ML20128M750

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Proposed TS 3/4.6.1.2 Re Primary Containment Leakge
ML20128M750
Person / Time
Site: Clinton Constellation icon.png
Issue date: 02/17/1993
From:
ILLINOIS POWER CO.
To:
Shared Package
ML20128M747 List:
References
NUDOCS 9302220261
Download: ML20128M750 (9)
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(8) ' Post-Fuel' Loading Initial Test program (Section 14, SER, -SSER-5 and SSER 6);

Any chan'ges to the initial test program described in SectionL 14' off

' the FSAR made in accordance with the provisions of 10 CFR 50. 59 - O shall be reperted h ac.cordanse.with 50.59(b) withiri one month off such change.

(9) Emirgency Response Capabilitie , (Generic Lettar 82-33,_ Supplement li to NUREG-0737, Section-/.5.3.1, SSER S and SSER 8.--and Section I F - ~~

SER SSER S an M fety Evaluat:on Dated Arril 17,_19871

a. I? in accordance with the comitment contained.in a letter :

dated December 11,1986.- chall insta11'and have operational: ca separate power sources for each of the fue) zone level channels as provided for in Regulatory Guide 1.97 prior to startup- ,

following the first refueling outage.. -.

n - b. IP shall submit'a detailed control room design final-supple :

mental sumary report within.90 days of issuance of the fullr power license that ' completes all the. remainingL items; identified in Section 18.3 of the Safety Evaluation dated Apell 17,< 1987.-

b. D. The facility requires exemptions from certain requirements of.10 CFR Part 50 and 10 CFR Part 70. These include: (a) an_ exemption from the-requirements 'of 10 CFI170.2< for $he criticality als.rm. monitor: around - -

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the fue storage' area;c(b) an exemption from the: requirements of Appendix' A to 10 CFR Part SQL General Design Criterion 61 to p'ennit a' schedular-

-deferral of completion of preoperational testing of ra ' portion of the Fuel Handling System untilprior to offloading fuel frott the reactor vessel .

(bection 14, SSER B);L (c) an e:.eniption from the ' requirement *l of paragraph -

III.D.2(b)(ii) cf Appendix J, aubstituting the seal leakage' test at Pa of: A paragraph III.D.2(bj(iii)- for'.the entire air!ock test atlPa .of paragraph .

III.D.2(b)(ii) cf Appendix-4 when no maintenance has been perfonned in thei airlock -that:could affect Lits sealing capability (Section 6.2.6 of SSER 6);

(d) cn exemption from the requirement of paragraph III.C.3 of, Appendix J. -  ;

exempting the measured leakage rates from the main steam isolation valvesi from inclusion in the comb leak rate for- the local: leak rate':tetts' .

(Section 6.2.6 of SSER 6); (e) an exemption!from theLrequirements of. 1-paragraph III.B.3 of Appen , exempting -leakage from the; valve- packing -

and the body-to-bonnet seal of valve 1E51-F374 associated with=contairnenti per-tration 1MC-44 from inclusion in the combined leakage rate for;penetra s tions and valves subject to Type.Blard C testh a special circumstances regarding cach exenption, hept: foge (e) above,Lare: identified in the referenced section of theTatety evaluat n-re rt and the _ supple ?

ments thereto.- -

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Amendment No. 78, 62 L 9302220261 930217 e_ ,PDR >ADOCM 05000461- ,4 1 PDR'

Attachraont 3- y; -

~- ~to U-60?O97-

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Insert for NPT-62 patnd -- *

(f) an exernption frorn _the. requirement of paragraph III.A.1.(a) of-L Appendix J to terrninate the Type A test if potentially excessiva leakage ,

7 is identifled; (g) an exemption frorn the requirernent of paragraph 1 ,

-III. A.S.(b)-of Appendix J acceptance criteria for Type A tests,-such that -

7, the single criterion is replaced with_an "as-found" limit and an "ase i

-left" liinit; and (h);an excaption from the requirement of_ paragraph 1 III.D.1.(a) to conduct the third Type A test offeach 10 year. service period when _tha plant is shut down for tbe 10. year plant _ inservice

-inspections.

