ML20072Q984

Safety Evaluation Supporting Amends 64 & 53 to Licenses NPF-76 & NPF-80,respectively

ML20072Q984
Person / Time
Site:	South Texas
Issue date:	08/29/1994
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20072Q948	List: ML20072Q945 ML20072Q984
References
NUDOCS 9409120317
Download: ML20072Q984 (3)

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NUCLEAR REGULATORY COMMISSION 5

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WASHINGTON, D C. 20555-0001 l

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HOUSTON LIGHTING & POWER COMPANY l

CITY PUBLIC SERVICE BOARD OF SAN ANTONIO i

CENTRAL POWER AND LIGHT COMPANY

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CITY OF AUSTIN. TEXAS i

i DOCKET NO. 50-499 SOUTH TEXAS PROJECT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 53

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License No. NPF-80 1.

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

i A.

The application for amendment by Houston Lighting & Power Company *

(HL&P) acting on behalf of itself and for the City Public Service

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Board of San Antonio (CPS), Central Power and Light Company (CPL),

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and City of Austin, Texas (C0A) (the licensees), dated April 28, 1994, complies with the standards and requirements of the Atomic i

Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; 4

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4 B.

The facility will operate in conformity with the application, as i

amended, the provisions of the Act, and the rules and regulations of l

the Commission; i

C.

There is reasonable assurance:

(i) that the activities authorized I.

by this anendment 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; i

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 i

of the Commission's regulations and all applicable requirements have been satisfied, i

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

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 9409120317 940829 PDR ADOCK 05000498 P

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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-80 is hereby amended to read as follows:

2.

Technical Soecifications The Technical Specifications contained in Appendix A, as revised i

through Amendment No. 53, 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 10 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION y s h.:-- o. & &

William D. Beckner, Director Project Directorate IV-1 Division of Reactor Projects III/IV

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Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical i

Specifications l

Date of Issuance:

August 29, 1994

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ATTACHMENT TO LICENSE AMENDMENT N05.64 AND 53 FACillTY OPERATING LICENSE NOS. NPF-76 AND NPF-80 DOCKET NOS. 50-498 AND 50-499 Replace the following page of the Appendix A Technical Specifications with the attached page. The revised page is identified by Amendment number and contains a marginal line indicating the areas of change.

The corresponding overleaf page is also provided to maintain document completeness.

REMOVE-INSERT 3/4 6-6 3/4 6-6

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i CONTAINMENT SYSTEMS I

_C_0NTAINMENT AIR LOCKS 4

LIMITING CONDITION FOR OPERATION 4

3.6.1.3 Each containe.ent air lock shall be OPERABLE with:

Both doors closed except when the air lock is being used for normal a.

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 of less than or equal to 0.05 L, at P., 41.2 psig.

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

i ACTION:

a.

With one containment air lock door inoperable:

1.

Maintain at least the OPERABLE air lock door closed and either i

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 i

required overall air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed at least j

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 4

hours 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 />.

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SOUTH TEXAS - UNITS 1 & 2 3/4 6-5 Unit 1 - Amendment No. 61 Unit 2 - Amendment No. 50 1

CONTAINMENT SYSTEMS SURVEILLANCE RE0VIREMENTS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:

a.

Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following each closing, except when the air lock is being used for multiple entries, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, by verifying seal leakage is less than 0.01 L as determined by precision flow measurements when measured for at least 30 seconds with the volume between the seals at a constant pressure not less than P,;

b.

By conducting overall air lock leakage tests at not less than P,,

41.2 psig, and verifying the overall air lock leakage rate is within its limit:

1)

At least once per 6 months,* and 2)

Prior to establishing CONTAINMENT INTEGRITY when maintenance has been performed on the air lock that could affect the air lock sealing capability.**

c.

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

d.

By verifying at least once per 7 days that the instrument air pressure in the header to the personnel airlock seals is 2 90 psig.

e.

By verifying the door seal pneumatic system OPERABLE at least once 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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• The provisions of Specification 4.0.2 are not applicable.

• • This represents an exemption to Appendix J, paragraph III.D.2 of 10 CFR Part 50.

SOUTH TEXAS - UNITS 1 & 2 3/4 6-6 Unit 1 - Amendment No. H,64 Unit 2 - Amendment No. M,53

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NUCLEAR REGULATORY COMMISSION y w4/

WASHINGTON. D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N05.64 AND 53 TO FACILITY OPERATING LICENSE NOS. NPF-76 AND NPF-80 HOUSTON LIGHTING & POWER COMPANY i

CITY PUBLIC SERVICE BOARD OF SAN ANTONIO 1

CENTRAL POWER AND LIGHT COMPANY CITY OF AUSTIN. TEXAS DOCKET NOS. 50-498 AND 50-499 i

SOUTH TEXAS PROJECT. UNITS 1 AND 2

1.0 INTRODUCTION

By application dated April 28, 1994, Houston Lighting & Power Company, et.al.,

(the licensee) requested changes to the Technical Specifications (TSs)

(Appendix A to Facility Operating License Nos. NPF-76 and NPF-80) for the South Texas Project, Units 1 and 2 (STP). The proposed changes would revise TS 4.6.1.3.e to add an option that will allow the personnel airlock pneumatic system leak test to be completed in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with a pressure drop of 0.50 psi.

2.0 DISCUSSION Both units at STP have a main personnel airlock which consists of an inner door and an outer door.

The door seal pneumatic system consists of a three-way ball valve which inflates and deflates the seals, an air reservoir tank which provides sufficient capacity to maintain the seals for 15 days without instrument air, and a check valve that ensures the reservoir tank maintains capacity.

With a door in the closed position, two seals are inflated against the airlock barrel to provide containment integrity.

TS 4.6.1.3.e requires the door seal pneumatic system be verified operable at least once per 18-month period by " verifying that the 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 />." This requirement is met by performing OPSP11-XC-0009, " Personnel Airlock Pneumatic Seal System Pressure Drop Test." A minimum of 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> is required to complete test OPSP11-XC-0009.

For this reason, the test is scheduled at the outage conclusion.

As a result, the test is always on critical path for restart following an outage. The proposed change to the TS would add the option of the personnel airlock pneumatic system leak test to be completed in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with a pressure drop of 0.50 psi.

The suggested optional test would shorten a critical path item and thus expedite return to operation.

. 3.0 EVALVATION The proposed change does not alter the door pneumatic seal system pressure decay test, but does provide an optional 8-hour decay test.

Generally, higher leakage is observed at the beginning of the test period and experience has shown that leaks do not suddenly manifest themselves late in' the test, after conditions have stabilized.

By verifying tha; system pressure does not decay more than 0.50 psi within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, the optional test limits the average maximum leakage rate to the same value of the current' test of not more than a pressure drop of 1.5 psi within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Empirical data shows that pressure decay-test failures can be predicted very early in the test. The proposed optional test duration is consistent with ANSI /ANS-56.8-1987, " Containment System Leakage Testing Requirements," and conservative engineering practices recognize that pressure leaks typically stabilize within an hour. Based on the above, the staff finds that the

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proposed alternative 8-hour test is acceptable for STP.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Texas State official was notified of the proposed issuance of the amendments.

The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change a surveillance requirement.

The NRC staff has determined that the amendments involve no significant increase in the amounts, j

and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.

The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (59 FR 27057).

Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).

Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be l

prepared in connection with the issuance of the amendments.

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6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, l

that:

(1) there is reasonable assurance that the health and safety of the

.... i public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common i

defense and security or to the health and safety of the public.

Principal Contributor:

A. Bryant, NRR Date: August 29, 1994 l

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