • e

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 LO IDA P WE I

HT COMPANY D

CKET 0 50-335 T. LU DMENT UNIT NO.

PE TIN ICE E

Amendment No.153 License No. DPR-67 The Nuclear Regulatory Commission (the Commission) has found that:

A.

The. application for amendment by Florida Power & Light Company, (the licensee), dated August 22, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facilitywilloperate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment'can be conducted without endangering the health and safety of the public, and (ii) that such activities willbe conducted in compliance with the Commission's regulations; D.

The issuance of this amendment willnot be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

9803ii0264 980225 PDR ADQCK 05000335.

PDR Accordingly, Facility Operating License No. DPR-67 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph 2.C.(2) to read as follows:

(2)

Technical c'

io s The Technical Specifications contained in Appendices A and B, as revised through Amendment No.153, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION Frederick J. Hebdon Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

February 25, 1998

I I'

TTAC MENT LI ENSE A END NT N 3

T FACIL PE NG LICEN DPR-7 DOC ET NO. 50-3 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.

The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

C e

P 3/4 0-2 3/4 0-3 3/4 1-12 3/4 1-13 3/4 1-14 3/4 1-15 3/4 4-2 3/4 4-3 3/4 5-5 3/4 6-15a 3/4 6-19 3/4 6-26 3/4 7-1 3/4 7-9 B 3/4 0-8 B 3/4 4-2 6-1 5c 3/4 0-2 3/4 0-3 3/4 1-12 3/4 1-13 3/4 1-14 3/4 1-15 3/4 4-2 3/4 4-3 3/4 5-5 3/4 6-15a 3/4 6-19 3/4 6-26 3/4 7-1 3/4 7-9 B 3/4 0-8 B 3/4 4-2 6-15c

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4.0.1 Surveillance Requirements shall be applicable during the OPERATIONALMODES or other conditions specified for individual LimitingConditions for Operation unless otherwise stated in an individual Surveillance Requirement.

4 4.0.2 Each Surveillance Requirement shall be performed within the specified sutveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

4.0.3 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 LimitingCondition for Operation. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Surveillance Requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONALMODE or other specified applicability condition shall not be made unless the Surveillance Requirement(s) associated with the LimitingCondition for Operation have been performed within the stated surveillance interval or as otherwise specified. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.

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 1 3/4 0-2 Amendment No. 95, 48, 99, e8,4',

153

4.0.5 (Continued) d.

Performance of the above inservice inspection activities shall be in addition to other specified Surveillance Requirements e.

Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.

ST. LUCIE-UNIT1 3f4 0-3 Amendment No. 99,4' 53

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P IVTY 0 OLS GING PUM S - S UTDO 3.1.2.3 At least one charging pump or high pressure safety injection pump in the boron injection flowpath required OPERABLE pursuant to Specification 3.1.2.1 shall be OPERABLE and capable of being powered from an OPERABLE emergency bus.

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1 With no charging pump or high pressure safety injection pump* OPERABLE, suspend all operations involving CORE ALTERATIONSor positive reactivity changes until at least one of the required pumps is restored to OPERABLE status.

4.1.2.3 At least one of the above required pumps shall be demonstrated OPERABLE by verifying the charging pump develops a flowrate of greater than or equal to 40 gpm or the high pressure safety injection pump develops a total head of greater than or equal to 2571 ft.

when tested pursuant to the Inservice Testing Program.

The flowpath from the RWT to the RCS via a single HPSI pump shall be established only if:

(a) the RCS pressure boundary does not exist, or (b) RCS pressure boundary integrity exists and no charging pumps are operable.

In the latter case:

1) all charging pumps shall be disabled;

2) heatup and cooidown rates shall be limited in accordance with Figure 3.1-1b; and 3) at RCS temperatures below 115'F, any two of the followingvalves in the operable HPSI header shall be verified closed and have their power removed:

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HCV-3617 HCV-3627 HCV-3637 HCV<647 ST. LUCIE-UNIT.1 3I'4 1-12 Amendment No.. 68, e1, 99, 4e4,+e,~,m, 153

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IN8 3.1.2.4 At least two charging pumps shall be OPERABLE.

MODES1,2,3 and 4.

