Text

Proposed Tech Specs,Relocating Requirements for wide-range Iodine & Particulate Samplers from Tech Spec 3.3.3.8 to Table 3.3-6 to Require Operation & Surveillance of wide-range Sampler,Per NUREG-0737,Item II.F.1
	ML20117B346
Person / Time
Site:	Calvert Cliffs
Issue date:	04/26/1985
From:	; BALTIMORE GAS & ELECTRIC CO.
To:	;
Shared Package
ML20117B337	List: ML20117B333; ML20117B346;
References
	RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-TM NUDOCS 8505090039
	Download: ML20117B346 (39)
	v • d • e

- . _. .. - _ .

- i

.. ATTACHMENT (1) l l

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

/

SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE...................................... 3/4 2-1 3/4.2.2 TOTAL PLANAR RADI AL PEAKING FACT 0R. . . . . . . . . . . . . . . . . . . . 3/4 2-6 3/4.2.3 TOTAL INTEGRATED RADI AL PEAKING FACTOR. . . . . . . . . . . . . . . . 3/4 2-9 3/4.2.4 AZIMUTHAL POWER TILT.................................. 3/4 2-12 3/4.2.5 DNB PARAMETERS .'. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 2-13 l 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTE1TIVE INSTRUMENTATION.................... 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEA1URE ALTUATION SYSTEM INSTRUMENTATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-10 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation.................. 3/4 3-25 Incore Detectors...................................... 3/4 3-29 Seismic Instrumentation............ - ..s.............. 3/4 3-31 Meteorological Instrumentation........................ 3/4 3-34 l, Remote Shutdown Instrumentation....................... 3/4 3-37 Post Accident Instrumentation......................... 3/4 3-40 Fi re Detection Instrumentation. . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-43 l -Aadioacthe C::::: Efment ":-it Ws l -I ns trumentation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4-3 ,

3/4.4 REACTOR COOLANT SYSTEM -

3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION................. 3/4 4-1 S ta rtup . a nd Power. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-1

' Hot Standby........ ~ ' .... 3/4 4-2 8505090039 850426 Shutdown......... PDR ADOCK 05000317 .... 3/4 4-2a P PDR 3/4.4.2 SAFETY VALVESe. ......................-.............. 3/4 4-3 3/4.4.3 RELIEF VALVES......................................... 3/4 4-4 CALVERT CLIFFS - UNIT I~ IV Amendment No. 39,53,55,99 1

TABLE 3.3-6 9 '

G RADIATION MONITORING INSTRUMENTATION i -g MINIMUM l2 CHANNEyS APPLICABLE ALARM / TRIP MEASUREMENT INSTRUMENT OPERAB,.E MODES SETPOINT RANGE ACTION

1. AREA MONITORS E

~

" a. Containment

~ i. Purge & Iahaust .j Isolation 3 6 4 l

's 220 mr/hr 10 - 10 mr/hr 16 l

b. Containment A'"a High Range 2 1, 2, 3, & 4 1 10 R/hr 1 - 108 R/hr 30 g 2. PROCESS MONITOR',

a y a. Containment eu

! 1. Gaseous A.tivity a) RCS Leakage Detectson 1 1, 2, 3, & 4 Not Applicable 6 1 - 10 cpm 14 ii. Particulat Activity l E a) RCS Leaka9e k Detectton 1 1, 2, 3, & 4 Not Applicable 1 - 106 cpm 14 i 2 l '?, b. " ": C:: Effluent i 2 Monitors l

P 1. Main Vent Wide Range 1 1, 2, 3, & 4 * -7

. 10 to 10+5 uCi/cc 30 m w M NcGLC hn_ _ _ _ >__ _ . - 4'

. blloowE._5Ames crt . . if _ _ _ _ _ L L_. 3 ,1'4._ _. .N eta Pfu t994L._ _ __ bl:T /FrutA46 E.__._...__ _ _3 0 m 4 PART_tcu LATE.5Ap4PML L_.__ .. t ,1, J , .J 'l _

N u . 479u m m c.._ _ h /spuc.ndcE._... ____30

Alarm setpoint to t,c specified in a controlled document (e.g., setpoint control manual)

TABLE 4.3-3 9

G RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

w CHANNEL MODES IN WHICH P CHANNEL CHANNEL FUNCTIONAL

SURVEILLANCE INSTRUMENT CHECK CALIBRATION TEST REQUIRED 3

. 1. AREA MONITORS C

5

-o

a. Containment

_ i. Purge & Exhaust Isolation S R M 6

b. Containment Area High Range S R M 1, 2, 3, & 4 w

l 1 2. PROCESS MONITORS w

l 4 es

a. Containment

i. Gaseous Activity a) RCS Leakage Detection S R M 1, 2, 3, & 4 ii. Particulate Activity

'a) RCS Leakage F Detection S R M 1, 2, 3, & 4 E

l [ b. 9 h'- En Effluent Monitor A 1. Main Vent Wide Range S R M 1, 2, 3, & 4 g

4 Noem Gas __ .

o

O Ioome samecca .M. h. Amuo c _16aWumat .1,2.,3,.4 y-D PART cVuTC SAethER M bier /%nuca<5.<r . Ar Ayucxoce_ t,2, s,. 5 v 1

l

O

a TABLE 3.3-11 FIRE DETECTION INSTRUMENTS UNIT 1 INSTRUMENT LOCATION MINIMUM INSTRUMENTS OPERABLE HEAT FLAME SM0KE Spent Fuel Pool Heat Exchanger Room 320 3 Main Control Room 405 6 Control Room Vent Duct "A" 2 Main. Plant Exhaust Equip Room 524 8 Control Room HVAC Equip Room 512 4

. 27, Wive AufY P::::;: and Filter Room 323 3 SW Cstegr Cactc i% nit ' 00nt S" El:: P:n "r::*- +

,+

NE CNTMf(A$f hd daiI I CenA NC CI AC I n f2 *~ 16 CarM r Unit 1 Cent East RCPS*

CNreer Unit 1 C;nt West RCPS* 16

-Centrel Reesa "ent Ouct "S"= Mmes to 0 -1 T 5' +

West Passage 319 Elev 27'-0"Awo crow 5 6 5

E/W Corridor 10[f 100 6406 - Elev (-) 10'-0" -44 2.4 Intake Structure,UM Saoe.. '

1 Unit i Waste Proc Control Room 111

Coolant Waste Rec / Mon TK Pp Room 110 2 11 Diesel Generator ** 2

' 12 Diesel Generator ** 2 4 l Unit i Cable Tunnel Elev 83'-0" 1

Cable Chase 1 A 1.

Cable Chase IB

" nit 1 C.S.R. & Cable Chase IC** Room 306 2 10 C urm r Unit : re,sennel Access Area Room 525 3 Unit 1 Switchgdar Elev 27'-0" Room 317** 6

" nit 1 Switchgear Elev 45'-0" Room 430** 8:

" nit i Elec Equip Room 529 3 Unit i East Elec Pen Room 429 - 3

" nit 1 West Elec Pen Room 423 3 Unit i Refueling Water TK Pump Room 439 2

" nit i East Piping Pen Rooms 227 and 316 3 5 Unit i Purge Air Supply Room 318 2

" nit i West Piping Pen Rooms 221 and 326 2 3

" nit 1 Letdown Heat Exchanger Room 324 1 Unit ' Volume Control TK Room 218 1 Unit-1 ECCS Pump Rooms 118 and 122 7 4

Unit i Coolant Waste Rec TK Room 114 and 117 4 nit-4 ECCS Pump Rooms 119 and 12/3 7 4 nit 4 Elev 27'-0" Swgr Room Vent Duct Room 3t7 1

-Unit-1 Elev 45'-0"$fwgr Room Vent Duct Roon 430 1

petection instruments located within the containment are not required to be' OPERABLE during the performance of type A Containment Leakage Rate Tests.' '

- Detectors which automatically actuate fire suppression systems.

