ML17229A231

Amends 149 & 88 to Licenses DPR-67 & NPF-16,respectively, Consisting of Changes to TSs in Response to 961028 Applications for Units 1 & 2 Re Containment Leakage Tests & Removal of Certain Component Lists from TS

ML17229A231
Person / Time
Site:	Saint Lucie   (DPR-67-A-149, NPF-16-A-088, NPF-16-A-88)
Issue date:	02/10/1997
From:	Hebdon F NRC (Affiliation Not Assigned)
To:
Shared Package
ML17229A229	List: ML17229A228 ML17229A231 ML17229A232
References
NUDOCS 9702180026
Download: ML17229A231 (35)

Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055$ 4001 FLORIDA POWER

& LIGHT COMPANY DOCKET O. 50-335 ST.

LUCIE PLANT UNIT NO 1

MENDMENT TO ACI ITY OPERAT NG ICENSE Amendment No.

149 License No.

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

A.

B.

C.

.D.

E.

The application for amendment by Florida Power

& Light Company, et al.

(the licensee),

dated October 28,

1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the

Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the

public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

9702xso'026 97ozxo PDR ADQCK 05000335 P

PDR

2.

Accordingly, Facility Operating License No.

DPR-67 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph 2.C.(2) to read as follows:

(2)

Technical S ecifications The Technical Specifications contained revised through Amendment No. 149, are license.

The licensee shall operate the the Technical Specifications.

in Appendices A and B,

as hereby incorporated in the.

facility in accordance with 3.

This license amendment is effective as of its date of issuance and shall be implemented within 60 days.

FOR THE NUCLEAR REGULATORY CONHISSION Frederick J.

He don, 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 10, 1997

ATTACHMENT TO LICENSE AMENDMENT NO.

149 TO FACILITY OPERATING LICENSE NO. DPR-67 DOCKET NO. 50-335 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.

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

Remove Pa es 1-2 3/4 6-1 3/4 6-2 3/4 6-3 3/4 6-4 3/4 6-5 3/4 6-6 3/4 6-7 3/4 6-8 3/4 6-9 3/4 6-10 3/4 6-11 3/4 6-14 3/4 6-18 3/4 6-19 3/4 6-20 3/4 6-21 3/4 6-22

. 3/4 6-31 B3/4 6-1 B3/4 6-2 6-15b Insert Pa es 1-2 3/4 6-1 3/4 6-2 3/4 6-3 3/4 6-10 3/4 6-11 3/4 6-14 3/4 6-18 3/4 6-19 3/4 6-20 3/4 6-31 B3/4 6-1 B3/4 6-2 6-15b 6-15c

• DEFINITIONS CHANNEL FUNCTIONALTEST 1.6 A CHANNEL FUNCTIONALTEST shall be the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

CONTAINMENTVESSEL INTEGRITY 1.7 CONTAINMENTVESSEL INTEGRITYshall exist when:

a.

All containment vessel penetrations required to be closed during accident conditions are either:

Capable of being closed by an OPERABLE containment automatic isolation valve system, or 2,

Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed position except for valves that are open on an intermittent basis under administrative control.

b.

All containment vessel equipment hatches are closed and sealed, c.

Each containment vessel air lock is in compliance with the requirements of Specification 3.6.1.3, d.

The containment leakage rates are within the limits of Specification 3.6.1.2, and e.

The sealing mechanism associated with each penetration (e.g., welds, bellows or 0-rings) is OPERABLE.

CONTROLLED LEAKAGE 1.8 CONTROLLED LEAKAGEshall be the seal water flow supplied from the reactor coolant pump seals.

CORE ALTERATION 1.9 CORE ALTERATIONshall be the movement or manipulation of any fuel, sources, reactivity control components, or other components affecting reactivity within the reactor vessel with the vessel head removed and fuel in the vessel, Exceptions to the above include shared (4 fingered) control element assemblies (CEAs) withdrawn into the upper guide structure (UGS) or evolutions performed with the UGS in place such as CEA latching/unlatching or verification of latching/

unlatching which do not constitute a CORE ALTERATION. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position, ST. LUCIE-UNIT 1 1-2 Amendment No. 80,446149.