QQTI~O With only one charging pump OPERABLE, restore at least two charging pumps to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT STANDBYwithin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore at least two charging pumps to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

4.1,2.4 At least two charging pumps shall be demonstrated OPERABLE by verifying that each pump develops a flowrate of greater than or equal to 40 gpm when tested pursuant to the Inservice Testing Program.

ST. LUCIE-UNIT 1 3/4 1-13 Amendment No.~

153

1

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WN 3.1.2.5 At least one boric acid pump shall be OPERABLE ifonly the flowpath through the boric acid pump in Specification 3.1.2.1a above, is OPERABLE.

S MODES d

With no boric acid pump OPERABLE as required to complete the flowpath of Specification 3.1.2.1a, suspend all operations involving CORE ALTERATIONSor positive reactivity changes until at least one boric acid pump is restored to OPERABLE status.

4.1.2.5 The above required boric acid pump shall be demonstrated OPERABLE by verifying that on recirculating flow, the pump develops a discharge pressure of 2 75 psig when tested pursuant to the Inservice Testing Program.

ST. LUCIE-UNIT 1 Gf4 1-14 Amendment N0.99, 153

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- OPERAT 3.1.2.6 At least the boric acid pump(s) in the boron injection flowpath(s) required OPERABLE pursuant to Specification 3.1.2.2a shall be OPERABLE ifthe flowpath through the boric acid pump in Specification 3.1.2.2a is OPERABLE.

~OA: MODES.,

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With one boric acid pump required for the boron injection flowpath(s) pursuant to Specification 3.1.2.2a inoperable, restore the boric acid pump 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-withinthe next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following30 hours.

4.1.2.6 The above required boric acid pump(s) shall be demonstrated OPERABLE by verifying that on recirculating flow, the pump develops a discharge pressure of > 75 psig when tested pursuant to the Inservice Testing Program.

ST. LUCIE-UNIT 1 3/4 1-15 Amendment N0.99, 153

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V V S-S U D 3.4.2 A minimum of one pressurizer code safety valve shall be OPERABLE with a liftsetting of 2500 PSIA+ 1%.

II MODES 4 and 5.

With no pressurizer code safety valve OPERABLE, immediately suspend all operations involving positive reactivity changes and place an OPERABLE shutdown cooling loop into operation.

4.4.2 No additional Surveillance Requirements other than those required by the Inservice Testing Program.

ST. LUCIE-UNIT1 3/4 4-2 Amendment N0.99, 153

II ACT C 0 V LVES-0 E

3.4.3 Allpressurizer code safety valves shall be OPERABLE with a liftsetting of 2500 PSIA 2 1%.

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M~IO With no pressurizer code safety valve inoperable, either rest'ore the inoperable valve to OPERABLE status within 15 minutes or be in HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4.3 No additional Sutveillance Requirements other than those required by the Inservice Testing Program.

ST. LUCIE-UNIT 1 3/4 4-3 Amendment No.eo, 153

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EMERGENCY CO E

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At least once per 18 months, during shutdown, by:

1.

Verifyingthat each automatic valve in the flowpath actuates to its correct position on a Safety Injection Actuation Signal.

2.

Verifying that each of the followingpumps start atuomatically upon receipt of a Safety Injection Actuation SignaI; a.

High-Pressure Safety Injection Pump.

b.

Low-Pressure Safety Injection Pump.

3.

Verifyingon a Sump Recirculation Actuation Test Signal, the containment sump isolation valves open and the recirculation valve to the refueling water tank closed.

f.

By verifying that each of the following pumps develops the specified total developed head on recurculation flowwhen tested pursuant to the lnservice Testing Program.

1.

High-Pressure Safety Injection pumps: greater than or equal to 2571 ft.

2.

Low-Pressure Safety Injection pumps: greater than or equal to 350 ft.

ST. LUCIE-UNIT 1 3/4 5-5 Amendment No. &8,99, 153

4.6.2.1 Each containment spray system shall be demonstrated OPERABLE:

At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flowpath that is not locked, seaied, or otherwise secured in position, is positioned to take suction from the RWT on a Containment Pressure

- - High High test signal

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b.

By verifying that on recirculation flow, each spray pump develops a discharge pressure oft 200 psig, when tested pursuant to the Inservice Testing Program.

ST. LUCIE-UNIT1 Amendment No.~,

153

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,4.6.3.1.2 Each containment isolation valve shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:

a.

