ML20116M790

Amends 84 & 7l to Licenses NPF-76 & NPF-80,changing TSs to Implement 10CFR50,App J,Option B

ML20116M790
Person / Time
Site:	South Texas
Issue date:	08/13/1996
From:	Alexion T NRC (Affiliation Not Assigned)
To:
Shared Package
ML20116M793	List: ML20116M790 ML20116M800 ML20116M811
References
NUDOCS 9608210080
Download: ML20116M790 (12)

Text

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UNITED STATES y

j NUCLEAR REGULATORY COMMISSION f

WASHINGTON, D.C. sese6 eem l

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HOUSTON LIGHTING & POWER COMPANY CITY PUBLIC SERVICE BOARD OF SAN ANTONIO l

CENTRAL POWER AND LIGHT COMPANY CITY OF AUSTIN. TEXAS DOCKET NO. 50-498 SOUTH TEXAS PROJECT. UNIT 1 A ENDMENT TO FACILITY OPERATING LICENSE i

Amendment No. 84 License No. NPF-76 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Houston Lighting & Power Company *

(HL&P) acting on behalf of itself and for the City Public Service Board of San Antonio (CPS), Central Power and Light Company (CPL),

i and City of Austin, Texas (C0A) (the licensees), dated May 1,1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; 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 license amendment will not be inimical to the comon 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 Comission's regulations and all applicabic requirements have been satisfied.

• Houston Lighting & Power Company is authorized to act for the City Public Service Board of San Antonio, Central Power and Light Company and City of Austin, Texas and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.

9608210000 960813 I

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2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-76 is hereby amended to read as follows:

2.

Technical Specifications l

The Technical Specifications contained in Appendix A, as revised through Amendment No. 84, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the l

Technical Specifications and the Environmental Protection Plan.

3.

The license amendment is effective as of its date of issuance to be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Q194/

A %.)

Thomas W. Alexion, Project Manager i

Project Directorate IV-1 i

Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications l

Date of Issuance:

August 13, 1996 i

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4 UNITED STATES g

g NUCLEAR REGULATORY COMMISSION i

t WASHINGTON. D.C. ensam mang l

%, * * *. *,o HOUSTON LIGHTING & POWER COMPANY CITY PUBLIC SERVICE BOARD OF SAN ANTONIO CENTRAL POWER AND LIGHT COMPANY CITY OF AUSTIN. TEXAS DOCKET NO. 50-499 SOUTH TEXAS PROJECT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.71 License No. NPF-80 1.

The Nuclear Regulatory Commission (the Comission) has found that:

A.

The application for amendment by Houston Lighting & Power Company *

(HL&P) acting on behalf of itself and for the City Public Service Board of San Antonio (CPS), Central Power and Light Company (CPL),

and City of Austin, Texas (C0A) (the licensees), dated May 1,1996, 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; B.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission;

)

C.

There is reasonable assurance:

(i) that the activities authorized i

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 license amendment will not 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.

j

• Houston Lighting & Power Company is authorized to act for the City Public

- Service Board of San Antonio, Central Power and Light Company and City of Austin, Texas and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.

.I

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-80 is hereby amended to read as follows:

2.

Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 71, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

The license amendment is effective as of its date of issuance to be implemented within 30 days of issuance.

1 FOR THE NUCLEAR REGULATORY COMMISSION I

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Thomas W. Alexion, Projec Manager Project Directorate IV-1 i

Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

August 13, 1996

ATTACHMENT TO LICENSE AMENDMENT NOS. 84 AND 71 FACILITY OPERATING LICENSE NOS. NPF-76 AND NPF-80 DOCKET NOS.'50-498 AND 50-499 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain marginal lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.

1 REMOVE INSERT 3/4 6-1 3/4 6-1 3/4 6-2 3/4 6-2 3/4 6-5 3/4 6-5 3/4 6-6 3/4 6-6 B 3/4 6-1 B 3/4 6-1 6-18a

3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

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

ACTION:

Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within I hour or 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 />.

SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall 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 as provided in Specification 3.6.3; b.

By verifying that each containment air lock is in compliance with the requirements of 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 verification need not be performed more often than once per 92 days.

SOUTH TEXAS - UNITS 1 & 2 3/4 6-1 Unit 1 - Amendment No. Gh80, 84 Unit 2 - Amendrtent No. 50d9, 71

CONTAINMENT SYSTEME CONTAINMENT LEAKAGE LIMITING CONDITION 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 either the measured overall integrated containment leakage rate or the l

measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding the allowances in the Containment Leakage Rate Testing Program, restore the overall integrated leakage rate and the combined leakage rate for all penetrations subject to Type B and C tests to within the allowances in the Containment Leakage Rate Testing Program within I hour or 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 />.

SURVEILLANCE RE0VIREMENTS 4.6.1.2 Perform required visual examinations and leakage rate testing in accordance with the Containment Leakage Rate Testing Program.

The provisions of Specification 4.0.2 are not applicable.

4 SOUTH TEXAS - UNITS 1 & 2 3/4 6-2 Unit 1 - Amendment No. 25,51,75,80, 84 Unit 2 - Amendment No. 45,50,54,50,71

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

a.

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

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 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 />; and 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 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 />.

SOUTH TEXAS - UNITS 1 & 2 3/4 6-5 Unit 1 - Amendment No. 6h80, 84 Unit 2 - Amendment No. 50,69, 71

CONTAINMENT SYSTEMS SURVEILLANCE REOUIREMENTS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:

a.

By verifying leakage rates in accordance with the Containment Leakage Rate Testing Program.

b.