084itortCS GV N Paoriu.vo Lle g.cs CALVERT CLIFFS - UNIT 1 3/4 3 45 Amendment No. 26. df. 96 m-

TABLE 3.3-11 (Continued) -

FIRE DETECTIO'N INSTRUMENTS UNIT 1 INSTRUMENT LOCATION MINIMUM INSTRUMENTS OPERABLE HEAT FLAME SM0KE MainSteamPipingRoom31% 6 Hot Machine Shop 223 4 Battery Room 30t :nd 301 301,30't Ano Cognicoa 300 3 1

Misc. Waste":

Charging niter"1 Dank Room 113,,, Rcceivra Pump Room 3

East Piping Room 428 7

% rth Sc th C:rrid:r 410 ,' Spent Fuel Pool +39-AneA Rooms 530, ni no 533 5 17

,/ Radiation Ch::.g L:b Office, 5. 5135- Ano CEMistny AncAs Rocer y/ 510 :nd 510, ocrrid r 521. 522 :nd 586 - 590, Ey.t , E93,

+34 F95 5'i7 Ano Cor.nimens S'il A u b 5'2.3 + -- M 2,o V Cask and Equipment Loadina Area Rm. 4Wr 14 3. 4 t*t 420, 025, :nd $20 42.0. Ano 414 - 4Ab 3 22 Spent Fuel Vent Equip. Room 526 2

- Component Cool Room 228 8 EuAusT ":dicti:n 5:W Vent Equip. Room 225 4 Boric Hold Tank & Pump Room 217 2 Reactor 0 : ling 4 gut Room 211 Coe,. mar MAm up 1 Hot Instrument Shop Room 222 2 Service Water Room 226 3 6 Cast Tirins L m 224 i2 MSiv 44Yo Ac.c4 Roos 21'l 10 Corridor 200. 200, ad 210 Aca., LO9,260,261 mo 189 13 Solid Waste Room 418 and 417 . 2 3 Spent Resin Metering Tank Roon 441 1 Waste Gas Equipment Room 207 Ano 103 +3 Auxiliary Feed ,.

oom 603 Pomp 2 Misc. Waste Equi ment Room I6 ANo 537 l 3

Cerrid:r 300 -fr gy ....e N/S Corridor Room 410 4 N/S Corridor Room 308 6 Degasifier Pump Room 220 1 2 ::: 0:: C x;r::::r ".::: 208

,, +

CALVERT CLIFFS - UNIT 1 3/4 3-46 Amendment No. 96 t -

INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 The main vent iodine and particulate sampler b PERABLE.

APPLICABILITY: All MODES.

ACTION:

a. With the main vent iodine and par a ler inoperable, initiate the preplanned alternate method pling the main vent for the appropriate ter(s)withi hours; and

1. either restore th templer to OPERABLE status within 7 d v . or ,

2. prepare and submit "

pursuant to Specifica rt to the Comission within 30 days following the eve outlining th on taken, the cause-of the inopera ,and plans and schedule for restoring the syst P status.

b. The sions o ications 3.0.3 and 3.0.4 are not applicable.

CE S t

l 4.3.3.8 main vent iodine and particulate sampler shall be demonstrated ERAELE comparing samples independently drawn from the main vent at t on r month.

i CALVERT CLIFFS - UNIT 1 3/4 3-47 Amendment No. 99 4

u_- - . -.__-_A - -- _ -- AAf

CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CON 0! TION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:

a. An overall integrated leakage rate of:

~

1.

1airL,pe(346.000 r 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SCCM) at P,, 500.20 psig,percent or by weight of the cor.tainment

2. <Lg (61.600 SCCM). 0.058 percent by weight of the containment .

Ilr per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at a reduced pressure of Pt. 25 'psig.

b. A combined leakage rate of 10.60' L (207.600 SCCM). for all penetra-tions and valves subject to Type B $nd C tests when pressurized to P,.

APPLICA81LITY: MODES 1, 2. 3 and 4.

ACTION:

With either (a) the measured overall integrated containment leakage rate exceedin 0.75 L SCCM) or 0.75 L (46.200 SCCM), as applicable, or (b) w th the Aea(259.500sured combined 1.akage Tate for all penetrations a subject to Types B and C tests exceedin 0.60 L restore the leakage rate (s) to within the limit (s) prior to increas ng the Ae, actor Cooiant,5ystem temperature above 200*F.

' D '

( < i ,. *1

. , SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the follow-ing test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR Part 50X using the methods and provisions gg of AN51 N34.4 - 1972: .

a. Three Type A tests (overall Integrated Containment Leakage Rate) shall be conducted at 40 + 10 month intervals during shutdown at either Pa (50 psig) or at7t (25 psig) during each 10-year service period. 'he th'd t= t O' =:5 ::t the!' h t = fret d due49 th thtfn:: fe- th 100=r plet 8 nevice ine- etien?

,.u.

.16. .64.2 . . ,4. 399=. m4c, 73 4,44p g :=g..: g driq :;r' ; 1^"5 U-it 1--r:'ec1'e; =te;:s CALVERT CLIFFS - UNIT 1 3/4 6-2 AmendmentNo.15.54,

. l

. CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (C'ntinued) o In addition,' determining that the average of the normalized lift-off forces for each sample population (hoop, vertical, dome) is equal to or greater than the required average prestress level; 536 kips for hoop tendons, 622 kips for vertical tendons, and 555 kips for dome tendons (reference Figures 4.6-1, -2, and -3). If the average is below the required average prestress force, it shall be considered as evidence of possible abnonnal degradation of the containment structure.

b. Removing one wire from each of a dome, vertical and hoop tendon checked for lift off force, and determining over the entire length of the wire:

1. The extent of corrosion, cracks, or other damage. The presence of abnormal corrosion, cracks or other damage shall be considered evidence of possible abnormal degradation of the containment structure.

2. A minimum tensile strength value of 240 Ksi (guaranteed ultimate strength of the tendon material) for at least three wire samples (one from each end and one at mid-length) cut from each removed wire. Failure of any one of the wire samples to meet the minimum tensile strength test is evidence of possible abnormal degradation of the containment structure,

c. Perform a chemical analysis to detect changes in the chemical properties

/

~1 of the sheath filler grease. Any unusual changes in physical appearance

' or chemical properties that could adversely affect the ability of the filler grease to adhere to the tendon wires or othenvise inhibit corro-sion shall be reported to the Commission pursuant to Specification 6.9.2 within the next 30 days. ,,, , ,,3 4.6.1.6.2 End Anchorages and Adf Concrete Surfaces. The structural integrity of the end anchorages and adjacpht concrete surfaces shall be demonstrated by determining appearance of through inspection ^thatgppga,rpnt the end anchoragesToncrete changes exterior surfaces.Or have occ[urggdJ th concrele crack g patterns adjacent to es end anchorages)^*Qnspections of the c0ncrete shall be performed during the Type A containment leakage rate tests (reference Specification 4.6.1.2) while the containment is at its maximum testArgsure. _ m -- - -

Essa Arrygen sury m cPiqTd 4.6.1.6.3 Liner Plate. The structural integrity of the containment liner plate shall be determined during the shutdown for each Type A containment leakage rate test (reference Specification 4.6.1.2) by a visual inspection of the plate and verifying no apparent changes in appearance or other abnormal degradation.

