ML17229A106

Proposed Tech Specs 1.6 Re Channel Functional test,1.7 Re Containment Vessel integrity,1.8 Re Controlled leakage,1.9 Re Core alteration,3/4.6 Re Containment Systems & 3/4.6.1 Re Containment Vessel

ML17229A106
Person / Time
Site:	Saint Lucie
Issue date:	10/28/1996
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17229A105	List: ML17229A104 ML17229A106
References
NUDOCS 9611010271
Download: ML17229A106 (45)

Text

ATTACHMENT 3 PROPOSED LICENSE AMENDMENT FOR IMPLEMENTATION OF 10 CFR 50~APPENDIX iT OPTION B 1-2 3/4 6-1 thru 3/4 6-11 3/4 6-14 3/4 6-18 thru 3/4 6-22 3/4 6-31 B3/4 6-1 B3/4 6-2 6-15b Insert Pages VhiiOf0271 961028 PDR ADOCK 05000335 P PDR

1.6 A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal into the channel as close 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.1.Capable of being dosed by an OPERABLE containment automatic isolation valve system, or 2.Closed by manual valves, blind fianges, or deactivated automatic valves secured in their closed'fov Qalve5+4~4 oLic open on an in4ar A1r>~~n~4R5'I~e~~~wi'nrSk~a~i'vc.

Conf~ol.b.All n inment vesse eq ent hatches are closed and sealed,'.Each containment vessel air lock is in compliance with the requirements of Specification 3.6.1.3, d.The containment leakage rates are within the limits of Specification 3,6.1.2, and 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 seals..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head removed and fuel in the vessel.Exceptions to the above Include shared (4 fingered}control element assemblies (CEAs)withdrawn into the upper guide structure (UGS)or evolutions performed with the UGS in place such as CEA latching/unlatching or verification of latching/unlatching which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-UNIT 1 1-2 1,~t1'V~11'1~~~~VS'"ii,;1,~.1 261.6 CONTAINMENT SY 3 4.6.1 CONTAXNMZXT SEL CONTAINMENT VESSEL LXMXTINt" CONDXTXON FOR OPERATION 3~6~I.~I.CONTAINMENT VESSEL shall be maintained.

d ACTION dd INTEGRITY within one hour 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 UIREMENTS 4.6.I..I.CONTAINMENT VESSEL shall be demonstrated:

a.At least once per 31 days by verifying that: 1 0-gr valve@+l+~c open oe an lnher~tkfenI 4<'s der<<Aw~i~<~All containment vessel 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 positions, except a4oa-i and b.2.All con axnment vessel equipment hatches are closed and sealed.By verifying that each containment vessel air lock is OPERABLE per Specification 3.6.1.3.*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 pene-trations shall be verified closed during each COLD SHUTDOMN except that such verification need not be performed more often than once per 92 days.ST.LUCIE-UNIT I.3/4 6-I.Amendment No.

I II'l 262 CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited~Cow(alarne+f LegMge,'palm~C'S'ki'n5

+Ogr.pe, 9~l~~ou~<&+&BI t h~-oman-'I" d-'~~APPLICABILITY:

MODES 1, 2, 3 and 4.eeonda~oah6n a ACTION: 200'F.C+Q58~1 AQ red-over d-k 1~store th leakage rate~to within-the prior to increasing the R actor Coolant S stem te era ab)ps'~<Ph<5 spec,'4)eJ by t"~Oyggsk'll COhkigkinmgh}

L@t~gC.~fi'4'g P<omrsgm SURVEILLANCE RE UIREMENTS e f 4$akar cd'c,bede>~4.6.1.2 The containment leakage rates shall be demonstrated at the and shall be determined in conf nce with'riteria specified in Coqgskfn~n4.

L~4~I ST.LUCIE'UNIT 1 3/4 6-2~~nmennment no.gg, 4 I'~l~I!~Fl~I~I II I~~b.~~4~I~I II~~~~T~4~I~I a~'4 263 CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continued C.d.e.Rp5~/g (n-3 fhvougQ 3/c/(-P have 6eeg 3AF7c-8~<ye.3/g (-fO S she.nag/V~/,'~p<~<.

