ML20083L337

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Proposed TS 3.6.1.2 SRs for Containment Leakage,Reflecting Removal of Schedular Criteria for Type a Testing
ML20083L337
Person / Time
Site: Waterford Entergy icon.png
Issue date: 05/12/1995
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20083L330 List:
References
NUDOCS 9505180274
Download: ML20083L337 (9)
v • d • e


Text

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J CONTAINMENT SYSTEMS i

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

a.

An overall integrated leakage rate of:

1. Less than or equal to L 0 containment air per 24 S,ur.50 o s at percent by weight of the P,, 44 psig, or
2. Less than or equal to L 0 containment air per 24 k,ur.25 o percent by weight of the 22 psig. s at a reduced pressure of P ,

b.

A combined leakage rate of less than or equal to 0.60 L for all penetrations and valves subject to Type B and C to:;ts w$en pr,essurized to P..

c.

A combined bypass leakage rate of less than or equal to 0.06 all penetratior-when pressuri- that

ACTION:

With either (a) the measured overall integrated containment leakage rate leakage rate , or for,all c penetr,ations and valves subje)c exceeding 0.06 L restore 0.60 L.the ov(er)all integrated leakage rate twith t o less than or equal to0.7%,L,teforallpenetrationsador leakage ra n

less than or equal to 0.7 less than or equal to 0.60 L valves subject to Type 8 and C tests to equal to 0.06 L, prior to inc, ared the bypass leakage rate to less than or above 200*F. reasing the Reactor Coolant System temperature SURVEILLANCE REQUIREMENTS 4.6.1.2  !

test schedule and shall be determined ir conformance w specified ANSI in Appendix N45.4-1972: J of 10 CFR Part 50 using the methods and provisions 1

WATERFORD - UNIT 3 3/4 6-2 AMEN 0 MENT NO. 76,85 i-

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CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Cont'inued)

a. Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 i 10 month intervals ** during shutdown at either P 44 psig, or at P , 22 psig, during each 10-year service l period. ,The third test of ,each set shall be conducted during the shutdown for the 10-year plant inservice inspection.
b. If any periodic Type A test fails to meet either 0.75 L the test schedule for subsequent Type A tests shall be or 0.75 approved by the Cosmiission. If two consecutive Type Areviewed an L'd tests fail to meet either 0.75 L or 0.75 L,, a Type A test shall be performed at leastevery18monIhsuntiltwoconsecutiveTypeAtestsmeeteither 0.75 L or 0.75 L, at which time the above test schedule may bt-resume 8.
c. The accuracy of each Type A test shall be verified by a scpplemental tes)which:
1. Confirms the accuracy of the test by verifying that the supple-mental test result, L,, minus the sum of the Type A and the superimposed leak, L., are equal to or less than 0.25 L,.
2. Has a duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.
3. Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be between 0.75 L, and 1.25 L,.
d. Type B and C tests shall be conducted with gas at P , 44 psig, at intervalt no greater than 24 months
  • except for tests involving:
1. Air locks,
2. Purge supply and exhaust isolation valves with resilient material seals.
  • Testing for the first cycle of operation shall be done during the first refueling outage.
    • A one time extension of the test interval is allowed for the third Type A test of the first 10-year service period, provided that performance of the Type A test occurs prior to unit restart following Refuel 7.

WATERFORD - UNIT 3 3/4 6-3 AMENOMENT N0. 4, 85

CONTAllMENT SYSIEMS SURVEILLANCE REQUIREMENTS (Continued) l:

e. Purge supply and exhaust isolation valves with resilient material sea's shall be tested and demonstrated OPERA 8LE per Surveillance Requirement 4.6.f.7.2. _
f. The combined bypass leakage rate shall be determined to be less than or equal to 0.06 L by applicable Type 8 and C tests at least once '

per 24 months

  • exc,ept 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., 44 psig, dur9ng each Type A test.
g. Air locks shall be tested and demonstrated OPERA 8LE per Surveill'ance Requirement 4.6.1.3.
h. Tge provisions of Specification 4.0.2 are not applicable.
  • Testing for the first cycle of operation shall be done during the first refueling outage.

WATERFORD - UNIT 3 3/4 6-4 AMEN 0 MENT N0. 4,85

l i 3/4.6 CONTAllPAEWT SYSTEMS i

BASES 3/4.6.1 PRIMARY CONTAIMENT 3/4.6.1.1 CONTAIMENT INTERRITY

~

Primary CONTAIMENT INTEGRITY ensures that the release of radioactive 4

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, will limit the SITE BOUNDARY radiation doses to within the limits of 10 CFR Part 100 during accident conditions.

