ML17229A109

Proposed Tech Specs Rev to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria

ML17229A109
Person / Time
Site:	Saint Lucie
Issue date:	10/28/1996
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17229A108	List: ML17229A107 ML17229A109
References
NUDOCS 9611010288
Download: ML17229A109 (45)

Text

ATTACHMENT 3 PROPOSED LICENSE AMENDMENT FOR IMPLEMENTATION OF 10 CFR 50'PPENDIX J OPTION B 1-2 3/4 6-1 thru 3/4 6-10 3/4 6-13 3/4 6-19 thru 3/4 6-23 3/4 6-31 B3/4 6-1 B3/4 6-2 6-15b Insert Pages (Inserts A, B, and C)96iiOi0288 961028 PDR ADQCK 05000389 P 1.6-A CHANNEL FUNCTIONAL TEST shall be the'injection of a simulated signal into the channel as dose to the primary sensor as practicable to verify.OPERABILITY including alarm and/or trip functions.

1.7 CONTAINMENT

VESSEL INTEGRITY shall exist when: a.All containment vessel penetrations required to be dosed during accident conditions are either.Capable of being dosed by an OPERABLE containment automatic isolation valve system, or 2.Closed by manual valves, blind flanges, or deactivated automatic valves secured in their dosed Itions ce t a ovidecHn-Fabl 4c Uptakes~ha4 ai~4'pen c~~n rnlev<,'SIcnk Q'ne'er-R8<i'n:Stm]l de Coo>rot.equtpmen ha e are dosed and sealed, c.Each containment, vessel air lock is in compliance with the requirements of Specificatio 3.6.1.3, d.The containment leakage rates are within the limits of Specification 3.6.12, and II e.The sealing mechanism associated with each penetration (e.g., welds, bellows or O-rings)is OPERABLE.1.8 CONTROLLED LEAKAGE shall be the seal water flow supplied from the reactor coolant pump seats.1.9 CORE ALTERATiON shall be the movement or manipulation of any fuel, sources, reactivity control components, or other components affecting reactivity within the reactor vessel with the vessel head removed and fuel in the vessel.Exceptions to the above include shared (4 fingered)control element assemblies (CEAs)withdrawn into the upper guide structure (UGS)or evolutions perfommd with the UGS in phce such as CEA latching/unlatching or verification of latching/unlatching which do not constitute a CORE ALTERATION.

Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.ST.LUCIE-UNIT2 1-2 V A)Sl k>>~~')L~I ply i Vp~j~ij a f 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

APPLICABILITY:

MODES 1", 2", 3, and 4.ACTION: Without primary CONTAINMENT INTEGRITY, restore CONTAINMEHT INTEGRITY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.SURVEILLANCE RE UIREHENTS 4.6.1.1 b.Primary CONTAINMENT INTEGRITY shall be demonstrated:

P At least once per 31 days by verifying that all.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 flanges, or deactivated automatic valves secured in their positi pov vctlvcs>hat oy'Q gloPA 0~cNA<Ate.I mtklin0 hasi's Qo~e~n Jni'8>'5trR9ive Q~)roL y verifying at eac n r lock is in compliance.

with the requirements of Specification 3.6.1.3.be a~0~a In MODES 1 and 2, the RCB polar crane shall be rendered inoperable by locking the power supply breaker open.Except valves, blind flanges, and deactivated automatic valves which 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 SHUTDOWN except that such verification need not be performed more often than once per 92 days.ST.LUCIE-UNIT 2 3/4 6-1 Amendment.'to.

It)4 8 I).$g Q f V I<~i'b CONTAINMENT SYSTEM'CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited'.i6 accordance.

