Text

Proposed Tech Specs Adopting Option B of 10CFR50,App J to Require Types B & C Containment Leakage Rate Testing to Be Performed on performance-based Testing Schedule
	ML20135A523
Person / Time
Site:	Calvert Cliffs
Issue date:	11/26/1996
From:	; BALTIMORE GAS & ELECTRIC CO.
To:	;
Shared Package
ML20135A521	List: ML20135A517; ML20135A523;
References
	NUDOCS 9612030273
	Download: ML20135A523 (22)
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UNIT 1 MARKED-UP TECHNICAL SPECIFICATION ,

I PAGES 3/46-1--3/46-5 3/4 9-10 6-7 B 3/4 6-1 l

i 9612030273 961126 PDR ADOCK 05000317 l P PDR Baltimore Gas and Electric Company License Amendment Request November 26,1996

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3/4.6 CONTAINMENT SYSTEMS j 3/4.6.1 PRIMARY CONTAINMENT

_ CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.' '

l APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION: Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least NOT STANDBY within the next t 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD $NUTD0WN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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l SURVEILLANCE REQUIREMENTS I 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

a. At least once per 31 days by verifying that all penetrations ** l l not capable of being closed by 0PERABLE containment automatic '

isolation valves and required to be closed during accident I conditions are closed by valves, blind flanges, or deactivated i l autcmatic valves secured in their positions, except for valves that are open under administrative control as permitted by Specification 3.6.4.1.

b. By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3.

c. By verifying that the equipment hat'h is closed and sealed, )rior

! to entering M0DE 4 following a shutdown gquipment latch i by conducting a Type B test h a feyi J.g Dauge} akal ,

L Hydrogen purge containment vent isolation valves shall be opened for containment pressure control, airborne radioactivity control, and surveillance testing purposes only.

j The shutdown cooling isolation valves may be opened when the RCS l temperature is below 300 F to establish shutdown cooling flow.

ea Except valves, blind flanges, and deactivated automatic valves which l l 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 SNUTDOWN except that such verification need not be perfonned more often then once per 92 days.

l CALVERT CLIFFS - UNIT 1 3/4 6-1 Amendment No. 187 l

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3/4.6 CONTAINMENT SYSTEMS l'

3/4.6.1 PRIMARY CONTAINMENT Containment Leakage LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:

a. A maximum allowable containment leakage rate, L , as specified in Specification 6.5.6, " Containment Leakage Rate testing Program." l

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b. A combined leakage rate of 5 L '173 f all genetr on and valves subjec typeg ,0^0 an C S"C")

ests YY

,as specifiAd in Spee;$1cabok 4.S.6, APPLICABILITY: MODES 1, 2, 3 and 4. 'Confain,+,enf Ic8EA9e ble 7elEN NF ACTION: With either (a) the measured overall integrated containment leakage rate exceeding the acceptance criteria specified in the Containment Leakage Rate Testing Program, or (b) with the measured combined leakage rate for netraticns and valves subject to Types B and C tests r exceediM L , restore the overall integrated containment leakage rate to within OOl>O Testing acceptance criteria specified in the containm eaka Rate ProcramGd 'the combined Teakage_ rate for _a

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penetrations an Walvis subject ttTypesB and C_ testM ) : fth:1 Or_ca= Ltc ^.50 to increasing the Reactor Coolant System temperature above 200 F. ] prior tAe Confainment Jeak 9 e 1?de Testi,,9Pqram SURVEILLANCE REQUIREMENTS

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i 1.2 T co in nt 1 akage rates 6:'] l-J05d treISE

'ellu.nri tc;t_ che t!=

eTwith__th criteria, methgand pM:n. sionsshall be detennined specified in lv CFnf ortj0,],pp' Q :

[a. Perform required visual examinations and t :th,;; in sccordance with the Containment Leakage R N Testing Program.

(,6cheolule, -

leakage- rate lesfing,except s .

L c ntaini, lent air leek fesIin9 l

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I CALVERT CLIFFS - UNIT 1 3/4 6-2 Amendment No. 216 l

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3/4.6 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b kpe an Ct ts ha b co duc ed ith as t ( ps ) t l g in erv ls o 24 ont s ce f r t sts iny lvi a 1 ks.

