Text

Proposed Tech Specs,Performing Containment leakage-rate Testing Per 10CFR50,App J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors, Option B
	ML20115A911
Person / Time
Site:	Limerick
Issue date:	06/28/1996
From:	; PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	;
Shared Package
ML20115A910	List: ML20115A907; ML20115A911;
References
	NUDOCS 9607090110
	Download: ML20115A911 (26)
	v • d • e

. .- ..

l ATTACHMENT 2

, LIMERICK GENERATING STATION UNITS 1 AND 2 4 :

Docket Nos. I 50-352 50-353 License Nos.

! NPF-39 i NPF-85 4

TECHNICAL SPECIFICATIONS CHANGE REQUEST NO. 95-14-0 AFFECTED PAGES UNIT 1 UNIT 2 l FOL FOL4-3/4 6-1 3/46-1 3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3 3/464 3/4 6 4 3/4 6-5 3/4 6-5 !

3/4 6-6 3/4 6-6 3/4 6-8 3/4 6-8 j 3/4 6-14 3/4 6-14 B3/46-1 83/44-1 B3/4 6-2 B3/4 6-2 !

. 6-14b 6-14b !

9607090110 960628 !

PDR ADOCK 05000352 ;

PDR j

.l

3872003733 3885125590 (14) Refueling Floor Volume Connection to Standbv Gas Treatment System (Sect 1on 6.2.3. 55ER-2 anc 55ER-3)

Pr'ior to any movement of irradiated fuel within the refueling floor volume the licensee shall complete and test all modifi-cations required to connect the refueling floor volume to

- standby gas treatment system. During the interim period, the licensee shall not remove the reactor pressure vessel heaa prior to the NRC staff review and approval.

(15) Emercency Planning Procedures Subject to 44 CFR Part 350 In the event the NRC finds that the lack of progress in comple-tion of the procedures in the Federal Emergency Management .

Agency's final rule, 44 CFR Part 350, is an indication that a major substantive problem exists in achieving or maintaining an adequate state of emergency prepareoness, the provisions of 10 CFR Section 50.54(s)(2) will apply.

D. The facility requires exemptions from certain requirements of

10 CFR Part 50. These include (a) exemption from General Design Criteria (GDC) 61 of Appendix A, operation of that portion of the >

standby gas treatment system (SGTS) that serves the refueling area until the first refueling (Section 6.2.3 of SSER-2 and SSER-3), (b) exemption from GDC-56 of Appendix A, the requirement for additional automatic containment isolation valves for the hydrogen recombiner lines and the requirement for automatic isolation of existing isolation valves in the Drywell Chilled Water (DCW) and the Reactor Enclosure Cooling Water (RECW) systems until prior to startup following the first refueling outage (Section 6.2.4.2 of the SER, SSER-1 and SSER-3), (c) exemption from GDC-ig of Appendix A, as related to the requirement for redundant remote shutdown capability (Section 7

! exemption from the requirement W.4.2.3 of SSER-3

-" !!I.0_' (RNofand SSER-5), (d)

Appendix

,J, the testing of containment air locu ;t times wnen the containment s" integrity is not required (Section 5.J.6.1 nf the wn and ssER-3b l (e) exemption from the requirements Gf ;;r;;r:2.: II.M.d . and IF r#

of Appendix J, the leak rate testing of the MainTreem Iiwinion Valves (MSIVs) at the peak calculated containment oressure, Pa, and exemption from the requirements E pacair:0 !!hC.Dof Appendix J that the i

measured MSIV leak rates be included in the summation for the local leak rate tes (Section 6.2.6 of sSER-31 i lfexemption from the requiremen of ;;;r: t W II ".1 and IIT.T.o of Appendix J, the local leak rate testing of the Traversing Incore Probe Shear Valves (Section 6.2.6 of the SER and SSER-3),(g) a one-time exemption from the requirement of Appendix J to perfonn local leak i 7 AUt 8 1985 m

is is f0 L ,0% j

)

+s- 4 A..- - _-- - a. -- - 4 4-. - -- - - ~ - - - - - - - - -- _.

3/4.6 CONTAfl# TENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT

, PRIMARY CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION

3. 6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be maintained.

APPLICA8ILITY: OPERATIONAL CONDITIONS 1, 2*, and 3.

ACTION:

Without PRIMARY CONTAINMENT INTEGRITY, restore PRIMARY CONTAI M ENT INTEGRITY I

4 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in CO 2 5HUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

i j- , SURVEILLANCE REQUIREMENTS 4.* 6.1.1 PRIMARY CONTAIMENT INTEGRITY shall be demonstrated:

i .

d

a. After each closing of each penetration subject to Type 8 testing, j

except the primary. containment air locks, if opened following Type A j -

or 8 ---m,,.,.

-- tast, by leak rata testing?

~

, d:. _ _ _ ' ' _ . . - -Hth ;r n ",, G.C Z;._

__ ._ - - e tr1 a c c o c.) o ce. m' s % % .G i s.. -2~-'-

' : ~ '"' ' ~i W ~ s

/ Wib N M* [ n 1.:. t.' 1 i Co W H ' ] "- [' P:" ' ^^"" "" $ '"" *'= = 2 4 ^ - " 55 ' a D ' W f M 5 3 -

I 0'W b. At least' once per 31' days by verifying that all primary containment

! g.gy /<,9%. v penetrations ** not capable of being closed by OPERABLE containment s

automatic isolation valves and required be closed during accident conditions are closed by valves, blind anges, or deactivata,d j autametic valves secured in position, except as provided in ' Table 1

3.6.3-1 of Specification 3.6.3. -

l c. By verifying the primary containment air lock is in comipliance with

, the requirements of Specification 3.6.1.3.

4

d. By verifying the suppression chamber is in compliance with the

. requirements of Specification 3.6.2.1.

.n. -

~

"See 5pecial Test Exception 3.10.1 i

! **Except valves, blind flanges, and deactivated automatic valves which are located

. inside the containment, and are locked, saaled, or otherwise secured in the closed position. These penetrations shall be verified closed during each CO2 SWTDOWN except such verification need not be performed when the primary containment has not been deinerted since the last verification or more often i than once per 92' days. .

t LIMERICK - UNIT 1 3/4 6-1 I i

9

^l '

CONTAINMENT SYSTEMS

PRIMARY CONTAINMENT LEAKAGE I

LIMITTNG CONDITTON FOR OPERATTON 3.6.1.2 Primary containment leakage rates shall be limited to:

a.

ctg A DsV)

An overall integrated leakage rate s. .er th Or w el te

] 1;, 0.500 pt cent h-te u;.; vi u.. uviii.. n.n-iii .. ee.- 20 h: r: :t 1 D

s. ^^ n m&n achs w w ,71. -n.s / % vy Co & w ee +

^

' ] A ss k --se M p s N H f m ~ ~

! b. A combined leakage rate of-iets-thr. e. ewei 6u 0.00L/forall 4

penetrations and all valves listed in Table 3.6.3-1, except for main f 4

steam line isolation valves

and valves which are hydrostatically .

