ML20035F663

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Proposed TS 3/4.6.1.2 Re Limiting Primary Containment Leakage Rates for Inclined Fuel Transfer Sys Containment Penetrations
ML20035F663
Person / Time
Site: Clinton 
Issue date: 04/16/1993
From:
ILLINOIS POWER CO.
To:
Shared Package
ML20035F662 List:
References
NUDOCS 9304220144
Download: ML20035F663 (9)
v • d • e


Text

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'Attachmant'3

.i to U-602116 l

. CONTAINMENT SYSTEMS f

LS-93-003 PRIMARY CONTAINMENT LEAKAGE Page~ 1 of. 3'-

l t

LIMITING CONDITION FOR OPERATION i

3.6.1.2 Primary containment leakage rates shall be limited to:

l An overall integrated leakage rate of less than or equal to:

f a.

1.

La, 0.65% 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 Pa, 9.0 psig.

b.

combined leakage rate of less than or equal to 0.60 La, for all penetra-l I

tions and all valves subject to Type 8 and C-tests when pressurized to Pa, 9.0 psig.

c.*

Less than or equal to 28 scf per hour for any one main steam line through.

hrough the isolation valves when tested at Pa, 9.0 psig..

d.

A combined leaka'ge rate of less than or equal to 0.08 La, for all penetra-l' tions that are secondary containment bypass leakage paths when pressurized to Pa, 9.0 psig.

A combined leakage rate of less than or equal to 1 gpm times the. total l

c.

number of containment isolation valves in hydrostatically tested lines j

which penetrate the primary containment, when tested at 1.10 Pa, 9.9 psig.

{

't APPLICABILITY: OPERATIONAL CONDITIONS 1, 2**, and 3.

q ACTION:

With:

The measured ^overall integrated primary containment. leakage rate exceeding a.

i 0.75 La, or b.

The measured combined leakage rate for all penetrations and all valves l

~

subject to Type B.and C tests exceeding 0.60 La, or The measured leakage rate exceeding 28 scf per hour for any one main steam c.

line through the isolation valves, or d.

The combined leakage rate for all penetrations which are secondary _

containment bypass leakage paths exceeding 0.08 La; or-j The measured combined leakage rate for all containment isolation valves. in e.

hydrostatically tested lines which penetrate - the primary containment.-

i exceeding I gpm times the total number of such valves, t

restore:

  • Exemption to Appendix J of-10 CFR 50.
    • ee Snecial Test Exception 3.10.1.

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CLINTON - UNIT 1 3/4 6-2 Amendment No.ff, 9304220144 930416 PDR ADOCK 05000461

P PDR i

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No C.bnge frbdchd b Codinu Onls/.

to U-602116 LS-93-003 g g @T'SYSTER p Page 2 of 3 e

PRIMARY CONTAINMENT LEAKAGE tIMITING CONDITION FOR OPERATION (Continued) i 3.6.1.2 ACTION (Continued):

The overall integrated leakage rate (s) to less than or equal to 0.75 La, 4

a.

and b.

The combined leakage rate for all penetrations and all valves subject to Type B and C tests to less than or equal to 0.60 La, and The leakage rate to less than 28 scf per hour for any one main steam line c.

through the isolation valves, and d.

The combined leakage rate for all penetrations which are secondary containment bypass leakage paths to less than or equal to 0.08 La, and The combined leakage rate for all containment isolation valves in hydro-e.

statically tested lines which penetrate the primary containment to less than or equal to I gpm times the total number of such valves prior to increasing reactor coolant system temperature above 200*F.

SURVElllANCE RE0VIREMENTS 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-fled in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972 and BN-TOP-1 and verifying the result by the Mass Point Metho-dology described in ANSI /ANS N56.8-1981.

t Three Type A Overall Integrated Containment Leakage Rate tests shall be a.

conducted at 40 i 10 month intervals during shutdown at Pa, 9.0 psig during each 10-year service 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 0.75 La the test schedule for i

subsequent Type A tests shall be reviewed and approved by the Commission.

-[

If two consecutive Type A tests fail to meet 0.75 La a Type A test shall t

be performed at least every 18 months until two consecutive Type A tests meet 0.75 La at which time the above test schedule may be resumed.

i The accuracy of each Type A test shall be verified by a supplemental test c.

which:

1.