Mv i ir ock sha l b tes ed nd em st te 0P BL pe l q S rye lla e R qui men 4. 1. .

'd. 11 Typ B d C tes lea age ra s al be alc ate us g l to abs lu v ues bse ve dat con (ert i

Containment purge isolation valves shall be demonstrated OPERABLE l l any time upon entering MODE 5 from power operation modes, unless l the last surveillance test has been perfomed within the past six months or any time after being opened and prior to entering i MODE 4 from shutdown modes by verifying that when the measured OG1'2'aTechnical

< leakaoe rate is added to the leakage rates detemined pursuant to Specificatidid.S.I.2.9 for all other Type B or C l

3 trat s te ined leakage rate is less than or equal to aSO <

. L, IL,,0y0 SCCW . The leakage rate for the containment j purge isolation valves shall also be compared to the previously measured leakage rate to detect excessive valve degradation. ;

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The containment purge isolation valve seals shall be replaced I !

with new seals at a frequency to ensure no individual seal

! remains in service greater than 2 consecutive fuel reload cycles.

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I DELEM Cxcmpti;n to 10 CFR i' art 50, Appendn J.

i CALVERT CLIFFS - UNIT 1 3/4 6-3 Amendment No. 212

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3/4.6 CONTAINNENT SYSTEMS

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-3/4.6.1 PRIMARY CONTAINMENT Containment Air Locks LIMITING CONDITION FOR OPERATION o .

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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

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, nomal transit entry and exit through the containment, then at' >

o least one air lock door shall be closed, and ,

b.

r.Anumoverall m _ air lock leakage rate of 5 0.05 L Q",tdM _ ;

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&cinealin Sm;p;askn4.5.6lc;,tinmer,+ h.aky l APPLICABILITY: MODES l', 2, 3, and 4. , gf g ,'*

t ACTION:

a. With an air lock inoperable, except as a result of an inoperable l

door gasket, restore the air lock to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least NOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and

! in COLD SNUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . -

b. With an air lock inoperable due to an inoperable door gasket: ,

l 1. MaintainL the remaining door of the affected air lock closed and sealed, and

2. Restore the air lock to OPERABLE status within 7 days or be in at least NOT STANDBY within the next_6 hours and in COLD SitUTD0WN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILUDICE REQUIREMENTS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE: ,

a.(Atereahche n ceht he t ar oc is be ng us d or mu ti le nt i , he a< 1 st on e r2 ur r yi g y th t t e ea 1 ka e 's 0 00 L .2 SC ) s et ne b l f J re is n lo s rer n w .n he vol me be ee te oo s al f s r ur ze t a on ta t re ur o __ 1 ps ,

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perferr.ang confainmenf air lock % leak e rAl& ksk f in acconlame wi/b QB,e C.,Jainned Lak A y,,,,,ar,,t u

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n l CALVERT CLIFFS - UNIT 1 3/4 6-4 Amendment No. 212 l l

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3/4.6 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

. I le st o e pe 6 t b c nd ct g an ov rd 1 a c !

le ka s ( si d y e f in t at t ye a ir lo k ea a e t i wi hi is im t, an Oh, (j}) At least once per 6 months by verifying that only one door in

,jf each air lock can be opened at a time.

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CALVERT CLIFFS - UNIT 1 3/4 6-5 Amendment No. 212 l

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3/4.9 REFUELING OPERATIONS

3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION I l l LIMITING CONDITION FOR OPERATION l

3.9.8.1 At least one shutdown cooling loop shall be in operation.* !

1 l APPLICABILITY: MODE 6 at all reactor water levels. l ACTION:

a. With less than one shutdown cooling loop in operation *, suspend i all operations involving an increase in the reactor decay heat )

load or a reduction in boron concentration of the Reactor Coolant System and, specifically, the charging pumps shall be de-energized and the charging flow paths shall be closed. Close l all containment penetrations providing direct access from one l containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

t The shutdown cooling pumps may be de-energized during the time intervals required for local leak rate testing of containment

