ML20086G282

Proposed Tech Spec Sections 3/4 6-2,3/4 6-3,3/4 6-3a & B 3/4 6-1 Re Containment Leakage Rates & Surveillance Testing for Measuring Leakage Rates

ML20086G282
Person / Time
Site:	Calvert Cliffs
Issue date:	11/27/1991
From:	BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20086G279	List: ML20086G276 ML20086G282
References
NUDOCS 9112050009
Download: ML20086G282 (9)

Text

..

e i

NffAC11h1ENT 1 ItEQUESTI:1) AMENI) MENT ltlNISEI) l' AGES UNIT 1 3/462 3/463 3/46-3a 113/461 I

?ti205000-9 911127 P D;i ADOCK 05000917 F< Flh

, CONTAINMENT SYSTrug CONTAINMENT LEAKAGE I

LlHITING CONDITION F0il OPEPATION 3.6.1.2 Containment leakage rates shall be limited to:

a. An overall integrated leakage rate of:

1. 5La (346,000 SCCH), 0.20 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 a

, 50 psig, or

2. sL (61,600 SCCH), 0.058 percent by weight of the i conkainment 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 .

25 psig. ,

OJO 11 000

b. .t combined leakage rate of S G L -( . SCCH),forall X ,

penetrationsandvalvessubjecttoTypeBandCtestswhen pressurized to P,.

APPLICABILITY: MODES 1, 2, 3 and 4. i EM: .so With either (a) the measured worail integrated cent inment leaktie cate exceeding 0.75 La (259,500 SCCH) or 0.75 Lt (46,200 SCCH), as app'icable, or (b) with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding L , restore thed- )01 h e;= ,ataa;-to ~

tMnIM limit!Bpriortoincrea!ingtheReactor Coolant System temnerature above 200VF.

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, methods and provisions specified in Appendix J of 10 CFR Part 50:

a. Three Type A tests (Overall Integrated containment Leakage Rate) shall be conducted at approximately equal intervals during shutdown at either P (50 psig) or at Pt (25 psig) during each 10 year service period.

overaB Megra4ed cnMnmtwt ledage rn4c f less bn or ep,d 4 er les b or eqwd % 0.v L t , m CPP N tMe . M N o, rf L.,

cmdined ledge rede -%r 4 penekrc&c. ad vdver caQeti 6 Tqe B 44 C bts 4 less On or equal 4c O,50 La CALVERT CLIFFS - UNIT 1 3/4 6-2 Amendment No. 75/JE/JJJ,1Y/,

~ . . , . , , - , . , - , , , , . , - . - . . - - - - - - , - . - , _ , , . - - - , ------,,,--.r. , - - - , - - - - , . - - - - , , . , , - . - - -

o. -

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Centinued) j

b. If any periodic T 21 A test fails to ireet eithe 0.75 L )o '

(259.500 SCCM)ork73Lt(46,200SCCM),thetestseed0lefor e subsequent Type A tests shall be reviewed and approved by the Commis If two consecutiv e A Tests fail to meet either la (259.500 SCCF) o L( (46,200 SCCM), a Type A #

test s be performed at less every IB_ months until tw c0nsecutive Type A tests meet either X75 (259,500 SCCM) 7  %

L+ (46,200 SCCM) at which time the a ove est schedule may risumed.

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

1

1. _ Confirms the accuracy of the Type A test by verifying that the difference between supplemental and Type A test data is within 0.25 La (86,500 SCCM) or 0.25 L t (15,400 SCCM).

2. Has a duration sufficient to establish accurately the change in leakage between the Type A test and supplemental test.

3. Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be equivalent to at least 25 percent of the total measureo leakage rate at Pa (50 psig) or Pt (25 psig).

d. Type B and C tests shall be conducted with gas at Pa (50 psig) at interval s p.wsper-ttr 24 months except for tests lg involving air locks. e.5

e. Air locks shall be testad and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.