./

l tested per Table 3.6.3-1, subject to Type B and C tests wehen

p-: :r & ed te o g, 11 0 petr j

c. *Less than or equal to 100 scf per hour through any one main steam 1,

isolation valve not to exceed 200 scf per hour for all four main . steam

, lines, when tested at Pt , 22.0 psig.

i

{ d. A combined leakage rate of less than or equal to 1 gpm times the i total number of containment isolation valves in hydrostatically 3 tested lines which penetrate the primary containment, when tested at

1.10 Pa, 48.4 psig.

!. APPLICABILITY: When PRIMARY CONTAINMENT INTEGRITY is required per i Specification 3.6.1.1 __ __

ACTTON: jn a.cco,.,/ w wTh. &c. h,h C de In m c.J. b/cg e.

( % Trsh' fis 7 i

l With:

a.

ktw -

The measured overall integrated primary containment leakage rate (7p /

ts;;;ed..; 0.75 L;, or I

b. The measured combined leakage rate for all penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation i valves

and valves which are hydrostatically tested per Table 3.6.3-1, Q bject to Type 8 and C tests 7.- . . ., . . -- 'a , o r j c. The measured leakage rate exceeding 100 scf per hour through any one 4

main steam isolation valve, or exceeding 200 scf per hour for all four main steam lines, or 9

i d. The measured combined leakage rate for all containment isolation valves in hydrostatically tested lines which penetrate the primary

containment exceeding 1 gpm times the total number of such valves, restore: j g4g3

a. The L.,

overall integrated leakage rate (s)gte. ' :: th= or e ,.i te 0.7" and

Exemption to Appendix J of 10 CFR Part 50. pg i 2196 3

LIMERICK - UNIT 1 3/4 6-2 -^ --i= nt No. 107

- - . - - - . = - . . . - - . . . - - . . - - _ _ .

k CONTA?NMENT SYSTEMS LfMITVNG CONDITTON FOR OPERATTON (Continued)

ACTION: (Continued) ,

b. The combined leakage rate for all penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation valves

and i valves which are hydrostatically tested per Table 3.6.3-1, subject

- ~M ' a ^'a' M i- to u% Type o.swk.uB anda;h. Css tests fa q c.4.* to W N :4w.y ocCM7 ky=~ , s.l

c. The leakage rate to $11.5 scf per hour for any main steam isolation valve that exceeds 100 scf per hour, and restore the combined maximum pathway leakage to $200 scf per hour, and .

I d. The combined leakage rate for all containment isolation valves.in hydrostatically tested lines which penetrate the primary containment I . to less than or equal to 1 gpm times the total number of such valves,

.' prior to increasing the reactor coolant system temperature above 200*F.

SURVEILLANCE RE0VIREMENTS 4

4 ' 0.:.'

. T;m primary cont inment leakage ratus an.il L= uw-uns 6r.6eu at t

- f lowing test schedule an shall be determined in conformance with the riteria spe ied in Appendix J of CFR Part 50 using the methods and provi ons of ANSI 4 4-1972 and BN-TOP-1 an verifying the result by the Mass Poi i

-1981

! Methodolo described in ANSI N5 i i

< a. Ty A Overall Integrate ontainment Leakage Rate sts shall

be co in acco ance with 10CFR50, A endix J, as '

modified eted at Pa,d approve exemptio .

f any period Type A test fails, or if tw consecutive Type A tests i

4

b. ccordance with 10CFR50, 1, a Type A t shall be perfo di App dix J, as modi d by approved e tions.

c. The acc acy of each Typ test s 1 be erified by a supplemental a

test whic ;

1. Confirm the accuracy test by veri ing that the difference i between t supplem al dat and the Type test data is within 0.25La. Th fa a to be use s: [L Lam - 0.25 Lal 5 Lc 5 La] where Lc - ppie+m ental est result; to =

i

$ (Lo + Lam .

superimposed kage; Lam - measure v e A leak e.

i l 2. Has dur ' on suf ient to establish accur ly the an e in leaka rate betwo the Type A test and the lemen test.

73. R uires the quantity f gas injected into the conta n r ed from the conta h 1' t o.75 La and 1.251a m;; th; ; ppi;;;.;;t;l t;;; . ,,;

Exemption to Appendix "J" to 10 CFR Part 50.

i LIMERICK - UNIT 1 3/4 6-3 p ramant No. 67, M4 108 FEB 121996 4

CONTAINMENT SYSTEMS SURVFillANCE REOUTREMENTS (Continuedi Type B and C tests shall be conducted with gas at P,, 44.0 psig*, a a frequency. in accordance with 10 CFR 50, Appendix J, as modified roved. exemptions, except for tests involving: .

1. locks, c

2.. Main st line isolation valves,

3. Containment is tion. valves in hydrost cally tested lines which penetrate t rimary containm , and

e. Air locks shall be tested and ns ted OPERABl.E per Surveillance

' Requirement 4.6.1.3. .,,

f. Main steam line isolation y es shall b ak tested at a frequency in accordance with.10 CF , Appendix J, as dified by approved exemptions.

g. Containment iso on valves in hydrostatically teste nes which '

penetrate th timary containment shall be leak tested at ast once per 24 mo s, nc+,to exceed the requirements of 10 CFR 50, ndix J.

h. The ovisions of Specification 4.0.2 are not applicable to Specift t s 4.6.1.2a. , 4.6.1.2b. , 4.6.1.2c. , 4.6.1.2d. , 4.6.1.2e. , and 4.6.1 rJs sM L- (

4. & . i.1 7f,_ y;;wa<y coMm e.J laiya A u. s A t ;,,. . u. .g, urA. & A m 7 C* M ~ < + 4a9 AsTuA9 Aum y pw %j.u.~ 7:

a. Tg a. A Te /

b. Typ

/3 x2 c 7arh (in& dig au /~Ls) w

,n. ..

.c c . et u A a Q M (ns, , v s u ,

J My Jo w4 Me) c.s;>-r+- En LA n /,-

u-i-~ > t= :.2 tm m , y re s r .:,n :.:.3 a .

LIMERICK - UNIT 1 3/4 6-4 Amendmenc No. 2, 33, 71, 83 DEC 191994

i i

3901000402 CbNTAINMENTSYSTEMS .

PRIMARY CONTAINMENT AIR LOCK -

LIMITINGCONDIT-[0NFOROPERATION 3.6.1.3 The primary containment air lock shall be OPERA 8LE with:

a. - Both doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed, and

b. An overall air lock leakage rate .T ... ..'.:.. cr ="=1 +a p

, u n o g W R<h % ,,.g ,,,, a y a t s . /t,. %

'Tss+*,~1 &* <*~.

427 .. h 0_at i % gta j:t- ,

APPLICA8ILITY: OPERATIONAL CONDITIONS 1, 2*), and 3.

, ACTIg:

a. With one primary containment air lock door inoperable:

1. Maintain at least the OPERA 8LE air lock door closed and either restore the inoperable air lock door to OPERA 8LE status within ~

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or lock the OPERABLE air lock door closed. .

2. Operation may then continue until performance of the next required overall air lock leakage test provided that the OPERA 8LE air lock door is verified to be locked closed at least once per 31 days.