3/4.6.1.2 CONTAIMENT 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 fhe peak accident pressure, P measured overall integrated leakage rate I.sAs an added further conservatism, limited theor to less than equal to 0.75 L or less than or equal to 0.75 (, as applicable during performance of Ihe periodic tests to account for possible degradation of the containment leakage barriers between leakage tests.

l The surveillance requirements for measuring leakage rates are consistent with the requirements of Appendix J of 10 CFR Part 50.*

l' Secondary containment bypass leakage paths previously, Table 3.6-1, have been incorporated into plant procedure UNT-005.026.

3/4.6.1.3 CONTAlmENT AIR Lners The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAIMENT INTEGRITY and containment leak rate. Surveillance testing of the air lock seals provides assurance that the overall air lock leakage wi 1 not become excessive due to seal damage during the intervals between air lock leakage tests.

  • A one time extension of the test interval is allowed for the third Type A test of the first 10-year service period, as required by Surveillance Requirement 4.6.1.2.a and by Section III.D.(a) of Appendix J to 10 CFR

' Part 50, provided the performance of the Type A test occurs prior to unit restart following Refuel 7.

WATERFORD - UNIT 3 8 3/4 6-1 AMENOMENT NO. M,85

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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:
1. Less than or equal to L., 0.50 percent 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., 44 psig, or
2. Less than or equal to Lt. 0.25 percent 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 a reduced Pressure of Pt. 22 psig.
b. A combined leakage rate of less than or equal to 0.60 L. for all penetrations and valves subject to Type B and C tests when pressurized to P..
c. A combined bypass leakage rate of less than or equal to 0.06 L. for all penetrations that are secondary containment bypass leakage paths when pressurized to P..

1 APPLICABILITY: MODES 1. 2, 3, and 4 ACTION:

With either (a) the measured overall integrated containment leakage ate exceeding 0.75 L. or  :

0.75 Lt. as applicable, or (b) with the measured combined leakage rate for all penetrations )

and valves subject to Types B and C tests exceeding 0.60 L., or (c) with the combined bypass leakage rate exceeding 0.06 L., restore the overall integrated leakage rate to less than or equal to 0.75 L. or less than or equal to 0.75 Lt. as applicable, and the combined leakage )

rate for all penetrations and valves subject to Type B and C tests to less than or equal to O.60 L. and the bypass leakage rate to less than or equal to 0.06 L. prior to increasing the Reactor Coolant System temperature above 200T. ,

i SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated as at--the follows: ing test schedule and cha" be deteramet-*n conformance "ith the criteria specified in .^ppendir J of M-GR--PFt 50 using the methcdt and provisions of M!S! "15.' 1972:

WATERFORD - UNIT 3 3/4 6-2 AMENDMENT NO. 85

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CONTAINMENT SYSTEMS SURVEILLANCE Requirements (Continued) '

a. Type A tests shall be conducted in accordance with the schedule and criteria specified in 10 CFR 50. Appendix J, as modified by approved exemptions, ,

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p_4- Type B and C tests shall be conducted with gas at P., 44 psig, at intervals no greater than 24 months

  • _except for tests involving:
1. Air locks,
2. Purge supply and exhaust isolation valves with resilient material seal s.

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ww WATERFORD - UNIT 3 3/4 6-3 AMENDMENT NO. 85

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) c,er Purge supply and exhaust isolation valves with resilient material seals l shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.7.2.

d fr The combined bypass leakage l' ate shall be determined to be less-than or equal to 0.06 L. by applicable Type B and C tests at least once per 24 months 1-. 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., 44 psig, during each Type A test, e.9- Air locks shall be tested and demonstrated OPERABLE per Surveillance l requirement 4.6.1.3.

.f_N The provisions of Specification 4.0.2 are not applicable. l

  • Testing for-the-f4rst cyc!c of operation sha" be done during the first-r+fw14ng

-- Ou tage .-

l 1

WATERFORD - UNIT 3 3/4 6-4 AMENDMENT NO. 85 1 1

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 restriction, in conjunction with the leakage rate limitation, will limit the SITE BOUNDARY radiation doses to within the limits 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.. As an added conservatism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 L. or less than or equal to 0.75 Lt as [

applicable during performance of the periodic tests to account for possible degradation of the containment leakage barriers between leakage tests. I The surveillance requirements for measuring leakage rates are consistent with the requirements of 10 CFR 50, Appendix J and, performed in accordance with the methods and provisions of ANSI N45.4-1972 Secondary containment bypass leakage paths previously. Table 3.6-1, have been incorporated into plant procedure UNT-005-026.

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 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.

AAdme-time-eatension c4he-test-4nterval is allowed for the-third Type A test of the first 10 year serv 4ce-per4ed-as-required by Surveillance Requirement A.S.I.2.a and by Section 4M4aw-Anatix J to 10 CFR Part 50.provided the performance of the Type A test _oces pr4ef-te-um4-restart following Refuel '

WATERFORD - UNIT 3 8 3/4 6-1 AMENDMENT NO. 85

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