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~ombinedHeaka h y-wHght-of-4he-uced-pressure-o&P;, APPL'ICABILITY:

MODES 1, 2, 3, and 4.ACTION: Q~sgRg Ag~b'-Typ.8 d-e-I g , prior to increasin the Reactor Coolant System temperature above 200 F.Rcsio~e~he.meant(legs~~~v cxbe.~(ess,+4c~%ha,k-speci[(Q 4 h y t 4 Con4~fvlmenk Leq~c'Ra)c.Vcskang'ProgrR~

SURVEILLANCE RE UIR NTS 4.6.1.2 The containment leakage rates shall be demonstrated at the-$e44evAag-rqu'~~A test schedule and shall be determined in conformance with the criteria specified in 4ppen:~P,~~;~~<Lc w~~gi~-p,<<p, ck.~p t pic.ST.LUCIE-UNIT 2 3/4 6-2 Amendment No.36, 81, N.P

~-'8 h~Q~I N~~~f" 4 ill g~~Jf CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS (Continued)

+<QFC~.~c"0.

~i5c 3/9 6"9 i's gAg flcpck Ilnli'4 page..If any periodic Type A test fails to meet either.75 L or.75 L the test schedule for subsequent Type A tests shall be reviewe and pproved by the Commission.

If two consecutive Type A tests ail to me either.75 L or.75 Lt, a Type A test shall be perfo ed at a least very 18 months until two consecutive Type A test meet either.75 L.75 L at which time the above test scheduli may be resumed.c.The accuracy o each Type A test shall be verif d by a supplemental test which: 1.Confirms the ac racy of the Type A st by verifying that the difference betwee supplemental an ype A test data is within 0.25 L or 0.25 Lt.2.Has a duration sufficie to stablish accurately the change in leakage rate between the e A test and the supplemental test.3.Requires the quantity o gas s ected into the containment or'bled from the contai nt during the supplemental test to be equivalent to at le t 25K of the tal measured leakage rate at P , 41.8 psig Pt, 20.9 psig.d.Type B and C tests all be conducted with ga at P , 41.8 psig at intervals no gre er than 24 months except for t ts involving:

l.Air loc e.2.Pur supply and exhaust isolation valves with resi ent m erial seals.Pur supply and exhaust isolation valves with resilient mater 1 s s shall be tested and demonstrated OPERABLE per Surveillance equirements 4.6.1.7.3 and 4.6.1.7.4.

ST.LUCIE-UNIT 2 3/4 6-3 Amendnent No.ff, 66

~~4 E CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continued QECC.ran The combined bypass lea ge e s all be deterinined to be less o ual to G.I2 L by applicable Type B and C tests at le nce per 24 mon except for penetrations which are no ividually testable;penetr s not individually tes shall be determined to have no detectable e when tes with soap bubbles while the containment is pressuriz , 41.8 psig during each Type A test.g.Air locks shal tested and demonstrated OPE Requi.6.1.3.er Survei 1 lance~h i e provisions of Specification 4.0.2 are not applicable.

.ST.LUCIE-UNIT 2 3/4 6-4 Amendment S).~

TABLE 3.6-1 CONTAINMENT LEAKAGE PATHS g Penetrattnn

~S stem t 7 Ma up Mater Station A Valve Ta Number T e I-HCV-15-1 Globe I-V-15-328 Check I-V-18-794 Globe I-V-18-1270 Check I-V-18-797 Globe I-HCV-18-2 Globe Location to Containment Outside Inside Outside Inside Annulus Outside Service Primary Makeup Mat Station A Supply T T e*BYPASS/TYPE C BYPASS/TYPE C 10 I 11 14 I'p4 rt O 25 Instrument Afr Containment Purge Containment Purge Maste Management Component Coolin Compon Cooling.I-V-18-1 Globe I-V-195 Check I-FCV-25-5

'FLY I-FCV-25-4 B'I-FCV-25-2 B'F I-FCV-25-3 LY V-67 Globe V 92 Check I-HCV-14-7 B'FLY I-HCV-14-1 O'PLY-I-HCV-14-6 B'FLY I-HCV-14-2 B'FLY CVCS I-V-2516 Globe I-V-2522 Globe Puel Transfer Tube Oouble Gasket Flange Outside Insi Annulus Inside Annulus Inside 0 ide Ins Outside Inside Outside Inside Inside Inside Outside Containment Purge Exhaust Containment Purge Supply N2 Supply to Safety In).Tanks RC Pump Cooling ater Supply RC Pu Cooling Mater Re rn Fuel Transfer, Letdown Line TYPE C TYPE C BYPASS/TYPE C BYPASS/TYPE C BYPASS/TYPE C BYPASS/TYPE C YPASS/T C Instrument Air Supply BYPASS/TYPE C TABLE 9;6-1~~untinued)