3/4.6 CONTAINM SYSTEMS 3/4.6.1 CONTAINMENTVESSEL CONTAINMENTVESSEL INTEGRITY LIMITINGCONDITION FOR OPERATION 3.6.1.1 CONTAINMENTVESSEL INTEGRITYshall be maintained.

SPP I

• I III:

MODES 1.,

I

~CTION:

Without CONTAINMENTVESSEL INTEGRITY, restore CONTAINMENTVESSEL INTEGRITY within one hour o'r be in at least HOT STANDBYwithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCEREQUIREMENTS 4.6.1.1 CONTAINMENTVESSEL INTEGRITYshall be demonstrated:

a.

At least once per 31 days by verifying that:

1.

All containment vessel penetrations* not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind.flanges, or deactivated automatic valves secured in their positions, except for valves that are open on an intermittent basis under administrative control, and 2.

All containment vessel equipment hatches are closed and sealed.

b.

By verifying that each containment vessel air lock is OPERABLE per Specification 3.6.1.3.

Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that such ve'rification need not be performed more often than once per 92 days.

ST. LUCIE - UNIT 1

.3/4 6-1 Amendment No. 448, 428 149

CONTAINMENTSYSTE CONTAINMENTLEAKAGE LIMITINGCONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited in accordance with the Containment Leakage Rate Testing Program, APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With the containment leakage rate exceeding the acceptance criteria of the Containment Leakage Rate Testing Program, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate action to be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Restore the overall leakage rate to less than that specified by the Containment Leakage Rate Testing Program prior to increasing the Reactor Coolant System temperature above 200'F.

SURVEILLANCEREQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the required test schedule and shall be determined in conformance with the criteria specified in the Containment Leakage Rate Testing Program.

ST. LUCIE - UNIT 1 3/4 6-2 Amendment No. 88, 08. 4&7 ) 49

CONTAINMENTSYSTE SURVEILLANCEREQUIREMENTS continued Pages 3/4 6-3 through 3/4 6-9 have been DELETED.

Page 3/4 6-10 Is the next valid page.

ST. LUCIE - UNIT 1 3/4 6-3 Amendment No.88,497- ~49

CONTAINMENTSYSTE CONTAINMENTAIR LOCKS LIMITINGCONDITION 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 STANDBYwithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

4.

The provisions of Specification 3.0.4 are not applicable.

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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBYwithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCEREQUIREMENTS 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 3f4 6-10 Amendment, No. 88 "49

CONTAINMENTSYSTE CONTAINMENTAIR LOCKS SURVEILLANCEREQUIREMENTS continued a.

By verifying leakage rates and air lock door seals in accordance with the Containment Leakage Rate Testing Program; and b.

At least once per 6 months by verifying that only one door in each air lock can be opened at a time.

ST. LUCIE - UNIT 1 3/4 6-11 Amendment No. 86, 487 1 49

CONTAINMENTSYSTE i

CONTAINMENTVESSEL STRUCTURAL INTEGRITY LIMITINGCONDITION FOR OPERATION 3.6.1.6 The structural integrity of the containment vessel shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6.

APPLICABILITY:

MODES 1, 2, 3 and 4.

~CTION:

With the structural integrity of the containment vessel not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200'F.

SURVEILLANCEREQUIREMENTS 4.6.1.6 The structural integrity of the containment vessel shall be determined, in accordance with the containment Leakage Rate Testing Program, by a visual inspection of the accessible interior and exterior surfaces of the vessel and verifying no apparent changes in appearance of the surfaces or other abnormal degradation.

ST. LUCIE - UNIT 1 3/4 6-14 Amendment No. 69, 149

CONTAINMENTSYSTE 3/4.6.3 CONTAINMENTISOLATIONVALVES LIMITINGCONDITION FOR OPERATION 3.6.3.1 The containment isolation valves shall be OPERABLE:

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With one or more of the isolation valve(s) inoperable, either:

a.