Verifyingthat on a Containment Isolation test signal, ancVor SIAS test signal; each isolation valve actuates to its isolation position.

4.6.3.1.3 The isolation time of each power operated or automatic containment isolation valve shall be determined to be within its limits when tested pursuant to the Inservice Testing Program.

ST. LUCIE-UNIT 1 3/4 6-19 Amendment No. 98, ~153

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E EFV LVE 3.6.5.1 The containment vessel to annulus vacuum relief valves shall be OPERABLE with an actuation'setpoint of 2.25+ 0.25 inches Water Gauge differential.

~EZILII MODES.,

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With one containment vessel to annulus vacuum relief valve inoperable, restore the valve to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT STANDBYwithin 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 .

4.6.5.1 No additional Surveillance Requirements other than those required by the Inservice Testing Program and at least once per 3 years verify that the vacuum relief valves open fullywithin 8 seconds at 2.25 2 0.25 inches Water Gauge differential.

ST. LUCIE-UNIT1 3/4 6-26 Amendment No. 99,~

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"MSS VVVVV VV 3.7.1.1 Allmain steam line code safety valves shall be OPERABLE with liftsettings as specified in Table 4.7-1.

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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 STANDBYwithin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following30 hours.

b.

The piovisions of Specification 3.0.4 are not applicable.

- 4.7.1

~ 1 No additional Surveillance Requirements other than those required by the Inservice Testing Program.

ST. LUCIE-UNIT 1 St4 7-1 Amendment N0.99, 153

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STEAM LINE SO A VES 3.7.1.5 Each main steam line isolation valve shall be OPERABLE.

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MODE 1 MODE 2 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 STANDBYwithin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

With one or both main steam isolation 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 following24 hours.

The provisions of Specification 3.0.4 are not applicable.

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 Inseryice Testing Program.

ST. LUCIE-UNIT1 3/4 7-9 Amendment No. 98,+H; 153

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I BL Suiveillance Requirements do not have to be performed on inoperable equipment because the ACTION requirements define the remedial measures that apply. However, the Surveillance Requirements have to be met to demonstrate that inoperable equipment has been restored to OPERABLE status.

4.0.4 This specification establishes the requirement that all applicable surveillances must be met before entry into an OPERATIONALMODE or other condition or operation specified in the Applicabilitystatement.

The purpose of this specification is to ensure that system and component OPERABILITYrequirements or parameter limits are met before entry into a MODE or condition forwhich these systems and components ensure safe operation of the facility. This provision applies to changes in OPERATIONALMODES 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 sutveillance 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 placing the facilityin a lower MODE of operation.

4.0.5 This specification ensures that inservice inspection and testing of ASME Code Class 1, 2 and 3 components willbe performed in accordance with a periodically updated version of Section XIof 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 a part of these Technical Specifications.

ST. LUCIE-UNIT1 B 3/4 0-8 Amendment No.98 1 53

E CTO COOLAN 4.4.2 and 3/4.4.3 A

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ed During operation, all pressurizer code safety valves must be OPERABLE to prevent the RCS from being pressurized above its safety limitof 2750 psia. The combined relief capacity of these valves is sufficient to limitthe Reactor Coolant System pressure to within its Safety Limitof 2750 psia following a complete loss of turbine generator load while operating at RATED THERMALPOWER and assuming no reactor trip until the first Reactor Protective System trip setpoint (Pressurizer Pressure-High) is reached (i.e., no credit is taken for a direct reactor trip on the loss of turbine) and also assuming no operation of the pressurizer power operated relief valve or steam dump valves.

Demonstration of the safety valves'ift settings willoccur only during shutdown and willbe performed in accordance with the provisions of the Inservice Testing Program.

/4.4.4 PRESSURIZE A steam bubble in the pressurizer ensures that the RCS is not a hydraulically solid system and is capable of accommodating pressure surges during operation. The steam bubble also protects the pressurizer code safety valves and power operated relief valve against water relief. The power operated relief valve and steam bubble function to relieve RCS pressure during all design transients.

Operation of the power operated relief valve in conjunction with a reactor trip on a Pressurizer-Pressure-High signal minimizes the undesirable opening of the spring-loaded pressurizer code safety valves. The required pressuzier heater capacity is capable of maintaining natural circulation sub~oling. Operability of the heaters, which are powered by a diesel generator bus, ensures ability to maintain pressure control even with loss of offsite power.

