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 FUNCTIONALTEST 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 CONTAINMENTVESSEL 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 Uptakes ~ha4 ai~ 4'pen c ~ ~n rnlev <,'SIcnk 4c 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 LEAKAGEshall be the seal water flow supplied from the reactor coolant pump seats.

1.9 CORE ALTERATiONshall 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 Exceptions to the above include shared (4 fingered) control element assemblies (CEAs) withdrawn into the upper guide structure (UGS) or evolutions perfommd with the UGS in phce such as CEA latching/unlatching or verification of latching/unlatching which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

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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 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

b. y verifying at eac n r lock is in compliance. with the requirements of Specification 3.6.1.3.

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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.

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CONTAINMENT SYSTEM

'CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited'. i6 accordance. cuI'

<he gyyfyinm~4/'ea4tg~ gp/c 7cyp;np i regrang.

~-& ~~ ~&+i 4I-1 I. %6-p~mb S, f-fJ y-wHghtof-4he-

~nt-ament ai~per24-h uced-pressure-o&P;,

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APPL'ICABILITY:

ACTION:

MODES 1, 2, 3, and 4.

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, prior to increasin the Reactor Coolant System temperature above 200 F.

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~ (ess, +4c~ %ha,k- speci[(Q Leq~c 'Ra)c. Vcskang'ProgrR~

SURVEILLANCE RE UIR NTS rqu'~~A 4.6.1.2 test specified in

~p 4ppen:

The containment leakage rates shall be demonstrated at the -$ e44evAag-schedule and shall be determined in conformance with the criteria

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ST. LUCIE - UNIT 2 3/4 6-2 Amendment No. 36, 81, N.P

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CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS (Continued)

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~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 La or .75 Lt, a Type A test shall be perfo ed at 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

2. Pur supply and exhaust isolation valves with resi ent m erial seals.

e. 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

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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 er Survei 1 lance Requi .6.1.3.

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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 Location to g Penetrattnn ~S stem Valve Ta Number T e Containment Service T T e*

t 7 Ma up Mater I-HCV-15-1 Globe Outside Primary Makeup Mat BYPASS/

I-V-15-328 Check Inside TYPE C Station A I-V-18-794 Globe Outside Station A Supply BYPASS/

I-V-18-1270 Check Inside TYPE C I-V-18-797 Globe Annulus I-HCV-18-2 Globe Outside Instrument Afr I- V-18-1 Globe Outside Instrument Air Supply BYPASS/

I-V- 195 Check Insi TYPE C 10 Containment Purge I-FCV-25-5 'FLY Annulus Containment TYPE C I-FCV-25-4 B' Inside Purge Exhaust I

11 Containment Purge I-FCV-25-2 B'F Annulus Containment TYPE C I-FCV-25-3 LY Inside Purge Supply 14 Maste Management V-67 Globe 0 ide N2 Supply to BYPASS/

V 92 Check Ins Safety In). Tanks TYPE C I' Component Coolin I-HCV-14-7 B'FLY Outside RC Pump Cooling BYPASS/

I-HCV-14-1 O'PLY- Inside ater Supply TYPE C p4 Compon Cooling. I-HCV-14-6 B'FLY Outside RC Pu Cooling BYPASS/

rt I-HCV-14-2 B'FLY Inside Mater Re rn TYPE C O

25 Puel Transfer Tube Oouble Gasket Flange Inside Fuel Transfer, BYPASS/

TYPE C CVCS I-V-2516 Globe Inside Letdown Line YPASS/

I-V-2522 Globe Outside T C

TABLE 9;6-1 ~~untinued)

CONTAINMENT LEAKAGE PATHS Location to rn Penet tien ~S stem Val ve Ta Number/T e Containment Service Test T I

28A . Sampling ISE-05-1A,18,1C10 Globe Inside Safety/Injection ASS ISE"05-lE Globe Outside Tank Sample TYPE C 208 Samp I-V-5200 Globe Inside RCS Hot BYPASS I-V-5203 Globe Outside Leg Sample TYPE C 29A Sampling I"V-5204 Globe Outside Press Surge BYPASS I-V-5201 Globe Inside Sa e TYPE C 298 Sampling -5205 Globe Outside Pressure Steam BYPASS I"V- 02 Globe Inside Sample ~

TYPE C 4J 31 Waste Management I-V"6718 D h I >de Containment Vent BYPASS I-V-6750 Oiap utside 'eader TYPE C a 41 Safety Injection I"SE" 03" 2A,28 Glob Inside Safety Injection Tank BYPASS I-V-3463 Gate Outside Fill/Orain agd TYPE C Sampling 4