4.6.1.6.4 Reports. Any abnormal degradation of the containment structure detected during the above required tests and inspections shall be reported to the Commission pursuant to Specification 6.9.2 within the next 30 ' days. This report shall include l a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedures , the tolerances on cracking, and the corrective actions taken, c

( CALVERT CLIFFS - UNIT 1 3/4 6-9 Amendment No. E6,94

O .

/

2

4. 4 .1. L. 2. E% A9cs.%.s aus Airacer C m m L st. css.

7d ,,,,,,, ,,

. ~,< . m.m msc~ -, est _ r - , s_s , _ et 3 a' 4 aumes.uro vt o e x m s yre r-te.a gy ce remia ac, -ram.w a . , a s ea c-,.. a e

- _ .. _, s.,._ .,_y...0 . ., _ 4,,

cwas Awe. o c.c.o,vt e a -nt visu4u aceeausco .* -rae. sxb A9cA**A( M c..J tAETE. EXTEft, s o rt., su%AAce.s , Ai.s o , in escr.. 4s ** we "rAELstt. #\4 7 AC.1 M'T o ft.

,k k

hkk.kk M NkTk 8T k d(d

'T'tAf s WS t,)w g,g4 e -reve Typt A co-A,, ym m 4 ,y,( . .r t

) S MLL 69 I

/ w asur T.is- c.eainare T is 6eaci,. 4-r..A V.4. 4, z)

Tesfs [ M ram acs

'fEst M53S"*' . -

A-r i-es exiaon h

b -

o ts Ph6L 3l*\ G- R C AGVtJL'T c g.s p p $ -

u tJ s ="f l l

l L. _

._m

CONTAINMENT SYSTEMS 3/4.6.5 COM8USTIBLE GAS CONTROL HYDROGEN ANALYZERS

~

LIMITING C0NDITICd FOR OPERATION

3. 6. 5.1 Two indeptadent contairment hydrogen analyzers shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTION:

hith one hydrogen analyzer inoperablei, restore the inoperable analyzer l to OPERABLE status within 30 days 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 .

h.Ylfh bcFh ytp valpta incpr8, cesIWL d llast one incppcdk amtyy

+o Orrtm dck wN% 72 kn or l><. ia d Itas r Itor STANpay a + fen t 4hz next 6 Aoub, SURVEILLANCE REQUIREMENTS

^

4.(,. 5.1 OcA W *ad9u' vaE. * *da>rrarg ort.mu a sw a, ca a. Arueevo Tev 8/55 h cituw.' 0, samp/A Frora e t Waste &qs %(em (Ar @ rapa e,44f w ,

4 4.6.5.S.'Each hydrogen analyzer shall be demonstrated OPERABLE at least l once per 92 days on a STAGGERED TEST BASIS by performing a CHANNEL CALIBRATION using sample gases in accordance with manufacturers' H recommendations. <>

wr ..; e Ane iod fran ray is to auiy is, ivua, one nyaro aa=iy::r ..y l>e made inoperable, % er.; P an time. fne the p. ws o replacing systen solenoid valves with =ad. e.. anh During this time, E

--I. kartan 1.0.4 11 not applicahlo tn this renuirement_ ~

l CALVERT CLIFFS - UNIT 1 3/4 6-26 AmendmentNo.69,7A,fj

PLANT SYSTEMS ,

AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 Two auxiliary feedwater trains consisting of one steam-driven and one '

motor-driven pump and a ociated flow paths capable of automatically initiating I flow shall be OPERABLE. (An OPERABLE steam-driven train shall consist of one pump aligned for automatic flow initiation and one pump aligned in standby.)*X (

APPLICABILITY: MODES 1, 2 and 3 ,

ACTION:

a. With any single pump inoperable, perform the following: ,

1. With No. 13 motor-driven pump inoperable:

(a) Align the standby steam-driven pump to automatic initiating status g within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , '

and (b) Restore No.13 motor-driven pump to OPERABLE status within the b next M days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . t 9 2.

7 Wi.th one steam-driven pump inoperable:

f

. L (a) Align the OPERABLE ste:m-driven pump to automatic initiating status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT SHUT 00WN within the next 4 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and j i

(b) Restore the inoperable steam-driven pump to standby status (or automatic initiating status if the other steam-driven pump is to be placed in standby) within the next 36 days or be in HOT SHUT-DOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . 7 A

- 4

b. With any two pumps inoperable: 4 4

1. Verify that the remaining pump is aligned to automatic initiating status within one hour, and

2. Verify within one hour that No. 23 motor-driven pump is OPERABLE j and valve 2-CV-4550 has been exercised within the last 30 days,

.and <

3. Restore a second pump to automatic initiating stat [within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 9 or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . 4 L

!for o pcried of up to 30 day; following the catcring inte-Meda 3 (;p thr0;gh /

) end including "00: I cpcratica) fics the Cycle 7 Unit i 5te we U.e out; matie ::te:tien featwes-of-the-auxiliary feed :ter syster may 50 ineper: '

A stanh pump shall be available for operation but aligned so that automatic 2 flow initiation is defeated upon AFAS actuation.

CALVERT CLIFFS - UNIT 1 Ji' 7-5 Amendment No. EA, 67, 78, j(

.. . m ar

o ,

PLANT SYSTEMS ,

AUXILIARY FEEDWATER SYSTEM E

SURVEILLANCE REQUIREM'NTS (Continued)

S characteristh not required) and each auxiliary feedwater automatically starts upon receipt of each AFAS test signal 2 4

2. Verifying that the auxiliary feedwater system is capable of J; ,

providing a minimum of 200 gpm nominal flow to each flow leg.

. . . h 4

l CALVERT CLIFFS - UNIT 1 3/4 7-5b Amendment No. 87 / /

s

~

--W._

~

) '.. . -

U I FLECTRICAL POWER SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

a. At least once per 31 days on a STAGGERED TEST BASIS by:

1. Verifying the fuel level in the day fuel tank.

2. Verifying the fuel level in the fuel storage tank.

3. Verifying the fuel transfer pump can be started and transfers fuel from the storage system to the day tank.

4. Verifying the diesel starts from ambient condition and accelerates to at least 900 rpm in < 10 seconds.

! 5. Verifying the generator is synchronized, loaded to >_

1250 kw, and operates for > 60 minutes.

6. Verifying the diesel generator is aligned to provide

'- standby power to the associated emergency busses.

(

l 7. Verifying that'$he automatic load sequence timer is l OP.ERABLE with the interval between each load block within

+ 10% of its design interval.

f

b. At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank is within the acceptable limits specified in Table 1 of ASTM 0975-68 when checked for ~ viscosity, ;

. water and sediment. .

c. At least once per 18 months by:

1. Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for this class of standby service.

2. Verifying the generator capability to reject a load of >

450- hp without tripping. l 500

3. Simulating a loss of offsite power in conjunction with a safety injection actuation test signal, and:

a) Verifying de-energization of the emergency busses and load shedding from the emergency busses.

t '

ApwbMFNr NO.

CALVERT CLIFFS-UNIT 1 3/4 8-3

ELECTRICAL POWER SYSTEMS

0. C. DISTRIBUTION - OPERATING LIMITING CONDITION FOR OPERATION 3.8.2.3 The following 0.C. bus trains shall be energized and OPERABLE:

('see MLc.wi.v, po M a.