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

9 Containment purge isolation valves shall be demonstrated OPERABLE any time upon entering MODE 5 from power operation modes, unless the last surveillance test has been performed within the past 6 months or any time after being opened and prior to entering MODE 4 from shutdown modes by verifying that when the meat.ured leakage rate is added to the leakage rates determined.pi.rsuant to Technical Specification 4.6.1.2.d for i u

~ n - + +. w m nyc n o, p CAf. VERT CLIFFS - UNIT 1 3/4 6 3 AmendmentNo.75/12E,///3

I CONTAINMENT SYSTEMS SURVElllAtK[lE0VIREMENTS (Continued) ,

all other Type B or C pen t at ons, the mi leaka e rate is less than or equal to L The eakage f<

rateforthecontainmentourgeiso(C@.fAGSCCM). lation valves shall also be compared to the previously measured leakage rate to detect excessive valve degradation,

h. The containment purge isolation valve seals shall be replaced with new seals at a frequency to ensure no individual seal remains in service greater than 2 consecutive fuel reload cycles.

l CALVERT CLIFFS - UNIT 1 3/4 6 3a Amendment No. H/p g,152

3/4.6 CONTALNMENT SYSTEMS fLAlU 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY In HODES ), 2, 3, and 4, primary CONTAINMENT' INTEGRITY ensures that the reinase ci -adi6 active materials from the containment atmosphere will b4 restricted u %ose leakage paths and is.ociated leak rates assumed in the accident 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. In H0 DES 5 and 6, the probability and consequences of these events are reduced because of the Reactor Coolant System (RCS) pressure and temperature limitations of these modes, by preventing operations which could lead to a need for containment isolation, and by providing containment isolation through penetration closure.

3/4.6.1.2 C_QNTAINMENT 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, Pa . As an added conservatism, thc measured overall integrated leakage rate is further

-' limited to 1 0.75 I or 0.7: Lt (as applicable) during performance of the periodic tests so account for possible degradation of the containment leakage barriers between leak tests. ~_

TFe surveillance testing for measuring leakage rates are consistent with the recuirements of Appendix "J" of 10 CFR 50g)eyu pt fo r +k f

' ~

3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure ar d leak rate for the containment air 1'icks 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, perkoennwce ok y Tpe E and C Ike bng, Th.

a\\ede. leMp ro.h kot been pq wtlewn felg ruba.ceh, u recernended im Generic. Lt her 'I I -C 'l, +o c.ct.cuk ko t- u v+oded wve'd\aue schdde o(

94 nc 8 f h ?lo (per .GpeciDen % m 4. 0. 2 ) . TklS

}5 An e r.eghico Irm ApJ,e 'J +

lo crE iar+ G-CAlVERT CLIFFS - UNIT 1 B 3/4 6-1 Amendment No 155

ATI'ACilMENT 2 ItEQUESTED AMENI) MENT llEVISED PAGES UNIT 2 3/462 3/4 6 3 113/461

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. 1L (346,000 SCCM), 0.20 percent by weight of the con $ainmentairper24hoursatP,50psig,or a

2. 1Lt (44,600 SCCM), 0.042 percent by weight of the cortainmen+. 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 '

25 psig.

0.50 IJ3, coo b.

A combined leakage rate of i @ Lpenetrations )o and valves subje e B and C tests when pressurized to P a-APPLICABILITY: HODES 1, 2, 3 and 4.

ACTION:

With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L. 259 500 SCCM), or 0.75 Lt (33,400 SCCM), as applicable, or ($)(withf.e measured combined leakage rate for all O#O penetrations and valves subject to Types B and C tests exceeding L' a [

restore thgenece rateis; to within the Htimprior to 0 M increasingtheReactorCoolantSystemtemperaturepbove200F, SURVEILL AEE 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, methods and provisions specified in Appendix J of 10 CFR Part 50:

a. Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at approximately equal intervals during shutdown at either Pa (50 psig) or at Pt (25 psig) during each 10 year service period.

, ~ ~ __

overJ W4ec3rded cnd6med ledage raQ 4 /ess An er qual +o

0. W L x er less de or egmI f3 0.7f/-t > u e//N e^Ue, eud b c.c m b iM eu leakage nde 4ct all peneltrbs avd valWI rdjecl do Wyf e 8 awl 0 -bs h fc lns ba n cr' qN bo050La CALVERT CLIFFS - UNIT 2 3/4 6-2 AmendmentNo.JE/ EEL 95,J//,

l w ,:

. i.;

- CONT AINMENT SYSTE A15 St'R\'EILL ANCE REOUIRE Af ENTS ICsntinued

b. If anv periodic Type A test; fails to meet either L,-(259.500 SCCMI 2 i- o Li (33.400 SCCM), the test schedule for subsequent Type A tests )a l s e reviewed and approved he Commission. If two ecutise Type A Tests fail to meet eithe 6.75 L (25.9,,,00 SCCM) or Li p

-(33.400 SCCM), a Type A test shall be. performed at- every is months unt' two consecutive Type A tests meet either _ _ La (259.500 )0 .