Waste Management I-LCV- 11A Globe Insi Reactor Cavity Sump BYPASS I-L 118 Globe Outside Pump Discharge TYPE C 43 Waste Management I-V-6341 Oi aph Inside actor Orain Tank BYPASS I-V-6342 Oiaph Outside Pui Suction TYPE C 44 CVCS I-V-2524 Globe Inside Reactor lant Pump BYPASS I-V-2505 Globe Outside Controlled edoff TYPE C el Pool I-V-07-206 Gate Outside Fuel Pool BYPASS I-V-07"189 Gate Inside Cleanup (inl et) TYPE C 47 Fuel Pool I-V"07-170 Gate Outside Fuel Pool B SS I-V-07-188 Gate Inside Cleanup (outlet) TYPE

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TABLE 3. 6 'Continued) e CONTAINMENT LEAKAGE PATHS Location to m .Penetra n ~Setem Valve Ta Number/T e Containment Service Test T I

g 48A ampling I-FSE-27-8,9,10-11 Globe Inside H2 Sampling T C I-FSE-27-15 Globe Outside Outlet 48B Sampling I-V-27-101 Check Inside H2 Sampling TYPE C I-FSC.27-16 Globe Outside Inlet 51A Sampling I-FSE-27-12,13,14 Globe Inside Hz-Samp ng TYPE C

-FSE-27-18 Globe Outside Outl 518 Sampling I-V- -102 Check Inside 2 Sampling TYPE C I"FSE-2 7 Globe Outside Inlet 52A Sampling I"FCV"26" 1 Glo In e Containment Radiation BYPASS I-FCV-26-2 Globe tside Honitoring TYPE C M'28 Sampling I-FCV-26-3 Globe Inside Containment Radiation BYPASS I-FCV-26-4 Globe utside Honitoring TYPE C 52C Sampling I-FCV-26-5 be Insi Containment Radiation BYPASS I-FCV Globe Outside Honitoring TYPE C 52D ILRT I- 0-140 Globe Inside BYPASS

-V-00-143 Globe Outside TYPE C 52E ILRT I-V-00-139 Globe Inside ILRT BYPASS I-V-00-144 Globe Outside ILRT TYPE C 54 ILRT I-V-00-101 Gate Outside ILRT BYPASS/

Blind Flange Inside TYPE C 55 Containment I-FCV"25"26 B'FLY Outside Cont. Containment BYPA Q H2 Purge I-FCV-?5-36 B'FLY Inside H2 Purge Hakeup Inlet TYPE C~

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TABLE 3.6-1 {Continued)

CONTAINMENT LEAKAGE PATHS Location to P tratfon ~Sstem Valve Ta Number/T e Containment Secvtce Test e" 57 Containment I"V"FCV-25" 20 B'FLY Inside Cont. Containment B ASS/

H~ Purge I-FCV"25" 21 8'LY Outside Purge

- Exhaust YPE C 67 cuum I-V"25-20 Check Inside Containment . TYPE C Re ef I-FCV"25"7 8'FLY Outside Vacuum Relfef Vacuum .I-V<<25-21 Check Inside Containme Rel fef I"FCV"25"8 8'FLY Outs! de Vacuum lief Personnel HA Hone HA In ess and Egress Lock o Containment Escape Lock Emergency Ingress and TYPE 8 Egress to Contafnment Maintenance HA None Vessel Maintenance TYPE 8 Hatch Electrical HA All Prfmary Can er TYPE B Penetratfons .except welded spar 1 Main Steam Steel Tap 1 Outside Expansion Bellows TYPE 8 Containment Nozzle Tap 2 side Mafn Steam Steel Tap 1 Outs Expansfon Bellows TYPE 8 Containment Te Outside Nozzles Feedwater Steel Tap 1 Outside Ex sion Bellows TYPE 8 Containment H les Tap 2 Outside Feedwater eel Tap 1 Outside Expansion llows TYPE 8 Contaf ent Hozfles Tap 2 Outside 25 F Tube Steel Tap 1 Inside Expansion Bellows TYPE 8 ontafnment Hozzles 50 Temporary Services Blind Flange Outside Construction/Outage T 8 Blind Flange Inside Use ype an ypass ests are conducted in the same manner, the only difference fs in the acceptance criteria.

that fs applicable.

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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 in hours'nd 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

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4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:

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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 Ao~

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oCcor d.~~c e Lea <egaRa .la Teskn~ P,'rg(ra~ a~ J ST. LUCIE - UNIT 2 3/4 &10 Amendment No. 86,~

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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.