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LS-91 -o16 Page 3 of 9 An exemption was previously granted pursuant to 10 CFR 70.24. The exemption was granted with NRC materials license No. SNM-1886, issued Hovember 27, 1985, and relieved IP from the requiretrent of having a r.rtticality alam system. IP is hereby exempted from the criticality alarm system provision of 10 CFR 70.24 so far as this section applies to the storage of fuel assemblies held under this license. )

The special circumstances regarding the exemption identified in l Itam (e) above are icentified in t e SafetyscyduallorLAccqmpacying-m67 toqis J.icensa d '.

b-Acondment..No Iff "I A D c.uumeaues spec..a "! W N;@ Treg $ <w{f Ug hhMe[exempthns~arra6TONNd83MD M *W f bdtyrennt'arrun$ue'4~'

risk to the public health and safety, and are consistent with the conrnon defense and security. The exemptions in items (b), (c) and (d) above are granted pursuaat to 10 CFR 50.12. With these exemptions, the facility will operate, to the extent authorized herein, in con- ,

formity with the application, as amended, the provisions of the Act, and the rules and regulations of the Connission. ,

E. The licensacs shall fully implement and maintain ;n effect all provi-sions of the Commission-approved pi,ysical security plan, guard training -

and qualification, and safeguards contingency plans including amendments

.nade pursuant to provisions of the Miscellaneous Amendments and 3earch Requirements revisions to 10 CFR 73.55 (51 FR 27817'and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, wirich contain Safeguards Informtion protected under 10 CFR 73.21, are entitled: "Clinton Power Station Physical Security Plan," with

. revisions submitted through November 30,1987; "Clinton Power Station Training and Qualification Plan," with revtsions cubmitted through October 1,1987; and "Clinton Power Station Safeguards Cont ngency Plan," ,

with revisions submitted through October 1,1987. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with ,

the schedule set forth therein.

F. IP shall implement and n tintain in effect all provisions of the .

. approved fire protectior program as described in the Final Safety Analysis Report as amended, for the Clinten Power Station, Unit i No. 1, and as approved in the Safety Evaluation Report (NUREG-0853) l dated February 1982 and Supplement Nos. I thru 8 thereto subject to the following provision:

IP may make changes to the approved fire protection program without prior approval of the Comission only if those changes would not adversely affect the atility to achieve and maintain l safe shutdown in the event of a fire.

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l G. Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, ip shall report any violations of the reqcirements contained in Section 2.C of this license in the following runner: initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Oper ons Center via the Emergency Notification System with wrt tten ulowup within thirty days in accordance with toe procedures .

described in 10 CFR 50.73(b), (c), and (e).

Amendment No. 3. 62

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IAttaclimht; 3c t'o' U-6_02h97 1.s- w ot6- a a .

Page 4'of 9r CONTAltitjQlJ _$ySTEMS PRIMARY _ CMTAUfjENT tEAXAGE

-LJMITING COND.lflotJ FOR OPRATION A __

6.1.2 Primary containment seakage rates shall= be limited toi

' . %- - -- mn m An overall integrated leakage rate of less-than o,r equal t y a.

(La r 0.65% by weight of the containment air per 24_ hours at Pa, W

94Psta -~ wg b.# A combinedTakage 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 Pa',

9.0 psig. '

c.* Less than or equal- to _28 scf per hour for any one mali steam line'through

-- through the isolation valves when tested at Pa,'9.0 psig.

d.f# A combine'd leaka'ge rate of less than.or equal to 0.08 La, for' all penetra-tions that are secundary containment bypass leakage paths when U pressurized to Pa, 9.0 psig. ,

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

number of containment isolation valvec;in hydrostatically: tested : lines--

which penetrate the pricary containment, when tested at-1.10 Pa,- J 9.9 psig.

APPLICABILIlY: OPERATIONAL CONDITION! 1,'<.**, and 3.

&QTiot With:

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

0.75 La, or D. 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 leakags rate for all penetrations which - are: secondary containment bypass sleakage-paths exceeding 0.08 La; -or r e. The measured combined ieakage rate for all containment isolation valves in hydccstatically tested ' lines which penetrate - the primary 1 containment y exceeding 1 gpm times the total number of such valves,

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    • See Special Test Exception 3.10.1. _
  1. The leakage rates of valves IB214332A and B are not required to be _ included

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4 until startup from the third refueling outage in accordance with an = approved

" exemption to- Appendix J of 10 CFR50. _ .

    1. The leakage. rates of valves IB21-F032A and _B:are. not required to be included until startup :from the third refueling -outage. .

CL NTON %. UNIT 1- :3/4 6-2 /cendment No.///,1684.

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LS;91-0161 Page_5 off9:

CONTAWM.fNT' SYSTEMS-PRINARY CONTAJJIMENT LEAKAGE j,lMITING CONDITION FOR OPERATIQt{_(,(ontinued) __

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3.6.1.2 ACTION (Continued):

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

c. The leakage ra.c to less than 28 scf per hour for any one main steam line 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
e. The combined let.kage rate for all containment irolation-valves in hydro-statically tested lines wl.ich penetrate the primary containment to-less ,

than or equal to 1 gpm times the total r. umber of sucS valves prior to increasing reactor coolant system temperature above 200*F.