A G

One OPERABLE steam generator provides sufficient heat removal capability to remove decay heat after a reactor shutdown. The requirement fortwo steam generators capable of removing decay heat, combined with the requirements of Specifications 3.7.1.1, 3.7.1.2 and 3.7.1'.3 ensures adequate decay heat removal capabilities for RCS temperatures greater than 325'F ifone steam generator becomes inoperable due to signal failure considerations.

Below 325'F, decay heat is removed by the shutdown cooling system.

The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS willbe maintained.

The program for inservice inspection of steam generator tubes is based on a modification of Regulatoiy Guide 1.83, Revision 1. Insetvice inspection of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical damage or progressive degradation due to design manufacturing erron, or in-service conditions that lead to corrosion.

Inseivice inspection of Steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that corrective measures can be taken.

ST. LUCIE-UNIT 1 B-3/4 4-2 Amendment No.28,87,66,$ t

The provisions of T.S. 4.0.2 do not apply to test frequencies in the Containment Leak Rate Testing Program.

The provisions of T.S. 4.0.3 are applicable to the Containment Leak Rate Testing Program.

This program provides controls for inservice testing of ASME Code Class 1, 2 and 3 components (pumps and valves). The program shall include the following:

a.

Testing frequencies specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as follows:

ASME Boiler and Pressure Vessel Code and applicable Addenda terminology for Required Frequencies for performing Weekly Monthly.

Quarterly or evety 3 months Semiannually or every 6 months Eveng 9 months Yearly or annually Biennially or every 2 years At least once per 7 days At least once per 31 days At least once per 92 days At least once per 184 days At least once per 276 days At least once per 366 days At least once per 731 days b.

The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing Inservice testing activities; c.

The provisions of Specification 4.0.3 are applicable to inservice testing activities; and d.

Nothing in the ASME Boiler and Pressure Vessel Code* shall be construed to supersede the requirements of any technical specification.

Where ASME Boiler and Pressure Vessel Code is referenced it also refers to the applicable portions of ASME/ANSIOM-Code, "Operation and Maintenance of Nuclear Power Plants" with applicable addenda, to the extent it is referenced in the Code.

6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the NRC.

Asummary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal or hydraulic performance of the plant.

ST. LUCIE-UNIT1 Amendment No. 449, 153

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 2055&4001 RID P

ER IGH MPANY LANDO TILI I

SION OF THE CITY OF 0 ND FLORIDA.

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9 ST. LUCIE LA T E

D E T OFCIL ING L GENS Amendment No. 91 License No. NPF-16 The Nuclear Regulatory Commission (the Commission) has found that:

The application for amendment by Florida Power & Light Company, et al. (the licensee), dated August 22, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facilitywilloperate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment willnot be inimical to the common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

Accordingly, Facility Operating License No. NPF-16 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph 2.C.2 to read as follows:

2.

Technical

'f io s The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 91, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORYCOMMISSION Frederick J. Hebd n, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

February 25, 1998

l I

TA ENT TO LICENSE AMENDMENTN0.91 T

F CILITYOPER G LICENS NO F-1 DOCKET NO. 50-389 Replace the following pages of the Appendix "A"Technical Specifications with the enclosed pages.

The revised, pages are identified by amendment number and contain vertical lines indicating the area of change.

3/4 0-2 3/4 0-3 3/4 1-9 3/4 1-10 3/4 1-11 3/4 1-12 3/4 4-7 3/4 4-8 3/4 4-36 3/4 5-5 3/4 6-15a 3/4 6-17 3/4 6-20 3/4 6-26 3/4 7-1 3/4 7-9 3/4 7-10 B 3/4 0-6 B 3/4 4-2 6-15c 3/4 0-2.

3/4 0-3 3/4 1-9 3/4 1-10 3/4 1-11 3/4 1-12 3/4 4-7 3/4 4-8 3/4 4-36 3/4 5-5 3/4 6-15a 3/4 6-17 3/4 6-20 3/4 6-26 3/4 7-1 3/4 7-9 3/4 7-10 B 3/4 0-6 B 3/4 4-2 6-1 5c

,4.0.1 Surveillance Requirements shall be applicable during the OPERATIONALMODES or other conditions specified for individual LimitingConditions for Operation unless otherwise stated in an individual Surveillance Requirement.