125-volt 0.C. bus No.11, a 125-volt 0.C. battery bank ad'f s

full capic (charger.

b. 125-volt 0.C. buPNo,12, a 125-volt D.fb C tery b'ank and a full capacity charger. f

c. 125-volt 0.C. bus No. j21-1 -v t 0.C. battery bank and a full capacity char er.

d. 125-volt,0Cf us No. 22, a 125-volt 0.C. batt ank and a fupcapacity charger. \

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

ACTION:

a. With one 125-volt 0.C. bus inoperable, restore the inoperable bus j to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT STANOBY l

within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUT 00WN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months D.

aHoMlb \^t5^-VctV b4.% ad- @ s&iedWith

~

duringone 125-volt 0.C surveil'ladce testing per Specificationo 4.C.2.3.2.u.2, 4.8.2.3.2.d =d 4.3.2.3.2.P 1.

b Restore the inoperable battery to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or replace the inoperable battery with the OPERABLE Reserve Battery within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or

2. Be in at least HOT STANOBY wit?.in the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUT 00WN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c. With both 125-volt 0.C. battery chargers from the same O.C. bus .

inoperable:

1. Except when necessary during surveillance testing per Specifi-l cation 4.8.2.3.2.d.1, restore at least one 125-volt 0.C.

battery charger to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at

! least HOT STANOBY within the next.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUT 00WN l within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

N r 2. During surveillance testing per Specification 4.8.2.3.2.d.1, restore at least one 125-volt 0.C. battery charger to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the folicwing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

l d 0.C. battery inoperable duringJrysi44ance't6g of the battery per Spee ion 4 v3-2 C. .and 4.8.2.3.2.d.2, operation may cojitinue-provT ed W associa d bus is being powered

jn-ope 6cnarger and reserve battery.

CALVERT CLIFFS - UNIT 1 3/4 8-8 Amendment No.

r ,,

u

a. I25-Voit Df. bar Alo.ll, .

assoc e _.12F- Wli- D.C. Wfem a

ba^k cr c6 Mosalf N SeselveSoffery ank one-

assocledt) Sal \ capasti pckrger, b .12T- volF bC by No.12.,4te as.oclqQt N- vo(F b C. befaq bank. or a s rgcessqr3 4ke Reserve Bahr anelen asscohfatl bl_f _ cofnc ii _c hafpr.

c.125-volf D.C. ks No. 24 + ie c(cogigted _12=r- vpLb.C. deq bank.or as necenogy th3 R.eserve Batbarg q d one associatecd -fd _

capacitg c6aryr- . _ .

d . t z-7. volt b.c. bus Ala. n,%e associatec( ns - va b t beeg __

bank. oc as necesswy +he kerve htbuy , aal one __ ___

mseciateck4N cynci+) c6ger _ _

w e -,-

_--nw==vs e-- - m+- -w-m- -+= edume-* - ' = ... -=

,.. -ww a- m.

,. , ,. ,_,, . %.- m.- - ** - -. m - -m-m.e m-me.mme,e-. % .-,..., +,p

_.,m.m.m _w m,, -,,e-w m a=.e.-4e >=Me *

e e-w -- g wm

..ah m+ gw,o_.mme. -.-um--smmm. +w-**== * -' e ,*-= , - -

-em -% . # m.. --mi * --

.,a,eaa, -m--,,- s-- - m w = - - - =- am awmmm-

_o ,w e.,mm. -

,,e---aw ee-h-- m. -- -s.- - ---me ,==-s..w-- ,,

-m e-n-ee.y.-4 w a.e w.o -mwa -- - e-u- -,* + - * - ***--*--*m.u-- --e- m-- - * ---me.*.em-.m p---_.me.-*g - e-eu.-- ey--s- ---,,.we- --.-emes-e .+-e.- -4e+,e-e-..+*ww e eun,-..m>+emiew.ewee,.m&

. - . , _ . _. mw. -- , ---.s _ - - . . - - - . - - - - - - - - . - - - . - - .

a.s-= eww -

..-w i.e*M'** = = =

_ me m,- w e osma

. ad - .mme.4-.- ..mmeme nam e, weese mm- - - %w

- "* ee-- m-- em - = , 4.- -e==--e e.% +mmmme,m ,

e_ e.-

-m *P -- .-

, m o .m_ c .. ..a ... ,,. c... ,

- - _ - am.m u -

ELECTRICAL POWER SYSTEMS Lit 1ITI'4G CONDITION FOR OPERATION (Continued)

e. lii th on .C. battery inoperable durin s M4etrM of the battery per Spec d. . . operation may continue t-provided the ass .

is being pow e Reserve Battery p E charger.

@X. With single cells having a voltage decrease of more than 0.10 volts l from the previous performance discharge test (4.8.2.3.2.f. ) value, but still 1 2.10 vol ts per surveillance requirement 4.8.2.3.2.b.l . ,

either restore / replace cells or replace the affected battery with the Reserve Battery within 24 huurs or be in 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 .

SURVEILLANCE REQUIREMENTS

_~

4.8.2.3.1 Each D.C. bus train shall be determined OPERABLE and energized at least once per 7 days by verifying correct breaker alignment and indicated power

availability.

4. 8. 2. 3. 2 Each 125-volt battery bank and charger and the Reserve Battery shall be demonstrated OPERABLE;

a. At least once per 7 days by verifying that:

1. The electrolyte level of each pilot cell is between the minimum and maximum level indica tion marks.

i 2. The pilot cell specific gravity, corrected to 77'F and full electrolyte level is 1 1.200.

3. The pilot cell vol tage is ; 2.10 voits.

4. The overall battery voltage is 1 125 vol ts.

l ll o. At ieast once per 92 days by verifyiig that:

-el l 1. The vditage of each connected cell is - 2.10 vol ts under floa t

. cr.arge and nas not decreased more than 0.1] eolts from :ne i: value observed during the latest performance '2ischarge tes-

,t (4.8.2.3.2.f).

2. _ The specific gravi ty, corrected to 77 F and full electmlyte

!: level, of each connected cell is > 1.200 and has not decreased I more than 0.02 from the value observed during the previous test.

I The electrolyte level of each connected cell is between the i 3.

minimu;a and maximum level indication : narks .

l I CALVERT CLIFFS - UNIT 1 3/4 3-9 Amendment Nc.

i i

ELECTRICAL POWER SYSTEMS D.C. DISTRIBUTION - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.2.4 As a minimum, the following D. C. electrical equipment and bu l shall be energized and OPERABLE:

2 - 125-volt D.C. b_u es, d 6 Mrg 2 - 125-volt ery banksYind chargers supplying the above l 0.C. busses.

APPLICABILITY: MODES 5 and 6.

ACTION:

With less than the above complement of D.C. equipment and bus OPERABLE, l establish CONTAINMENT INTEGRITY within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

SURVEILLANCE REQUIREMENTS 4.8.2.4.1 The above required 125-volt D.C. busses shall be determined OPERABLE and energized at least once per 7 days by verifying correct breaker alignment and indicated power availability.

4.8.2.4.2 The above required 125-volt battery banks and chargers shall be demonstrated OPERABLE per Surveillance Requirement 4.8.2.3.2.

i-CALVERT CLIFFS-UNIT 1 3/4 8-11 AQge,d- Mo.

INSTRUMENTATION J l

BASES )

l by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded. .

IN SERT @

3/4.3.3.2 INCORE DETECTORS The OPERABILITY of the incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core.

3/4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that suffi-cient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety. This capability is required to permit comparison of the measured response to that used_in the design basis for the facility and is consistent with the recomendations of Regulatory Guide 1.12, " Instrumentation for Earthquakes", April 1974.

3/4.3.3.4. METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential

~ radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23 "0nsite Meteorological Programs",

February 1972.

3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room.

This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.