@ M netration number 41 Aursuant to the requirements of

, Specification 4.6.1.7.1Dand/or to pemit maintenance on valves l located in the common shutdown cooling suction line, provided l

(1) no operations are Demitted which could cause dilution of the Reactor Coolant System boron concentration and, specifically, the charging pumps shall be de-energized and the charging flow paths shall be closed (2) all CORE ALTERATIONS are suspended, (3) all containment penetrations providing direct access from the l

containment atmos)here to the outside atmosphere are maintained closed, and (4) t1e water level above the top of the irradiated fuel is greater than 23 feet.

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.8.1 A shutdown cooling loop shall be determined to be in operation and circulating reactor coolant at a flow rate of > 1500 gpm at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

, The shutdown cooling loop may be removed from operation for up to

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' 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period during the perfomance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs.

CALVERT CLIFFS - UNIT 1 3/4 9-10 Amendment No. 169

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l 6.0 ADMINISTRATIVE CONTROLS l

l h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR Part 50, Appendix I;

i. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in l gaseous effluents released from each unit to areas beyond the l site boundary, conforming to 10 CFR Part 50, Appendix I; and l

l j. Limitations on the annual dose or dose commitment to any member I of the public due to releases to radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR Part 190.

6.5.6 Containment Leakaae Rate Testina Proaram l A program shall be established to implement the leakage testing of the containment as r_equired by 10 CFR 50.54 40and 10 CFR Part 50, Appendix J, Option B " -*dm at'" ~----"-' eg ptjeng . This program shall be in

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accordance w th the guidelines contained in Regulatory Guide 1.163,

" Performance-BasedContainmentLeak-TestProgram,"datedSeptember1995@

Qadi+1edbyappra"ed :cepu;?.p. 4 The peak calculated containment internal pressure for the design basis l loss-of-coolant accident, P,, is 49.4 psig. The containment design l pressure is 50 psig. !

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q The maximum allowable containment leakage rate, L., shall be 0.20 percent M of containment air weight per day at P,.

l C a- -_. 3-. C -.. T --.--_. nh k 17":" " ";"' I'""rm1.7::T""7:, 't ~:'. '.:"Z:4 2.m% 7 J.'."." J.'~ .u-g C. .'. C ""i. .:. : '" ' :Z. '". I" .'. ". C.7: ' ";"J ' ~ ~ ~ T ' --".r ~

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The provisions of Specification 4.0.2 do not apply to the test frequencies I specified in the Containment Leakage Rate Testing Program.

The provisions of Specification 4.0.3 are applicable to the Containment Leakage Rate Testing Program.

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i CALVERT CLIFFS - UNIT 1 6-7 Amendment No. 216

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INSERT 6.5.6 Leakage rate acceptance criteria are:

a. Containment leakage rate acceptance criterion is s 1.0 aL . During the first unit startup, i l following testing in accordance with this program, the leakage rate acceptance criteria are s 0.60 Lafor Types B and C tests and s 0.75 La for Type A tests.

b. Air lock testing acceptance criteria are:

1. Overall air lock leakage rate is s 0.05 La when tested at 2 P .

2. For each door, leakage rate is s 0.0002 Lawhen pressurized to 215 psig.

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3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY In MODES 1, 2, 3, and 4, 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 accident analyses. This restriction, in conjunction with the leakage rate limitation, will limit the SITE _B0UNDARY radiation doses to within the limits of 10 CFR Part 100 during accident conditions. In MODES 5 and 6 j

the probability and consequences of these events are reduced because of the l Reactor Coolant System (RCS) pressure and temperature limitations of these '

modes, by preventing operations which could lead to a need for containment isolation, and by providing containment isolation through penetration closure.