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 Failure to perform a Surveillance Requirement within the allowed sutveillance interval, defined by Specification 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a Limiting Condition for Operation. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Surveillance Requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONALMODE or other specified applicability condition shall not be made unless the Sutveillance Requirement(s) associated with the LimitingCondition for Operation have been performed within the stated surveillance interval or as otherwise specified. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.

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

aO 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-UNIT2 3/4 0-2 Amendment No. 83,48

~

LICABLl 4.0.5 (Continued) d.

Performance of the above inservice inspection activities shall be in addition to other specified Surveillance Requirements e.

Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.

ST. LUCIE-UNIT2 3/4 0-3 Amendment No. 91

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M CHA G G PUMPS - S UTDOWN 3.1.2.3 At least one charging pump or high pressure safety injection pump in the boron injection flow path required OPERABLE pursuant to Specification 3.1.2.1 shall be OPERABLE and capable of being powered from an OPERABLE emergency power source.

IC:

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~CT~IO With no charging pump or high pressure safety injection pump OPERABLE or capable of being powered from an OPERABLE emergency power source, suspend all operations involving CORE ALTERATIONSor positive reactivity changes.

4.1.2.3 At least the above required pump shall be demonstrated OPERABLE by verifying the charging pump develops a flowrate of greater than or equal to 40 gpm or the high pressure safety injection pump develops a total head of greater than or equal to 2854 ft.

when tested pursuant to the Inservice Testing Program.

ST. LUCIE-UNIT2 3/4 1-9 Amendment No.

91

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U 3.1.2.4 At least two charging pumps shall be OPERABLE.

~M: MDDESI.,

d bCT~IO With only one charging pump OPERABLE, restore at least two charging 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 STANDBYand borated to a SHUTDOWN MARGINequivalent to at least 3000 pcm at 200'F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore at least two charging pumps to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

4.1.2.4.1 4.1.2.4.2 At least two charging pumps shall be demonstrated OPERABLE by verifying that each pump develops a flow rate of greater than or equal to 40 gpm when tested pursuant to the Inservice Testing Program.

At least once per 18 months verifythat each charging pump starts automatically on an SIAS test signal.

ST. LUCIE-UNIT2 Sf4 1-10 Amendment No. e, 95~

~ g r

~

EC I

CO 0

C CD D W 3.1.2.5 At least one boric acid makeup pump shall be OPERABLE and capable of being powered from an OPERABLE emergency bus ifonly the flowpath through the boric acid pump in Specification 3.1.2.1a is OPERABLE.

APEUQA>>:

MODES d

~CT ON:

With no boric acid makeup pump OPERABLE as required to complete the flowpath of Specification 3.1.2.1a, suspend all operations involving CORE ALTERATIONSor positive reactivitychanges.

4.1.2.5 The above required boric acid makeup pump shall be demonstrated OPERABLE by verifying, that on recirculation flow, the pump develops a discharge pressure of greater than or equal to 90 psig when tested pursuant to the Inservice Testing Program.

ST. LUCIE - UNIT2 3/4 1-11 Amendment No. 91

E VI D

U U

P -OE I

3.1.2.6 At least the boric acid makeup pump(s) in the boron injection flowpath(s) required OPERABLE pursuant to Specification 3.1.2.2 shall be OPERABLE and capable of being powered from an OPERABLE emergency bus ifthe flowpath through the boric acid pump(s) in Specification 3.1.2.2 is OPERABLE.

LEIMMMSID MODES,,

d hQIIQhl:

With one boric acid makeup pump required for the boron injection flowpath(s) pursuant to Specification 3.1.2.2 inoperable, restore the boric acid makeup pump to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be at least HOT STANDBYwithin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and borated to a SHUTDOWN MARGINequivalent to at least 3000 pcm at 200'F; restore the above required boric acid makeup pump(s) to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

4.1.2.6 The above required boric acid makeup pump(s) shall be demonstrated OPERABLE by verifying, that on recirculation flow, the pump(s) develop a discharge pressure of greater than or equal to 90 psig when tested pursuant to the Inseivice Testing Program.