CALVERT CLIFFS - UNIT 1 8 3/4 3-2

INSTRUMENTATION BASES 3/4.3.3.6 POST-ACCIDENT INSTRUMENTATION The OPERABILITY of the post-accident instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, "Instrumen-tation for Light-Water-Cooled Nuclear Plants ~ to' Assess Plant Conditions During and Following an Accident," December 1975, and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."

3/4.3.3.7 . FIRE DETECTION INSTRUMENTATION .

OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of-fires. This capability is required in order to detect and locate fires -

in their early stages. Prompt detection of fires will reduce the poten '

tial for damage to safety related equipment and is an integral element #

in the overall facility fire protection program.

In the event that a portion of the fire detection inst' umentation r -

is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to operability.

3/4.3.3.8 MACTIVE GASEOUSJiMtt ENT MONITORINGd1ETRUMENTATION IODINE AMT PARTI ;ULATE SAMPL9r l

( p i

he OPERAB .ITY of e Iodine and Par culate Sat pler en s that Io e and Pa culate amples ca be o ned for ana lysi ring and

, f owing an ciden The surve e requirements e a high d ree-l availabilit I nmm %mwe l move -ro l s 2A,3.3.8

[ The,samplerswil' installed to meet the requirements of NUREG-0737 Item II.F.1. ,The sampler /A' operation was not assumed in any accident analysis.

(})

~

i .

, CALVERT CLIFFS - UNIT 1 B 3/4 3-3 Amendment No. 26, 53, 99

I N i

l t

CONTAINMENT SYSTEMS BASES 3/4.6.1.4 INTERNAL PRESSURE The limitations on~ containment internal pressure ensure that.1) the containment structure is prevented from exceeding its design negative pressure differential with respect to the outside atmosphere of 3.0 psig and 2) the containment peak pressure does not exceed the design pressure of'50 psig during LOCA conditions.

The maximum peak pressure expected to be obtained from a LOCA event is 47.6 psig. The limit of 148.psig for initial positive containment pressure will limit the tptal pressure to 49.4 psig which is less than the design pressure and is consistent with the accident analyses.

3/4.6.1.5 -AIR TEMPERATURE The limitation on containment average air temperature ensures that the containment peak air temperature does not exceed the design temperature of 276*F during LOCA conditions. The containment temperature limit is consistent with the accident analyses.

3/4.6.1.6 CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the con-tainment will be maintained comparable to the original design standards for the life of the facility.- Structural integrity is required to i

ensure that the containment will withstand the maximum pressure of 47.6-psig in the event of a LOCA. The measurement of containment tendon lift off force, the visual and metallurgical examination of tendons, anchor-ages and liner and the Type A leakage tests are sufficient to demonstrate this capability.

The surveillance requirements fpr demonstratingthyontainment's structural integrity are ' '!NWSce with the*Y'ecomm,endations of Regulatory Guide 1.35 " Inservice Surveillance of Ungrouted Tendons in Prestressed Concrete Containment Structures",' January 1976.

%=_ m ucouvi. comaen uruu.s. wee.s 3._ ueca viso*u y r=.s e

iM h s cA T.oM S OF ABraore # L N A rE>tWL TW.MvieN t3uft.sr44 T(NocA si> & ELLLAn(E.

L gpgcy,,ug ,e Pret.stugefrca cesetitE CRAM. PATTE*As ^^E- W ** O no ri.ia c, -nn. rv et A c.arai-wr wucit em *sts , co~sisr<ar

! wera -rwt Gem o c-com. ruxweiry -rtst,

, CALVERT CLIFFS - UNIT 1 8 3/4 6-2

q ATTACHMENT (2)

INDEX '

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE SECTION P.AG. E, 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT '!

RATE..................................... 3/4 2-1 ;

3/4.2.2 TOTAL PLANAR RADIAL. PEAKING FACT 0R. . . . . . . .

3/4.2.3 TOTAL INTEGRATED RADIAL PEAKING FACTOR............... 3/4 2-9 3/4.2.4 AZIMUTHAL POWER TILT.................................

3/4 2-12 3/4.2.5 DN8 PARAMETERS. . ; . . . . . . . . . . . . . . . . . . . . . . . '. . . . . . . . . . . . . 3 3/4.3 INSTRUMENTATION 3/4.3.1 2 REACTOR PROTECTIVE INSTRUMENTATION. . . . . . .

3/4.3.2.

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION.....................................~3/4 3-10 3/4.3.3 MDNITORING INSTRUMENTATION e

Radiation Monitoring Instrumentation................. 3/4 3-25 Incore

- Detectors..................................... 3/4 3-29 Seismic Instrumentation.............................. 3/4 3-31 Meteorolooical Instrumentation.... - ...'............. 3/4 3-34

Remote snutdown Instrumentation...................... 3/4 3-37 Post-Accident Instrumentation. . . . . . . . . . . . . . . . . . . . . . -

Fi re Detection Instrumentation. . . . . . . . . . . . . . . . . . . . .

Radioncti ve - Ga seous - Effl uent - Moni tori ng -

Instrumentation.................................... 3/4 3 47- '

~

3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION. . . . . .

Sta rtup a nd Powe r. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-1 Hot Standby................................. ........ 3/4 4-2 Shutdown.................................... ........ 3/4 4-2a 3/4.4.2 SAFETY VALVES...................... w ~ ......... 3/4 4-3 3/4.4.3 REL IEF 1rEVE5. . . . . . . . . . . . . . . . . . . . .-. . . . . . . . . . . . .

CALVERT CLIFFS - UNIT 2 IV Amendment No. JS, DS, 33, 81

_ =

TABLE 3.3-6 g RADIATION MONITORING INSTRUMENTATION g.

g MINIMUM CHANNELS APPLICABLE ALARM / TRIP p INSTRUMENT OPERABLE MODES MEASUREMENT SETPOINT RANGE- ACTION 4

g 1. AREA MONITORS *

a. Containment 2

a 1. Purge & Exhaust y Isolation -4 3 6 1 220 mr/hr 10 .- 104 mr/hr 16

b. Containment Area High Range 2 1, 2, 3 & 4 5 10 R/hr 1 - 108 R/hr 30

2. PROCESS MONITORS Ra

a. Containment ,

w i. Gaseous Activity 4, a) RCS Leakage Detection 1 1, 2, 3 & 4 Not Applicable 1 6 10 - 10 cpm 14

' 11. Particulate Activity a) RCS Leakage Detection I 1 1, 2, 3 & 4 Not Applicable 10 - 106 cpm 14 y b. tbk On Effluent

@ Monitors k i. Main Vent Wide A Ran 1 1, 2, 3 & 4

m c0 c6LE GAS 10-7 to 105 uCi/cc 30

) P M m

is b) Icome Samacen ~

c> paar,euw wnep I

i t ; 1, 3 4 4 1, t , 3 ,t it Mor Apvuviott-Nor Aerunesus Wor Ar#>acasm Ner Arettessic jg

Alam setpoint to be specified in a controlled document (e.g. , setpoint control manual).

i i

n TABLE 4.3-3

?

M E RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS n

E CHANNEL CHANNEL MODES IN WHICH CHANNEL FUNCTIONAL

]- INSTRUMENT CHECK CALIBRATION TEST SURVEILLANCE.

