ML20070F249

Proposed Tech Spec 3/4.6.1.2 Re Limiting Condition for Operating for Containment Leakage

ML20070F249
Person / Time
Site:	Davis Besse
Issue date:	03/01/1991
From:	CENTERIOR ENERGY
To:
Shared Package
ML20070F233	List: ML20070F231 ML20070F246 ML20070F249
References
NUDOCS 9103080203
Download: ML20070F249 (5)

Text

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CONTA!NMENT SY5TEMS Docket Number 50-346 License tiember NPF-3

'CONTA!NMFNT LEAKAGE Serial Number 1900 Attachment  :

age 5 of 9 LIMITING CONDITION FOR OPERATION )

3.6.1.2 Containment leakage rates snall be limited to:

a. An overall integrated leakage rate of 1 La, 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,, 38 psig,

b. A combined leakage rate of 1 0.60 La, for all penetrations and valves subject to Type B and C tests, when pressurized to Pa '

S

c. A comtWned leakage rate of 1 0.0Mr La for al'. penetrations uti ore -

identi'ied in Tat,4c 3.51 as secondary contairrnent bypass leakage paths, when pressurized to P,.

c. A single penetration leakage rate of < 0.15 La for the contain-ment purge and exhaust isolation valvo special test.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

a. With either (a) the measured verall integrated containment leakage rate exceeding 0.75 % (b) with the measured comoined leakage rate for all penetrations and valves subject to Type B and C tests exceeding 0.60 Le, or (c) with the combined bypass leakaoe rate exceedino om La, restore the leakage rate (s) to O'N '

within the limit (s) prior' to increasing the Reactor Coolant System temperature above 200'F.

1

! b. 'itt

.. a single containment purge and exhaust isolation valve peretration having leakage rate exceeding 0.15 L,; restore the Isakage 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 iTANDBY 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 witnin the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

4 SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the l following 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:

I

a. Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 ' 10 month intervals during shutdown at P,, 3B psig, during each TO year service period. ,

l DAVIS-BESSE, UNIT 1 3/4 6-2 Amenoment No. 97,146 91030e0203 9 M301 DR ADOCK 0500 g

Docket Number 50-346 License Number NPF-3

• Serial Number 1900 Attachment Page 6 of 9 CONTAINMENT SYSTEH',

SURVEILLANCE P'.0UIREMENTS (Continued)

b. If any periodic Type A test fails to meet 0.75 L , the test schedule frc subsequent Type A tests shall be revieved an$ appreved by the (osaission. If two consecutive Type A tests fail to meet 0.75 L

'ype

. A test shall be performed at least every 1B sonths until tv$, a t.onsecutive Type A tests meet 0.75 L, at which tiee the above test schedule may be resumed.

c. The accuracy of each Type A test shs.ll be verified by a suppleeental test which:

1. Confirms the accuracy of the Type A test by verifyeg that the difference between supplemental and Type A test da.A is vithin 0.25 L,.

2. Eas a duration sufficient to establish a curately the change 3.1

laakage between the Type A test and the supplemental tert,

, 3

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

containnent or bled from the containment during the suppleeental t es t is be t ween 0. 75 L, and 1. 25 L,.

y d. Type B and C tests shall be conducted with gas at P , 38 psig, .it d intervals no greater than 24 acnths except for testI involving &oJr /ocks.

_1_ Ai r4eg

-3,--Penetrat-sens-using-oontin"a'n 1- ' ge-moritering-systeas,-and.

3. 'Jelve s-pres s ur4 s ed-vi c hfluid-d roe--e-sea l- sy s4e n-CaO3

e. The combined bypass laakage rate shall be determined to be < GrM5 L by applicable Type B and C tests Et 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 vhan tested with soap bubbles while the containment is pressurised to P,, 38 psiF, during each Type A test.

f. Air lo".is shall be tuted and demonstrated OPERABLE per Surveillance S m irement 4.6.1.3.

DAVIS-BESSE, UNIT 1 3/4 6-3 Amencaent No. 90, 120

Docket Number 50-346 '

License Number NPF-3 Serial Number 1900 Attachment

' Page 7 of 9 C0tCAINNDTT SYSTEMS SURVEILLANCE REQUIREMDTIS (Continued) g.

t'"==e-f ree-isolation-velves-the t-ere-sealed--vi v ".1vid-free a real syates-may-t -axcludedreubject-to-the-peevisions1f-APPendin-4 r-4eet6en-HLCr3r t.r. determinieg-the-eeabined-lea.lage-rate provided-the-seal-systes .r.d valver-ere-pressurteed-to-e t-4 east-1r10-P r-4hB-