Restore the inoperable valve(s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or b.

Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or c.

Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange; or d.

Be in at least HOT STANDBYwithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCEREQUIREMENTS 4.6.3.1.1 The isolation valves shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by performance of the cycling test, and verification of isolation time.

ST. LUCIE - UNIT 1 3/4 6-18 Amendment No. QQ 149

CONTAINMENTSYSTE SURVEILLANCEREQUIREMENTS continued 4.6.3.1.2 4.6.3.1.3 Each 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, and/or SIAS test signal, each isolation 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 limits when tested pursuant to Specification 4.0.5.

ST. LUCIE -.UNIT 1 3/4 6-19 Amendment No. 89

Pages 3/4 6-20 through 3/4 6-22 have been DELETED.

Page 3/4 6-23 is the next valid page.

ST. LUCIE - UNIT 1 3/4 6-20 Amendment No.,SS, 448 149

CONTAINMENTSYSTE SHIELD BUILDINGSTRUCTURAL INTEGRITY LIMITINGCONDITION FOR OPERATION 3.6.6.3 The structural integrity of the shield building shall be maintained at a level consistent with the acceptance criteria in Specification 4.6,6,3.

4 I EBILI:

MBBEBI,,

4 4.

ACTION:

With the structural integrity of the shield building not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200'F.

SURVEILLANCEREQUIREMENTS 4.6.6.3 The structural integrity of the shield building shall be determined, in accordance with the Containment Leakage Rate Testing Program, by a visual inspection of the accessible interior and exterior surfaces. of the shield building and verifying no apparent changes in appearance of the concrete surfaces or other abnormal degradation.

ST. LUCIE - UNIT 1 3/4 6-31 Amendment No. 68" 49

3/4.6 CONTAINM SYSTEMS BASES 3/4.6.1 CONTAINMENTVESSEL 3/4.6.1.1 CONTAINMENTVESSEL INTEGRITY CONTAINMENTVESSEL INTEGRITYensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses.

This restriction, in conjunction with the leakage rate limitation, will limitthe site boundary radiation doses to within the limits of 10 CFR Part 100 during accident conditions.

In accordance with Generic Letter 91-08, "Removal of Component Lists from Technical Specifications," the opening of locked or sealed closed containment isolation valves on an intermittent basis under administrative control includes the following considerations:

(1) stationing an operator, who is in constant communication with the control room, at the valve controls, (2) instructing this operator to close these valves in an accident situation, and (3) assuring that environmental conditions will not preclude access to close the valves and that this action will prevent the release of radioactivity outside the containment.

3/4.6.1.2 CONTAINMENTLEAKAGE The limitations on containment leakage rates ensuie that the total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident

pressure, P, (39.6 psig) which results from the limiting design basis loss of coolant accident.

The surveillance testing for measuring leakage rates is performed in accordance with the Containment Leakage Rate Testing Program and is consistent with the requirements of Appendix "J" of 10 CFR 50, Option B and Regulatory Guide 1.163 Rev. 0, as modified by approved exemptions.

3/4.6.1.3 CONTAINMENTAIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENTINTEGRITYand containment leak rate.

Surveillance testing of the air lock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.

ST. LUCIE - UNIT 1 B 3/4 6-1 Amendment No. 86,~, 4971 "9

CONTAINMENTSYSTE BASES 3/4.6.1.4 INTERNALPRESSURE The limitations on containment internal pressure ensure that 1) the containment structural is prevented from exceeding its design negative pressure differential with respect to the annulus atmosphere of 0.70 psi and 2) the containment peak pressure does not exceed the design pressure of 44 psig during steam line break accident conditions.