If any periodic Type A test fails to meet either.75 L or.75-the test schedule for subsequent Type A tests shall be review and approved by the Comnission.

If two consecutive Type A ests fail to meet either.75 L or.75 L , a Type A'test s ll be performed at least every 18 months until two co sec ive Type A tests meet either.75 L or.75 Lt at w ich time e above test schedule may be res5med.The accu cy of each Type A test shall be verifie by a supplement test which: 1.Confirms e accuracy of the Type A tes by verifying that the di ference between supplemen 1 and Type A test data is withi 0.25 L or 0.25 Lt, a 2.Has a duration s ficient to est lish accurately the change in leakage tween the A test and the supplemental test.3.Requires the quantity o s injected into the containment or b'ied from the contai t during the supplemental test to be equivalent to at eas 25 percent of the total measured leakage rat at P 9.6 psig)or P (19.8 psig).Type B and C tests sh be conducted ith gas at P (39.6 psig)at intervals no grea r than,24 months cept for tests in-, volving air locks.The combined b ass leakage rate shall be de rmined to be<0.27 L by plicable Type B and C tests at ast once per 24 months e ept for penetrations which are not dividually testable;enetrations not individually testable s all be determin d to have no detectable leakage when teste with soap bubble while the containment is pressurized to P (3 6 psig)duri each Type A test.f.A locks shall be tested and demonstrated OPERABLE per urveillance Requirement 4.6.1.3.ST.LUCIE-UNIT 1 3/4 6-3 Amendment No.gg~

~t i~H'I~"'E l*

CONTAINMENT SYSTEMS SURYEILLANCE RE UIREMEHTS.

Continued et.87ED All Type A test leakage rates shall be calculated using ob rved data converted to absolute values.Error analyses shall e performed to select a balanced integrated leakage meas ent stem ST.LUCIE-UNIT 1 3/4 6-4 4~

Location Makeup Water ation hir Gate (I-MV-15-1)

Cheok (I V-15328)Globe (I V 18-794)Globe (I>>V-18-796)

Outside Inside Outside Outside Primary Makeup Wate Station hir upply Bypass Bypass 10 Instrument hir Containment Purge p Containment Purge Gate (I-MV-18-1)

Cheok (I<<V 18195)Butt ly (I-PCV-25-4)

Butterf (I-FCV-25-5)

Butterfly (I--25<<3)Butterfly (I<<PCV--2)Outside Inside Insi 0 side Inside Outside Containment Purge Exhaust Containment Purge Supply Type C~Type C Instrument Air Supply Bypass 23 25 Waste Management Component Cooling Component Cooling Fuel Transfer Tube Globe (V 6741)Cheok (V-6779)Butterfly-HCV 14-7)Butterf (I<<HCV-14-1)

Bu erfly (I-HCV-14-6) tterfly (I-HCV-14-2)

Double Gasket Flange Outside Outside Ou ide Outs Outside Outside Inside Nitrogen supply to SI Tanks RC Pump CW Supply RC Pump CW Return Fuel T sfer Bypass Bypass Bypass Bypass 26 28 CVCS ampling Globe Globe Globe Globe Globe Globe (V 2515)(V-2516)V-5200 y-5203 I PCV-03-18)