. psig-,-and-the-seal-eye t es-capa ci ty-i e-edeq ua t e-t o-ma in t a i n-syI t em -

.prassura for'-et-4 east-30-days,--

-4n Type B. tera for-tenetrations-esploying-4-continuous-leakage-sor.1 tor 4ng-sya ten-shall--be-condueted-u t-Pp-38-psigra t-intervale-no-

. greater th=n nace-pe r-3-yeerer-

3. +v Each time the containment purge and exhaust isolation valves are I opened, a special test shall ge,de 4 from med) 5, whichever is later The special test is conducted by pressurizing the piping section

-including one valve inside and one valve outside the containeent to a pressure greater or equal-to 20 psig. The leakage rate per penetration shall not exceed 0.15 L,.  ;

3 '

h . .fv The special test as defined in Surveillance Requirement 4.6.1.2.f l shall be performed for the cont @mant purge i ation valves when the plant has been in any : .abination of 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' .equired by Surveillance Requirement / 4.6.1.2.# cr Li L2.d .hva not bee' performed in the ,

previous 6 months. 3 h A3

- .4c All test leak. age rates shall be calculated using observed data converted to absolute values. Error analyses shall be perforeed to

! select a balanced integrated leakage measurement system.

,J . 4r ' The provisions of Specifiestion 4.0.2. are not applicable.

l 1

h DAVIS-RESSI.12 TIT 1 1/4 6-4 Amenement No. 90

ss gg TABLE 3.6-1

5 SECONDARY CONTAINNENT BYPASS (IAKAGE PATHS

' PENETRATION SERVICE

'P(essurizer sample line

$_ l' g5 13 Co'n tainment vessel normal surj drain line 1

-4 14 Letdownsline to purificatica_demineralizers

' 16 Containment-vessel equipment vent header

. 21 . Demineralized'wa.er t suppl 3 line 23 Fuel Transfer Tu6es, ' '~ -

24 Fuel Transfer Tube 42A Service air supply line. -

43A Instrument Air supply line- 's,

~

t:a 448 Pressurizer quench tank Np supply line 49 Refueling canal fill line .

~

52- Reactor coolant pump seal water supply '.,

?>

e' 53 Reactor coolant pump seal water supply e 54 Reactor coolant pump seal water supply eg h. je

's s 55 Reactor coolant pump seal water supply qC (?

Reactor. coolant pump seal water return 56 67 Hydrogen dilution supply line s N

68A Pressurizer quench tank sample line s '

69 ' Hydrogen dilution' supply line- '

74r Pressurizer auxiliary spray line 80 Emergency' lock Personnel lock 7 3; jp ! g. ,

81

'82 Equipment hatch ;gagg '

101 Electrical penetrations a> E- E. E "i 102 Electrical penetretions og2 a -

2

• - 3i E EE c c a-C U* O

.o

"r we ,

t E - - - - _ - - . - - - _ . -

, Dockot Nu:bar 50-346 4

Licsnsa Nunber NPF . .

' +

Sarial Nunber 1900 l 3/4.6 CONTAINMENT SYSTEMS Attachment Page 9 of 9

• l BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY _

Primary CONTAINEENT 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 100 during accident conditions.

3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that tne total containment leakage volmne will not exceed the value assumed in tne safety analyses at the peak accident pressure of 38 psig, P a. As an added conservatism, the measured overall integrated leakage rate is furtner limited to .5,0.75 La, during performance of the periodic fests to account for possible degradation of the containment leakage carriers 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 exemption. The third test.of each Type A testing set need not be centucted when the plant is shutdown for.the 10.-year plant intervice inspections.

The operational readiness of the vessel is considered proven by the ILRT, and in accordance with license requirements, when completed per the 40 +

10.me'ntns frequency.

The spec'ial teEr for the-containment purge and exhaust isolation valves is intended tv detect gross degradation of seals on the valve seats. "lhe special test is performad in addition to the Appenoix J (equirements.

t 3 /4. 6.1. 3 CONTAINMEUT AIR LOCKS The Mmitations on closure and leak rate for the containment air locks.sre required to meet the restrictions on CONTAINMENT INTEGoITY and.

containment leak rate. Surveillance testing of the air lock seals provide a;.surance that the overall air lock. leaka,qe will not become

,- excessive due to seal damage during the intervals between air lock

{- leakage tests.

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().S A R f,, 2 ;+ iden Hhes Ctll j?erte Mi o!G Y t O fL Secondarj Con fa m n M b pa y s.S IeONG} 2 f?afAs, DAVIS-BESSE. UNIT 1 B 3/4 6-1 Amenament ho. 90.146

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