The maximum peak pressure obtained from a steam line break accident is 41.6 psig. The limitof 2.4 psig for initial positive containment pressure will limit the total pressure to 44.0 psig which is the design pressure and is consistent with the accident analyses, 3/4.6.1.5 AIR TEMPERATURE The limitation on containment air temperature ensures that the containment vessel temperature does not exceed the design temperature of 264'F during LOCA conditions.

The containment temperature limit is consistent with the accident analyses.

3/4.6.1.6 CONTAINMENTVESSEL STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment steel vessel will be maintained comparable to the'original design standards for the life of the facility. Structural integrity is required to ensure that the vessel will withstand the maximum pressure of 39.6 psig in the event of the limiting design basis loss of coolant accident.

A visual inspection in accordance with the Containment Leakage Rate Testing Program is sufficient to demonstrate this capability.

ST. LUCIE - UNIT 1 B 3/4 6-2 Amendment No. 484

] 49

ADMINISTRATIVECON LS (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1)

Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM.

2)

A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARYare identified and that modifications to the monitoring program are made if required by the results of this census, and

')

Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

h.

Containment Leakage Rate Testing Program A program to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50 Appendix J, Option B, as modified by approved exemptions.

This program is in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," as modified by the following exception:

a.

Bechtel Topical Report, BN-TOP-1 or ANS 56.8-1994 (as recommended by R.G. 1.163) will be used for type A testing.

The peak calculated containment internal pressure for the design basis loss of coolant accident P is 39.6 psig. The containment design pressure is 44 pslg.

The maximum allow containment leakage rate, Lat Pshall be 0.50% of containment air weight per day.

Leakage rate acceptance criteria are:

a.

Containment leakage rate acceptance criterion is 6 1.0 L,, During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 6.0 L, for the Type B and C tests, 6 0.75 L,for Type A tests, and 6 0,27 L, for secondary containment bypass leakage paths, b.

Air lock testing acceptance criteria are:

1)

Overall air lock leakage rate is 6 0.05 L, when tested at 2 P,.

2)

For the personnel air lock door seal, leakage rate is < 0.01 L, when pressurized to 2 1.0 P,.

3)

For the emergency air lock door seal, leakage rate is < 0.01 L, when pressurized to 2 10 psig.

ST. LUCIE - UNIT 1 6-15b Amendment No. 69, 86, 428 149

ADMINISTRATIVECON S

continued l

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.

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 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.

STARTUP REPORT 6.9.1.1 A summary 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 IBVBI, (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 - UNIT 1 6-15c Amendment No. 149

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UNITED STATES NUCLEAR REGULATORY COMMISStON WASHINGTON, D.C. 20555-0001 FLORIDA POWER

& LIGHT COMPANY ORLANDO UTILITIES COMMISSION OF THE CITY OF ORLANDO FLORIDA

~ND FLORIDA MUNICIPAL POWER AGENCY DOCKET NO. 50-389 ST.

LUCIE PLANT UNIT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.88 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 October 28,

1996, complies with the

'tandards 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.

C.

D.

E.

The facility will operate in conformity with the application, the provisions of the

Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the

public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; The issuance of this amendment will not be inimical to the common defense and,security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and a11 applicable requirements have been satisfied.

TTACHMENT TO LICENSE A NDMENT NO. 88 TO F CILITY OP A I G

C NSE NO. NPF-16 DOCKET NO. 50-389 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.

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

Remove Pa es 1-2 3/4 6-1 3/4 6-2 3/4 6-3 3/4 6-4 3/4 6-5 3/4 6-6 3/4 6-7 3/4 6-8 3/4 6-9 3/4 6-10 3/4 6-13.

3/4 6-19 3/4 6-20 3/4 6-21 3/4 6-22 3/4 6-23 3/4 6-31 B3/4 6-1 B3/4 6-2 6-15b Insert Pa es 1-2 3/4 6-1 3/4 6-2 3/4 6-3 3/4 6-9 3/4 6-10 3/4 6-13 3/4 6-19 3/4 6-20 3/4 6-21 3/4 6-31 B3/4 6-1 B3/4 6-2 6-15b 6-15c

• EFINITIONS CHANNEL FUNCTIONALTEST 1.6 A CHANNEL FUNCTIONALTEST shall be the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

CONTAININENTVESSEL INTEGRITY 1.7 CONTAINMENTVESSEL INTEGRITYshall exist when:

a.