CONTAINMENT LEAKAGE PATHS Samp 29A Sampling 298 Sampling 4J 31 a 41 Waste Management Safety Injection Waste Management 43 Waste Management 44 CVCS el Pool rn Penet tien~S stem I 28A.Sampling 208 Val ve Ta Number/T e ISE-05-1A,18,1C10 Globe ISE"05-lE Globe I-V-5200 Globe I-V-5203 Globe I"V-5204 Globe I-V-5201 Globe-5205 Globe I"V-02 Globe I-V" 6718 D h I-V-6750 Oiap I" SE" 03" 2A,28 Glob I-V-3463 Gate I-LCV-11A Globe I-L-07-118 Globe I-V-6341 Oi aph I-V-6342 Oiaph I-V-2524 Globe I-V-2505 Globe I-V-07-206 Gate I-V-07"189 Gate Location to Containment Inside Outside Inside Outside Outside Inside Outside Inside I>de utside Inside Outside Insi Outside Inside Outside Inside Outside Outside Inside Service Safety/Injection Tank Sample RCS Hot Leg Sample Press Surge Sa e Pressure Steam Sample~Containment Vent'eader Safety Injection Tank Fill/Orain agd Sampling 4 Reactor Cavity Sump Pump Discharge actor Orain Tank Pui Suction Reactor lant Pump Controlled edoff Fuel Pool Cleanup (inl et)Test T ASS TYPE C BYPASS TYPE C BYPASS TYPE C BYPASS TYPE C BYPASS TYPE C BYPASS TYPE C BYPASS TYPE C BYPASS TYPE C BYPASS TYPE C BYPASS TYPE C 47 Fuel Pool I-V"07-170 Gate I-V-07-188 Gate Outside Inside Fuel Pool Cleanup (outlet)B SS TYPE

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TABLE 3.6'Continued) e CONTAINMENT LEAKAGE PATHS m.Penetra I g 48A 48B 51A 518 52A M'28 52C 52D 52E 54 55 n~Setem ampling Sampling Sampling Sampling Sampling Sampling Sampling ILRT ILRT ILRT Containment H2 Purge Valve Ta Number/T e I-FSE-27-8,9,10-11 Globe I-FSE-27-15 Globe I-V-27-101 Check I-FSC.27-16 Globe I-FSE-27-12,13,14 Globe-FSE-27-18 Globe I-V--102 Check I" FSE-2 7 Globe I" FCV" 26" 1 Glo I-FCV-26-2 Globe I-FCV-26-3 Globe I-FCV-26-4 Globe I-FCV-26-5 be I-FCV-26-Globe I-0-140 Globe-V-00-143 Globe I-V-00-139 Globe I-V-00-144 Globe I-V-00-101 Gate Blind Flange I-FCV"25"26 B'FLY I-FCV-?5-36 B'FLY Location to Containment Inside Outside Inside Outside Inside Outside Inside Outside In e tside Inside utside Insi Outside Inside Outside Inside Outside Outside Inside Outside Inside Service H2 Sampling Outlet H2 Sampling Inlet Hz-Samp ng Outl 2 Sampling Inlet Containment Radiation Honitoring Containment Radiation Honitoring Containment Radiation Honitoring ILRT ILRT ILRT Cont.Containment H2 Purge Hakeup Inlet Test T T C TYPE C TYPE C TYPE C BYPASS TYPE C BYPASS TYPE C BYPASS TYPE C BYPASS TYPE C BYPASS TYPE C BYPASS/TYPE C BYPA Q TYPE C~

~~J/J'/1/i t l/

TABLE 3.6-1{Continued)