3. Otherwise, be in at.least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4'. The provisions of Specification 3.0.4 are not applicable.

b. With the primary containment air lock inoperable, except as a result of an inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to 0PERA8LE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in CDLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

y.-

"See Special Test Exception 3.10.1.

S uMERICK - UNIT 1 3/4 6-5 Amendment No. 33 OCT 3 8151

- - ^

3901000402 CONTAINMENT SYSTEMS

SURVEILLANCE REQUIREMENTS -

l . .

l 4.6.1.3' The primary containment air lock shall be demonstrated OPERABLE:

a. By verifying the seal leakage raht; b lee; the.. ;r :;;;! ::

pu_m e- mke- +h. nan h.,w..n 5 ::f th. saa,

==e!s is ; :::eH ::: : --

i M-9?%

b- --w44Mft- 32 Iiva. . e ft; r e e.i.. w;e.i6s , eace t 3.;; th; eir i.ei i; beine- .;;;;d fer e.;i.;ph .ai.. 'un, U.e n et ;;e t ea; ;;r 70 heers; .

and--

t

4. prior 6. ==6saiisulny FRi^iARY CGrGainnen INTEGRITY when the aC i v6k has u.... ...J .a : .e r, tea.as. Le. ..... g..Ter ;d :- +h.

ak ie i."

b. %

l

By conducting an overall air lock leakage test t.f" ,. ** n pefg, '

4 e-M h, .erifjk;; that the e..r.ii air i.oca isek.v. .et; i:

i+- !!;it;

.;'*hia

-L At leert :::: pry:::th:,*:S 2_ o ,,4._ . ._ ._.. . u. ,._.u. . , .am. m.. _. ..-o.o- .- n- .-.-.

___ . . . . n . --...o~..1_

in

==f-t: ac; h:: be-- a.cfa - d e- th: ;ir leci u.et es.;c-a#4est th; ei. 1865 ...isov 6.p oiiity.--

c. At least once per 6 months by veHfying that only one door in the air lock can be opened at a time.***

g /a Aeco vo/, w g;% f/o hIWu r7 b *

dedq< /Lh Tuliy P(p

- 1 I

.- l l

"'hE ;r:v h ba Of !;::!*!:sti-- '_a * .-- aa+ maaH e=M - V aeg.---t ha ;; a;; 744. j,

. o.... .nh rit n_9_r5)i44) -f la cra n r [

- - Except that the airlock doors need not be opened to verify interlock OPERA-BILITY when the primary containment is inerted, provided that the atriock )

doors' interlock is tested within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after the primary containment has been deinerted and provided the shield door to the airlock is maintained locked closed. .

O LIMERICK - UNIT 1 3/4 6-6

~

p

.m eemme-

k i

i

! CONTAINMEN SYSTEMS i

! PRIMARY CONTAINMENT STRUCTURAL

INTEGRITY i

l LIMITING CONDITION FOR OPERATION 4

j 3.6.1.5 The structural integrity of the primary containment shall be maintained at a level cor.sistent with the acceptance criteria in Specification

! 4.6.1.5. *

! APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3'.

j ACTION:

J With the structural integrity ~of the primary containment not conforming to the i above requirements, restore the structural. integrity to within the limits l within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HDT SWTDOWN within the next 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months and in j- COLD SHitTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . -

i SURVEILLANCE REDUIREMENTS j .

1 .

{ 4.6.1.5.1 The structural integrity of the exposed accessible interior and 4

exterior surfaces of the primary containment, including the liner plata, shall be determined i.:q ^.' - E ^ ~ '- r o Tm ?. ::- * = 4 - ^ '- ' ;: . . ^

by a visual inspection of these surfaces. -This ins

^- ^ 'pection shall

! v. l , - ^ - 't- T,p i, ^ '- '---

. ' _ : __ _ - - '*" -- -be performed i *l k de ec wh 'u #Th. .A ' /C* ****"7 i -

m- .-.

j Cm die _h< l,AJ+ %__ _'iks. _itig. Wg;.:d..

f a . -. . -

j 4.6.1.5.2 Amy abnormal degradation of the primary containment t structurs during thn above required inspections shall be reported in i a Special Resort to the Commission pursuant to Specification 6.9.2 within

! 30 days. This report shall include a description of the condition of the l Ifner and concreta, the inspection procedure, the tolerances on cracking, and j the corrective actions taken.,

4 i

j .

7 1

i 4

4 i

t LIMERICK - UNIT 1 3/4 6-8 ADE 8 115 i

' CONTAINMENT SYSTEMS l

l SURVEILLANCE RE00fREMENTS (Continued)

L l c. By verifying at least 8. suppression pool water temperature indicators in i at least 8 locations, OPERABLE by performance of a:

1. CHANNEL CHECK at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

l 2. CHANNEL FUNCTIONAL TEST at least once per 31 days, and l l

3. CHANNEL CALIBRATION at least once per 24 months, with the temperature alarm setpoint for:

1. High water temperature:

a) First setpoint s 95'F b) Second setpoint $ 105'F c) Third setpoint s 110*F d) Fourth setpoint s 120*F

d. By verifying at least two suppression chamber water level indicators I OPERABLE by performance of a: !

1. CHANNEL CHIECK at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , !

2. CHANNEL .9)NCTIONAL TEST at least once per 92 days, and

3. CHANNEL :ALIBRATION at least once per 24* months, with the watei level alarm setpoint for high water level 124'l-1/2"

e. Drywell-to-suppression chamber bypass leak tests shall be conducted to Appeadt;; J, ::

coincide with the Type A test ~at ._.

p*aan ee;;d:::initialith 10Ci"it,l pressure of 4 psi differentia

=Mmad and verifyingW .,,,..that..__the.

- ._A/7k' calculated from the measured leakage is within the specified iimit. If any drywell-to-suppression chamber bypass leak test fails to met the specified limit, the test schedule for subsequent tests shall be reviewed and approved by the Commission. If two consecutive tests fail to meet the specified limit, a test shall be performed at least every 24 months. until two consecutive tests meet the specified limit, at which time the test schedule may be resumed.

f. .By conducting a leakage test on the drywell-to-suppression chamber vacuum

jbreakers at a differential pressure of at least 4.0 psi and verifying that the total leakage area A//k contributed by all vacuum breakers is less than or equal to 24% of the specified limit and the leakage area for an individual set of vacuum breakers is less thn or equal to 12% of the specified limit. The vacuum breaker leakage test shall be conducted during each refueling cutage for which the drywell-to-suppression chamber bypass leak '.est in Specification 4.6.2.1.e is not conducted. l

The CHANNEL ' CALIBRATION for level transmitters LT-55-1N062B, -1N062F shall be performed at least once per 18 months. -- -

FS I 2 E Amendment No. 68, 79, 7I, 108 LINERICK - UXIT 1 3/4 6-14

(- .

3/4.6 CONTAINMENT SYSTEMS BASES l 3/4.6.1 ' PRIMARY CONTAINMENT i

3/4.6.1.1 PRIMARY CONTAINMENT'INTEGRTTY I

PRIMARY CONTAINMENT INTEGRITY ensures that the release of radioactive mate-rials 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 C_FR Part 100 during accident conditions.