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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. 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

d. Be in at least HOT STANDBY within the next 6 hours 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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. Haximu Penetration Testable During lsol ion A) Con nment Isolat I-HCV Primary Hakeup Mater (CIS) Yes I-HCV-18-2 Station Air Supply I-HCV-18-1 Instrument Air Supply (CIS) 1-FCV-25-5,4 10 Containment Purge Exhaust S) No I-FCV-25-2,3 Containment Purge Hak (CIS) No V-6741 Nit en Supply Safety Yes Inject Tank (C IS)

I-HCV-14-7 23 Reactor C t Pump Cooling I-HCV-14-1 Mater ply ( )

I-HCV-14-6 24 R tor Coolant Pump oling I-HCV-14-2 ater Return (SIAS)

I-V-2516 26 Letdown Line (CIS)

I-V-2522 I-SE-05-1A)]B, IC,ID,IE 28 Safety Injection Tank Sample Yes I-V-5200 28B Reactor Coolant System Hot Leg Yes I-V-5203 Sample (CIS)

I-V-5204 29A Pressurizer Surge Yes I-V-5 Sample (CIS)

-5205 29B Pressurizer Steam Yes I-V-5202 Sample (CIS)

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TABLE 3.6-2 (Continued)

CONTAINHENT ISOLATION VALVES Haximu Penetration Testable Outing Iso )on

'alve Ta umber Number Function ah I"V-6718 31 Containment Vent Yes I"V-6750 Header (CIS)

I"SE"03-2A,28 41 Safety Injection Tank Test Line Yes (CIS/SIAS)

I"LCV-07"11A 42 Reactor Cavity Sump Yes I"LCV"07" 118 Pump Oischarge (CIS/SIAS)

I-V-6341 43 T Pump Suction (CIS Yes 5 I"V"6342 I"V-2524 RCP Contro No I-V"2505 Bleed-off I I-FCV"26" 1 52A Con nment Radiatio Yes 10 I-FCU-26-2 itoring (CIS)

I-FCV"26"3 Containment Radiation Yes 10 I-FCV-26-4 Honitoring (CIS)

I-FCV"26-5 Containment Radiation Yes 10 I-FCV"26"6 Monitoring (CIS)

I"FCV-25-26 56 Cont. Containment/Hz Purge Yes I-FCV-2 6 Hakeup Inlet (CIS)

V"25-20 57 Cont. Containment/Hq Purge Yes

-FCV-25-21 Exhaust (CIS)

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TASLE 3.6-2 (Continued)

CONTAINMENT ISOLATION VALVES I

n M Haximum m Penetration Testable 'During Isolat I lve Ta Number Number Function ~P) t. II t.l li S

8) Ha al CR .

Remot anual I"V"18"79 Station Air Supply (Hanual) Yes NA I-V-18-1270 Station Air Supply {Check) No NA I"V"3463 Safety Injection Tank Test Yes Line (Hanual)

I"V"07"206 46 Fuel Pool Cleanup (Inl Yes 4l I-V-07-189 nual)

I-V-07"170 Fuel Po Clea (Outlet) Yes NA I ~

tO I-V"07"188 {Hanual )

I-FSE"27"8)9)10, 48 , Hq Sam ng (Remo Hanual) Yes 11>15,16 I"FSE-27"12,13,14, 51 Hq Sampling (Remote Hanual Yes 17,18 I"V-00-140 520 ILRT (Hanual)

I-V-00"143 I-V-00"139 52E ILRT (Hanual) Yes NA I"V"00-144 O

I-V-00" 1 ILRT {Hanual) Yes NA

1I COHTAIHMEHT 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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ST. LUCIE - UHIT 2 3/4 6-31 Amendment No.

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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.

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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 P k **kh P .P.~~

containment leakage volte will not exceed the value assumed in the accident Pk

',hh h P<<Phh The surveillance testing for measuring leakage rates~consistent with the requirements of Appendix 0 of 10 CFR 50 as modified by approved exemptions R

'-the-r~A4s 3/4.6.1.3 CONTAINMENT AIR LOCKS 5 aod Qp f/~ )o~bc R<g4 ta<o<144ide. l l(o3 >~)eel limitations on closure and leak r

'e p e conta R5'he 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.

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. ~ ~

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

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CONTAINMENT SYSTEMS BASES 3/4.6. 1. 5 AIR TEMPERATURE CONTAINMENT VESSEL STRUCTURAL INTEGRITY This limitation ensures that the structural integr'

'l 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 l 8 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 i'd tg g+ggg &gal,'5 Ib5s oI Coolant Aoci'af

/ .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.

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,. 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 STANDBYwithin 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) willbe used for type A testing.

The peak calculated containment internal pressure for the design basis loss of coolant accident, P is 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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