I PCV 03 1P)Inside Inside Outside Outside Outside Outside Letdown Line Reaotor Coolant Sample SI Tank Sample SI Tank Sample Bypass pass TABLE 3.6-1 Continued enetrat$on~S stem 29 Sampling 29 Sa ling 31 Waste Management Valve Ta Number Globe (V-5202)Globe (V-5205)Globe (V-5201)Globe (V-5204)Gate (V-6554)Gate (V-6555)42 43 44 Waste Management Waste Management CVCS Gate (I-LC 7-llA)Gate (I-LCV-0 lB)Gate (V-6301 Gate V-6302 Gate V 05)Gate-SE-01-1)Safety Injection Ga V-3463)Tank Test Lines Gate-V-07009)Location to Containment Outside Outside Outside Outside Outside Outside Outsid Outs e utside Outside Outside Outside Ou de Inside Service Pressuri zer Steam Space Sample Pressurizer rge Line Samp Con nment Vent ader Test T Bypass Bypass Bypass Reactor Drain Tank Pump Suction HC Pump Controlled Bleedoff Bypass Bypass Safety Injection Tank Bypass Fill and Sampling Reactor Cavity Sump Bypass Pump Oischarge Fuel Pool Cleanup ate I-V-07-206)

Gate I-V-07-189)

Outside Inside fueling Cavity Pu ication Flow Inlet Bypass 47 Fuel ool Gate (I-V 07-170)C anup Gate (I-V-07-188)

Outside Inside Refueling C ity Purification w Outlet Bypass 48 Sampling Globe (3, 4)Globe (I-FSE-27-'l, 2, I-FSE-27-8)

Inside Outside K2 Sampling e C Penetratten

~S stem TABLE 3.6-1 Continued Location VV1TUN b t C tl Ser vice Test T e+n tel 5lc Sampling 51 a 48c Sampling Gl obe (I-FSE-27-11)

Check I-V-27101)Globe I-FSE-27-5,6,7)

Globe I-FSE-27-9)

Globe I-FSE-27-10)

Check (I-V-27102)Outside Inside'Inside Outside Outside Inside H2 Sampling H2 Sampli H ampling Type C Type C Type C 52a 52b 52c 52d 52e 54 56 57 Sampling Sampling Sampling ILRT ILRT ILR Containment H2 Purge Containment H2 Purge ate I-FCY-26-1)

Ga I-FCV-26-2)

Gate I--26-3)Gate I-FCV--4)Gate I-FCV-2 Gate I-FC 6-6)Glob I-V00140)G e I<<V00143)Globe I-V0013g)~Globe I-V00144)Blincl Flange Gate (I-V00101)Gate I-V-25-11)

Gate I-V-25-12)

I Gate I-V-25-13)

Gate I-V-25-14)Insi 0 side Inside Outside Inside Outside lns e Outsi Inside Outside Inside Outside Outside Outside Outside Outside Radi ation Monitoring Radiation Monitoring Radiation Monitoring Return ILRT Test Tap Bypass Bypass Bypass Bypass I Test Tap Bypass Bypass Hydrogen Purge Exhaust Bypass ILRT Pressu Connection Hydrogen Purge f)utside pass Air Makeup l/1 h L I'//S I TABLE 3.6-1 Continued netration~S stem Valve Ta Number Location to Containment Service Test*I n m 68 Vac Relief Vacuum Relief 58 Containment H2 Purge Gate (I-V-25-15}

Gate{I-V-25-16)-Check (I-V-25-20)

Butterfly (I-FCV-25-7)

Check (I-V-25-21) utter fly (I-FCV-25-8)

Outside Outside Inside Outside Inside.Outside Containment

, Vacuum Rel f Cont nment V uum Relief Type C Type C Hydrogen Purge'xhaust ypass Personnel N.A.Lock N.A.Ingress&Egress to Containment Type 8**Escape N.A.Lock I Hafntenance N.A.Hatch None None N.A.N.A.Emergency Ingress&Type 8**Egress to Containment Vessel Maintenance Type B (Gasket Interspace)

Electrical N.A.Penetrations Hain S m Steel Cont nment zles All-mary canisters a flanged electr ical penetrations except welded spares Tap 1'ap 2 N.A.Outside Outside Electrical nections in PCV Expansion Be ws Type 8 Type 0 f0 CL B tD rt 0 Hain Steam Steel Containmen't Nozzles Tap 1 Tap 2 Outs ide Expans ion 8el 1ows Outside e 8 Feedwater Steel Tap 1 Containment Nozzles Tap 2 Outs i de Expa ns i on 8e11ows Outside Type 8

///r//

I C n M m Penetratio tern Feedwater Stee Containment Nozzles Valve Ta Number Tap 1 2 TABLE 3.6-1 Continued Location t C t I t S Outside Expan Bellows Outside st~Te*Type B Fuel Tube Steel Containment Nozzles Tap 1 Expansion Bellows Type B*Type C and bypass ts are conducted in the same manner, the only difference is in the acceptance eria that is applicable.