ST. LUCIE-UNIT2 3/4 1-12 Amendment No.e,76,48

~

91

ECT C

YTi 344.2 S FETYVALVES 3.4.2.1 A minimum of one pressurizer code safety valve shall be OPERABLE with a liftsetting of 2500 PSIA + 1%. *

~LI L: MODES 4 4

hQXLOH:

4 With no pressurizer code safety valve OPERABLE, immediately suspend all operations, involving positive reactivity changes and place an OPERABLE shutdown cooling loop into operation.

4.4.2.1 No additional Surveillance Requirements other than those required by the Inservice Testing Program.

The liftsetting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

ST. LUCIE-UNIT2 3/4 4-7 Amendment N0.91

C

'COO S

S 3.4.2.2 Allpressurizer code safety valves shall be OPERABLE with a liftsetting of 2500 psia k1%.

3223332

'MOBE31,2 23.

With one pressurizer code safety valve inoperable, either restore the inoperable valve to OPERABLE status within 15 minutes or be in at least HOT STANDBYwithin 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 .

4.4.2.2 No additional Surveillance Requirements other than those required by the Inservice Testing Program.

The liftsetting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

ST. LUCIE-UNIT2 3/4 4-8 Amendment No.

91

COOLAN VE E

URE P E

S 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.

The provisions of Specification 3.0.4 are not applicable.

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 fulltravel at least once per 18 months.

ST. LUCIE-UNIT2 Amendment No.V6,et3 91

, i.v 2.

A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion.

3.

Verifyingthat a minimum total of 173 cubic feet of solid granular trisodium phosphate dodecahydrate (TSP) is contained within the TSP storage baskets.

4, Verifying that when a representative sample of 70.5 2 0,5 grams of TSP from a TSP storage basket is submerged, without agitation, in 10.0 2 0.1 gallons of 120 210'F borated water from the RWT, the pH of the mixed solution is raised to greater than or equal to 7 within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

f; At least once per 18 months, during shutdown, by:

1.

Verifyingthat each automatic valve in the flowpath actuates to its correct position on SIAS and/or RAS test signals.

2.

Verifyingthat each of the following pumps start automatically upon receipt of a Safety Injection Actuation Test Signal:

a.

High-Pressure Safety Injection pump.

b.

Low-Pressure Safety Injection pump.

3.

Verifying that on a Sump Recirculation Actuation Test Signal, the containment sump isolation valves open and the recirculation valve to the refueling water tank closed.

g.

By verifying that each of the following pumps develops the specified total developed head on recirculation flowwhen tested pursuant to the Inservice Testing Program:

1.

High-Pressure Safety Injection pumps: greater than or equal to 2854 ft, 2.

Low-Pressure Safety Injection pump: greater than or equal to 374 ft.

h.

By verifying the correct position of each electrical and/or mechanical position stop forthe following ECCS throttle valves:

1.

During valve stroking operation or following maintenance on the valve and prior to declaring the valve OPERABLE when the ECCS subsystems are required to be OPERABLE.

ST. LUCIE-UNIT2 3/4 &5 Amendment No. 91

'I

r -,p

4.6.2.1 Each containment spray system shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flowpath that is not locked, sealed, or otherwise secured in position, is positioned to take suction from the RWT on a Containment Pressure --

High-High test signal.

b.

By verifying, that on recirculation flow, each pump develops a discharge pressure of greater than or equal to 200 psig when tested pursuant to the Inservice Testing Program.

At least once per 18 months, during shutdown, by:

1.

Verifyingthat each automatic valve in the flowpath actuates to its correct position on a CSAS test signal ~

2.

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

ST. LUCIE-UNIT2 3/4 6-15a Amendment NO.V8~ 9"

~.g

(

P I

e CON INMENTS S E

S IODINE EMOVALS S 3.6.2.2 The Iodine Removal System shall be OPERABLE with:

a.

A hydrazine storage tank containing a minimum volume of 675 gallons oft 25.4%

by weight N,H, (Hydrazine) solution, and b.

Two iodine removal pumps each capable of adding N,H, solution from the hydrazine storage tank to a containment spray system pump flow.

MODES 1, d

~C~O With the Iodine Removal System inoperable restore the system 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 STANDBYwithin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore the Iodine Removal System to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

4.6.2.2 The Iodine Removal System shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each valve (manual, powerwperated, or automatic) in the flowpath that is not locked, sealed, or otherwise secured in position, is in its correct position.

b.