3/4.6.1.2 PRIMARY CONTAINMENT LEAKAGE M ** E' "'

- &cdoIcas. ba-~- si.s

-The limitation on primary containment leakage rates ensure that the total containment leaka e volume will not exceed the value calculated in the safety analyses for the ;::' :::id; .; pressure of s 44 psig, Pa. As an added conserva-tism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 La during performance of th periodic tests to account for possible degradation of the containment leakage arriers between leakage tests.

p A Tu r)

Operating experience with the main steam line isolation valves has l 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

((f t: - - b-- 'E- -

Wh9 rd T!" :h:;r .;he . g fd3 Cabaw Lage 14 Tu Fy U 3/4.6.1.3 PRIMARY CONTAINMENT AIR L The limitations on closure and leak rate for the primary containment air lock are required to meet the restrictions on PRIMARY CONTAINMENT INTEGRITY

_a ,nd 2 . ' ___

.1.1u H ^-

e i e h pm' . ry...

-- ",4. . u .. _. 6. ,',1--3 ' '-. .,.'; r;t:

. . r ;h:2 '- ! r.,

o ,. ,6; ::i'.+':n:th:: ., ,6...

^" i; w T. 55 a i r. bkh5hhb"Ni h* 4" ' '*l a'"d Md !"b ^

aa 4+4aa M aa -trt:r :;:r:thR Only one closed door in the air lock is required to maintain the integrity of the containment.

3/4.6.1.4 MSIV LEAKAGE ALTERNATE DRAIN PATHWAY Calculated doses resulting from the maximum leakage allowances for the main steamline isolation valves in the postulated LOCA situations will not exceed the criteria of 10 CFR Part 100 guidelines, provided the main steam line system lfrom the isolation valves up to and including the turbine condenser remains intact. Operating experience has indicated that degradation has occasionally occurred in the leak tightness of the MSIVs such that the specified leakage requirements have not always been continuously maintained. The requirement for the MSIV Leakage Alternate Drain Pathway serves to reduce the offsite dose.

LIMERICK - UNIT 1 B 3/4 6-1 .t = h nt No. 33, IN , 107 FEB 12 896 i

~~ ~ ~ ~ ~

CONTAINMENT SYSTEMS BASES 3 /4. 6.1. 5 PRIMARY CONTAINMENT STRUCTURAL INTEGRITY {

This lisiltation ensures that the structural integrity of the containment l will be maintained comparable to the original design standards for the life of '

the unit. Structural integrity is required to ensure that the containment will withstand the maximum calculated pressure in the event of a LOCA. A visual (

inspection ' wja-the 8th ";r a 1= % = in ts is sufficient to demonstrate this capability. e .J .

A h f,6v7 ce * ~ M 3/4.6.1.6 DRWELL AND surrRESSION CHAMBER INTERNAL PRESSURE The limitations on drywell and suppression chamber internal pressure ensure .

that the calculated containment peak pressure does not exceed the design l pressure of 55 psig during LOCA conditions or that the external pressure differ-ential does not exceed the design maximum external pressure differential of i 5.0 psid. The limit of - 1.0 to + 2.0 psig for initial containment pressure ~

will limit the total pressure to s 44 psig which is less than the design l pressure and is consistent with the safety analysis.

. 3/4.6.1.7 DRWELL AVERAGE AIR TEMPERATURE The limitation on drywell average air temperature ensures that the con-tainment peak air temperature does not exceed the design temperature of 340*F 1 during steam line break conditions and is consistent with the safety analysis. '

3/4.6.1 d _,D. W ELL AND SUPPRESSION CHAMBER PURGE SYSTEM 1he drywell and suppression chamber purge supply and exhaust isolation valves are required to be closed during plant operation except as required for inerting, deinerting and pressure control. The 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months per 365 day limit on purge valve operation is imposed to protect the integrity of the SGTS filters.

Analysis indicates that should a LOCA occur while this pathway is being utilized, the associated pressure surge through the (18 or 24") purge lines will adversely affect the integrity of SGTS. This limit is not imposed, however, on the subject valves when pressure control is being performed through the 2-inch bypass line, !

since a pressure surge through this line does not threaten the OPERABILITY of '

SGTS.

l' T '

i I

j LIMERICK - UNIT 1 8 3/4 6-2.. Amendment No. 29,106 I

. FF.B 1 2 1996 s . .. -

, ADMINISTRATIVE CONTROLS t

[ .

PROCEDURES AND PROGRAMS (Continusd) t

8) Limitations on the annual. quarterly air doses resulting from i

i noble gases released in gaseous effluents. from each unit to j areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, k 9)

Limitations on the annual and quarterly doses to a MEMBER OF i THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit.to areas j

beyond the SITE BOUNDARY conforming to Appendix I to 20 CFR Part 50, '

10) Limitations on venting and purging of.the Mark II containment .

i -

through the Standby Gas Treatment System to maintain releases 1

as low as. reasonably achievable, and

11) Limitations on the annual dose or dose commitment to any MEMBER j

j OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

e. Meteorological Monitorino Program A program shall ba provided to provide meteorological information in

the environs of the plant. The program shall provide sufficient i meteorological data for estimating potential radiation doses to the public.

i The program sha'll (1) be contained in the ODCM, (2) conform to the l j

guidance of Regulatory Guide 1.23, " Safety Guide 23 - Onsite !

Meteorlogical Program", and (3) include limitations on the opera- ,

bility of meteorological monitoring instrumentation including

] surveillance tests in accordance with the methodology in the ODCM.

l f. l Radiological Environmental Monitorino Procram '

i A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) repre-

sentative measurements of radioactivity in the highest potential ,

exposure pathways, and (2) verification of the accuracy of the ,

4 i

effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) con- .

i i form to the guidance of Appendix I to 10 CFR Part 50, and (3) include j l the following:

i 1)' Monitoring, sampling, analysis, and reporting of radiation and I i

radionuclides in the environment in accordance with the methodology and parameters in the ODCM, ,

j i ;l' 2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that i

i modifications to the monitoring program are made if required by j the results of this census, and

! l

3) Participation in a Interlaboratory Comparison Program to ensure i '

that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program !

for environmental monitoring.

LIMERICK.- UNIT 1 6-14b Amendment No.48

~ ~

l C.A.a. 444 Tuw3 i p;

, f<. r -

r LA !

_I

g. Primary Containment Leakaoe Rate Testino Prooram !

A program shall be estatuhed to implement the leakage rate testing of the .

containment as required by 10 CFR 50.54 (o) and 10 CFR 50, Appendix J, !

Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163.

~

" Performance-Based Containment Leakage Test program," dated September 1995.- ;

The peak calculated containment intemal pressure for the design basis loss of poolant accident, P., is 44.0 psig.

The maximum allowable primary containment leakage rate, L., at P., shall be ,

0.5% of primary containment air weight per day.

Leakage rate acceptance criteria are:

a. Primary Containment leakage rate acceptance criterion is less than or equal to 1.0 L.. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are less than or equal to 0.60 L. for the Type B and Type C tests and less than or equal to 0.75 L. for Type A tests-l

! b. Air lock testing acceptance criteria are:

0oF/a

$ 1) Overall airlock leakage rate is less than or equal to h when tested at greater than or equal to P.,

2) Seal leakage rate is less than or equal to 5 scf per hour when the gap between the door seals is pressurized to 10 psig.