• • In acc nce with Specification 4.6.1.3.b.

I LO 0 gf/5 270 CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 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 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 s4-9>A accov-d~ce.

coit4~c Con@.nrnenf L&<<ge Rnfe 7cSf'ng P og ra~.APPLICABILITY:

N)DES 1, 2, 3 and 4.ACTION: a.Mith one containment air lock door inoperable+:

1.Maintain at least the OPERABLE afr 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 overall air lock leakage test provided that the OPERABLE air lock door is verified to be 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 /> 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 />.4-The provisions of Specification 3.0;4 are not applicable.

SURVEILLANCE RE UIREMENTS b.Mfth the containment air lock inoperable, except as the result of an inoperable air lock door, maintafn 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 fn COED SHUT-DOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:~g h-a~g~gg<<9<<If the inner air lock door is inoperable, passage through the OPERABLE outer air lock door is permitted to effect repairs to the inoperable inner air lock door.No more than one airlock door shall be open at any tiara.ST.LUCIE-UNIT 1 3/4 6-10 Amendment No.~

ai+cotld--veFifyiag-@e-everalMir-lee aI~heeaHag.-eapabil~4.At least once per 6 months by verifying that only one door in each air lock can be opened at a time.a,'By per i Py:ng)eztcp.rake<anat zl lactcd.oo~

~<<~~~~~a.~'W 44e.Con&:n~~~k Lgpk'p P'~+<l~<~'dg Piogro~~a~J ST.LUCIE-UNIT1 3/4 6-11 Amendment No.65,+R 274 CONTAINMENT SYSTEMS CONTAINMENT VESSEL STRUCTURAl.

INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.6 The structural integrity of the containment vessel shall be maintained at a level consistent with the acceptance criteria in.Speci-fication 4.6.1.6.APPLICABILITY:

MODES 1, 2, 3 and 4.ACTION: Mith the structural integrity of the containment vessel not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200'F.SURVEILLANCE RE UIREMENTS 4.6.1.6 The structural integrity of the containment vessel shall be determined dur4n nc..by a visual inspection of the accessible nterior and exterior surfaces of the vessel and verifying no apparent cha es in appearance of the surfaces or other abnormal degra-dation.aCCO~QOWC.

W,'kh IM COq+a i'ha II A 5)Ln~e l4kr.7~8king T.LUCIE-UNIT 1 3/4 6-14 Amendment No.~

280 I CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALYES.LIMITING CONDITION FOR OPERATION 3.6.3.1 The containment isolation valves shall be OPERABLE.APPLICABILITY:

MODES 1, 2, 3 and 4.ACTION: With one or more of the isolation valve{s)inoperable, 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 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 />.SURVEILLAHCE RE UIREMENTS 4.6.3.1.1 The isolation valves shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement wor k is performed on the valve or its associated actuator, control or power circuit hy performance of the cycling test, and verification of isolation time.ST.LUCIE-UNIT 1 3/4 6-18 Awndutent te.-96

CONTAINMENT SYSTEMS 281 SURVEILLANCE PE UIREMENTS (Continued)

Con Ia'n anent'.6.3.1.2 Each isolation valve V.shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by: a.Verifying that on a Containment Isolation test signal, and/or SIAS.t'est signal, each isolation valve actuates to its isolation position.Con)a nrnen)4.6.3.1.3 The isolation time of each power operated or automatic+valve-e+

to Specification 4.0.5.ST.LUCIE-UNIT 1 3/4 6-19 Amendment No.AO rI'C C 1~4F 1 E~lfll l 4~