All containment vessel penetrations required to be closed during accident conditions are either:

Capable of being closed by an OPERABLE containment automatic isolation valve system, or 2,

Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except for valves that are open on an intermittent basis under administrative control.

b.

All containment vessel equipment hatches are closed and sealed, c.

Each containment vessel air lock is in compliance with the requirements of Specification 3.6.1.3, d.

The containment leakage rates are within the limits of Specification 3.6.1.2, and e,

The sealing mechanism associated with each penetration (e.g., welds, bellows or 0-rings) is OPERABLE, CONTROLLED LEAKAGE

'I.8 CONTROLLED LEAKAGEshall be the seal water flow supplied from the reactor

'coolant pump seals.

CORE ALTERATION 1.9 CORE ALTERATIONshall be the movement or manipulation of any fuel, sources, reactivity control components, or other components affecting reactivity within the reactor vessel with the vessel head removed and fuel in the vessel.

Exceptions to the above include shared (4 fingered) control element assemblies (CEAs) withdrawn into the upper guide structure (UGS) or evolutions performed with the UGS in place such as CEA latching/unlatching or verification of latching/

unlatching which do not constitute a CORE ALTERATION. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

,ST. LUCIE-UNIT2 1-2 Amendment No. 8688'--

3/4.6 I

CONTAINM SYSTEMS 3/4.6.1 PRIMARYCONTAINMENT CONTAINMENTINTEGRITY LIMITINGCONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENTINTEGRITYshall be maintained.

APPLICABILITY:

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

ACTION:

Without primary CONTAINMENTINTEGRITY, restore CONTAINMENTINTEGRITYwithin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBYwithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, SURVEILLANCEREQUIREMENTS 4.6.1.1 Primaty CONTAINMENTINTEGRITYshall be demonstrated:

a.

At least once per 31 days by verifying that all penetrations **not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except for valves that are open on an intermittent basis under administrative control.

b.

By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3, In MODES 1 and 2, the RCB polar crane shall be rendered inoperable by locking the power supply breaker open.

• • Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed or otherwise secured in the closed position.

These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.

ST. LUCIE-UNIT2

'/4 6-1 Amendment No. 88,4688

CONTAINMENTSYSTE I

CONTAINMENTLEAKAGE LIMITINGCONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited in accordance with the Containment Leakage Rate Testing Program.

EPPLI

• ILIEP:

MODEM I,,E, 44.

ACTION:

With the containment leakage rate exceeding the acceptance criteria of the Containment Leakage Rate Testing Program, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate action to be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Restore the overall leakage rate to less than that specified by the Containment Leakage Rate Testing Program, prior to increasing the Reactor Coolant System temperature above 200'F.

SURVEILLANCEREQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the required test schedule and shall be determined in conformance with the criteria specified in the Containment Leakage Rate Testing Program.

ST. LUCIE-UNIT2 3/4 6-2 Amendment No. 36,8t 69,88 66

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o CONTAINMENTSYSTEh SURVEILLANCEREQUIREMENTS continued Pages 3/4 6-3 through 3/4 6-8 have been DELETED.

Page 3/4 6-9 Is the next valid page.

ST. LUCIE - UNIT 2 3/4 6-3 Amendment No. 86, 88 88'

CONTAINMENTSYSTE CONTAINMENTAIR LOCKS LIMITINGCONDITION 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 feast HOT STANDBYwithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

4.

The provisions of Specification 3.0.4 are not applicable.

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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBYwithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, 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-UNIT2 3/4 6-9 Amendment No. 8888

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CONTAINMENTSYSTE SURVEILLANCEREQUIREMENTS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:

a.

By verifying leakage rates and air lock door seals in accordance with the Containment Leakage Rate Testing Program; and b.