At least once per 6 months by verifying that only one door in each l

air lock can be opened at a time.

c.

By verifying at least once per 7 days that the instrument air l

pressure in the header to the personnel airlock seals is 2 90 psig.

d.

By verifying the door seal pneumatic system OPERABLE at least once l

per 18 months by conducting a seal pneumatic system leak test and verifying one of the following:

1)

That system pressure does not decay more than 1.5 psi from 90 psig minimum within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or 2)

That system pressure does not decay more than.50 psi from 90 psig minimum within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

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SOUTH TEXAS - UNITS 1 & 2 3/4 6-6 Unit 1 - Amendment No. 51,5',00, 84 i

Unit 2 - Amendment No. 50,53,50, 71 i

CONTAINMENT SYSTEMS BASES 3/4.6.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensure that the overall containment average air temperature does not exceed the initial temperature condition assumed in the safety analysis for a LOCA or steam line break accident. Measurements shall be made by fixed instruments, prior to determininq the average air temperature.

3/4.6.1.6 CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standards for the life of the facility.

Structural integrity is required to ensure that the containment will withstand the maximum pressure of 41.2 psig (P,) in the event of a LOCA l

or steam line break accident. The measurement of containment tendon lift-off force, the tensile tests of the tendon wires, the visual examination of tendons, anchorages and exposed interior and exterior surfaces of the containment, and the Type A leakage test are sufficient to demonstrate this capability.

i The Surveillance Requirements for demonstrating the containment's structural integrity are in compliance with the recommendations of Regulatory i

Guide 1.35, " Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containment Structures," and proposed Regulatory Guide 1.35.1, " Determining Prestressing Forces for Inspection of Prestressed Concrete Containments,"

April 1979.

The required Special Reports from any engineering evaluation of containment abnormalities shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedures, the tolerances on cracking, the results of the engineering evaluation, and the corrective actions taken.

3/4.6.I.7 CONTAINMENT VENTILATION SYSTEM The 48-inch containment purge supply and exhaust isolation valves are required to be sealed closed during plant operations since these valves have not been demonstrated capable of closing during a LOCA or steam line break accident. Maintaining these valves sealed closed during plant operation ensures that excessive quantities of radioact M materials will not be released via the Containment Purge System. To provide assurance that these containment valves cannot be inadvertently opened, the valves are sealed closed in accordance with Standard Review Plan 6.2.4 which includes mechanical devices to seal or lock the valve closed, or prevents power from being supplied to the valve operator.

The use of the containment purge lines is restricted to the 18-inch purge supply and exhaust isolation valves since, unlike the 48-inch valves, the 18-inch valves are capable of closing during a LOCA or steam line break accident. There-SOUTH TEXAS - UNITS 1 & 2 B 3/4 6-2 Unit 1 - Amendment No. 61 Unit 2 - Amendment No.50

3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures 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 dose guidelines values of 10 CFR Part 100 during accident conditions.

3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the safety analyses at the peak accident pressure, P, (41.2 psig). As an added conservatism, the measured overall integrated leakage rate is further limited before returning the Unit to service to less than or equal to 0.75 L, iodic test to account for possible degradation following performance of the per of the containment leakage barriers between leakage tests.

The surveillance testing for measuring leakage rates is consistent with the requirements of 10 CFR Part 50, Appendix J, Option B, and in accordance with the Containment Leakage Rate Testing Program.

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

The surveillance testing for measuring leakage rates is consistent with the requirements of 10 CFR Part 50, Appendix J, Option B and in accordance with the Containment Leakage Rate Testing Program.

3/4.6.1.4 INTERNAL PRESSURE 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 outside atmosphere of 3.5 psig, and (2) the containment peak pressure does not exceed the design pressure of 56.5 psig during LOCA or steam line break conditions.

The maximum peak pressure expected to be obtained from a LOCA or steam line break event is 41.2 psig (P The limit of 0.3 psig for initial positive containment pressure wil)l limit the total pressure to 41.2 psig, which is less than design pressure and is consistent with the safety analyses.

SOUTH TEXAS - UNITS 1 & 2 B 3/4 6-1 Unit 1 - Amendment No. 61,64 Unit 2 - Amendment No. 60,71

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ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) j)

Containment Leakaae Rate Testina Proaram A program shall be established to implement the leakage rate testing of the primary containment as required by 10 CFR 50.54(o) and 10 CFR Part 50, Appendix J. Option B, as modified by approved exemptions.

This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak-Testing Program", dated September 1995.

Peak calculated primary containment internal pressure for the design basis loss of coolant accident (LOCA), P, is 41.2 psig.

The maximum allowable primary containment leakage rate, L,, is 0.3%

of primary containment air weight per day.

Leakage rate acceptance criteria are:

a.

Primary containment overall leakage rate acceptance criterion is s 1.0 L. During the first unit start-up following testing in accorda,nce with this program, the leakage rate acceptance criteria are s 0.60 L, for the combined Type B and Type C tests, and s 0.75 L, as-left and s 1.0 L, as-found for Type A tests.

j b.

Air lock testing acceptance criteria for the overall air lock leakage rate is s 0.05 L, when tested at ;t P,.

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The provisions of Surveillance Requirement 4.0.2 do not apply to the test intervals specified in the Containment Leakage Rate Testing Program.

The provisions of Surveillance Requirement 4.0.3 apply to the Containment Leakage Rate Testing Program.

SOUTH TEXAS - UNITS 1 & 2 6-18a Unit 1 - Amendment No. 84 Unit 2 - Amendment No. 71 i