CONTAINMENT LEAKAGE PATHS P tratfon 57 67 Personnel Lock Escape Lock Maintenance Hatch Electrical Penetratfons 1 25 50~Sstem Containment H~Purge cuum Re ef Vacuum Rel fef HA HA HA Main Steam Steel Containment Nozzle Mafn Steam Steel Containment Nozzles Feedwater Steel Containment H les Feedwater eel Contaf ent Hozfles F Tube Steel ontafnment Hozzles Temporary Services Valve Ta Number/T e I"V" FCV-25" 20 B'FLY I-FCV" 25" 21 8'LY I-V"25-20 Check I-FCV"25"7 8'FLY.I-V<<25-21 Check I"FCV"25"8 8'FLY Hone None All Prfmary Can er.except welded spar Tap 1 Tap 2 Tap 1 Te Tap 1 Tap 2 Tap 1 Tap 2 Tap 1 Blind Flange Blind Flange Location to Containment Inside Outside Inside Outside Inside Outs!de HA Outside side Outs Outside Outside Outside Outside Outside Inside Outside Inside Test e" Secvtce Cont.Containment Purge-Exhaust Containment

.Vacuum Relfef Containme Vacuum lief In ess and Egress o Containment Emergency Ingress and TYPE 8 Egress to Contafnment Vessel Maintenance TYPE 8 B ASS/YPE C TYPE C TYPE B Expansion Bellows Expansfon Bellows TYPE 8 TYPE 8 Ex sion Bellows Expansion llows Expansion Bellows TYPE 8 TYPE 8 TYPE 8 Construction/Outage T 8 Use ype an ypass ests are conducted in the same manner, the only difference fs in the acceptance criteria.that fs applicable.

/,r f i'l,/h CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION III 3.6.1.3 Each containment air lock shall be OPERABLE with: a.Both doors closed except when the air lock is being used for normal transi%entry and exit through the containment, then at least one air lock door shall be closed, and b.An overall air loc leakage rateof-loess-4han-o~ua4-4o-0&5-L

-a4-again APPLICABILITY:

MODES 1, 2, 3, and 4.ACTlON: With one containment air lock door inoperable~:

1.Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock the OPERABLE air lock door closed.2.Operation may then continue until performance of the next required overa11 air lock 1eakage test provided that the OPERABLE air lock door is verified to be locked closed at least once per 31 days.3.Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />'nd in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.4.The provisions of Specification 3.0.4 are not app1icable.

With the containment air lock inoperable, except as the result of an inoperable air lock door, maintain at least one air lock door closed;restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.If the inner air lock door is inoperable, passage trough the OPERABLE outer air lock door is permitted to effect repairs to the inoperable inner air lock door.Ho more than one airlock door shall be open at any time.ST.LUCIE-UNIT 2 3/4 6-9 Amendment No.W 0 J 1 1 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE: jf~ai~hM=capabiaty.-

4 At least once per 6 months by verifying that only one door in each air lock can be opened at a time.a.'ey ve~I'y,'ng l&Lkeg~rates a~g~;~loci>.Ao~oCcor d.~~c e Lea<egaRa.la Teskn~P,'rg(ra~a~J ST.LUCIE-UNIT 2 3/4&10 Amendment No.86,~

v~f.I I si I~~~I1 I~" II CONTAIINENT SYSTB6 CDHTAINHENT VESSEL STRUCTURAL INTEGRITY LIHITIHG COHOITION FOR OPERATION 3.6.1.6 The structural integrity of the contaireent vessel shall be aaintaincd at a level consistent

~ith thc acceptance criteria in Surveillance Rcqui~nt 4.6.1.6.APPLICABILITY:

DOGES 1, 2, 3 and 4.ACTION: With the structural integrity of the containacnt vessel not conforming to the above requiresents, restore the structural integrity to within fM liaits prior to increasing the Reactor Coolant Systce teaperature above 2OOoF SURVEILLANCE RE UIRENEHTS~'a ac~<~c~~,+OAhe Gn4ai'AIr end L encage.'Rale 7cz$(ng'Prop ra~4.6.1.The structural integrity of the contaicment vessel shall be detcr-ained dur-in exposed accessible interior and exterior surfaces of the vessel and ver-fying no apparent changes in appearance of the surfaces or other abnormal degra-dation.i 5T.LUCIK-UNIT 2 3/4 6-13 Amendment l)o.