,4 g- 3 4. 1. nt in n L k e cr at ta in t nt in en 0E L re ui es c pl an e it t s 1 q-90 fxainaion ad a ge ra e es r u e nt o te on ai te Tes ing Pr gr a g r yp A te ts, a R a 5, )p d 0 io A or yp B an C e s. A -1 ft le a i t ~t e ir (N st tu a er e o in a e i d ea ag t t s e ir d o e j q 0 75 r er 11 Ty ak ge ,at te ts, t a ce ta ce er e 'a s as le ka e. A a he t me b tw n e i d i M

o er 11 Ty 1 aka e mi o < .0 . A < . L, th o si e os c s ue ce ae

! %. bo nd b th as;um ti ,ns f he sa et a 1 is he fr ue cy o Ty l

es in is spe if d n he Co a me t ea g Ra e es in P gr m.

Te rv ill nc te ti ; r a ur g lea ag r te ar c ns t t it k th r qui em ts f0 FR 2a 5, p d J 0 ti 1 fo T e t st .

kb or Ty e an C s ng t lo ab e ea ge ra ei s ee op rt'on el re uc , s ec e de i G e c et r 1- 4, to cc un l T ,

fr e te ed sur et la e ch du o m nt ; + 25 ( r '

l b p ci ic io 4. 2) hi is an ex p o fr m , R ar 5 p nd .

l 3/4.6.1.3 Containment Air Locks gThe limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate. Surveillance testing of the air lock seals provides assurance l that the overall air lock leakage will not become excessive due to seal l damage during the intervals between air lock leakage tests.

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_ m l 7$c Sepency of confainmenY air lock leakage rale lesNng is l \' speciked in 8e Conbanment leakage 'Na/e lesN S tam. y

-m M =y _ _

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, We overall ale lsck Ieakage rate is _ de[h be f 0.OS La Q7,300 Sccb1) af Pa {

and 4 0 0002 La (49.2Qwhe vokmejefween ile ole sea [is pywized 6 , !

CALVERT CLIFFS - UNIT 1 5 3/4 6-1 I

~ Amendment No. 212 /IMf' l l

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I INSERT "3/4.6.1.2 - BASES" 3/4.6.1.2 Containment I rakaoe l l Maintaining the containment OPERABLE requires compliance with the visual examinations and ;

leakage rate test requirements of the Containment Leakage Rate Testing Program. He surveillance j testing for measuring leakage rates is consistent with the requirements of 10 CFR Part 50, Appendix J, j

l. Option B. '

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As-left leakage, prior to the first startup after performing a required leakage test, is required to be s 0.60 L. (207,600 SCCM) for combined Types B and C leakage, and s 0.75 L, (259,500 SCCM) for i overall containment Type A leakage. At all other times between required leakage rate tests, the acceptance criteria is based on an overall containment leakage limit of s 1.0 L. (346,000 SCCM). At s 1.0 L., the offsite dose consequences are bounded by the assumptions of the safety analysis. ;

- Surveillance Requirement frequencies are as required by Appendix J. ;

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i These periodic testing requirements verify that the containment leakage rate does not exceed the leakage I rate assumed in the safety analysis.

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i 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT

! CONTAINMENT INTEGRITY l

LIMITING CONDITION FOR OPERATION l 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.' '

l l APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION: Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least NOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SNUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . l SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated: i

a. At least once per 31 days by verifying that all penetrations **

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not capable of being closed by 0PERABLE 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 for valves ;

that are open under administrative control as permitted by '

Specification 3.6.4.1.

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b. By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3.

c. By verifying that the equipment hatch is closed and sealed, prior to entering MODE 4 following a shutdown where theg hatch !

pe ed by conducting a Type B test Q C3 7. m l n acc.onolance wid de Contaimenf lalage he TisIing hram. -

Hydrogen purge containment vent isolation valves shall be opened for' containment pressure control, airborne radioactivity control, and surveillance testing purposes only.

The shutdown cooling isolation valves may be opened when the RCS temperat : is below 300 F to establish shutdown cooling flow.

Except valves, blind flanges, and deactivated automatic valves which l l

are located inside the containment and are locked, sealed, or otherwise secured in the closed position. These penetrations shall l l be verified closed during each COLD SHUTDOWN except that such

-verification need not be perfonned more often then once per 92 days.