Confirms the accuracy of the test by verifying that the difference between the supplemental data and the Type A test data is within 0.25 La. The formula to be used is : [Lo + 1 am - 0.25 La] < Lc <

[to 4 Lam + 0.25 La] where Lc - supplemental test result, Lo -

superimposed leakage and Lam - measured Type A leakage.

1 LLINTON - UNIT 1 3/4 6-3 Amendment No. 68 e

to U-602116 LS-93-003 CONTAINMENT SYSTEMS Page 3 of 3 l

PRIMARY CONTAINMENT LEAKAGE i

SURVElttANCE REOUIREMENTS (Continued) i 4.6.1.2 (Continued) 2.

Has dura

  • ion sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.

3.

Requircs the quantity of gas injected into the primary containment or bled from the primary containment du ing the supplemental test to be between 0.75 La and 1.25 La.

d.

Type B and C tests shall be conducted ****with gas at Pa, 9.0 psig, at

-l intervals no greater than 24 months except for tests involving:

1.

Air locks, 2.

Main steam line isolation valves, 3.

Penetrations using continuous leakage monitoring systems, 4.

All containment isolation valves in hydrostatically tested lines which penetrate the primary containment, and 5.

Purge supply and exhaust isolation valves with resilient material seals.

Air locks shall be tested and demonstrated OPERABLE per Surveillance e.

Requirement 4.6.1.3.

f.

Main steam line isolation valves shall be leak tested with gas at Pa, 9.0 psig, at least once per 16 months.

g.

Type B tests for penetrations employing a continuous leakage monitoring system i

shall be conducted at Pa, 9.0 psig, at every other reactor shutdown for refueling, but in no case at intervals greater than 3 years.

h.

All containment isolation valves in hydrostatically tested lines which penetrate the primary containment shall be leak tested at 1.10 Pa, 9.9 psig, at least once per 18 months.

i.

Purge supply and exhaust isolation valves with resilient material seals shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.8.3.

J.

The provisions of Specification 4.0.2 are not applicable to Specifica-tions 4.6.i.2.a. 4.6.1.2.b, 4.6.1.2.d, and 4.6.1.2.g.

i

      • Except as provided in NRC-approved exemption to Appendix J to 10 CFR' 50 for containment penetration 1HC-44.

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to U-602116 CONTAINMENT SYSTEMS Page 1 of 6 PRIMARY CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION L

3.6.1.2 Primary containment leakage rates shall be limited tn-

/

An overall integrated leakage rate of less than or equal tok a.

C a, 0.65% 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 Pa, l

9.0 psig A

y b.[ A combined leakage rate of less than or equal to 0.60 La, for all penetra-tions and all valves subject to Type B and C tests when pressurized to fa, 9.0 psig.

c.*

Less than or equal to 28 scf per hour for any one main steam line through through the isolation valves when tested at Pa, 9.0 psig.

d.

A combined leaka'ge rate of less than or equal to 0.08 La, for all penetra-l tions that are secondary containment bypass leakage paths when pressurized to Pa, 9.0 psig.

A combined leakage rate of less than or equal to 1 gpm times the total c.

number of containment isolation valves in hydrost.atically tested lines which penetrate the primary containment, when tested at 1.10 Pa, 9.9 psig.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2**, and 3.

ACTION:

With The measured overall integrated primary containment leakage rate exceeding a.

0.75 La, or b.

The measured combined leakage rate for all penetrations and all valves

+

subject to Type B.and C tests exceeding 0.60 La, or The measured leakage rate exceeding 28 scf per hour for any one main steam c.

line through the isolation valves, or d.

The combined leakage rate for all penetrations which are secondary containment bypass leakage paths exceeding 0.08 La; or The measured combined leakage rate for all containment isolation valves in e.

hydrostatically tested lines which penetrate the primary containment exceeding I gpm times the total number of such valves, restore:

V

    • a Special Test Exception 3.10.1.

4The leakage-rates-6f-vahes 1821 F032A-and-B-ere-not-required-to-be-inchded.

i

-unt41-+tertup-from-the-third-refueWg-outage-itt-eeeerdancwith-en-approved-i

= exempticr. te-Appendix J cf 10 CFR50.

-##Re-leakagc rates-of-vehes-M24-f432A-and S Orc r.ot-required-to-be-fec4eded-

--vat-44-stertep-from-the-t4 tied-refeeWg Ot:iage.

