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 FUNCTIONALTEST 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 CONTAINMENTVESSEL 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

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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 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 Exceptions to the above Include shared (4 fingered} control element assemblies (CEAs) withdrawn into the upper guide structure (UGS) or evolutions performed with the UGS in place such as CEA latching/unlatching or verification of latching/unlatching which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

~ t1'V1, ~ 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 hours 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:

10 All containment vessel penetrations* not capable

-gr valve@ +l of being closed by OPERABLE containment automatic

+~c open oe an isolation valves and required to be closed. during lnher~tkfenI 4<'s accident conditions are closed by valves, blind flanges, der <<Aw~i~<~ in their or deactivated automatic valves secured positions, except a4oa- i and

2. All con axnment vessel equipment hatches are closed and sealed.

b. 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.

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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,

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APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

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 200'F. )ps'~< Ph<5 spec,'4)eJ by t"~

Oyggsk'll COhkigkinmgh} L@t~gC. ~fi'4'g P<omrsgm SURVEILLANCE RE UIREMENTS f 4$ akar cd' ec,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~

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ST. LUCIE' UNIT 1 3/4 6-2 nmennment no. gg,

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263 CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continued 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

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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.

C. 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).

d. 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.

e. 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 ~

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• 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 Gate (I-MV-15-1) Outside Primary Makeup Wate Bypass Cheok (I V-15328) Inside ation hir Globe (I V 18-794) Outside Station hir upply Bypass Globe (I>>V-18-796) Outside Instrument hir Gate (I-MV-18-1) Outside Instrument Air Supply Bypass Cheok (I<<V 18195) Inside 10 Containment Butt ly (I-PCV-25-4) Insi Containment Purge Type C ~

Purge p Butterf (I-FCV-25-5) 0 side Exhaust Containment Butterfly (I- -25<<3) Inside Containment Purge Type C Purge Butterfly (I<<PCV- -2) Outside Supply Waste Globe (V 6741) Outside Nitrogen supply to Bypass Management Cheok (V-6779) Outside SI Tanks 23 Component Butterfly -HCV 14-7) Ou ide RC Pump CW Supply Bypass Cooling Butterf (I<<HCV-14-1) Outs Component Bu erfly (I-HCV-14-6) Outside RC Pump CW Return Bypass Cooling tterfly (I-HCV-14-2) Outside 25 Fuel Transfer Double Gasket Flange Inside Fuel T sfer Bypass Tube 26 CVCS Globe (V 2515) Inside Letdown Line Bypass Globe (V-2516) Inside 28 ampling Globe V-5200 Outside Reaotor Coolant pass Globe y-5203 Outside Sample Globe I PCV-03-18) Outside SI Tank Sample Globe I PCV 03 1P) Outside SI Tank Sample

TABLE 3.6-1 Continued Location Test enetrat$ on ~S stem Valve Ta Number to Containment Service T 29 Sampling Globe (V-5202) Outside Pressuri zer Steam Bypass Globe (V-5205) Outside Space Sample 29 Sa ling Globe (V-5201) Outside Pressurizer rge Bypass Globe (V-5204) Outside Line Samp 31 Waste Gate (V-6554) Outside Con nment Vent Bypass Management Gate (V-6555) Outside ader Safety Injection Ga V-3463) Outsid Safety Injection Tank Bypass Tank Test Lines Gate -V-07009) Outs e Fill and Sampling 42 Waste Gate ( I-LC 7-llA) utside Reactor Cavity Sump Bypass Management Gate ( I-LCV-0 lB) Outside Pump Oischarge 43 Waste Gate (V-6301 Outside Reactor Drain Tank Bypass Management Gate V-6302 Outside Pump Suction 44 CVCS Gate V 05) Ou de HC Pump Controlled Bypass Gate -SE-01-1) Inside Bleedoff Fuel Pool ate I-V-07-206) Outside fueling Cavity Bypass Cleanup Gate I-V-07-189) Inside Pu ication Flow Inlet 47 Fuel ool Gate (I-V 07-170) Outside Refueling C ity Bypass C anup Gate (I-V-07-188) Inside Purification w Outlet 48 Sampling Globe ( I-FSE-27-'l, 2, Inside K2 Sampling e C 3, 4)