CALVERT CLIFFS - UNIT 2 3/4 6-1 Amendment No. 164

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3/4.6 CONTAINMENT SYSTEMS l

3/4.6.1 PRIMARY CONTAINMENT l Containment Leakane LIMITING CONDITION FOR OPERATION '

3.6.1.2 Containment leakage rates shall be limited to: .

a. A maximum allowable containment leakage rate, L., as specified in Specification 6.19, " tainment Leakage Rate Testing Program."

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b. A combined leakage ra e of 5 fo I penetrations and valves subj tokyL 6 ^00and C";C03[s'ts 11

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' ' ' " ' ' ' ' _ " " , AS speaIfied in Specification b. S. 4, APPLICABILITY: MODES 1, 2, 3 and 4. " '##""'* " ## #98 #

"8 8 ACTION: With either (a) the measured overall integrated containment leakage rate exceeding the acceptance criteria specified in the Containment Leakage Rate Testing Program, or (b) with the measured combined leakage rate formall tenetrations and valves subject to Types B and C tests O,6 ~ exceedin Mg yL.

to within the ac.,cerestore the overall nce criteria integrated spe_cified in thecontainment Containment leakage laakaae_rate Rate Ating Proa

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T he comb ~ined ~ leakage rate forill'penetritions_ ahO (valves s'ubj t_ to_ Type _B and C_ testji,(t:je5; th; , et cgal t; 0.5Q to increasing the Reactor Coolant System temperature above 20D F.~ gprior de C dainn,ent Leakage Rde 7e~ sting % yam SURVEILLANCE REQUIREMENTS 4 6.1. The containment leakage rates fe.h>P.; _tect @hh'6ddSQ shall be determined in conformance with the criteria, methodsfancFprovisions specified in Q07 CIT." ft 50Ll,ppfhdii ':

a. Perform required visual examinations and '^^ i t;:;tj-- in accordance with the Containment Leakage RMiFting YEogram. I

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k' age tafe lesiIng,eitcep ^

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i l CALVERT CLIFFS - UNIT 2 3/4 6-2 Amendment No. 189

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. -3/4.6 CONTAINMENT SYSTEMS

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!- SURVEILLANCE REQUIREMENTS (Continued) i

b. T e ad te ts ha 1 nd et th ga a P (5 p ig l

1. . p , in r. 1s of 4 n s xc t or te ts 'n lv ng lo k

k. c. A c 's al be te e an d tr te 0 LE e l t tu h Su ve la ce Re i t 6. 3 -

g) d. A1 p B n C es le ka ite s al b ca cu te u in l

'l ob er d a nv rt t a so' te va ue .

j @ Containment purge isolation valves shall be demonstrated OPERABLE l i any time upon entering MODE 5 from POWER OPERATION MODES, unless the last surveillance test has been performed within the past 6

' months or any time after.being opened and prior to entering MODE 4 from shutdown modes by verifying that when the measured i _

leakage rate is added to the leakage rates determined pursuant to j V.4.f. 2.a Technical Specificationf.0.1.2.9 for all other Type B or C l i

a ined leakage rate is less than or equal to

'4 . The leakage rate for the containment purge Is... you molaTion valvTes shall also be compared to the previously measured leakage rate to detect excessive valve degradation, k The containment purge isolation valve seals shall be replaced 1~ l with new seals at a frequency to ensure no individual seal i

remains in service greater than 2 consecutive fuel reload cycles.

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DELEYE W= 216 CALVERT CLIFFS - UNIT 2 3/4 6-3 Amendment No. 189 4

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3/4.6 CONTAINMENT SYSTEMS l 3/4.6.1 PRIMARY CONTAINMENT l Containment Air Locks l

LIMITING CONDITION FOR OPERATION 'l l

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3.6.1.3 Each containment air lock shall be OPERABLE with:

l a. Both doors closed except when the air lock is being used for nomal 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 of 5 0 "Q ;

hpeuYieel in Specification gsi," Cadainment APPLICABILITY: MODES 1, 2, 37 and 4.