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CLINTON - UNIT 1 3/4 6-2 Amendment No.///,

w

to U-602116 C0fiTAINMENT SYSTEMS Page 2 of 6

)

PRIMARY CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION (Continued) 3.6.1.2 ACTIONjContinued):

The overall integrated leakage rate (s) to less than or equal to 0.75 La, a.

and b.

The combined leakage rate for all penetrations and all valves subject to Type B and C tests to less than or equal to 0.60 La, and The leakage rate to less than 28 scf per hour for any one main steam line c.

through the isolation valves, and d.

The combined leakage rate for all penetrations which are secondary containment bypass leakage paths to less than or equal to 0.08 La, and The combined leakage rate for all containment isolation valves in hydro-e.

statically tested lines which penetrate the primary containment to less than or equal to I gpm times the total number of such valves prior to increasing reactor coolant system temperature above 200*F.

SURVEILLANCE REOUIREMENTS 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 spect-fled in Appendix J of 10 CFR 50 using the methods and provisions of NiSI N45.4-1972 and BN-TOP-1 and verifying the result by the Mass Point Metho-dology described in ANSI /ANS H56.8-1981.

Three Type A Overall Integrated Containment Leakage Rate tests shall be a.

conducted at 40 1 10 month intervals "no shutdow a 9.0 si durina each

- ear service period. -The third' test Of each sc.-sh ll be-C--c4nduc-t --dur4ng t..e shutdown-for.he 10-year-plant-inservice inspectiem b.

If any M ed'c ype A test fails to meet La, the test schedule for a

ed by the Commission.

subsequent ype A tests shall be reviewed an a,

Type A test shall If two consecutivefType A tests fail to meet s

be performed at least every 18 months until two7on ecutiveAType A tests t which time the above test schedule may be resumed G5 -(ovnd) meet The accuracy of each Type A test shall be verified by a supplemental test c.

which:

1.

Confirms the accuracy of the test by verifying that the difference between the supplemental data and the Type A test data is within 0.25 La. The formula to be used is : [Lo + Lam - 0.25 La] $ Lc 5

[Lo + Lam + 0.25 La] where Lc - supplemental test result, Lo -

superimposed leakage and Lam - measured Typa A leakage.

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as.-leci ova.J Qakd con Wmmed led,,&

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Attaciunent 4 to U-602116 CONTAINMENT SYST[_MS Page 3 of 6 PRIMARY CONTAINMENT LEAKAGE SURVEILLANCE RE0VIREMENTS (Continued) l 4.6.1.2 (Continued) 2.

Has 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 primary containment or bled from the primary containment d the supplemental test to be between 0.75 La and 1.25 La.

3**

d.

Type B and C tests shall be conducted *** with gas at Pa, 9.0 psig, at

]

intervals no greater than 24 months except for tests involving:

1.

Air locks, 2.

Main steam line isolation valves, 3.

Penetrations using continuous leakage monitoring systems, 4.

All containment isolation valves in hydrostatically tested lines which penetrate the primary containment, and 5.

Purge supply and exhaust isolation valves with resilient material seals.

Air locks shall be tested and demonstrated OPERABLE per Surveillance e.

Requirement 4.6.1.3.

f.

Main steam line isolation valves shall be leak tested with gas at Pa, 9.0 psig, at least ~once per 18 months.

g.

Type B tests for penetrations employing a continuous leakage monitoring system shall be conducted at Pa, 9.0 psig, at every other reactor shutdown for refueling, but in no case at intervals greater than 3 years.

t h.

All containment isolation valves in hydrostatically tested lines which penetrate the primary containment shall be leak tested at 1.10 Pa, 9.9 psig, at least once per 18 months.

i.

Purge supply and exhaust isolation valves with resilient material seals shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.8.3.

j.

The provisions of Specification 4.0.2 are not applicable to Specifica-tions 4.6.1.2.a, 4.6.1.2.b, 4.6.1.2.d, and 4.6.1.2.g.

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3/4 6-

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to U-602116 I

Page 4 of 6 3.4.6 CONTAINMENT SYSTEMS I

BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 PRIMARY CONTAINMENT INTEGRITY PRIMARY CONTAINMENT INTEGRITY ensures that the release cf radioactive materials from the containment atraosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses. This restriction, in conjunction with the leakage rate limitation, will limit the site b'oundary radia-tion do.ses to within the limits of 10 CFR Part 100 during accident conditions.