The above required iodine removal pumps shall be demonstrated OPERABLE by verifying a flow rate of between 0.71 gpm and 0.82 gpm when tested pursuant to the Inservice Testing Program.

c.

At least once per 6 months by:

1.

Verifying the contained solution volume in the tank, and 2.

Verifying the concentration of the N,Hsolution by chemical analysis.

d.

At least once per 18 months, during shutdown, by verifying that each automatic valve in the flowpath actuates to its correct position on a CSAS test signal.

Applicable only when pressurizer pressure is 2 1750 psia.

'T.

LUCIE-UNIT2 3/4 6-17 Amendment No. 91

>r

AN 4.6.3.2 Each automatic containment isolation valve shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:

a.

Verifying that on a Containment Isolation test signal (CIAS) and/or a Safety Injection test signal (SIAS), each isolation valve actuates to its isolation position.

4.6.3.3 b.

Verifying that on a Containment Radiation-High test signal, each containment purge valve actuates to its isolation position.

The isolation time of each power-operated or automatic containment isolation valve shall be determined to be within its limitwhen tested pursuant to the Inservice Testing Program..

ST. LUCIE-UNIT2 3/4 6-20 Amendment N0.88, 91

~

pl

~'"

CO ENT S 3/

6 VACU E IEF 3.6.5 The primary containment vessel to annulus vacuum relief valves shall be OPERABLE with an actuation setpoint of less than or equal to 9.85 2 0.35 inches water gauge.

P MODES.,

d With one primary containment vessel to annulus vacuum relief valve inoperable, restore the valve to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT STANDBYwithin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following30 hours.

4.6.5 No additional Surveillance Requirements other than those required by the InseNIce Testing Program.

ST. LUCIE-UNIT2 3/4 6-26 Amendment No.69,69 gf

47 PLANTSYS

/4.7.2 TURBINE CYCLE SAF VALVES 3,7.1.1 Allmain steam line code safety valves shall be OPERABLE with liftsettings and orifice sizes as shown in Table 3.7-2.

APPig>EJ:

MD ES, d

~CION:

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; othetwise, be in at least HOT STANDBYwithin 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.

The provisions of Specification 3,0.4 are not applicable.

4.7.1,1 No additional Surveillance Requirements other than those required by the Insetvice Testing Program.

ST. LUCIE-UNIT2 3/4 7-1 Amendment No. 8, 6B g1

Ir L

tg

+ ~

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~ il

SYSTEMS A

AM LI 3.7.1.5 Each main steam line isolation valve shall be OPERABLE.

~LILIY:MDDBH..

d

~C~IO MODE 1 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 STANDBYwithin 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 line isolation valve(s) inoperable, subsequent and 4 operation in MODES 2, 3 or 4 may proceed provided the isolation valve(s) is (are) maintained closed.

Otherwise, be in at least HOT STANDBYwithin the'next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following24 hours.

The provisions of Specification 3.0.4 are not applicable.

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-UNIT2 3/4 7-9 Amendment No. 85, 6Q 91

a b

<i a'c MAIN EEDWAT SO 0

LIMITINGCONDI 0 FO OPE IO 3.7.1.6 Four main feedwater isolation valves (MFIVs) shall be OPERABLE.

." M

~CTION:

a.

With one MFIVinoperable in one or more main feedwater lines, OPERATION may continue provided each inoperable valve is restored to OPERABLE status, closed, or isolated within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Otherwise, be in HOT STANDBYwithin 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 MFIVs inoperable in the same flowpath, restore at least one of the inoperable MFIVs to OPERABLE status or close one of the inoperable valves within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . Otherwise, be in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCERE UIREME S

4.7.1.6.a Each MFIVshall be demonstrated OPERABLE by verifying full closure within 5.15 seconds when tested pursuant to the Inservice Testing Program.

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

4.7.1.6.b For each inoperable MFIV, verify that it is dosed or isolated once per 7 days.

Each MFIVshall be treated independently.

ST. LUCIE-UNIT2 3/4 7-10 Amendment No. 6,95,52, M 91

4.0.4 This specification establishes the requirement that all applicable surveillances must be met before entry into an OPERATIONALMODE or other condition of operation specified

~

in the Applicabilitystatement.

