ML20078H901

Proposed Tech Spec 3/4.6.1.2 Re Containment Sys, Containment Leakage & Associated Bases 3/4.6.1.2,primary Containment & Containment Leakage

ML20078H901
Person / Time
Site:	Davis Besse
Issue date:	01/30/1995
From:	CENTERIOR ENERGY
To:
Shared Package
ML20078H900	List: ML20078H897 ML20078H901
References
NUDOCS 9502070090
Download: ML20078H901 (4)

Text

.

- - LAR 94-0014 Page 6 CONTAINMENT SYSTEMS

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CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION j 3.6.1.2 Containment leakage rates shall be limited to:

0.50 percent by weight  ;

a. Anof theoverall integratdd containment air per leakage rate 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P,. of < L ,38 psig.  :

b. A combined leakage rate of < 0.60 L,. for all penetrations and valves subject to Type B and C tesEs. when pressurized to P,.  ;

c. A combined leakage rate of < 0.03 L, for all penetrations that are secondary containment bypass leakage paths, when pressurized to P .  !

d. A single penetration leakage rate of < 0.15 L for the containment purge and exhaust isolation valve special tesl.

APPLICABILITY: MODES 1. 2. 3 and 4.

ACTION:

a. With either (a) the measured overall integrated containment leakage t b) with the measured combined leakage rate rate for allexceeding penetrations 0.75anL. (d valves subject to Type B and C tests exceeding 0.60 L,. or (c) with the combined bypass leakage rate exceeding 0.03 L,. restore the leakage rate (s) to within the limit (s) -

prior to increasing the Reactor Coolant System temperature above 200 F.

b. With a single containment purge and exhaust isolation valve penetration having leakage rate exceeding 0.15 L, restore the '

i leakage rate to within limits in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 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 '

i following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

l SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following i test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4 - 1972:

a. Ttmee Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 10110 '"onth intervi during shutdown at

( q b . D 3i bflapproyediexed DAVIS-BESSE. UNIT 1 3/4 6-2 Amendment 90 I46 I60 950207o090 950130 PDR ADOCK 05000346  !

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9 LAR 94-0014 Pcgs 7 CONTAINMEN'T SYSTEMS S'URVElltANCE REQUIREMENTS (Continued) ,

b. If any periodic Type A test fails to meet 0.75 L,. the test schedule for subsequent Type A tests shall be reviewed and approved by the Commission. If two consecutive Type A tests fail to meet 0.75 L,. a Type A test shall be performed at least every 18 months until two consecutive

,-uma. .u Type A tests meet 0.75 L,@ at dich the the 2cyc test

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c. The accuracy of each Type A test shall be verified by a supplemental 4 test which: .

1. Confirms the accuracy of the Type A test by verifying that the ,

difference between supplemental and Type A test data is within j 0.25 L,.

2. Has a duration sufficient to establish accurately the change in leakage between the Type A test and the supplemental test.

3. Requires that the rate at which gas is injected into the  ;

containment or bled from the containment during the supplemental test is between 0.75 L, and 1.25 L,. .

38 psig, at i

d. Type B and intervals C tests than no greater shall24 bemonths conducted with except forgas testsat P , involving air locks.

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e. The combined bypass leakage rate shall be determined to be < 0.03 L, -

by applicable Type B and C tests at least once every 24 months except for penetrations which are not individually testable; '

penetrations not individually testable shall be determined to have no detectable leakage when tested with soap bubbles while the containment is pressurized to P., 38 psig, during each Type A test.

f. Air locks shall be in compliance with the requirements of Specification 3/4.6.1.3.

DAVIS-BESSE. UNIT 1 3/4 6-3 Amendment No. 90.I20.I60.

194

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4 1AR 94-0014 THIS PAGE PROVIDED l

, CONTAINMENT SYSTEMS FORINFORMATION ONIY SURVEILLANCE REQUIREMENTS (Continued) l

g. Each time the containment purge and exhaust isolation valves are l opened, a special test shall be perfonned within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> af ter valve closure or prior to entering MODE 4 from H0DE 5, whichever j is later. The special test is conducted by pressurizing the piping section including one valve inside and one valve outside the contairunent to a pressure greater or equal to 20 psig. The leakage rate per penetration shall not exceed 0.15 L

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h. The special test as defined in Surveillance Requirement 4.6.1.2 9 shall be performed for the containment purge and isolation valves  !

when the plant has been in any combination of MODES 3, 4, 5 or 6 for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided that the test requiredLby Surveil-lance Requirement 4.6.1.2 9 has not been perfonned in the previous

, 6 monttc i

1. All tea 1okage rate, shall be calculated using observed data l converi 4 to absolute values. Error analyses shall be perfonned to select 3 balanced integrated leakage measurement system.

j. The provisions of Specification 4.0.2 are not applicable.

l DAVIS-BESSE UNIT 1 3/4 6-4 Amendment No, SD. 160 L

. LAR 94-0014 Page 9 3/4.6 CONT'AINMENT SYSTEMS i BASES -

3/4.6.1 PRIMARY CONTAINMENT i 3/4.6.1.1 CONTAINMFNT 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 and air lock door requirements, will limit the site boundary radiation doses to within the limits of 10 CFR 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 of 38 psig. Pa. As an added conservatism, the measured overall integrated leakage rate is further limited to < 0.75 L,, during performance of the periodic tests to account for possible degradation of the containment leakage barriers between leakage tests.  !

The surveillance testing for measuring leakage rates are consistent with .

the requirements of 10 CFR Part 50, Appendix J with the following exemation.  !

The third test of each Type A tetting set need not be conducted when tie plant is shutdown

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The special test for the containment purge and exhaust isolation valves t is intended to detect gross degradation of seals on the valve seats. The special test is performed in addition to the Appendix J requirements.

USAR 6.2.4 identifies all penetrations that are secondary containment bypass leakage paths.

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

DAVIS-BESSE. UNIT 1 B 3/4 6-1 Amendment No. 90.I46'I60, .

194 I

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