REQUIRED

!. AREA MONITORS E

Z a. Containment

i. Purge & Exhaust Isolation S- R M 6

b. Containment Area High Range S R M 1, 2, 3, & 4 w

1 2. PROCESS MONITORS w

g a. Containment

i. Gaseous Activity a) RCS Leakage Detection S R M 1, 2, 3, & 4 ii. Particulate Activity

$" a) RCS Leakage

{ Detection 5 R M 1, 2, 3, & 4 s b. " ble C : Effluent

[ Monitors

1. Main Vent Wide a> Range

~ g S R M 1, 2, 3, & 4 M NOGLt. 6AS - S b) Icowe. S AmetEll M N e,T Armcag$c ,

per Ay,y% E ( , 7. , '$ , 8 Cf L) 9peTteoLATF. SamaER. M Nor kn.c.wc. . Hs r Arouvase. I o 2 , 3, Z 'l

TABLE 3.3-11 FIRE DETECTION INSTRUMENTS

' UNIT 2 INSTRUMENT LOCATION MINIMUM INSTRUMENTS OPERABLE

HEAT FLAME SMOKE 3

Unit 2 East Elec Pen Room 409 3 Unit 2 West Elec Pen Room 414 6

" nit.2 Switchgear Elev 27'-0" Room 311**

8

-Unit 2 Switchgear Elev 45'-0" Room 407**

3 W t-2-Elec Equip Room 532 SW cNTMr c4acT48"' +it 2 Cent SEare:* Elec Per ' 4-HN CRINT C4acTanI+ Unit 2 Ceat N" El;; I;n "rCO*

16 (NTmr Unit 2 Cent East RCPS* 16 cMTMr " nit 2 C;nt West RCPS* 8 Unit 2 Main Plant Exh Equip Room 526 3

(NTM7 Unit 2 Per:enn:1 Access Area Room 527 4 Cable Tunnel U-2 Elev 83'-0" 1 i

Cable Chase 2A '

1 Cable Chase 2B #

2 10 Unit 2 C.S.R. & Cable Chase 2C#Re0M301. 1 Wit-2-Letdown Heat Exchanger Room 322 1

" nit 2 Volume Control Tank Room 214 4

" nit 2 Cool Waste-Ree-IK Room 107 and 109PcNiroR 7 Unit 2 ECCS Pump Rooms'101 and 120 1.

L' nit 2 Pump Room 108 Elev (-) 10'-0" U Nir 2. Sioc .

-46 #

-Unit Unit 22 Elev Intake Structure, 27'-0" Swgr Room Vent Duct Rook'.5tl 1 Unit 2 Elev 45'-0" Swgr Room Vent Duct Room 407 1 Unit 2 ECCS Pp Rooms 102 and-HO- 111 7l -

2 21 Diesel Generator ** 2 4Mi4.- Refueling Water Tk Pp Room 440 3 5 Udt- East Pp Pen Rooms 206 and 310 2

Unit Purge Air Supply Room 312 2 3 l

Unit-2-yest Piping Pen Rooms 211 and 321 t

l (_4m E heme Reem veur o wr'G' p (3_g y s.

Detection instruments located within the containment are not required to be OPERABLE during the performance of Type A Containment Leakage Rate Tests.

! ** Detectors which automatically actuate fire suppression systems. ,

bor4Tonco GvQ pgoraro hecs CALVERT CLIFFS - UNIT 2 3/4 3-45 Amendment No. 71 fyy,77 l

t l

l f

TABLE 3.3-11 (Continued)

FIRE DETECTION INSTRUMENTS INSTRUMENT LOCATION MINIMUM INSTRUMENT OPERABLE HEAT FLAME SM0KE Main Steam Piping Room 309 6 East Piping Area Room 203 10 Charging Pump Room 105 3 Battery Room-307 -and 305.ANo CcRRtooR 303 - 3 l Misc. Waste Monitor Tank Room i East Piping Area Room 408 7 Component Cooling Room 201 9 Radiation Exchange Equip. Room 204 4 Boric Acid Tank and Pump Room 215 2 Reactor C :M;gp Room 216A SooWe MyE -u P 2 l -

Service Water Room 205 3 6 Auxiliary Feed Pump Room 605 2 Degasifier Pump Room 1 4

4 I

i

?

i I

CALVERT CLIFFS - UNIT 2 3/4 3-46 Amendment No,. ,77 l

1 l

l

~

. 1 INSTRUMENTATION

/

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 The main vent fodine and particulate sampler 1 ERAB APPLICABILITY: All MODES.

, ACTION:

l

a. With the main vent iodine particulate 1er inoperable, initiate the preplanned te method o ling the main vent for the appropria er(s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

1. aither restore t bl ler to OPERABLE status

.. within 7 days of t t

2. prepare and -submit a Report to the Comission -

pursua Specif .9.2 within 30 days following

the'ev tlin e action taken, the cause of the i rab e plans and schedule for restoring -

ystem LE status. ,

b. T ions of ecifications 3.0.3 and.3.0.4 are not applicable., ,y

s.

I WEILLA RE NTS

..j -

I 3.3.8 e siain vent iodin and particulate sampler shall be demonstrated l L y comparing samples independently drawn from the main vent at 1 e per month.

t

\ -

I i

1 l

9 N&

CALVERT CLIFFS - UNIT 2 3/4 3-47 Amendment No. 81

e CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE

' ~

LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:

a. An overall integrated leakage rate of:

1. <La (346,000 SCCM), 0.20 percent by weight of the containment air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at P,, 50 psig, or

2. <Lt (44,600 SCCM), 0.042 percent by wetght of the containment air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at a reduced pressure of Pt . 25 psig.

b. A combined leakage rate of < 0.60 L (207,600 SCCM) for all penetra-tions and valves subject to Type B $nd C tests when pressurized to P,.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L SCCM), or 0.75 L (33,400 SCCM), as applicable, or (b) with the Bea(259.500sured combined leakage r$te for all penetrations

, restore the leakage valves rate (s) subject to withintothe.]imit(s)

Types B andpriorCtotests exceeding increasing the 0.60 L, Reactor Coolant S temperat6re above 200'F. Ag -4 g g h, SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the follow-ing test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50( using the methods and provisions of l ANSI N45.4 - 1972:

a. Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 + 10 month intervals during shutdown at either Pa (50 psig) or at Pt (25 psig) during each 10-year service period. The third 0::t Of :::h ::t 0h:11 b; :::d;:ted i..-ing th :httd:u- fer th: 10 y::r pl::: i - : rtice i :;::tica

4

H thi dr test Of th: #4 r:t 10-year ::r" ice peri d $h:11 b; ::nde:ted d;rin; the f:11 1005 Unit 2 ref :1ing : t:;;.

4 CALVERT CLIFFS - UNIT 2 3/4 6-2 Amendment No. 56, /fr

, --,*-em--,, ,an , - -

1 CONTAINMEhTSYSTEMS CONTAINMENT STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.6 The structural integrity of the containment shall be maintained at a level consistent with'the acceptance criteria in Specification 4.6.1.6.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With the structural integrity of the containment not conforming to the above requirements, restore the structural integrity to within the limits 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 SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS l

V 4.6.1.6.1 Containment Tendons The containment tendons' structural integrity shall be demonstrated at the end of one, three and five years following the initial containment structural integrity test and at five year. intervals thereafter. The tendons' structural integrity shall be