The provisions of Specification 4.0.2 do not apply to the test frequencies i

specified in the Primary Containment Leakage Rate Testing Program.

The provisions of Specification 4.0.3 are applicable to thefrimary Containment Gakage Rate Testing Program. T 9 %.

C g & h ylbtA

- E h(y,(ck.-l)>JLT l (,-t4 C r

\

I

, (4) Physical Security and Safecuards l The licensee shall fully implement and maintain in effect all provisions of the physical security, guard training and '

qualification and safeguards contingency plans previously approved by the Commission and all amendments and revisions to such plans made pursuant to the authority of 10 CFR 50.90 and 10

, CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: " Limerick Generating Station, Units 1 & 2, Physical Security Plan," with revisions ,

submitted through October 31, 1988; " Limerick Generating Station, Units 1 & 2, Plant Security Personnel Training and Qualification Plan," with revisions submitted through October 1,1985; and

" Limerick Generating Station, Units 1 & 2, Safeguards Contingency

Plan," with revisions submitted tnrough November 15, 1986.

' D. The facility requires exemptions from certain requirements of 10 CFR l Part 50 and 10 CFR _P_ art 70. These include (a) exemption from the ;

requirement C a*-----* " "-H+tDof Appendix J, the !

testing of containment air locks at times When the Containment

integrity is not required (Section 6 J. 6.1 of the SER and SSER-3) ,,,

l

, (b) exemption from the requirements (C------?.: !! .S.4 2. -iii.C.g of Appendix J, the leak rate testing of tne main steam isoiation 1 Valves (MSIVs) at the peak calculated containment prggsure, Pa, and i ;:r:;r:;t III.C.;Jof Appendix J exemption from MSIV that the measured the requirements leak rates (((be inciuoeu in tne summation for the local leak rate test LSection 6.2.6.1 of SSER-3), (c) exemption from the requirementdE[ r- _;-;;t: It" : : d : ;...zJof Appendix J, 4

a i

I T, 4 .

4 i

i

(, ~- DEC 2 01995

' M h f. o ( V d\ "2_

Amendment No.68 4

3/4.6 COWAIMENT SYSTDts .

3/4.6.1 PRIMARY CONTAI N NT s PRIMARY C0fffAIMENT INTEGRITY -

LIMITING COIGITION FOR OPERATION 3.6.1.1 PRIMARY CONTAIMENT INTEGRITY shall be ma'intained.

APPLICABILITY: OPERATIONAL ColeITIONS 1, 28, and 3.

ACTION: ,

Without PRIMARY CONTAll0ENT INTEGRITY, restore PRIMARY CONTAlfetENT INTEGRITY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least NOT SitfTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in -

COLD SHUTDOW within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REOUIREMENTS

.- 4.6.1.1 PRIMARY CONTAIMENT INTEGRITY shall be demonstrated:

a. After each closing of sach penetration subject to Type 8 tasting, except the primary containment air locks, if opened following Type A i ,

or a test, by Joak rate testingy :x:. 40. ;- et P,. ".e -1;.

la Acardan r ---w p;K g, fee,u ,w = v _m2 ./ L - .

+m t = -- +6. -- x.-e 1..h.

e ./ .__2 _.__7..

--*- f- r ;; ;n;;, 4,

,, e..l _,_33___f pam~- g

c. y .

i

q- uy 7" **",. ' .-.

. z . ' ..<" ***, . '".7- y. ' '." ". :,,-1, . _ 7 .:.. . . ;.y.

-- z , m

g- -

-. r.

1

___ .. .y. _ .. . . . _ . -

{

f.diq A r ""b. At least once per 31 days by verifyin.g that all primary containment

penetrations ** not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident

. conditions are closed by valves, blind flagges, or deactivated -

1 automatic valves secured in position, except as provided in Table i 3.5.3-1 pf Specification 3.5.3.

J l c. By verifying the primary containment air lock is in compliance with l the requirements of Specification 3.6.1.3.

! d. By verifying the suppression chaeber is in compliance with tho' l ,

requirements of Specification 3.5.2.1.

"SesspecialTestException3.10.1 j ""Except valves, blind flanges, and deactivated automatic valves whib are located

inside the containment, and are locked, sealed, or otherwise secured in the

closed position.. These penetrations shall be verified closed during each COLD

SIRITDOW eacept such verification need not be performed when the primary containment has not been deinertad since the last verification or more often then once per 92 days.

l ,

1

i. 4

- LDEEICK - tstIT 2 3/4 6-1 .. . - - '

Am 2 51911 f .

i 4

1

~

l CONTAINMENT SYSTEMS l _

.- ~

l PRIMARY CONTAINMENT LEAXAGE

[;,, a cu rs,, o gtt A Fam, I Vaa s.g . /se b st % On1' ~

c,,y_,,,j.

LIMITING CONDITION FOR OPERATION t 3c6.1.2 Primary containment leakage rates shall be limited to:

An overall integrated leakage (Trate gh;; t)..:n er equal to A*Tss a.

1, n _ r,nn percent by weipt a +h.r - +eiment :tr per 24 Luom 34 Pg, 11.0 p:ig.

b. A combined leakage rate Of t: th2' P equil t; 0.50-t4 for all penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation valves

and valves which are hydrostatically tested per Table 3.6.3-1, subject to Type B and C tests.when O_ AA A n e 4 rr n., reg ets,.4,aA t n . . . .

c. *Less than or equal to 100 scf per hour through any one main steam isolation valve not to exceed 200 sef per hour for all four main steam lines, when tested at Pt , 22.0 psig.

d. A combined leakage rate of less than or equal to 1 gpm times the total number of containment isolation valves in hydrostatically tested lines which penetrate the primary containment, when tested at 1.10 Pa, 48.4 psig.

APPLICABILITY: When PRIMARY CONTAINMENT INTEGRITY is required per Specificatior. 3.6.1.1.

ACTION: .

With:

a. The measured overall integrated primary containment leakage rate (1' e 4 Tn' u _. ^ 75 L 3 orfin a usao u u rtu n. #,,,,,7 c.s.t.. ,,+

L - 4.u r. a.se 7,,w,. e , y,. -

b. The measured combined leakage rate for all penetrations,and a 1 valves listed in Table 3.6.3-1, except for main steam line isolation valves

and valves which are hydrostatically tested per Table 3.6.3-1, subject to Type B and C tests tr::di. 3 E.? L., or L

c. The measured leakage rate exceeding 100 scf per hour through any one main steam isolation valve, or exceeding 200 sef per hour for all four j, main steam lines, or .

Ti

d. The measured combined leakage rate for all containment isolation valves in hydrostatically tested lines which penetrate the primary containment exceeding 1 gpm times the total number of such valves, LTyp. A f.0) h bs. [

a. The overall integrated leakage. rate (s)z te h:: th;r. cr e s u.1 tt 0.7-a, and

, *Exemption to Appendix J of 10 CFR Part 50. . _ . _ .