SURVEIRANCE REOUIREMENTS _

4.6.1.2 The containment Icakage rates shall be demonstrated at the. following. -

test schedule and shall_ be determined in conformance with the criteria spcci-fied 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.

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

conducted at 40 i 10 month interval 5 @ripg A4t@OEL Sgsj.9 '

A N SC N @ k" M M. . _U N _ I h - b " i,' T .. . _" Y' " N '""! ] ". '

b. If any WJ 1 Type A test falls to' meetha).he. test schedule for subseau(ent ' vpe A. tests shall be reviewed ang,Mnnved oy the Commission.-

dw If two consecutivelType A tests fail to meeti++i Lah Type -A tes'Cshall.

@S- b" r4 ) be pe fo ad at least every 18 months until twFC0iirecativelType' A tests - '

mee +r4 ~ La' t which. time the above test schedule may be resuma[d  :

c. The accuracy of each Type A test shall be verified by a supplemental- testy which: ,
1. Cenfirms the accuracy of the test by verifying that the difference between the supplemental data Land 'the Type A test data :is within-0.25 La. The formula to be used is : [Lo + Lam ,0.25 - La] < :Lc' 4 -

[Lo + Lam + 0.25 La] - where Lc = suppleumntal : test resul t, lo :-

-superimposed leakage and Lam - measured Type A leakage.

CLINTON - UNIT-1 3/4 6-? Amendment.Non 68 J

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COMTAINMdLTlVjh

{ f P"E" I9 PRIMARY CONTA_UiMfNT (fl %Q(

SURVElllANCLRBLUlRJMENTS (ContinuedL . _ _ _. _

4.6.1.2 (Continued) 2.

tias duration sufficient to establish accurately, the change in l' akage e

r4te between the Type A test and the supplementai test.

3.

Requires the quantity of gas injected into the primary containment or bled from the primary containment during the supplemental . test tobe between 0.75 La and 1.25 La.

d. Type B and C tests shall oe conducted *-** with gas at Pa 9.0 psig, et s

intervals no greater than 24 months except for tests involving:

1. Air locks,
2. Main steam line isolation valves, ,
3. venetrations using continuous leakage monitoring systems,
4. All containment isolation valves in hydrortatically tested lines which penetrate the primary containment, mid 5.

Purge supply and exhaust isolation valves with resilient material- seals.

c. Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4,6.1.3.

f.

Stain steam line isolation valves shall be leak tested with gas at Pa, 9.0 psig, at least once per 18 munths. j 9 Type B tests for penetrations employing a continut,as leakage monitoring system shall be conducted at Pa, 9.0 psig, at every other reactor shutdown for r> fueling, but in no case at intervals greater than 3 years, f

h.

All containment isolation valves in hydrostatically tested'11nes which penetrate at least once theper primary containment shall be leak tested at 'l.10_ Pa, 9.9 psig,.

18 months, i.

Purge supply and exhaurt isnlation valves with resilient material seals shall be tested and deconstrated 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..l.2.g.

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      • Except a:, provided in NRC approved exemption to Appendix J to 10 CFR 50 for
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, containment penetration IMC-44.

' CLINTON - UNIT 1 3/4 6-4 Amendment. No. 3,60. 68 .;

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3.4.6 CONTAINMENT SYSTEMS i

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3/4.0.1 PRIMARY CONTAINMENT l 1

l-3/4.6.1.1 PRIMARY CONTAINMENT INTEGRITY )

i PRIMARY CONTAINMENT INIESRITY ensures that the release of radioactive materials l from the containment atmosphere will be restricted to those ic-akage oaths and 1 l-associated leak rates c ,sumed in the accident Malyses. This restriction, in t conjunction with the leakage rate limitation, w!)1 limit the site boundary radia-l tion doses to within the limits of 10 FR Part 130 during accident conditions.

i 3/4. 6_._1. 2 PRIMARY CONTAINMENT LEAXAGE The limitations on containment leakage rates ensure that the total containment leakage volo:ue will not exceed the value assume 1 in the accident analyses at the peak accident pressurc of 9.0 psig, Pa. As ar. 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-dattor, of the containment reakage barriers between leakage tests.

Operating experience with the main steam line isolation valves nas indicated

that degradation has occasionally occurred in the leak tightness of the valves; l therefore the .special requirement for testing these valves.