~

demon'strated by a visual examination (to the extent practical and without dismantling load bearing components of the anchorage) of a representative sample of at least 21 tendons (6 dome, 5 vertical, and 10 hoop) and verifying no abnormal degradation. Unless there is evidence of abnormal degradation of the containment structure during the first three tests of the tendons. the number of tendons examined during subsequent tests may be reduced to a representative sample of at least 9 tendons (3 dome, 3 vertical and 3 hoop). , g ws.m. (wuws seu r.a,..r. uw) r 4.6.1.6.2 End Anchorages and Adjacent Concrete Surfaces _ The structural integrity of the end anchorages and adjacent cpncrete surfaces shall be demonstrated by determining through inspection ^ that no appareg,h,angg, have occurred in the viyp1 s ag'garance of the end anchoragestancrete exterior surfaces.cr th ,Eolicrete crack patterns adjacent to the.end anchorages)"4nspections of the*cer. rcte shall be performed during the Type A containment leakage rate tests (reference. Specification 4.6.1.2) while the containment is at its maximum test pressure. _

earr m er o

CAuERT CurrS - unit 2 m 6-8 m n y,

i

. 4.- ,

i i

I l

1 N. be I . b. k 6Hb kNc4%6 Au6 b b7AcAi*r bucas.ta. $ vet Fate.S , m egggg I

EE.re b ANCAenAcstS A*J 4 AhTA'8MT' cdJCAATe sustrAcg.Sl WA t.t Bt, t' A'11tAftxtyf c F" -t%e I

~N *

C= A "<. s eac-rio ,4 os A pa.PnesaurAmt

'DeM=NStrtA-re.t "W OE NAsni4C i I

J

-T4%-r M6 ! A ffe ^'#

) S Auf LE- *R "T4.*J 8 = 45 [ ttrfemE. fiascivescA-n.n 4.4. l.f. . t )

cWVIS 4 AVE o cc o mA4.S 4 -fkg VisuAt A cee A R.Af4CL, oF -t*g equJb Ap4CA*AA0lkS

(

c..*Jtaa n uxistsgr( suvAcos , Auso, SN SPfNha45 o f"

f--

. o ft. WAe.AR. A 4'IAcA Nei Tew . se. Lac.erdh c perts re cxAcet PA TytnNS A O tac /tw <= sua6 A4 c A*ft A A CT T/P._ A c..mA , ,, y ,,,. mA x Q R$-rc I 6 AAL.L. SL "PWJtf ortM Dues,seks "re4rt l want F. 'TkC- C'*td ' M*N'T 4 C Ita F4/ut** Nacif ic A-r aA M.4. 4. 2

~TS STS A~T g rs eAAXtMoA "' REST M E.SSvaE., ,

i t

7Asstir r Fore ert ese/4-r ' a e/t a iri 6 o ta Ph fat. 3[4 6-S l t

f 1

I I

~

( At.Velt-T c.a s F F 5 -

u rJ s T* 2

. CONTAINMENT SYSTEMS 3/4.6.5 COMBUSTIBLE GAS CONTROL s HYOR0 GEN ANALYZERS LIMITING CONDITION FOR OPERATION

. 3.6.5.1 Two independent containment hydrogen analyzers shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTION:

a.

Sith one hydrogen analyzer inoperableX, restore the inoperable analyzer I to OPERABLE status within 30 days 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 . .

b. WiH, bbth Iv; drops antl y ttrs inoptrnik, resloct al (MFou ic6psrobli m1d j ur -- 1

+o OPEM8l6 sinivs wit % 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or bl in af Jen( He r sTANbey wi1Ain ai uw-a. . ..

T -

SURVEILLANCE REQUIREMENTS

4. 0. 5. - - h nydrogen analyser shall be demonstrated OPERAhn once per 92 days o .GGPRFD TEST BA ng a CHANNEL

, CALIBRATI0N usin umMe n accor i4A maaf_a cturers ' ;;

P A ' ' ^^^ L..sna T nnt. ~ 4 p

%5' l Eod hjdnep anahper dall k diantmW 0tYRABufJ (auf bi ca frnu.secb tesr # sis h ama,.,a so pk fro #, Wasu 6s gsA #my +

kghp, anty w todi&c. * '

b 45,5.1 Eoek k % a ser shall k %cedr one er 9L Jk on a GTW M Test dAstS % per%grA iw a CH n lEL open,3tg at- lwf-

? CALIBUr/0A1 vsieg unph quo in aoardANL wik rev&&rert' MemmsetdabkS

} ^ . : ..; A - pe.-ted fcou. 11 7 15 te July 1", 1983, o.c hydcogec. e..e; m c - :, r f be made inoperab e, time, for * "r;;se or replacing system /

)

solenoid valves r:c.;edes y qu Qring this time, d ca- -Lion 3. .4 is not aoolicable to this recuirement. ~i

{

l CALVERT CLIFFS - UNIT 2 3/4 6-26 Amendment No. /2, 55,//

l l

I I

PLANT SYSTEMS .

AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION (Continued) u $

c. Whenever a s)(bsystem(3(0.Sdsgstem gonsisting of one pump, piping, valves and \

controls-in the direct flow path) required for operability is in-operable for the perfomance of periodic testing ( g. .1 dischargi valve closed for pump Total Dynamic Egad es 'eYea%d l operato@heControlRoom.ill tion t be stationed Upon completionatofthe anylocal testing, statio@ith the sub-d rect com syst equired for operability will be returned to its proper status and verified in its proper status by an independent operator check.

d. The requirements of- Specifica. tion 3.0.4 are not applicable whenever one motor and one steam-driven pump (or two steam-driven pumps) are p aligned for automatic flow initiation. f SURVEILLANCE REQUIREMENTS 4.7.1.2 Each auxiliary feedwater flowpath shall be demonstrated OPERABLE:

a. At. least once per .31. days by:

1 1. Verifying that each steam driven pump develops a Total Dynamic Head of > 2800 f t. on recirculation flow. (If verification must be demonTtrated during startup, surveillan_ce testing.shall be perfomed upon achieving an RCS temp,erature'~ > 3000F and prior to

, entering MODE 1).

2., Verifying that the motor driven pump develops a. Total Dynamic Head of > 3100 ft. on recirculation flow. -

3. Cycling each testable, remote operated valve that is not in its operating position through at least one complete cycle.

l 4. Verifying that each valve (manual, power operated or automatic in the direct flow path is in its correct position. T

b. Before entering MODE 3 after a COLD SHUT 00WN of at least 14 days by completing a flow test that verifies the flow path from the conden-sate storage tank to the steam generators.

c. .At least once, per 18 months by:

p .

... . n. g

1. Verifying that each automatic valve in the flow path actuates ?

to its correct position-(verification of flow-modulating >

- characteristics not required) and each auxiliary feedwater pump ?

f automatically starts upon receipt of each AFAS test signal, and. (

a

2. Verifying that the auxiliary feedwater system is capable of I '

providing a minimum of 200 gpm nominal flow to each flow leg. < ,

rat vror el TErc IINTT 2. 3/4 7-Sa amandmaar Nn K n~4 M

? ?

~

=

s - ELECTRICAL POWER SYSTEM #E C =0 51 SURVEILLANCE REQUIREMENTS (Continued) bl E

E=l ;

El

a. At least once per 31 days on a STAGGERED TEST BASIS by: @

g

-1. Verifying the fuel level in the day fuel tank. :Hj E

2. Verifying the fuel level in the fuel storage tank. [@

?M

3. Verifying the fuel transfer pump can be started and 5 transfers fuel from the storage system to the day tank. e Bij

4. Verifying the diesel starts from ambient condition and M accelerates to at least 900 rpm in < 10 seconds.

Jj Eu ap 5 Verifying the generator is synchronized, loaded to >

1250 kw, and operates for > 60 minutes.

_ M

M 55

6. Verifying the diesel generator is aligned to provide ),Ip standby power to the associated emergency busses. .g E=. M

7. Verifying that the automatie load sequence timer is 55j OPERABLE with the interval between each load block within ="l

~"

+ 10% of its design interval.

b. At least once per 92 days by verifying that a sample of diesel 5 fuel from the fuel storage tank is within the acceptable limits f specified in Table 1 of ASTM 0975-68 when checked for viscosity, M water and sediment. E+

W

c. At least once per 18 months by: -

6 Ke

1. Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for this class of standby service.

