ML20029B302

Proposed Tech Spec Surveillance 4.6.1.2 Re Containment Leakage Rates

ML20029B302
Person / Time
Site:	South Texas
Issue date:	02/26/1991
From:	HOUSTON LIGHTING & POWER CO.
To:
Shared Package
ML20029B301	List: ML20029B300 ML20029B302
References
NUDOCS 9103070024
Download: ML20029B302 (4)

Text

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ATTACllMENT 2 PROPOSED CllANCE TO TECl!NICAL SPECIFICATION SURVEILLANCE 4.6.1. 2 A1/011 N20 9103070024 910226 PDR P ADOCK 05000498 PDR __ _ _ _ _ _ _ _ _ _ _ _ _ _

- e.i i AdiUIE~Tl ST-HL AE 3703 0F- 1 PAGE 3 C0%iAINMENT SYSTEMS

( COWAINMENT LEAKAGE LMllE_1QRlllGLl0]LOPJfellp1 _

3. f .1. 2 Containment leakage rates chall be limited to:

a.

An overall integrated leakage rate of less than or equal0.30% to L,,~

by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P,,37.5 psig.

b.

A combined leakage rate of less than 0.60 L, for all penetrations and valves subject to Type d and C tests, when pressurized to P .

3 APk1CABILITY: MODES 1, 2, 3, and 4. '

ACHON: .

Win either the measured overall 0.E L, or the nicasured combineo leatage rate for all penetrations and valves.itegra sutject to Types B and C tests exceeding 0.60 L,, restore the overall inte-gra,ed leakage rate to less than 0.75 L, and the combined leakage rate for all pet +trations sJbject to Type B and C tests to less than 0.60 L prior to in-crusing the Reactor Coolant System temperature above 200'f. a

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4. f . ) . 2 The containment leakage rates shall be demonstrated at the fo lowing ten schedule i and shall be determined in conformence with the criteriaVspeci-fidA n

-H% ' A9W. Appendix J of 10 CFR Part 50;Weng-t-he-minWand-prov4+40nF+f-AREl-a.

Three Type A tests (Overall Integrated Containment Leakage Rate) ' '

, shall be conducted at 40110 month intervals during shutdown et a pressure not less than P,, 37.5 psig, during each 10 year service period.

.g9<l The third test of each set shall be conducted during the shutdown for the 10 year plant intervice inspection; SOU'H TEXAS - UNITS 1 & 2 3/4 6-2 1

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i ATTACllMENT 3 UPDATED FINAL SAFETY i ANALYSIS REPORT .-,

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• PAGE _.L OF J There are no radiolytic or pyrolytic decomposition products from these

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t. .5.6.2 Surolettentary containment Purge Eauirment: This equipment is described in Section 9.4.5.

6.2.6 Containment 1eakage Testin6 The Reactor Containment Integrated Leakage' Rate Test (Type A), the Containment Penetration Leakage Rate Test (Type B), and the Containment Isolation Valve i.eakaBe Race Test (Type C) comply with 10CFR50, Appendix A, ' General Design Criteria", and Appendix J. ' Primary Reactor Containment Leakage Testing for Vater Cooled Power Reactors'.

6.2.6.1 Containment Interrated Leakage Rate Test (Tyre A). After completion of et.nstruction of the primary Reactor Containment, including installation of all portions of mechanical, electrical, and instrumentation systems penetrating the primary reactor coolant pressure boundary (RCPB), and prior to any reactor operation, a peak pressure integrated leak rate test (ILRT) was performed in accordance with Appendix J to 10CTR50. The purpose of this test wast (a) to verify that the integrated leakage rate will not exceed the 0.3 percent by weight of Containment free air volume in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at the calculated peak accident pressure given in Section 6.2.1.1.3; and (b) to obtain data to establish a baseline leakage rate to serve as a reference for future Containment leak testing. A preoperational reduced pressure leak rate test was not performed. No consistent correlation has been observed between reduced and full pressure ILRTS.

A general inspection of the accessible interior and exterior surfaces of the Containment structure shall be performed prior to any Type A test. The purpose of this inspection is to uncover any evidence of structural daterioration which may affect either the Containment structural integrity or leaktightness. Any evidence of structural deterioration shall be cause not to perform Type A tests until corrective action is taken in accordance with repair procedures, nondestructive examinations, and tests as specified in the applicable code stated in 10CFR50.55a.

During preoperational testing, a structural integrity test (SIT) is performed prior to the first ILRT. The SIT is discussed in Section 3.8.1.7.

The ILRT is performed at the calculated peak accident pressure to demonstrch that the leakage rate of the Reactor Containment Building does not exceed 0.3 percent by weight Containment free air volume at the test pressure per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 7 period.WThe-absolute pressure / temperature-method-delineated -in- ANSI-N45T4 -

[ _ 1972-ehall-be-employed for-determining leakage-rate F Containment temperature, pressure,-dow-point-temperature,_and-ambient-barometric pressure are-j

-periodically _ monitored- during-the test m The -selection-of leakage rate'-

_ measuring, instrumentation-and the-Type-A test-procedure,is also-in accordance-

.with ANSI-N4524-1972 r-Test- duration -is-in accordance with-100FR50r

_ Appendix J. Localized pressure tests may be employed prior to Type A tests.

Those portions of fluid systems that are part of the RCPB or are open directly to the Containment atmosphere under post accident conditions, and become an

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extension of the boundary of the Containment, are designed to be opened or vented to the Containment atmosphere prior to and during the test. Portions

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