At least once per 6 months by verifying that only one door in each air lock can be opened at a time.

ST. LUCIE-UNIT2

=

3/4 6-10 Amendment No. 86, W 88

CONTAINMENTSYSTEM CONTAINMENTVESSEL STRUCTURAL INTEGRITY LIMmNG CONDITION FOR OPERATION 3.6.1.6 The structural integrity of the containment vessel shall be maintained at a level consistent with the acceptance criteria in Surveillance Requirement 4.6.1.6.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With the structural integrity of the containment vessel not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200'F.

SURVEILLANCEREQUIREMENTS 4.6.1.6 The structural integrity of the containment vessel shall be determined in accordance with the Containment Leakage Rate Testing Program by a visual inspection of the exposed accessible interior and exterior surfaces of the vessel and verifying no apparent changes in appearance of the surfaces or other abnormal degradation.

ST. LUCIE-UNIT2 3/4 6-13 Amendment No. 48 89

CONTAINMENTSYS 3/4.6.3 CONTAINMENTISOLATION VALVES LIMITINGCONDITION FOR OPERATION 3.6.3 The containment isolation valves shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With one or more containment isolation valve(s) inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and either:

a.

Restore the inoperable valve(s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or b.

Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or c.

Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange; or d.

Be in at least HOT STANDBYwithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCEREQUIREMENTS 4.6.3.1 The containment isolation valves shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by performance of a cycling test and verification of isolation time.

ST. LUCIE-UNIT2 3/4 6-19 Amendment No.

88

CONTAINMENTSYSTE SURVEILLANCE REQUIREMENTS Continued 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.

b.

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

4.6.3.3.

The isolation time of each power-operated or automatic containment isolation valve shall be determined to be within its limitwhen tested pursuant to Specification 4.0,5.

ST. LUCIE - UNIT2 C

3/4 6-20 Amendment No. 88

Pages 3/4 6-21 through 3/4 6-23 have been DELETED.

Page 3/4 6-24 Is the next valid page.

ST. LUCIE - UNIT 2 3/4 6-21 Amendment No. QS, 68 88

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2.

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

2.

Technical S ecifications 3.

The Technical Specifications contained in Appendices A and B,

as revised through Amendment No.88

, are hereby incorporated in the license.

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

This license amendment is effective as of its date of issuance and shall be implemented within 60 days.

FOR THE NUCLEAR REGULATORY COMMISSION 8-,.ws~ iM 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 10, 1997

3/4.6

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BASES CONTAINM SYSTEMS 3/4.6.1 PRIMARYCONTAINMENT 3/4.6.1.1 CONTAINMENTINTEGRITY Primary CONTAINMENTINTEGRITYensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the safety analyses.

This restriction, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.

In accordance with Generic Letter 91-08, "Removal of Component Lists from Technical Specifications," the opening of locked or sealed closed containment isolation valves on an intermittent basis under administrative control includes the following considerations:

(1) stationing an operator, who is in constant communication with the control room, at the valve controls, (2) instructing this operator to close these valves in an accident situation, and (3) assuring that environmental conditions will not preclude access to close the valves and that this action will prevent the release of radioactivity outside the containment, 3/4.6.1.2 CONTAINMENTLEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure, P, (41.8 psig) which results from the limiting design basis loss of coolant accident.

The surveillance testing for measuring leakage rates is performed in accordance with the Containment Leakage Rate Testing Program, and is consistent with the requirements of Appendix J of 10 CFR 50 Option B and Regulatory Guide 1.163 dated September,

1995, as modified by approved exemptions.

3/4.6.1.3 CONTAINMENTAIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENTINTEGRITYand containment leak rate.

Surveillance testing of the air lock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.

3/4.6.1.4 INTERNALPRESSURE The limitations on containment internal pressure ensure that (1) the containment structure is prevented from exceeding its design negative pressure differential with respect to the annulus atmosphere of 0.7 psi and (2) the containment peak pressure does not exceed the design pressure of 44 psig during steam line break conditions.