PayrS 3/y p-pc,<A~<<I, 3/cl~-PP have Lean~cled<J.gAo HTAINNENT ISOLATION 1.CV"25"4,5 2.I-FCV"-2,3 3.I-MV-15" 1.4.I"HV"18-1 5.V"6741 6~I-NCV-14"1 6 7.Penetration l0 23 Containment purge air exhaust, cIB containment purge supply, cIs Primary makeup water, CIS Instrument air supply, CIS Nitrogen supply to safety in)ection tanks, CIS Reaotor coolant pump coolin water supply, BIAS Testable During No Ye No Yes No Isolat n 1, 19 28 7~I-llCV" 14-6 6 2 8.V"2515,2516 9.V-5200,5203 10.V-5201,5204 ll.V"5202,5205 12~V 6554~6555 13'-LCV"07"llA,118 14.V"6301,6302 o 15.V-2505~~16.-SE" 01-1 26 28 29 29 31 42~43 44 44 Rea or coolant pum ooling water return SIAS Letdown lin CIS, BIAS Reaotor oolant mple, CIS Pr suriaer surge lin sample, CIs Pressurizer steam space sa e, cIS containment vent header, cIs Reactor oavity sump pump discharge, CIS Reactor drain tank pump suction/CIS Reactor coolant pump controlled bleedofi, CIS Reactor coolant pump controlled bleedoft, CIS No Yes Yes Yes Yes Yes Ye No 10 t t~r~IP, f l~s r/f J Penetration Testable During Isolatio Uhh OR REMOTE 1.I-V-1 794 I"V"18" 2o I-V-25 11,12 3o I V-25 13)14)15'6 4.V-3463 5e I-V"07009 6 o V-07206, V 07189 7~V-07170(V 07188 8 I F8E-27-1)2,3(4,Shall 9o I F8E-27-5q6y7q 9,10 56 5 58 41 41 46 47 48a 4 48c 1a 51c Station air supply, Manual Hydrogen purge outside air make-up, Manual (NC}Hydrogen purge exhaust, Manual (NC)Safety in)ection tank test e, nual (NC)Safet n)ection ta test line, Manual (Refueling c purification floe inlet, M al (N Ref ing cavity purif tion floe let, Manual (NC}Hydrogen sampling line, Remote manual Hydrogen sampling line, Remote ihnual Yes Yes Yes Yes Yes Yes Yes Nll Nll 0 Nh~Nh~5 Nh Nh NA*

'I l J ,l I/J//I//l Valve Ta mber 10.I-FCV-26-2 11.I-FCV-26-3 5 4 12.I-FCV-26-5 5 6 13.I-V00140 I-V00143 14.I-V00139 I-V00144'1 5.I-V00101 16.I-FCV-03-lE 8 1F Penetration Number 52a 52b 52c 52d 52e 54 28 TABLE 3.6-2 Continued Function Radiation monitoring R'adiation monitoring Radiation monitoring, return IL test tap ILRT test tap ILRT ssure connection I Tank Sample Testable During Plant 0 eration Yes Yes Yes Yes Yes Yes Isola n T Sec NA NA wNA NA anua a ve-ation time not applicable.

• Hay be ope on an intermittent basis under administrative control.**Normal closed valves-Isolation tfme.not applicable.

r/r'i,/I'/J//L//

293 CONTAINMENT SYSTEMS SHIELD BUILDING STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.6.3 The structural integrity of the shield building shall be main-tained at a.level consistent with the acceptance criteria in Specification 4.6.6.3./C APPLICABILITY:

MODES 1, 2, 3 and 4.ACTION Mith the structural integrity of the shield building not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200'F.'I SURVEIlLANCE RE UIREMENTS 4.6.6.3 The structural integrity of the shield building shall be deter-s l'l N~~~~I 0 by a visual inspection of the accessible interio and exterior surfaces of the shield building and verifying no apparent hanges in appearance of the concrete surfaces or other abnormal deqradatio