SCCM) or J.75 Li (33,400 SCCM) at which time the above test schedule p may be- resumed. ,

l- c.~ The a :uracy of each Type A test shall be verified by a supplemental test which. ' -

!' . 1. Confirms the sceuracy of the Type A test by verifying that the-difference between supplemental and Type A test data is within 0.25 La (36.500 SCCM) or 0.25 Li (ll,100' 5CCM).

2. Has a durstion sufficient to establish a: urately the change in leak- - .

age between the Type A test and supplemental test.

l Requires the quantity of gas injected into the containment of bled

~

l 3.

1 from the containment during the supplemental test to be equivalent to at least 25 percent of the total measured leakage rate' at Pa (50 psig) or Pt (25 P8il)*

d. Type B 'and C tesu sha_Il be conducted v ith gas at Pa (50 PSis)- at intervap gre;;e; C. 24 months except for tests involving air locks.* )d --

e. Air locks shall be teste and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.

f. ' All test leakage rates shall be calculated using observed data converted

l. to absolute values. Error analyses shall be performed' to select a bal -

l anced integrated leakage measurement system.

l l 3 Containment purge isolation valves shall be demonstrated OPERA 3LE any time upon entering MODE 5 from power operation modes, unless the last-

! surveillance test has-been performed within =the past 6 months or any-time after being opened and prior. to entering MODE 4 from ahutdown modes .by verifying that when the measured lakage rate is added to the leakage rates determiaed pursuant to Technical Specification 4.6.1.2.d for all other_ T or C- netrations, the combined leakage rate is less than or equal t La ( SCCM). The leakage rate for the , g containment purge isolation valves shall also be souspared 1o the previ-ously measured leakage rate Ito detect excessive valve degradation.

@73,00 @

h. The containment purge isolation valve aests shall be replaced with new seals at a frequency to ensure no individual seal remains in service -

greater than -2 consecutive fuel reload cycles. _s ----- y 1 Effec-' e upor reachin 99.9'F verageractorcodant sy m (RCS

-ces rature uring ial RC .eacup f loving t)e Unit Cycle f f g, / ]}

i o reruelir.e outare. .. claces ace 3/l. ' 3(t). /

CALVERT CL&rs - UNrr 2 3/4 6-3 Amendment No. .

3!

<3 N bfM e* b p )G dt, JD (',M 8h, t

.- ~J l

,. i

. e '

. 3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY .

In MODES 1, 2, 3, and 4, primary CONTAINMEW 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 accident 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. In H00ES 5 and 6 the probability and consequences of these events are reduced because of the Reactor Coolant System (RCS) pressure and temperature limitations of these modes, by preventing operations which could lead to a need for containment isolation, and by providing containment isolation through penetration closure.

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 accident analyses at the peak accident pressure, Pa . As an added

conservatism, the measured overall integrated leakage rate is further limited to 5. 0.75 L or 0 t (as applicable) during performance of theperiodictestsloaccou.75L nt for possible degradation of the containment-

_ leakage barriers between leak tests.

l Th surveillance test'.ng for measuring leakag rates ar consistent with tr.e requirements o' Appendix "J" of _10 CFR 5 except e r tkr  %

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.

awcc oQy Tpe 8 ed C leAke terf . Nt a.\\cwsk\c. \ebaq rn.ke kas %eh py oSraade IQ rehueh a recewenb!E h 6entric. Le$er WA> $0 0.c c.ou kor A* U+4aded surveMaue sckedde of 94 mod t as-*/o (per Spe &usn O. 2 % Ths is an etenp b fr~ Ay-p d,< T +o locre Ar+ 8-m -

L N!

CALVERTCLIFFS-UNIT / 8 3/4 6-1 Amendment No. G5