ML20236Y377

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Proposed Tech Spec 4.6.1.2c.3,Section 3/4.6.1.2 Re Containment Sys & Containment Leakage
ML20236Y377
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 12/08/1987
From:
TOLEDO EDISON CO.
To:
Shared Package
ML20236Y344 List:
References
NUDOCS 8712110280
Download: ML20236Y377 (4)


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COIrfAI1OINT SYSTDfS FORlNFeMBHM ,

l C0!ffAIMfDT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Coatsineemt leakage rates shall be limited to: ,

s. An overall integrated leakage rate of f L 0.50 percent by weight of the contalement air per 24 hourl,at F,, 38 peig.
b. A combined leakage rate of ( 0.60 L valves subject to Type 8 ami C test when $,for pressurized all penetrations-to P,.

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c. A combined leakage rate of i 0.015 L, for all penetrations identified in Table 3.6-1 as 62condaPy containment bypass leakage paths, when pressurized te P,.
d. A single penetration leakage rate of i 4.15 L purge and eahaust isolation valve special test.for the containment APPLICABILITY: NOCE 1, 2, 3 and 4.

ACTION: .

a. With either (a) the seasured overall integrated containment '

leakage rate exceeding 0.75 L leakage rate for all penetration (b) valves s and with the seasured subject to Typecombined 8

and C tests exceeding 0.60 L , or (c) with the combined bypass 8

leakage rate exceeding 0.0151 restore the leakage rate (s) to within the limit (s) prior to 1$c,reasing the Reactor Coelast Systaa temperstare above 200*F.

b. With a single contaissent perse and enhaast isolation valve penetraties havias leakage este eseeeding 0.15 L g restore the leakage rete to withis limits in 73 hears or be la at least NDT STANDBY vithis the seat 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN withis the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURW.ILIANCE REQUIREMENTS 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 specifie in Appendia J of 10 CR 50 using the methods and provisions of ANs(r N45.4 - 1972:

s. Three Type A tests (Overall Integrated Containment Leakage Rate) ,i Waltbe conducted at 40 + 10 month intervals during shutdown at i P 38 pois, during each I0 year service period. The third test

'of,eachsetshallbeconductedduringtheshutdownforthe10 year plaat inservice inspection.

8712110280 871200 DR p ADOCK0500g6 3/4 6-2 Amendment No. 90

g CONTAINMDrT SYSTDIS

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SURVEILLANCE REQUIRDIENTS (Continued) b.

If any periodic Type A test fails to meet .75 L the test scheduleforsubsequentTypeAtestsshallber$v,iewedand approved by the Commission.

If two consecutive Type A tests fail to meet .75 L , a Type A test shall be performed at least at which time the above test schedule may be resu c.

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

1.

Confires the accuracy of the Type A test by verifying that the difference between supplemental and Type A test data is

  • within 0.25 L,.

2.

Nas a duration sufficient to establish accurately the change in leakage between the Type A test sod the supplemental test.

3. Requires th& ther;de et 44 h3 iss 3 r tit; :f sas injected isto the containment or bled from the containment during the supplemental test is t: 5: :;;irl : t: et**1p::t  ?" pr:::t rf 't: t:t:1 r :: =:f 1:i;;; ::t: :t ?,, i;;-

bake o.Hi Lo. W l.25 L(-

d.

TypeBandCtestsshallbeconductedwithgasatPl,38puis,a intervals no greater than 24 months except for test involving:

1. Air locks, a; 2.

penetrations and using continuous leakage monitorir.g systems, 3.

7alves pressurized with fluid free a seal system.

e.

The cookimed bypass leakage rate shall be determined to be

< 0.015 L by applicable Type B and C tests at least once every 24 montha'escept for penetrations dich are not individually testable; penetrations not individually testable shall be determined to have ne detectable leakage when tested with soap bubbles during eachwhile Type the containment is pressurized to 38 A test. F,,pois, f.

Air locks shall be tested and demonstrated OpERABI.E per Surveillance Requirement 4.6.1.3.

DAVIS-BESSE, UNIT 1 3/4 6-3 Amendeent No. 90

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{o} m mod CONTAIMMElfT SYSTDfS J 0 l

BURVEIIIANCE REQUIREMENTS (Continued) 3 Leakage from isolation valves that are sealed with fluid from a seal system may be excluded, subject to the provisions of Appendiz J Section III.C.3, when determining the combined leakage rate provided the seal system and valves are pressurized to at least 1.10 P , 41.8 pois, and the seal system capacity is adequate tomaintainlystempressureforatleast30 days. l

h. Type 3 tests for penetrations employing a coat'inuous leakage monitoring system shall be conducted at F,, 34 pois, at intervals no greater than once per 3 years.
1. Each time the containment parse and exhaust isolation valves are i opened, a special test shall be performed withia 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after i valve closure or prior to entering mode 4 from mode 5, whichever is later. The special test is conducted by pressurizing the piping sectiou including one valve inside and one valve outside the con-tainment to a pressure greater or equal to 20 psig. The leskage ,

rate per penetration shall not exceed 0.15 L,.

j. The special test as defined in surveillance Requirement 4.6.1.2.1 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 tests required by Sur-veillance Requirements 4.6.1.2.1 or 4.6.1.2.d have not been performed in the previous 6 months.

t k. All test Icakage rates shall be calculated using observed data converted to absolute values. Error analyses shall be performed to select a balanced integrated leakage measurement system.

1. The provisions of Specification 4.0.2. are not applicable.

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DAVIS-BESSE, UNIT 1 3/4 6-4 Amendment No. 90 l _ _ _ _ _ - - - - - - - - _ - - - .

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3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAI MENT INTEGRITY Primary CONTAIMENT 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, vill limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.

3/4.6.1.2 CONTAINMENT LEAKAGE 4

The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value asstaned ir, the safety analyses at the peak accident pressure of 38 psig, P . As an added conservatism, the measured overall integrated leakage,ra'te is during performance of the periodic tests to accountlimited further for possible to degra

< 0.75 L ,dation of the containment leakage between leakage tests.

  • The surveillance testing for measuring leakage rates are consistent L

with the requirements of Appendix "J" of 10 CFR 50.

The special test for the containment purge and exhaust isolation valves seats.

is intended to detect gross degradation of seals on the valve The special test is performed in addition to the Appendix J requirements. ,

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3/4.6.1.3 CONTAINMENT AIR LOCKS l

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The limitations on closure and leak rate for the containment air I locks are required to meet the restrictions on CONTA!WENT INTEGRITY and containment leak rate. Surveillance testing of the air lock seats  !

provide assurance that the overall air lock leakage will not become 1 excessive due to seal damage during the intervals between air lock l leakage tests.

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i DAVIS-BESSE. UNIT 1 B 3/4 6-1 A.'endment No. 90 )