E'I'l~$I~~~&1~P 4 h t CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION APPLICABILITY:

MODES 1, 2, 3 and 4.ACTION: conga'.n conf Mith one or more~-the isolation valve(s)i noperabl e, maintain at least one isolation valve OPERABLE in each affected penetration that is open and either: a.Restore the inoperable valve(s)to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or b.Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or C.d.Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange;or Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOMN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.SURVEILLANCE RE UIREMENTS C0nka:e agnew$OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or.its associated actuator, control or power circuit by performance of a cycling test and verification of isolation time.ST.LUCIE-UNIT 2 3/4 6-19 CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS (Continued)

Cont~'n~o~0 4.6.3.2 Each automatic isolation valve shall be dem-onstrated.OPERABLE during the COLD SHUTDOMN or REFUELING MODE at least once per 18 months by: a.Verifying that on a Containment Isolation test signal (CIAS)and/or a Safety Injection test signal (SIAS), each isolation valve actuates to its isolation position.b.Verifying that on a Containment Radiation-High test signal, each containment purge valve actuates to its isolation position..~,so<<1"~'anker

<<~~4.6.3.3 The isolation time of each power operated or automatic valve ef-~He~~shall be determined to be within its limit when tested pursuant to Specification 4.0.5.ST.LUCIE-UNIT 2 3/4 6-20 peen Jeenh Q0.

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Penetration

.Haximu Testable During lsol ion A)Con nment Isolat I-HCV-15-I-HCV-18-2 I-HCV-18-1 1-FCV-25-5,4 I-FCV-25-2,3 V-6741 I-HCV-14-7 I-HCV-14-1 I-HCV-14-6 I-HCV-14-2 I-V-2516 I-V-2522 10 23 24 26 Primary Hakeup Mater (CIS)Station Air Supply Instrument Air Supply (CIS)Yes Containment Purge Hak (CIS)Nit en Supply Safety Inject Tank (C IS)Reactor C t Pump Cooling Mater ply ()R tor Coolant Pump oling ater Return (SIAS)Letdown Line (CIS)No Yes Containment Purge Exhaust S)No I-SE-05-1A)]B, IC,ID,IE 28 Safety Injection Tank Sample Yes I-V-5200 I-V-5203 I-V-5204 I-V-5-5205 I-V-5202 28B 29A 29B Reactor Coolant System Hot Leg Sample (CIS)Pressurizer Surge Sample (CIS)Pressurizer Steam Sample (CIS)Yes Yes Yes k'll I C'4 t/J f

'alve Ta umber I"V-6718 I"V-6750 Penetration Number 31 TABLE 3.6-2 (Continued)

CONTAINHENT ISOLATION VALVES Function Containment Vent Header (CIS)Haximu Testable Outing Iso)on ah Yes I"SE"03-2A,28 41 Safety Injection Tank Test Line Yes (CIS/SIAS)

I" LCV-07" 11A I" LCV" 07" 118 I-V-6341 I"V"6342 I"V-2524 I-V"2505 I-FCV" 26" 1 I-FCU-26-2 I-FCV"26"3 I-FCV-26-4 I-FCV"26-5 I-FCV"26"6 I"FCV-25-26 I-FCV-2 6 V"25-20-FCV-25-21 42 43 52A 56 57 Reactor Cavity Sump Pump Oischarge (CIS/SIAS)

T Pump Suction (CIS RCP Contro Bleed-off I Con nment Radiatio itoring (CIS)Containment Radiation Honitoring (CIS)Containment Radiation Monitoring (CIS)Cont.Containment/Hz Purge Hakeup Inlet (CIS)Cont.Containment/Hq Purge Exhaust (CIS)Yes Yes No Yes Yes Yes Yes Yes 5 10 10 10 P I I'y l!/V/1//

I n M m I lve Ta Number 8)Ha al CR.Remot anual Penetration Number TASLE 3.6-2 (Continued)