LIMERICK - UNIT 2 -

3/4 6-2 f = .h-..t No. 53 FEB 161995

l CONTAINMENT SYSTEMS .

LIMITING CONDITION FOR OPERATION (Continued M l ACTION:

W m a se . .t,, - u .7t- ts , Mm. 7 c. e + ~ .J. l (Continued) x 4 , % L369 f/. __

b.. The combined leakage rate for all penetrations and all valves listed I in Table 3.6.3-1, except for main steam line isolation valves

and i valves which are hydrostatically tested per Table 3.6.3-1, subject )

i to Type B and C tests te k u q M . . - - p;a.x r ;.,..~i- te 0. 0 i~a , andy t

t

c. The leakage rate to $11.5 scf per hour for any main steam isolation valve ,

1 that exceeds 100 scf per hour, and restore the combined maximum pathway l

} leakage to $200 scf per hour, and '

d. The combined leakage rate for all containment isolation valves in ,

' hydrostatically tested lines which penetrate the primary containment !

to less than or equal to 1 gpa times the total nuraber of such valves, l prior to increasing reactor coolant system temperature above 2'J0*F.

. SURVEftlANCE REOUTREMENTS -

.i l 4.G.1.2 Thu primary watainment ius.v. . .tes 2F.:' 24e C-- teetM st + N l fon ing 6.n ed.d.i. ano snali ce aetermneo confonnance witn tnMriteria i j specihed in Appendix J of 10 CFR P rt 50 usi the methods and prov fions of j ANSI 45.'4 972 and BN-TOP-1 and veri ing t result by the Mass P nt j i Methodology scribed in ANSI N56.8-19 ,

i ,

i a. Type overall Integrat cont nment Leakage R e tests shall i i be cond ed at Pa, accordanc with 10CFR5 , Appendix J, as modified '

. by approv xempt ns. ;

b. If any period e A test fails, or f wo consecutive pe A tests fail, l a Typ At shal e performed in ac ance with 10 50, Appendix J, as mod by approv exemptions.

c. The cur of er.ch Type est all be ve ' d by a supplemental

tot which:

1

! [1. Confirms th accurac of the t y verif 'ng that the difference between the su le ntal data he Type A est data is within .

, 0.25 La. The fo la to be ed is. Lo + Las -0.25 Lal 5 Lc l 5 [Lo + Las + .25 who Lc - supp ntal st result; to =

g- superimpose eakage; = measured Type leaka .

2. Has dur ion suffic nt to stablish accurately c ange in leak rate bet n the Typ test and the supple 1 test.

3. uires the quantity of gas injected into the containmen r led from the containment during the suppi 6.1 L.. t. .:

5:t:rr- 0M5 L .c.d 1.25 i a*

Exemption to Appendix "J" to 10 CFR Part 50.

~~

FEB 1 2 156 l LIMERICK - UNIT 2 3/4 6-3

-%t No. 73, 71 !

b_ _ _ _ _ _ _ , -

___ _. . . _ . _ _ _ _ ~ _ _ . . - __

CONTAINMENT SYSTEMS !

SURVEILLANCE RE00TREMENTS (Continued) 2 T" : S rd ' toda ,Geil us wuJudad w U. ve ; :t .".

a uency in accordance with 10 CFR 50, Appendix J, 00.0 as modifie p;ig',d" approve xemptions, except for tests involving:

1. Air loc ,

2. Main steam line olation valves,

3. Containment isolation ves in hydr atically tested lines which penetrate the prima cent ment, and ,

)

e. Air locks shall be tested and d str d OPERABLE per Surveillance l Requirement'4.6.1.3. '

f. Main steam line isolati valves shall be leak sted at a frequency in accordance with 1 R 50, Appendix J, ar = di..qi by approved exemptions.

g. Containment olation valves in hydrostatically tested lin which penetrat a primary containment shall. be leak tested at le once per 2 mor.t.hs, not to exceed the requirements of 10CFR50, Appen J.

h. e provisions of Specification 4.0.2 are not applicable to Specifica H a r ' .E.1. e. , 4.6. i .a. , 4.6.1.2c. , 4.6.1.2d. , 4.6.1.ze. , and 4.o.1.2.'.

'N C* H hlMA

}' V" 'S *$

4. 6. l. t. % stiN d~$o

)gmm sltde in a cco r uce r'i marf

$enbEM6N feakye h?e ksbhy ofr~a '

f $$1 e fNoy :

a.T A M h.

6 aud C h.i/s (hckliy lb N) n bh iS $ d eu Vsc Ve.c C- t$n S r%/a../ Mk& Zrs/dk () /m, d

/. lhkoxhd}

j M -10:: : . tic;:titt: tt:t 1: ;f r:d p:r Td': ?.S.? 1. "

LIMERICK - UNIT 2 3/4 6-4 Amendment No. 35, 4,4 DEC 1 g g 6

i c0NTAIMENT SYSTEMS 1

PRIMARY CONTAINMENT AIR LOCK .

f .

LIMITING CONDITION FOR OPERATION i 3.6.1.3 The primary containment air lock shall be OPERABLE with

1 ,

. a. Both doors closed except when the air lock is being used for normal

! -transit entry wid axit through the containment then at -least "one l air lock door shall be closed, and -

in a ce.,- b w A Yi % 0 *.

b. An overall air lock leakage reta ' i_ r_ r J. z i n j .

g ., ,_.,,.Cosw % tuk9 4Lh 7:.: N 7 ej o ~ . 1* *:t 6 ,

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

4 l-i ACTION:

j a. With one primary containment air lock d6er inoperable:

' 1.

Maintain at least the OPERABLE air lock door closed and either l restore the inoperable air lock door t6 OPERA 8LE status within i .

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or lock the OPERABLE air lock door closed.

l 2. Operation may then continue until perfomence of the next i required overal.1 air lock leakage test provided that the OPERABLE i' j air lock door is verified to be locked closed at least once per

31 days. , _

3. Otherwise, be in at least HOT SHUTDOWN within the next 12 havrs and in COLD SHUTDOWN withi,n the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4. The provisions of Specification 3.0.4 are not applicable. ;

b. With the primary containment air lock inoperable, except as a result i of an inoperable air lock door, maintain at least one air lock door i i closed; restore the inoperable air lock to OPERAELE status within i 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and j in COLD SIUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , p' - .

i

See Special Test Exception 3.10.1. .

i 4

LDERICK - UNIT 2 3/4 6-5

. AM 2 5 IIB 1 .5

d l

, CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS 1 .

j

4.6.1.3 The primary containment air lock shall be demonstrated OPERA 8LE:

i l a. By verifying the seal leakage rate - M h:: tM: Or : ::! *- 5 --*

, ; r '.:^. h:2 th- a-- Mir:: th: d:: :::h h preaeoriz.. ^e*

i la ;-iig

< 1 wi+hia 72 ha =_ ift.i ..w closing, excepr. ..... ;.; c'- ~6 4=

l Mt. ===-- f or mu i n p l e entri es , r a=n as i . i. .. . y.. 7^ ; , . !;

and--

1 4

4

,,_c1

...,u.

. . . ,... - .na.- - - - - . - - - - - -

ns initunai1 .....