The purpose of this specification is to ensure that system and component OPERABILITYrequirements 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 OPERATIONALMODES 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 followinga 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 placing the facilityin a lower MODE of operation.

4.0.5 This specification ensures that inservice inspection of ASME Code Class 1, 2 and 3 components willbe 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 a part of these Technical Specifications.

ST. LUCIE-UNIT2 B 3f4 0-6 Amendment No.88, 9f

($

'I I (g ll~~

EACTOR COOLANTSYS S

VALVES Continued During operation, all pressurizer code safety valves must be OPERABLE to prevent the RCS from being pressurized above its safety limitof 2750 psia. The combined relief capacity of these valves is sufficient to limitthe system pressure to within its Safety Limit of 2750 psia followinga complete loss of tutbine generator load while operating at RATED THERMALPOWER and assuming no reactor trip until the first Reactor Protective System trip setpoint (Pressurizer Pressure-High) is reached (i.e., no credit is taken for a direct reactor trip on the loss of turbine) and also assuming no operation of the pressurizer power-operated relief valve or steam dump valves.

Demonstration of the safety valves'ift settings willoccur only during shutdown and willbe performed in accordance with the provisions of the Inservice Testing Program.

SU E

An OPERABLE pressurizer provides pressure control for the Reactor Coolant System during operations with both forced reactor coolant flowand with natural circulation flow.

The minimum water level in the pressurizer assures the pressurizer heaters, which are required to achieve and maintain pressure control, remain covered with water to prevent failure, which could occur ifthe heaters were energized uncovered.

The maximum water level in the pressurizer ensures that this parameter is maintained within the envelope of operation assumed in the safety analysis.

The maximum water level also ensures that the RCS is not a hydraulically solid system and that a steam bubble willbe provided to accommodate pressure surges during operation. The steam bubble also protects the pressurizer code safety valves against water relief. The requirement to verifythat on an Engineered Safety Features Actuation test signal concurrent with a loss of offsite power the pressurizer heaters are automatically shed from the emergency power sources is to ensure that the non-Class 1E heaters do not reduce the reliabilityof o overioad the emergency power source. The requirement that a minimum number of pressurizer heaters be OPERABLE enhances the capability to control Reactor Coolant System pressure and establish and maintain natural circulation.

ST. LUCIE-UNIT2 B Sf44-2 Amendment No.

rk

Leakage rate acceptance criteria:

a.

Containment leakage rate acceptance is 6 1.0 L

. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria is < 0.60 I for the Type B and C tests, 6 0.75 LforType Atests, and 6 0.12 Lforsecondaty containment bypass leakage paths.

b.

Airlock testing acceptance criteria are:

1.

Overall air lock leakage rate is ~ 0.05 L when tested at 2 P, 2.

For each door seal, leakage rate is (0.01 lwhen pressurized tot P,.

C The provisions of T.S.4.0.2 do not apply to test frequencies in the Containment Leak Rate Testing Program.

The provisions of T.S.4.0.3 are applicable to the Containment Leak Rate Testing Program.

This program provides controls for inservice testing of ASME Code Class 1, 2 and 3 components (pumps and valves). The program shall include the following:

a.

Testing frequencies specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as follows:

ASME Boiler and Pressure Vessel Code'nd applicable Addenda terminology for Required Frequencies for performing Weekly Monthly Quarterly or every 3 months Semiannually or evety 6 months Evety 9 months Yearly or annually Biennially or every 2 years At least once per 7 days At least once per 31 days

'At least once per 92 days At least once per 184 days At least once per 276 days At least once per 366 days At least once per 731 days b.

The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice testing activities; c.

The provisions of Specification 4.0.3 are applicable to inservice testing activities; and d.

Nothing in the ASME Boiler and Pressure Vessel Code'hall be construed to supersede the requirements of any technical specification, Where ASME Boiler and Pressure Vessel Code is referenced it also refers to the applicable portions of ASME/ANSIOM-Code, "Operation and Maintenance of Nuclear Power Plants" with applicable addenda, to the extent it is referenced in the Code.

ST. LUCIE-UNIT2 Amendment No. 88, 91

ML17229A657

Text

Attachment:

Attachment:

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