Globe ( I-FSE-27-8) Outside

TABLE 3.6-1 Continued Location Penetratten ~S stem VV1TUN b t C tl Ser vice Test T e+

n tel 48c Sampling Gl obe ( I -FSE-27-11) Outside H2 Sampling Type C Check I- V-27101) Inside 5lc Sampling Globe I-FSE-27-5,6,7) 'Inside H2 Sampli Type C Globe I-FSE-27-9) Outside 51 a Globe I-FSE-27-10) Outside H ampling Type C Check (I- V-27102) Inside 52a Sampling ate I-FCY-26-1) Insi Radi ation Bypass Ga I-FCV-26-2) 0 side Monitoring 52b Sampling Gate I- 3) Inside Radiation Bypass Gate I-FCV- -4) Outside Monitoring 52c Sampling Gate I-FCV-2 Inside Radiation Bypass Gate I-FC 6-6) Outside Monitoring Return 52d ILRT Glob I-V00140) lns e ILRT Test Tap Bypass G e I<<V00143) Outsi 52e ILRT Globe I-V0013g) Inside I Test Tap Bypass

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Globe I-V00144) Outside 54 ILR Blincl Flange Inside ILRT Pressu Bypass Gate ( I-V00101) Outside Connection 56 Containment Gate I-V-25-11) Outside Hydrogen Purge f)utside pass H2 Purge Gate I-V-25-12) Outside Air Makeup I

57 Containment Gate I-V-25-13) Outside Hydrogen Purge Exhaust Bypass H2 Purge Gate I -V-25-14 ) Outside

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TABLE 3.6-1 Continued Location Test netration ~S stem Valve Ta Number to Containment Service

• I n 58 Containment Gate (I-V-25-15} Outside Hydrogen Purge'xhaust ypass m

H2 Purge Gate { I-V-25-16) Outside Vac -Check ( I-V-25-20) Inside Containment Type C Relief Butterfly (I-FCV-25-7) Outside , Vacuum Rel f 68 Vacuum Check ( I-V-25-21) Inside. Cont nment Type C Relief utter fly (I-FCV-25-8) Outside V uum Relief Personnel N.A. N.A. Ingress & Egress Type 8**

Lock to Containment Escape N.A. None N.A. Emergency Ingress & Type 8**

Lock Egress to Containment I

Hafntenance N.A. None N.A. Vessel Maintenance Type B Hatch (Gasket Interspace)

Electrical N.A. All- mary canisters N.A. Electrical Type 8 Penetrations a flanged electr ical nections in PCV penetrations except welded spares Hain S m Steel Tap Outside Expansion Be ws Type 0 Cont nment Outside 1'ap 2

f0 zles CL B

tD Hain Steam Steel Tap 1 Outs ide Expans ion 8el 1ows e 8 rt Containmen't Tap 2 Outside Nozzles 0

Feedwater Steel Tap 1 Outs i de Expa ns i on 8e11ows Type 8 Containment Nozzles Tap 2 Outside

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TABLE 3.6-1 Continued Location st Penetratio tern Valve Ta Number t C t I t S ~Te*

I nM C

Feedwater Stee Tap 1 Outside Expan Bellows Type B m Containment 2 Outside Nozzles Fuel Tube Tap 1 Expansion Bellows Type B Steel Containment Nozzles

• 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.

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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 APPLICABILITY: N)DES 1, 2, 3 and 4. L &<<ge Rnfe 7cSf 'ng P og ra~.

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.

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 />.

SURVEILLANCE RE UIREMENTS 4.6.1.3 Each containment

~g air lock shall 9

be demonstrated h-a~ g~ gg<<

OPERABLE:

<<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. ~

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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.

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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

281 CONTAINMENT SYSTEMS SURVEILLANCE PE UIREMENTS (Continued)

Con Ia'n V. shall be demonstrated Each isolation valve anent'.6.3.1.2 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

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PayrS 3/y p-pc, <A~<<I, 3/cl ~- PP have Lean ~cled < J.

