ML17352A264

Proposed Tech Specs Revising Surveillance Requirement 4.6.1.2a & Associated Bases to Conform w/NUREG-1431,STS, Westinghouse Plants,Rev 0

ML17352A264
Person / Time
Site:	Turkey Point
Issue date:	10/04/1993
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17352A263	List: ML17352A262 ML17352A264
References
RTR-NUREG-1431 NUDOCS 9310120275
Download: ML17352A264 (6)

Text

ATTACHMENT 3 Proposed Technical Specifications Marked-up Technical Specification Pages 3/4 6-2 S 3/4 6-X 9310120275 9>MO+-

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CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION

3. 6. 1. 2 Containment leakage rates shall be limited to:

a. An overall integrated leakage rate of less than or-equal 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, 49.9 psig.

a'.25K a'.

A combined leakage rate of less than 0.60 L for all penetrations and valves subject to Type B and C tests, when pressurized to APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

With either the measured overall integrated containment leakage rate exceeding 0.75 L or the measured combined leakage rate for all penetrations and valves subject to Types 8 and C tests exceeding 0. 60 L , restore the overall integrated leakage rate to less than 0.75 L and the combined leakage rate for all penetrations subject to Type B and C tests to less than 0.60 L prior to increasing the Reactor Coolant System temperature above 200'F.

SURVEILLANCE RE UIREMENTS 4.6. 1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria speci-fied in Appendix J of 10 CFR Part 50 using the methods and provisions of ANSI N45.4-1972:

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a e A tests (Overall Integrated Containment Leak t

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shall be con 40 + 10 month intervals 'hutdown at a pressure not less than , .9 , r>ng each 10-year service period. The third each set sha nducted during the shutdow e 10-year plant inservice inspection, TYPE A +est ahall be PeaA>r mac> te AccaaDAu(c mn-H tO CFR. SO hPPEVQlX D, hS &OQivt5& 8w APPcoV Ec7 C'kL MPT70AJZ, TURKEY POINT - UNITS 3 8( 4'/4 6-2 AMENDMENT NOS.137AND 132

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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 restric-tion, in conjunction with the leakage rate limitation, will limit the SITE BOUNDARY radiation doses to within the dose guideline 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 .'s an added conservatism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 L during performance of the periodic test to account for possible degradation of the containment leakage barriers between leakage tests.

The surveillance testing for measuring leakage rat s is consi nt w't the requirements of Appendix J of 10 CFR Part 50. ao rnooinlmDBY nponoumm Rsetnpfsons i 3/4. 6. 1. 3 CONTAINMENT AIR LOCKS add 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. In order to meet the ACTION requirement to lock the OPERABLE air lock door closed, the air lock door inter-lock may provide the required locking. In addition, the outer air lock door is secured under administrative controls.

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 of 2.5 psig with respect to the outside atmosphere, and (2) the containment peak pressure does not exceed the design pressure of 59 psig during LOCA conditions.

The maximum peak pressure expected to be obtained from a LOCA event is 49.9 psig assuming an initial containment pressure of 0.3 psig. An initial positive pressure of as much as 5 psi would result in a maximum containment pressure that is less than design pressure and is consistent with the safety analyses.

TURKEY POINT " UNITS 3 8t 4 B 3/4 6-1 AMENDMENT NOS. I37AND 132

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