[,,g,p, g[, 7,,f;ng g y,, ,"

ACTION:

a. With an air lock inoperable, except as a result of an inoperable door gasket, restore the air lock to 0PERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With an air lock inoperable due to an inoperable door gasket:

1. Maintain the remaining door of the affected air lock closed and sealed, and i

2. Restore the air lock to OPERABLE status within 7 days or be l in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD !

SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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SURVEILLANCE REQUIREMENTS l

l 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:

a. A te e ch op ni g, ex ep 'w en th a'r o i e fo m It'p1 et e en at 1 s o e 3e 7 h ur b he f n t t h s I le ae s 0 00'2 9. C s t rm e b p et si n lo m as re en en th y lu e e e t oo s al i p es u ize t c s n p s r o 1 p ig By perforn,ing containmenY dit locN lt&NRQe tafe festing in acconQ wit), lhe Cedainmenf Leakage hfe Es C

Exemption 10 10 CIR Part b Appendia J.

t OELETE CALVERT CLIFFS - UNIT 2 3/4 6-4 Amendment No. 189 l l

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3/4.6 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

(]{) At le st on e' e 6 n hs by co d 't g n y ra 1 1 1c le a st at P. (5 p ig ad y e f n t t th oe 1 y ir lo a g r te is i_i i im t, an - '

(jj) At least once per 6 months by verifying that only one door in each air lock can be opened at a time. -

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CALVERT CLIFFS - UNIT 2 3/4 6-5 Amendment No. 189 l

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3/4.9 REFUELING OPERATIONS 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION LIMITING CONDITION FOR OPERATION l

3.9.8.1 At least one shutdown cooling loop shall be in operation.*

APPLYCABILITY: M0DE 6 at all reactor water levels. {

ACTION:

a. With less than one shutdown cooling loop in operation *, suspend ;

all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System and, specifically, the charging pumps shall be de-energized and the charging flow paths shall be closed. Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . '

The shutdown cooling pumps may be de-energized during the time intervals required for local leak rate testing of containment penetration number 41 p_ursuant to the requirements of h(Specification located in the comott s 4.6.1.L@hutdown coolin and/or to pennit maintenance on valves no operations are pennitted which could cause dilution of the Reactor Coolant System boron concentration and, specifically, the charging pumps shall be de-energized and the charging flow paths shall be closed. (2) all CORE ALTERATIONS are suspended. (3) all '

containment penetrations providing direct access from the i containment atmosphere to the outside atmosphere are maintained closed, and (4) the water level above the top of the irradiated fuel is greater than 23 feet.

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.8.1 A shutdown cooling loop shall be determined to be in operation and circulating reactor coolant at a flow rate of 21500 gpm at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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The shutdown cooling loop may be removed from operation for up to k- 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period during the performance of CORE ALTER *TIONS in the vicinity of the reactor pressure vessel hot legs.

CALVERT CLIFFS - UNIT 2 3/4 9-10 Amendment No. 149

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6.0 ADMINISTRATIVE CONTROLS

h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR Part 50, Appendix I;

i. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each unit to areas beyond the :

site boundary, conforming to 10 CFR Part 50, Appendix I; and

j. Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation i from uranium fuel cycle sources, conforming to 40 CFR Part 190.

6.5.6 Containment Leakaae Rate Testino Program l A program shall be established to implement the leakage testing of the containment as required by 10 CFR 50.54(o) and 10 CFR Part 50, Appendix J.

Option B. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program," dated September 1 The peak calculated containment internal pressure for the design basis ,

loss-of-coolant accident, P , is 49.4 psig. The containment design ,

pressure is 50 psig.

The maximum allowable containment leakage rate, L., shall be 0.20 percent r -

of containment air weight per day at P .

. + i J .1 ..+. X . . C - , 2 Q'r!" " ' ' .."7 T _ l"'l' 4 U'...I ~ ~ ~ C"I' .'; ; ~ ~ '. '. "Z:,-- 2.i k'L+w.J '"_,"" J_ ~ . u n . 4 . ,,

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W The provisions of Specification 4.0.2 do not apply to the test frequencies l D specified in the Containment Leakage Rate Testing Program, h The provisions of Specification 4.0.3 are applicable to the Containment i Leakage Rate Testing Program. '

l CALVERT CLIFFS - UNIT 2 6-7 Amendment No. 193 l

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! I j- INSERT 6.5.6 I 1

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' Leakage rate acceptance criteria are:

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a. Containment leakage rate acceptance criterion is s 1.0 La. During the first unit startup, j following testing in accordance with this program, the leakage rate acceptance criteria :

are s 0.60 Lafor Types B and C tests and s 0.75 La for Type A tests.