. ..r

. w u k-- 5: ... a a na amintenan,. h--

t:_.. perf;. n f :- +6-i i

'r ; C '*

b.

6 -

By conducting an overall air lock leakage test :t .",, "." - ';,

. e hu, +w., +h. no. 41 ._4_ . 1 _ _ 6

<+, sa-n+. _ _ . 4 evi an.

1___'--_ . . . . * - - ma*'a-j

1

.. ,i,. ,__________,.___m_

..... .. 7.. . _ . . - . . ,

. __2 s

4 s e.t _ .- s_- _

s.u.s..u,

. . - . waini..- n- - - -- An.

4.i .. . . . L i l * ==iat-

_p p.,,

;; 5.::.t:- a=rformed on the air 1-6 + hat raald5P-At_ , l

.. . ..r .. ._._._ ,_ ____&. . y . . . i. >. A,_ _ . -e E E

j c. At least once per 6 months by verifying that only one door in the air, lock can be opened at a time.*** ,

~

l in a cc uh .. ee wi/k he fd w 6JOJ ofagq Lk Tu*~j hy y .

\

i m.._._._.._.,...... . .A.

or w ... ..... ..o ,,_m, 4 ,..... . m . . .

.ans,,_ .,.-. ____m -- m ,,,

....n.. .s.un.. . ,

r,,s, x,._... , r... ..r.. . .rn r .ri, av. 1

! ***Except that the airfock doors need not be apened to verify interlock OPERA-i BILITY when the primary containment is inerted, provided that the airlock i doors' interlock is tested within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after the primary containment has been deinerted and provided the shield door to the airlock is maintained locked closed. .

j LIMERICK - UNIT 2 3/4 6-6 ADE 2 5 BII 4

a

~

i l i .

l l

4 . .

] CONTAIMENT SYSTEMS

PRINARY CONTAINMENT STRUCTURAL INTEGRITY l

1 .

l

LIMITING CONDITION FOR OPERATI0ft_ . !

j .

l

. l j 3.6.1.5 The structural integrity of the primary containment shall be

maintained at a level consistant with the acceptance criteria in Specification l 5 4.6.1.5. -

i APPLICABILITY: CPERATIONAL CONDITIONS 1,.2, and 3.

l ACTION:

a 1 i With the struct. tral integrity of the yrimary containment not conforming to the

above regiairements, restore the structural integrity to within the limits !

within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least WT SMTDow within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in 1 j COLD SWTDOW within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . l

~

] SURVEILLANCE REOUIREMENTS

4 j 4.6.1.5.1 The structural integrity of the exposed accessible interior and 1 asterior surfaces of the primary containment, including the liner plata, shall j be deternined r!:;; tt r '-- : f;c m:' T,p a :-rt: "7 1: ^t* j by a visual inspection of those surfacesr. This inspection shall be performed +

l ;. "-- t ' % 7., - - -i _. ._ -tt;d;r ,;:xt " 7-in - = : .. .

. - . - 4 ._2_;.; - -

t l 4.6.1.5.2 A g abnormal degredation of the primary containment i structure during the above required. inspections shall be reported in

. a Special Report to the Commission pursuant to Specification 6.9.2 within j 30 days. This report shall include a description of the condition of the

liner and concreta, the inspection procedure, the tolerances on cracking, and l the corrective actions takan.

k p.ccov) s.a T D '

W/ * '

i l

e My fo)~ . -

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i i

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, . I

LDIERICK ~ UNIT 2 ,3/4 6-8 ~ ' ~ . AIE 2'5 W f

e 1

CONTAINMENT SYSTEMS !

SURVEILLANCE REQUIREMENTS (Continued) i c. By verifying at least 8 suppression pool water temperature indicators in at least 8 locations, OPERABLE by performance of a:

i i- 1. CHANNEL CHECK at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

j 2. CHANNEL FUNCTIONAL TEST at least once per 31 days, and j 3.. CHANNEL CALIBRATION at least' once per 24 months, 4

l with the teaperature alarm setpoint for:

^

1. High water temperature:

a) First setpoint 5 95'F b) Second setpoint s 105'F c) Third setpoint s 110*F i

d) Fourth setpoint 5 120*F 4

d. By verifying at least two suppression chamber water level indicators j OPERABLE by perfomance of a: .

i 1. CHANNEL CHECK at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , i

j 2. CHANNEL FUNCTIONAL TEST at least once per 92 days, and l

3. CHANNEL CALIBRATION at least once per 24* months, j with the water level alarm setpoint for high water level s 24'l-1/2"

e. Drywell-to-suppression chamber bypass leak tests shall be conducted to coincide with the Type A test ". .ee; d ::: d th MCF",Z , ".rpe. A J, ee

-Mi'4M by ;pr.med en--Me..e*at an initial differential pressure of 4 psi and verifying that the A k caluculation from the measured leakage is within the specified limit. If any drywell-to-suppression chamber bypass leak i test fails to meet the specified limit, the test schedule for subsequent i

, tests shall be reviewed and approved by the Commission. If two consecutive !

3psts fail to meet the specified limit, a test shall be performed at least every l

-24 months until two consecutive tests meet the specified limit, at which time the i test schedule may be resumed. i

f. By conducting a leakage test on the drywell-to-suppression chamber vacuum breakers at a differential pressure of at least 4.0 psi and <

verifying that the total leakage area A/(k contributed by all vacuum breakers is less than or equal to 24% of the specified limit and the leakage area for an individual set of vacuum breakers is less than or equal to 125 of ;

the specified limit. The' vacuum breaker leakage test shall be caducted during i each refueling outage for which the drywell-to-suppression chimoer bypass leak '

test in Specification 4.6.2.1.e is not conducted.

' ~]

.. . . :. . . 1

The CHANNEL CALIBRATION for level transmitters LT-55-2N0628, -2N062F shall be onsed i at least once per-18 months. -

ggg j LIMERICK - UNIT 2 3/4 6-14 A = nthent No. 31, 33, M , 71

3 /4. 6 CONTAINMENT SYSTEMS 4

BASES l 3/4.6.1 PRIMARY CONTAINMENT l

! 3 /4. 6.1.1 PRIMARY CONTAINMENT INTEGRITY 1

PRIMARY CONTAINMENT INTEGRITY ensures that the release of radioactive mate-rials 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 I radiation doses to within the limits of'10 CFR Part 100 during accident conditions.

3/4.6.1.2 PRIMARYCONTAINMENTLEAXAGE[8 .