.Penetration Testable During Isolat n 1,

gAo HTAINNENT ISOLATION

1. CV"25"4,5 l0 Containment purge air exhaust, cIB

2. I-FCV" -2,3 containment purge supply, cIs No

3. I-MV-15"1. Primary makeup water, CIS Ye 19

4. I"HV"18-1 Instrument air supply, CIS No 28

5. V"6741 Nitrogen supply to safety in)ection Yes tanks, CIS 6~ I-NCV-14"1 6 7 23 Reaotor coolant pump coolin water No supply, BIAS 7 ~ I-llCV"14-6 6 2 Rea or coolant pum ooling water return SIAS

8. V"2515,2516 26 Letdown lin CIS, BIAS No

9. V-5200,5203 28 Reaotor oolant mple, CIS Yes

10. V-5201,5204 29 Pr suriaer surge lin sample, CIs Yes ll. V"5202,5205 29 Pressurizer steam space sa e, cIS Yes 12 ~ V 6554 ~ 6555 31 containment vent header, cIs Yes 13 '-LCV"07"llA,118 42 Reactor oavity sump pump discharge, Yes 10 CIS

14. V"6301,6302 ~ 43 Reactor drain tank pump suction/ CIS Ye o 15. V-2505 44 Reactor coolant pump controlled No bleedofi, CIS 16.~ -SE" 01-1 44 Reactor coolant pump controlled bleedoft, CIS

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Penetration Testable During Isolatio Uhh OR REMOTE

1. I-V-1 794 Station air supply, Manual Nll I"V"18" 2o I-V-25 11,12 56 Hydrogen purge outside up, Manual (NC}

air make- Nll 0 3o I V-25 13)14) 5 58 Hydrogen purge exhaust, Manual Yes 15'6 (NC)

4. V-3463 41 Safety in)ection tank test e, Yes Nh~

nual (NC) 5e I-V"07009 41 Safet n)ection ta test line, Yes Nh~ 5 Manual (

6o V-07206, V 07189 46 Refueling c purification floe Yes Nh inlet, M al (N 7~ V-07170( V 07188 47 Ref ing cavity purif tion floe Yes Nh let, Manual (NC}

8 I F8E-27-1)2,3( 48a 4 Hydrogen sampling line, Remote Yes NA*

4,Shall 48c manual 9o I F8E-27-5q6y7q 1a Hydrogen sampling line, Remote Yes 9,10 51c ihnual

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TABLE 3.6-2 Continued Penetration Testable During Isola n Valve Ta mber Number Function Plant 0 eration T Sec

10. I-FCV 2 52a Radiation monitoring Yes NA

11. I-FCV-26-3 5 4 52b R'adiation monitoring NA

12. I-FCV-26-5 5 6 52c Radiation monitoring, return Yes w

13. I-V00140 52d IL test tap Yes NA I-V00143

14. I -V00139 52e ILRT test tap Yes NA I-V00144

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5. I-V00101 54 ILRT ssure connection Yes

16. I-FCV-03-lE 8 1F 28 I Tank Sample Yes anua a ve- ation time not applicable.

• Hay be ope on an intermittent basis under administrative control.

• • Normal closed valves - Isolation tfme. not applicable.

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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 sl 'l N~~

The interio and exterior surfaces apparent hanges in appearance deqradatio

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structural integrity of the shield building shall be deter-of of

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by the the a visual shield concrete inspection building surfaces m,'k4 p4.

and or I 0 of the accessible verifying no other abnormal Co~~a,'@monk ~<<~pe

'Rale. ~mt'vg Pr.cpm~

ST. LUCIE - UNIT 1 3/4 6-31 Amendment No.

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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.

~hi'ch A'Su//5 Prom QSQsew7'8Q /~ ~I<g ~5'gn 6tS75 los5 3/4.6.1. 2 CONTAINMENT LEAKAGE 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 ZS ppl'~

perMmcd In

'l analyses at the peak occident pressure, Pa (39.6 psig). -As-an-'added no@or unce e t.eh ccpI~ /he. ConIoInnr~

The the requirements of Appendix I.du<~ gaQ surveillance testing for measuring J'f 7GSF:<g Propre~

eakage rates 10 CFR 50 as

~an@'Q consistent with modified by approved exemptions, '

4 l~'-4h sis~ay-4RC-s) 14 g-@he 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~

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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 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 ofMMpsig in the event of accident. A visual ins ection d

~os onstrate this capability.

e-4e is sufficient to-

n accord.~narc. m'~ +>c C o~4a~ ~g~$ L-8~kngc. go~<

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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 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 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, P is 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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