The surveillance testing for measuring leakage rates is t.onsistent with the-o 1A CJG.,50 lv t,sxcejlion o_f_exepption(s) requirem h ,-ugfmAppgixy:

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l o grante n" ~--~~~ msi) y we NR), Ing* . _ _

3/4.6.1 3 PRIMARY CONTAINMENT AIR LOCKS The limitations on closure and leak rate for tile containment air lock are required to meet the- restrictions on PRIMARY CONTAINMENT IMEGRITY and the s.on-i tainment leakage rate given in Specifications 3.6.1.1 a'nd 3.6.1.2. The speci-fication makes allovances for the fact that there may be long pericds nf time when the air locks will be in a closed and secured position during reactor opei-

" ation. Only one closed coor in each air lock is required to maintain the inte-grity of the containment.

The s'irveillance testing for measuring leak rate for the containment air locks

is consistent with the requirements of Appendix J to_10 CFR 30 with the excep-tion of exemptien(s) grant,cd for the containment air lock leak testinn-l CLIRTON - UNIT 1 B 3/4 6-1

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t ito U-602097 -

LLS 91~-0161 _,

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Josert fpr page.B 3/4 6-1 In addition to: exemptions -related to test'ng of individual' i

< components, the following exemptions have-been granted from the 4

tequirements n' Appundix J of _10CFL Part $0:  ;

1. Section III . A.1. (a) = an exemption - f rom the re ;uirement tu

!= stop a Type A_ test if excessivofaeakkga.is dutected. This' z

exemption allows' the satisfactory completion of the Type A '

-test _tf_the leakage can be iso 1'ated and appropriately 1 i factored into the results (Reference NRC letter datedl ',

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2. Section III.A.S.(b) - an exemption'from the acceptance:

e criteria for Type A tests. This exemption allows, in:ll<u of the present single criterion that tb3 toe.r measured containment leakage rate'be less-than or equal.co 0.75 of.

. the maximum allowable Icakage rate, La, the "ao-found" allowable ?sakage ra*e must be less than La and the'"as-leit" allowable leakage rain n .st be les s thcn 0. 7 5 La .

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{ (Reference NRC letter dated .)

3 Sec tion III ..D. L. (a) - sat exemption that removes-the ,

, requirement that the third 1 Type A test for each 10ayear-i service period be conducted when the. plant'is shut down for  ;

che 10-year plant inservice l inspection. (Reference NRC l 1etter dated .) '

Exemption 1 allows the ntinuance of a Type A tesr-vhen exctisive leakaBe is detected'ptavided that signi'icant leaks are .dentified and-isolared. After completion of the modified Type A test '(.i.e. , e ' Type A U test with _ the significantl leakage. paths isolated), local leakage rates of those paths isolated during the modified Type A~ test will'be measured ~  ;,

L before and.afterfrepairs to those paths.- The adjusted "as-found" leakage rate for the. Type A test can=ce determined by adding the~ local.

c (minimum pathway) L leakage rates measured beforr any: repairs, to ' the , 4 containment integrated leakago -nessured during the' modified Type - A test, "

plus _ any _ leakage iuprovements / defined bolow) made _ prior to the - test, j

This adjusted "as found" -leakage rate is :to be used in determining the :

success or failure of the test and thus ths acheduling' of subsequent:

Type A tests in accordat.ce with'Section III;A.6'oT3ppendix J.

. The acceptability of the modified Type. A test can bel-determined by : <

calculating the .. adjusted "as-lef t"' containment overall integrated

,. laakaSe rate'and. comparing it to tho ' acceptance criteria of 0~.75.La; . j lThe adjusted "aa-lef t" Type A liakage rate is determined by adding the

[ ~ local- leakage raten measured after any repairs .end/or adjustments a?re .

1 made to the paths isolated durin2 the test. to the leakage, rate measured '  ;

i iluring the modified Type Airest. _It should be noted that. additional , i Edjustments for nonictandard lineups - and changes in" containmd.t' volume

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1 may beLadded to the measurnd leakage-ratev fer both "as-found" bnd "as- H lefra ~ determinations. f' I

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. - Leakage improvements are defined' as the dif ference between .a pre. .

ropair local leak rate ; test (LLRT) and post-repair LIAT done' on containraent penetrStions prior to the start of- the Type A test, j The only difference betwocn this approach-and Appandix:J requirements are'th.at: (1) pctentially excessive leakage paths will be repaired and/or adjusted.af ter the Type A test iu completuJ: 'and (2)(the Type A test leakage rate is partially determined by. calculation rather'

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