[ 5*O A##

8h The imitations on primary containment leakage rates ensure that the total containment leakage volume will not exceed the value calculated in the safety analyses da: 2.: m_k accident pressure of 5 44 psig, Pa. As an added conserva- l tism, the mtasured overall integrated leakage rate is further limited to less !

than or equal to 0.75 La during perfer;:::r.cc of the periodic tests to account for l possible degradation of the containment leakage arriers between leakage tests. '

<4 t e A +** )

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 p t'.c reptr:x;t; ef App;;dh 3 ef 10 CP ":rt 50 ;u. u. ww.puu . vi I ava rti;;; ;,..6.d Tv. 1;;k i::tinj; cf the ... L 4.m i soi s u un v.ives. u.e - /

eirleck ::d "" hee. . .i . ee,,

{% 6 9 C=h*J hh' M %HM M.y 3 /4. 6. I . 3 PRIMARY CONTAINMENT AIR LOCK j The limitations on closure and leak rate for the primary containment air 1 loc are required to meet the restrictions on PRIMARY CONTAINMENT INTEGRITY l and t' p i-~y nat;icx;t 'a=haa nte av.n in gar 4r4r +4ane im 1 1 + 1 2.5.'. 21 Th; pesificatiLi. Liek. illvw.usi; fe thi f ait that thi^. i .uay 'un )

!cr; p:ri;d; ef t; ;..n J.. .ir ic;k ill b; ir, e Cie ed er.d e w. cd ped tie- tr' ; r;;;ter ;;;. _ ' - Only one closed door in the air lock is required to maintain the integrity of the containment.

3/4.6.1.4 MSIV LEAXAGE ALTERNATE DRAIN pATWAY l

Calculated doses resulting from the maximum leakage allowances for the main steamlihe isolation valves in the postulated LOCA situations will not exceed the criteria of 10 CFR Part 100 guidelines, provided the main steam line system from the isolation valves up' to and including the turbine condenser remains intact. Operating experience has indicated that degradation has occasionally ,

occurred in the leak tightness of the MSIVs such that the specified leakage !

requirements have not always been continuously maintained. The requirement for the MSIV Leakage Alternate Drain Pathway serves to reduce the offsite dose.

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1 LIMERICK - UNIT 2 B 3/4 6-1 A=a*=nt No. 51, 53 FEB 161995 I W- e

CONTAINMENT SYSTEMS

~ BASES 3 /4. 6.1. 5 PRIMARY CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment l will be maintained comparable to the original design standards for the life of .

the unit. Structural integrity is required to ensure that the containment will l withstand the maximum calculated pressure in the event of a LOCA. A visual l l inspection in ~~-d"a m aa " Ma A ': L.m tat; is sufficient to demonstrate this capabilithaecusa+u.e wi/s. /n &6.<y c. Jam <#,649 AU, pg g 3/4.6.1.6 DRYWELL AND SUPPRESSION CHAMBER INTERNAL PRESSURE

\

The limitations on drywell and suppression chamber internal pressure ensure that the calculated containment peak pressure does not exceed the design l pressure of 55 psig during LOCA conditions or that the external pressure differ-ential does not exceed the design maximum external pressure differential of 5.0 psid. The limit of - 1.0 to + 2.0 psig for initial containment pressure will limit the total pressure to s 44 psig which is less than the design I pressure and is consistent with the safety analysis.

3/4.6.1.7 ORYWELL AVERAGE AIR TEMPERATURE The limitation on drywell average air temperature ensures that the con-tainment peak air temperature does not exceed the design temperature of 340*F during steam line break conditions and is consistent with the safety analysis.

3/4.6.1.8 DRYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM The drywell and suppression chamber purge supply and exhaust isolation valves are required to be closed during plant operation except as required for inerting, deinerting and pressure control. The 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months per 365 day limit on purge valve operation is imposed to protect the integrity of the SGTS filters.

Analysis indicates that should a LOCA occur while this pathway is being utilized, the associated pressure surge through the (18 or 24") purge lines will adversely affect the integrity of SGTS. This limit is not imposed, however, on the subject valves when pressure control is being performed through the 2-inch bypass line, since a pressure surge through this line does not threaten the OPERABILITY of SGTS. ,

d

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LIMERICK - UNIT 2 B 3/4 6-2 != = % t No. 51 FEB 1 61995

ADMINf5TRAT2VE CONTROLS '

i PROCEDURES AND PROGRAMS (Continued)

8) Limitations on the annual quarterly air doses resulting from noble gases released in gaseous effluents

from each unit to >

areas beyond the SITE BOUNDARY conforming to Appendix .I to 10 CFR Part 50, .

i

9) Limitations on the snnual and quarterly doses to a MEMBER OF !

THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas i beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, !

10) Limitations on venting and purging of the Mark' II containment through the Standby Gas Treatment System to maintain releases ~

as low as reasonably achievable, and

11) Limitations on the annual dose or dose commitment to any MEMBER !

0F THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

e. Meteorolooical Monitorino Procram A program shall be provided to provide meteorological information in ;

the environs of the plant. The program shall provide sufficient '

meteorological data for estimating potential radiation doses to the public. '

The program shall (1) be contained in the 00CM, (2) conform to the ,

guidance of Regulatory Guide 1.23, " Safety Guide 23 Onsite Meteoro-logical Program", and (3) include limitations on the operability of meteorological monitoring instrumentation including surveillance tests in accordance with the methodology in the 00CM.

t

f. Radiolocical Environmental Monitorino Procram A program shall be provided to monitor the radiation and radionuclides

~

in the environs of the plant. The program shn.1 m yide (1) represen-tative measurements of radioactivity in the hi potential exposure pa'th'.17ys, and (2) verification of the accuracy or use effluent moni- 1 toring program and modeling of environmental exposure patNays. The program shall (1) be contained in the ODCH, (2) conform to the guidance -

of Appendix I to 10 CFR Part 50, and (3) include the following: ,

1) Monitoring, sampling, analysis, and rep'orting of radiation and

,; . radionuclides in the environment in accordance with the N , methodology and parameters in the 00CM,

2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and i

3) Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitorino.

(5. e n c. u w % . % %

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LIMERICK - UNIT 2 6-14b ment No.11

.6=.a'iuth . LAX 0 2 !!!!

1 j g. ' Primary Containment Leakaae Rate Testino Prooram A program shall be established to implement the leakage rate testing of the 1 containment as required by 10 CFR 50.54 (o) and 10 CFR 50, Appendix J, l j - ' Option B, as modified by approved' exemptions. This program shall be in accordance with.the guidelines contained in Regulatory Guide 1.163. .

" Performance-Based Containment Leakage Test program," dated September - {

1995. !

i j The peak calculated containment internal pressure for the design basis loss of '

l coolant accident, P., is 44.0 psig.

l The maximum allowable primary containment leakage rate, L., at P., shall be j 0.5% of primary containment air weight per day.

! - Leakage rate acceptance criteria are:

a. Primary Containment leakage rate acceptance criterion is less than or j _ equal to 1.0 L.. During the first unit startup following testing in i accordance with this program, the leakage rate acceptance criteria are

less than or equal to 0.60 L. for the Type B and Type C tests and less than or equal to 0.75 L. for Type A tests, i 1

I b. Air lock testing acceptance criteria are:

i 'G5%.

1) Overall airlock leakage rate is less than or equal to mooseest when tested at greater than or equal to P., --

l= 2) Seal leakage rate is less than or equal to 5 scf per hour when the j gap between the door seals is pressurized to 10 psig.

i The provisions of Specification 4.0.2 do not apply to the test frequencies i specified in the Primary Containment Leakage Rate Testing Program. ,

I

{-u h oh wd. 4 M*- l

.The provisions of Specification 4.0.3 are applicable to the4Primary Containment !

! @.eakage Rate Testing Program 4

i

! I i

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ML20115A911

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