CONTAINMENT ISOLATION VALVES Function Haximum Testable'During Isolat~P)t.II t.lli S I"V"18"79 I-V-18-1270 Station Air Supply (Hanual)Station Air Supply{Check)Yes No NA NA 4l I tO I"V"3463 I"V"07"206 I-V-07-189 I-V-07" 170 I-V"07"188 46 I-FSE"27"8)9)10, 48 11>15,16 I"FSE-27"12,13,14, 51 17,18 Safety Injection Tank Test Line (Hanual)Fuel Pool Cleanup (Inl nual)Fuel Po Clea (Outlet){Hanual), Hq Sam ng (Remo Hanual)Hq Sampling (Remote Hanual Yes Yes~Yes Yes Yes NA O I"V-00-140 I-V-00"143 I-V-00"139 I"V"00-144 I-V-00" 1 520 52E ILRT (Hanual)ILRT (Hanual)ILRT{Hanual)Yes Yes NA NA 1I COHTAI HMEHT SYSTEMS SHIELD BUILDING STRUCTURAL INTEGRITY UNITING CONDITION FOR OPERATION 3.6.6.3 The structural integrity of the shield building shall be maintained at a level.consistent with the acceptance criteria in Surveillance Require-ment 4.6.6.3.APPLICABILITY:

KIDES 1, 2, 3 and 4.ACTION With the structural integrity of the shield building not conforming to the above requirements, restore the structural integrity to within the limits within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 3O hours.SVRYEILLAHCE RE UIREHEHTS 4.6.&.3 The structural integrity of the shield building shall be determined accessible interior and exterior surfaces of the shield building and verifying no apparent changes in appearance of the concrete su~faces or other abnormal degradation.

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4f<AS FI'n i inyra~ST.LUCIE-UHIT 2 3/4 6-31 Amendment No.

.Ig ,a II,~f ll\~~I 3/4.6 CONTAINMENT STEMS BASES.3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the safety analyses.This restriction, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.

LgdsEk7 Q5 (gt, g ps,'Q Mhi'ch rcs~llS 4io~3/4.6.1.2 CONTAINMENT LEAKAGE y4~);~,~;~~~tge basis, loss of Coo'l~~t ace.'ew+.The limitations on containment leakage ra es ensure tha t e total containment leakage volte will not exceed the value assumed in the accident P k**kh P.P.~~',hh Pk h P<<Phh leakage rates~consistent with as modified by approved exemptions The surveillance testing for measuring the requirements of Appendix 0 of 10 CFR 50 R'-the-r~A4s 3/4.6.1.3 CONTAINMENT AIR LOCKS The maximum peak pressure expected to be obtained from a steam line break event is 43.4 psig.The limit of 0,4 psig for initial positive containient pressure will limit the total pressure to 43.99 psig which is less than the design pressure and is consistent with the safety analyses.~~Qp f/~5 aod R<g4 ta<o<144ide.

l l(o3>~)eel'e p)o~bc R5'he limitations on closure and leak r e conta en ocks 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 leaka e tests.3/4.6.1.4 INTERNAL PRESSURE Cenkfnwonf Le<gcge,'R~ic-S~'")I J'"~q and I'5 The limitations on contaiaaent interna pressure ensure that (1)the containment structure is prevented from exceeding its design negative pressure differential with respect to the annulus atmosphere of 0.7 psi and (2)the containment peak pressure does not exceed the design pressure of 44 psig during steam line break conditions.

