ML20114B116

Proof & Review Combined TS 3.6.1.2 Re Containment Leakage Rates & 3/4.6.1.2 Re Limitations on Containment Leakage Rates

ML20114B116
Person / Time
Site:	Comanche Peak
Issue date:	08/21/1992
From:	TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
Shared Package
ML20114B114	List: ML20114B112 ML20114B116
References
NUDOCS 9208250016
Download: ML20114B116 (4)

Text

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- ', : Attachment to TXX 92407 Page 1 of 3 hh CONTAINi?ENT SYSTEMS CONTAINMENT LEAKACE

$h$Y LIMITING CONDITION FOR OPERATivN 3.6.1.2 Containment leakage rates shall be limited to:

a. An overall integrated leakage rate of

~

1) ([essthanorequaitol,,0.10%byweightofthecontainment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P a 18.3 psig g T2) Le than or qual to L , r05% by w 'ght'of th fifainment[

j perJ rs at y de ed pr3s of P g psia. J

b. 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 P '

a APPLICABIL!TY: MODES 1, 2, 3, and 4.

- ACTION: ,

With either_the measured overall integrated containment leakage rate exceeding 0.75 L a b*"' 7 ' t, p s--eppueabT r the measured combined leakage rate for all penetrations and valves subject to Types B and C tests excaeding 0.60 L,,

restoretheoverallintegratedleakageratetolessthan0.75L,{TB: th g l 6ffr-t[as-apt >14cabTCband 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 REQUIREMENTS l

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 50:

a. Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 1 10 n,onth intervals during shutdown at a pressure not less than eb P,, 48.3 psigf-ce]-et ,",, 24d7 M during each 10 year service period. The third test of each set she'l be conducted during the shutdown for the 10 year plant inservice inspection; COMANCHE PEAK - UNITS 1 AND 2. 3/4 6-2

$k bo f P

fa e 3 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) , _

b. IfanyperiodicTypeAtestfailstomeet)g 305k h the test schedule for subsequent Type A tests shall be reviewed and"'

approved ey the Commission. If two consecutive Type A tests fail to mect Q0.75 L, (5&c. 7F L], a Tyne A test shall be performed at least ever 0.75 L a O'?bmonths

" until two consecutive Type A tests meet W at which time the above test schedule aay be resumed; c.

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

1)

Confirms the accuracy of the test by verifying that the staple-mental followingtest result, L c, is in accordance with the appropriate equation:

lL c - (L am

• l o) l 5 0.25 La [ ( y - (L tm ^l)II^'

o where L am s the measured Type A test leakage and t o

is the supe-imposed leak; 2)

Has a d;' ration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test; and

3) Requires that the rate at which gas is injected into thc contain-O ment or bled from the containment during the supplemental test is between 0.75 L a and 1.25 L p y S_t aM i d.

Type B and C tests shall be conduct,d with gas at a pressure not less than P,, 48.3 psig, at intervals no greater than 24 months except for tests involving:

1) Air locks, 2)

Containment ventilation isolation valves with resilient material seals, 3)

Safety and injection valves as specified in Specification 4.6.1.2g,

, 4)

Containment spray valves as specified in Specification 4.6.1.2h.

e.

' Air locks shall be tested and demonstrated OPERABLE by the require-ments of Specification 4.6.1.3; f.

Containment ventilation isolation valves with resilient material seals shall be tested and demonstrated OPERABLE by the requirements of Specification 4.6.1.7.2 or 4.6.1.7.3, as applicable; g.

Safety injection valves 880SA, 88098, ano 8840 shall be leak tested with a gas at a pressure not less than Pa , 48.3 psig, or with water than 24atmonths; a pressure not less than 1.1 Pa , at intervals no greater h.

Containment spray valves HV-4776, HV-4777, CT-142, and CT-145 shall be leak tested with water at a pressure not less than 1.1 P , at interval.s no greater than 24 months; end a

i. The provisions of Specification 4.0.2 are not applicable.

COMANCHE PEAK - UN? f51 AND 2 3/4 6-3

Attachment to TXX-92407

. Page 3 of 3 gg 3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY .

Primary CMTAINMENT INTEGRITY ensures that the release of radioactive materials froc the containmer,t atmosphere will bc restricted to those leakage paths and associated leak rates assumed in the safety snalyses. This restric-tion, in conjunctivn with the leakage rate limitation, will limit the EXCLUSION AREA BOUNDARY radiation doces to within the dose guideline values of 10 CFR 100 during accident conditions.

3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakege rates ensure thac the tor,al containment leakage volume will not exceed the value assumed in the safety analyses at the peak accident pressure, P . As an added conservatism, the 3

measured overall integrated leakage rate is further limited to less than or equal to 0.75 L, Q 7p L , 1a m p Hea @ eduring perfonrance cf the periodic

,  : test to account for possible degradation of the containment leakage barriers between leakage tests.

For specific system configurations, credit may be taken for a 30-day water seal that will be maintained to prevent containment atmosphere leakage through the penetrations to the environment. The following is a list of the containment isolation valves that meet this systen configuration and the Maximum Allowed Leakage Rate (MALR) required to maintain the water seal for 30 days.

MALR Valve No. (cc/hr) 1-8809A 77 1-88098 77 2-8809A 75

,, 2-88098 73 1-8840 2577 2-8840 2382 CT-142 4734

, CT-145 4734 l HV-4776 4734 HV-4777 4734 The sur.eillance testing for neasuring leakage rates is consistent with the requirements of 10 CFR 50 Appendix J.

-3/4.6.1.3 CONTAINMENT AIR LOCKS

! The limitations on closure and leak rate for the containment air locks-l are required to meet the restrictions on CONTAINMENT INTEGRITY and containment l leak rate. Surveillance testing ef 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 'aakage tests.

COMANCHE PEAK - UNITS 1 AND 2 8 3/4 6-1 1

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