~'q q~rCtnnc~m,'k4 p4.Co~~a,'@monk

~<<~pe'Rale.~mt'vg Pr.cpm~ST.LUCIE-UNIT 1 3/4 6-31 Amendment No.

~~~

3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 CONTAINMENT VESSEL 3/4.6.1.1 CONTAINMENT VESSEL INTEGRITY CONTAINMENT VESSEL INTEGRITY ensures that the release of radioactive materiaTs from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses.This restriction, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR Part 100 during accident conditions.

QSQsew7'8Q 3/4.6.1.2 CONTAINMENT LEAKAGE~hi'ch A'Su//5 Prom/~~I<g~5'gn 6tS75 los5 oF CoofanF-abaci'den P The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value as umed in the accident analyses at the peak occident pressure, Pa (39.6 psig).-As-an-'added ppl'~'l e t.eh ZS perMmcd In no@or unce ccpI~/he.ConIoInnr~

I.du<~gaQ 7GSF:<g Propre~an@'Q The surveillance testing for measuring eakage rates~consistent with the requirements of Appendix J'f 10 CFR 50 as modified by approved exemptions, sis~ay-4RC-s) g-@he'4 l~'-4h 14 3/4 6 1 3 CONTAINMENT AIR LOCKS)OPk'm 6""g The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and contain-ment leak rate.Surveillance testing of the air lock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.ST.LUCIE-UNIT 1 B 3/4 6-1 Amendment No.%.]$.~7~

• .~r rlr Ir r i~,i+rr r~I II r~'2 CONTAINMENT SYSTEMS BASES 3/4.6.1.4 INTERNAL PRESSURE The limitations on containment internal pressure ensure that 1)the contai'nment structural is prevented from exceeding its design negative pressure differential with respect to the annulus atmosphere-of 0.70 psi and 2)the containment peak pressur e does not exceed the design pressure of 44 psig during steam line break accident conditions.

The maxiaam peak pressure obtained from a steam line break accident is 41.6 psig.The limit of 2.4 psig for initial positive containment pressure will limit the total pressure to 44.0 psig which is the design pressure and is consistent with the accident analyses.3/4.6.1.5 AIR TEMPERATURE The limitation on containment air temperature ensures that the containment vessel temperature does not exceed the design'emperature of 264'F during LOCA conditions.

The containment temperature limit is consistent with the accident analyses.3/4.6.1.6 CONTAINMENT VESSEL STRUCTURAL INTEGRITY ofMM psig in the event of ins ection~os d onstrate this capability.

accident.A visual e-4e is sufficient to-;n accord.~narc.

m'~+>c C o~4a~~g~$L-8~kngc.go~<Teak;Pf og<he.)l~lk.any des qn to45'osS op Coolan f-6,cc.d8~k This limitation ensures that the structural integrity of the con-tainment steel vessel will be maintained comparable to the original design standards for the life of the facility.Structural integrity is required to ensure that the vessel will withstand the maximum pressure ST.LUCIE-UNIT 1 B 3/4 6-2 Amendment Ho.~

hh I l~(hh hh h1 V 1 h~~II 0 h I h 498 ADMINISTRATIVE CONTROLS (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 radi onucl ides i n the envi ronment 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 omodifications to the monitoring program are made if required by the results of this census, and 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 assur-ance program for environmental monitoring.

Z45cL+(Q 6.9 RE ORTING RE UIREHENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the NRC.STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1)receipt of an operating license, (2)amendment to the license involving a planned increase in power level, (3)installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4)modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.ST.LUCIE-UNIT 1 6-15b Amendment No.69-,-86~~

[INSERT A Unit I]With the containment leakage rate exceeding the acceptance criteria of the Containment Leakage Rate Testing Program, within I hour 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 1]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)stationing 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 1]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 39.6 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,.')For the personnel air lock door seal, leakage rate is<0.01 L, when pressurized to>P,.3)For the emergency air lock door seal, leakage rate is<0.01 L, when pressurized to>10 psig.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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