ST.LUCIE-UNIT 2 B 3/4 6-1 Amendnent Ho.d+

4 4~"~4 I.V~~'V~4 4~I~~~4~4~4 A 4~~4~"V'j 4 j I CONTAINMENT SYSTEMS BASES 3/4.6.1.5 AIR TEMPERATURE The limitation on containment average air temperature ensures that the containment temperature does not exceed the design temperature of 264 F during steam line break conditions and is consistent with the safety analyses.3/4.6.1.6 CONTAINMENT VESSEL STRUCTURAL INTEGRITY'l l 8 This limitation ensures that the structural integr'of the containment steel vessel will be maintained ceaparable to the orig'nal design standards for the life of the facility.Structural integrity i required to ensure that the vessel will withstand the maximum pressure of.psig in the event of a A visual inspection in s i t to demonstrate this cap ity./'.J g+ggg&gal,'5 Ib5s oI Coolant Aoci'af i'd tg/.6..CONTAINMENT VENTILA N SYSTEM The 48-inch containment purge supply and exhaust isolation valves are required to be closed during plant operation since these valves have not been demonstrated capable of closing during a LOCA or steam line break accident.Maintaining these valves closed during plant operations ensures that excessive quantities of radioactive materials will not be released via the contairaent purge system.To provide assurance that the 48-inch valves cannot be inadvertently opened,=they are sealed closed in accordance with Standard Review Plan 6.2.4 which includes devices to lock the valve closed, or prevent power from being supplied to the valve operator.The use of the containment purge lines is restricted to the 8-inch purge supply and exhaust isolation valves since, unlike the 48-inch valves, the 8-inch valves will close during a LOCA or steam line break accident and therefore the site boundary dose guidelines of 10 CFR Part 100 would not be exceeded in the event of an accident during purging operations.

Leakage integrity tests with a maximum allowable leakage rate for purge supply and exhaust isolation valves will provide early indication of resilient material seal degradation and will allow the opportunity for repair before gross leakage failure develops.The 0.60 L leakage limit shall not be exceeded when the leakage rates determined 3y the leakage integrity tests of these valves are added to the previously determined total for all valves and penetrations subject to Type B and C tests.ST.LUCIE-UNIT 2 B 3/4 6-2 Atttendment No.

~I J~4 I~I e ,.ADMINISTRATIVE COHTRO than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, 10)Limitations on the annual dose or dose coaxnitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.g.Radiol ical Environmental Monitorin Pr ram A prepam shall be provided to monitor the radiation and radio-nuclides in the environs of the plant.The program shall.provide (1)representative measurements of radioactivity in the highest potential exposure pathways, and (2)verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways.The program shall (1)be contained in the ODCM, (2)conform to the guidance of Appendix I to 10 CFR Part 50, and (3)include the following:

1)Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM, 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 3)Participation in a Interlaboratory Coiparison 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 monitoring.

ST.LUCIE-UNIT 1 6-15b Amendment No.P PNSERT A Unit 2]With the containment leakage rate exceeding the acceptance criteria of the Containment Leakage Rate Testing Program, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate action to be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

[INSERT B Unit 2]In accordance with Generic Letter 91-08,"Removal of Component Lists from Technical Specifications," the opening of locked or sealed closed containment isolation valves on an intermittent basis under administrative control includes the following considerations:

(1)statio'ning an operator, who is in constant communication with the control room, at the valve controls, (2)instructing this operator to close these valves in an accident situation, and, (3)assuring that environmental conditions will not preclude access to close the valves and that this action will prevent the release of radioactivity outside the containment.

[INSERT C Unit 2]h.Containment Leakage Rate Testing Program A program 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 is in accordance with the guidelines contained in Regulatory Guide 1.163,"Performance-Based Containment Leak-Test Program," as modified by the following exception:

a.Bechtel Topical Report, BN-TOP-1 or ANS 56.8-1994 (as recommended by R.G.1.163)will be used for type A testing.The peak calculated containment internal pressure for the design basis loss of coolant accident, Pis 41.8 psig.The containment design pressure is 44 psig.The maximum allowable containment leakage rate, Lat Pshall be 0.50%of containment air weight per day.Leakage rate acceptance criteria are: Containment leakage rate acceptance criterion is<1.0 L,.During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are<0.60 L, for the Type B and C tests,<0.75 L;for Type A tests, and<0.27 L, for secondary containment bypass leakage paths.b.Air lock testing acceptance criteria are: 1)Overall air lock leakage rate is<0.05 L, when tested at>P,.2)For each door seal, leakage rate is<0.01 L, when pressurized to>P,.The provisions of T.S.4.0.2 do not apply to test frequencies in the Containment Leak Rate Testing Program.The provisions of T.S.4.0.3 are applicable to the Containment Leak Rate Testing Program.

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