The maximum peak pressure expected to be obtained from a steam line break event is 43.4 psig. The limitof 0.4 psig for initial positive containment pressure will limit the total pressure to 43.99 psig which is less than the design pressure and is consistent with the safety analyses.

ST. LUCIE - UNIT 2 B 3/4 6-1 Amendment No. 87;68 88

CONTAINMENTSYSTE BASES 3/4.6.1.5 AIR TEMPERATURE The limitation on containment average air temperature ensures that the containment temperature does not exceed the design temperature of 264'F during steam line break conditions and is consistent with the safety analyses.

3/4.6.1.6 CONTAINMENTVESSEL STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment steel vessel will be maintained comparable to the original design standards for the life of the facility. Structural integrity is required to ensure that the vessel will withstand the maximum pressure of 41.8 psig in the event of a limiting desigh basis loss of coolant accident.

A visual inspection in accordance with the Containment Leakage Rate Testing Program is sufficient to demonstrate this capability.

3/4.6.1.7 CONTAINMENTVENTILATIONSYSTEM The 48-inch containment purge supply and exhaust isolation valves are required to be closed during plant operation since these valves have not been demonstrated capable of closing during a LOCA or steam line break accident.

Maintaining these valves closed during plant operations ensures that excessive quantities of radioactive materials will not be released via the containment purge system.

To provide assurance that the 48-inch valves cannot be inadvertently opened, they are sealed closed in accordance with Standard Review Plan 6.2.4 which includes devices to lock the valve closed, or prevent power from being supplied to the valve operator.

The use of the containment purge lines is restricted to the 8-inch purge supply and exhaust isolation valves since, unlike the 48-inch valves, the 8-inch valves will close during a LOCA or steam line break accident and therefore the site boundary dose guidelines of 10 CFR Part 100 would not be exceeded in the event of an accident during purging operations.

Leakage integrity tests with a maximum allowable leakage rate for purge supply and exhaust isolation valves will provide early indication of resilient material seal degradation and will allow the opportunity for repair before gross leakage failure develops.

The 0.60 L, leakage limit shall not be exceeded when the leakage rates determined by the leakage integrity tests of these valves are added to the previously determined total for all valves and penetrations subject to Type B and C tests.

ST. LUCIE - UNIT 2 8 3/4 6-2 Amendment No. W 88

fi r

s DMINISTRATIVECONT LS than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARYconforming to Appendix I to 10 CFR Part 50,

10) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

g.

Radiolo ical Environmental Monitorin Pro ram A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways.

The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1)

Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM, 2)

A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARYare identified and that modifications to the monitoring program are made if required by the results of this census, and 3)

Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

h.

Containment Leakage Rate Testing Program A program to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50 Appendix J, Option B, as modified by approved exemptions, This program is in accordance with the guidelines contained in Regulatory Guide 1 ~163, "Performance-Based Containment Leak-Test Program," as modified by the following exception:

a.

Bechtel Topical Report, BN-TOP-1 or ANS 56,8-1994 (as recommended by R.G. 1.163) will be used for type A testing.

The peak calculated containment internal pressure for the design basis loss of coolant accident P is 41.8 psig. The containment design pressure is 44 psig.

The maximum allowable containment leakage rate,'at Pshall be 0.50%

of containment air weight per day.

ST. LUCIE-UNIT2 6-15b Amendment No. 64 88

4 I

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ADMINISTRATIVECON LS continued Leakage rate acceptance criteria are:

a.

Containment leakage rate acceptance criterion is (1.0 L,. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 L, for the Type B and C tests, 5 0.75 L, for Type A tests, and 5 0.27 L, for secondary containment bypass leakage paths.

b.

Air lock testing acceptance criteria are:

1)

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

2)

For each door seal, leakage rate is ( 0.01 L, when pressurized tohP,.

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.

ST. LUCIE - UNIT2 6-15c Amendment No. 88

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