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b. Air lock testing acceptance criteria are: !

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1. Overall air lock leakage rate is s 0.05 Lawhen tested at 2 P,. j i

l 2. For each door, leakage rate is s 0.0002 La when pressurized to 215 psig. I

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p..>y 3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY In MODES 1, 2, 3, and 4, 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 accider.t analyses. This restriction, in conjunction with the leakage rate limitation, will limit the SITE B0UNDARY radiation doses to within the limits of 10 CFR Part 100 during accident conditions. In MODES 5 and 6 the probability and consequences of these events are reduced because of the Reactor Coolant System (RCS) pressure and temperature limitations of these modes, by preventing operations which could lead to a need for containment isolation, and by providing containment isolation through penetration Closure.

g l6 3/ .6. . C tinknkLhkae Co L in in ng th c t nt OP N E e i sc 1 an e it t su 1 D Ie mi t ns an 1 k e at t t e1 t o te n i n L ak e Ra T t g ro a f pe st , n 1 C r<. 5 pe i J, l

k :

L pt n I ar p ft f

p rf e ad t st . s- e g r qu e le ka e es i r u e t b a ge pr o to th f s

! % 5 .7 L, or ov al T e a ge. 1 t r i s e ee r u e i le cag ra e st , e cc t nc cr te la is a d n n y a

! DM ea ge lim t 5 1. L.. _ 1. L, th o fs te o n q n s re e

un d te tsu t ns o th s et a 1 i he fr qu e o T e t ti i sp ci1 ed in he Co ta me t a g R e es in P g .

! he ur il nc t ti r a r g ea g r es ar c s t t i I

g te qu em ts of ",0 FR ar 5 pe di J Op to B o T e t st .

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Fo T e aa C esi. ng t a lo b El k e at h en ro or on tel re uc , s c e ec. in e ri L tt -0 e n

! r n te ded ur ei an e he le o 24 o hs + % pe I

Sp ci ic io 4. 2) is is n ce ti n 10 F Pa t ,

p nd x 3/4.6.1.3 Containment Air Locks The limitations on closure and leak rate for the containment air locks are l

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[ 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 I damage during the intervals between air lock leakage tests.% _

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in de Con &enbi t d lof cone;ninmenf & Iock leakage rate te n ~en ea cap Rafe tesRny Bosnam-

_L n = -

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~ 7%e overaIl a:r, leek leaka e rain is re$ aired b de 6 0 OS 4 (17 ,

l s o.0002 La (49.2 SocM) wl,en the v lame beLan k seals ispresswiad b Mys'y.

CALVERT CLIFFS - UNIT 2 B 3/4 6-1 Amendment No. 189 l

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1 INSERT "3/4.6.1.2 - BASES" :

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3/4.6.1.2 containment I rakao, i

Maintaining the containment OPERABLE requires compliance with the visual examinations and leakage rate test requirements of the Containment Leakage Rate Testing Program. The surveillance testing for measuring leakage rates is consistent with the requirements of 10 CFR Part 50, Appendix J, 1 Option B.

As-left leakage, prior to the first startup after performing a required leakage test, is required to be s 0.60 L. (207,600 SCCM) for combined Types B and C leakage, and s 0.75 L (259,500 SCCM) for l overall containment Type A leakage. At all other times between required leakage rate tests, the l acceptance criteria is based on an overall containment leakage limit of s 1.0 L. (346,000 SCCM). At s 1.0 L., the offsite dose consequences are bounded by the assumptions of the safety analysis.

Surveillance Requirement frequencies are as required by Appendix J. !

1 These periodic testing requirements verify that the containment leakage rate does not exceed the leakage rate assumed in the safety analysis.

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ML20135A523

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