3/4.6.1.2 PRIMARY CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure of 9.0 psig, Pa. As an added conservatism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 La during performance of the periodic tests to account for possible degra-dation of the containment leakage barriers between leakage tests.

Operating experience with the main-steam line isolation valves has indicated that degradation has occasionally occurred in the leak tightness of the valves; therefore the special requirement for testing these valves.

The surveillance testing for measuring leakage rates is consistent with the-requires ix J tn 10 CFR 50 fwith

-egnn of avaa iti n s

! tion v21Ic lecyc.ing). by %e NEC.).

neerf.

granted ster 3/4.6.1.3 PRIMARY CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are I

regt fred to meet the restrictions on PRIMARY CONTAINMENT INTEGRITY and the con-tainment leakage rate given in Specifications 3.6.1.1 and 3.6.1.2.

The speci-fication makes allowances for the fact that there may be long periods of time when the air locks will be in a closed and secured position during reactor oper-ation. Only one closed door in each air lock is required to maintain the inte-grity of the containment.

The surveil'1ance testing for measuring leak rate for the containment air locks

[

is consistent with the requirements of Appendix J to 10 CFR 50 with the excep-

~

tion of exemption (s) granted for the containment air lock leak testing.

1 CLINTON - UNIT I B 3/4 6-1

to U-602116 Page 5 of 6 Insert for pane B 3/4 6-1 In addition to exemptions related to testing of individual components, the following exemptions have been granted from the requirements of Appendix J of 10CFR Part 50:

1.

Section 111.A.l.(a) - an exemption from the requirement to stop a Type A test if excessive leakage is detected. This exemption allows the satisfactogy completion of the Type A if the leakage can be isolated and appropriately test factored into the results.

(Reference NRC letter dated

.)

2.

Section III.A.S.(b) - an exemption from the acceptance criteria for Type A tests.

This exemption allows, in lieu of the present single criterion that the total measured containment leakage rate be less than or equal to 0.75 of the maximum allowable leakage rate, La, the "as-found" allowable leakage rate must be less than La and the "as-le f t" allowable Icakage rate must be less than 0.75 La.

(Reference NRC Ictter dated

.)

an exemption that removes the 3.

Section III.D.l.(a) requirement that the third Type A test for each 10-year service period be conducted when the plant is shut down for the 10-year plant inservice inspection.

(Reference NRC letter dated

.)

Exemption 1 allows the continuance of a Type A test when excessive leakage is detected provided that significant leaks are identified and isolated. After completion of the modified Type A test (i.e., a Type A test with the significant leakage paths isolated), local leakage rates of those paths isolated during the modified Type A' test will be measured before and after repairs to those paths. The adjusted "as-found" leakage rate for the Type A test can be determined by adding the local (minimum pathway) leakage rates measured before aqy repairs, to the containment integrated Icakage measured during the modified Type A test, plus any leakage improvements (defined below) made prior to the test.

This adjusted "as-found" leakage rate is to be used in determining the success or failure of the test and thus the scheduling of subsequent Type A tests in accordance with Section III.A.6 of Appendix J.

The acceptability of the modified Type A test can be determined by calculating the adjusted "as-left" containment overall integrated Icakage rate and comparing it to the acceptance criteria of 0.75 La.

The adjusted "as-left" Type A leakage rate is determined by adding the local leakage rates measured after any repairs and/or adjustments are made to the paths isolated during the test, to the leakage rate measured during the modified Type A test.

It should be noted that additional adjustments for non-standard lineups and changes in containment volume may be added to the measured Icakage rate for both "as-found" and "as-Icit" determinations.

~ i.

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AL L'achtacnt 4 ^

to U-602116 Page 6 of 6 Leakage improvements are defined as the difference between a pre-repair local leak rate test (LIRT) and post-repair LIRT done on containment penetrations prior to the start of the Type A test.

The only difference between this approach and Appendix J requirements are that:

(1) potentially excessive leakage paths will be repaired and/or adjusted after the Type A test is completed; and (2) the Type A test leakage rate is partially determined by calculation rather than by direce measurement.

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