.E-

2. Verifying the generator capability to reject a load of >_

450-hp without tripping. l 600 ,21

3. Simulating a loss of offsite power in conjunction with a f.'j safety injection actuation test signal, and: M

=

3.

a) Verifying de-energization of the emergency busses @j and load shedding from the emergency busses. =

je ip

,.j 55 M' -'

IS CALVERT CLIFFS-UN' ~ 2- 3/4 8-3 U# #'

h-t n L. . .

O *, .o I'

ELECTRICAL POWER SYSTEMS .

I_ D. C. DISTRIBUTION - OPERATING LIMITING CONDITION FOR OPERATION 3.8.2 3 The followin be energized and OPERABLE:

(see d,ellowM<r page')g D.C. bus trains shal

a. 525-vaQ D.C. bus No.11, a 125-vol t 0.C. battery bank and'a full capacity charger.

b. 125-volt D.C. bus No 12, a 125-vol t D. tery bank and a full capacity charger.

c. 125-volt D.C. bus No. 21 M Wo D.C. battery bank and a full capacity charge [.

d. 125-volt 0. nk and a ful.1-ca'pacity charger.No. 22, a 125-volt D.C. battery-ba\

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

ACTION:

a. With one 125-volt 0.C. bus inoperable, restore the inoperable . bus to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT STAN0BY 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 i bee 3ss2qtEI 12%vojl,D C. bus not heiA3 -suppl @cl b' ee Pe.scere. D

b. With one 125-volt D.C. battery inoperabTie'rExcept during survei1TiFce d ed 0 .0.2.3.2. f-testing per Specification; 4.0.2.3.2.s.2, 4.8.2.3.2.b

1. Restore the inoperable battery to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or replace the inoperable battery with the OPERABLE Reserve Battery within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or

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

c. With both 125-volt 0.C. battery chargers from the same D.C. bus inoperable:

1. Except when necessary during surveillance testing per Specifi-cation 4.8.2.3.2.d.1, restore at least one 125-vol t 0.C.

battery charger to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 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 SHUTCOWN l

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

(

I 2. During surveillance testing per Specification 4.8.2.3.2.d.1, restore at least cne 125-volt 0.C. battery charger to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT STANOBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

d. -volt 0.C. battery inoperable during surveillance-testing of the battery pe S W ion L8.2 4 2 x.-2 ind 4.8.2.3.2.d.2, operation may continue-provideMhrusocirted bus is being powered ,

Aan-ocer3bTe~ charger and reserve I attery.

CALVERT CLIFFS - UNIT 2 3/4 8-8 Amendment No.

Q. -VO N D.(. _ hs _[_0.J1g OR 4%CCtob l 2 T-- Ved D 4. hh(q a

assee:aird Llt capacLty_ charger, __ . __ ._ _

b . t tr- velf- b.C. h>s No. I2.,tha. associated t z.T- Vo(f- b.c. 6ffery k A o< a s necesw.~ ..__..__ % Resen e. .%< . . . . . _ _ _ _ . .

. . . . . a_ p - .d. . . - _a n. .. . _ _ . _

associated Ell.cyc;t ...charpr.. _ ... _ _ _ . _ _

q,125-volf' b.C. ks No. 2.t ite. agociated i2T- volF b.C. _btferg .

g .

__ associaM Oli capacit) cAarger - __ _ ___

_d . t zr vell- b.c. bs Mo. zgue assotideo( t15 - vop- b t. Entfwg

__ . ._ - __ _ g. - _. . _.

awsdtd_Al! cyaci+y ck 3er- - . -

_ _ _ . ~ _ _ _ _ - - _ . - . _ .

. - - ~ .

_-- . . - . , . - ~ . _ . _ . . . . _ . . . . . . . . - . . . ~ .

. . _ . . - . - ~ -

. . - . _ _ _ . . - - _ . . _ _ - . . ~

,. . _m__.- -. . . , . . . _ . . O ..

g7 . Italtimure Gee ernt Electrie Company

r ELECTRICAL POWER SYSTEMS LIli!T!1G CONDITION FOR OPERATION (Continued)

e. 0.C. battery inoperable during_sutveillance' testing of the battery pe pe%ationAB.2.3r2:f7aperation may continue provi.1ed the assogjated-bus-1s Tetng-pow ed by the Reserve Battery p PERABEE charger.

hf. With single cells having a voltage decrease of more than 0.10. volts l from the previous performance discharge test (4.8.2.3.2.f.) value, but still > 2.10 volts per surveillance requirement 4.8.2.3.2.b.1.,

either restore / replace cells or replace the affected battery with the Reserve Battery within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in HOT STANOBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUT 00WN yithin the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS

~

4.8.2.3.1 Each 0.0. bus train shall be determined OPERABLE and energized at

~

least once per 7 days by verifying correct breaker alignment and indicated power availability.

~ 4.8.2.3.2 Each 125-volt battery bank and charger and the Reserve Battery shall be demonstrated OPERABLE;

a. At least once per 7 days by verifying that:

1. The electrolyte level of each pilot cell is between the minimum and maximum level indication marks.

2. The pilot cell specific gravity, corrected to 77'F and full electrolyte level is > 1.200. ,

3. The pilot cell voltage is > 2.10 volts.

4 The overall battery voltage is > 125 volts.

b. At least once per 92. days by verifying that:

1. The voltage of each connected cell is > 2.10 volts under float

~

charge and has not decreased more than 0.10 volts from the value observed during the latest performance discharge test

( 4. 8. 2. 3. 2. f) .

2. The specific gravity, corrected to 77'F and full electrolyte level, of each connected cell is > 1.200 and has not decreased more than 0.02 from the value o served during the previous test.

/

3. The electrolyte level of each connected cell is between the minimum and maximum level indication marks.

CALVERT CLIFFS - UNIT 2 3/4 8-9 Amendment No. .

P

$4

. . . . 'E.

m 3

- , m

~) ELECTRICAL POWER SYSTEMS h il D.C. DISTRIBUTION - SHUTDOWN $

a

. - . . . . . .. . y

.__...__...g LIMITING CONDITION FOR OPERATION Ei

=

EE El

=

3.8.2.4 As a minimum, the following D. C. electrical equipraent and bus sc5 l M shall be energized and OPERABLE: EE

=

a 2 - 125-volt 0.C._ busses. and g gg E 6cm of which mag e- :g 2 - 125-volt battery banksYand chargers supplying the ~above l iiit D.C. busses. EE

. E APPLTCABILITY: MODES 5 and 6. .. .

M

.=

=-

ACTION: M

=.

Ert/

With less than the above complement of 0.C. equipment and bus UPERABLE, l M

=-.

establish CONTAINMENT INTEGRITY within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . h E EE

.-g

~m..-

=.-

5 EM SURVEILLANCE REQUIREMENTS p;g E

g v--. -

. .. . . . _ =

'4.8.2.4.1 The above r,equired 125-v,olt D.C. busses shall be~ determined ?Z OPERABLE and energized at least once per 7 days by verifying correct EE breaker alignment and indicated power availability. M E

4.8.2.4.2 The above required 125-volt battery banks and chargers shall 5 be demonstrated OPERABLE per Surveillance Requirement 4.8.2.3.2. F Ei M

EE

=

~

=

is C.*

EE

=

FS

_ E is

=

" E5 V .}

ifi

r. p.E is a, CALVERT CLIFFS -

ilT 2 3/4 0-11 A(wmdref Mo. $S=

43 d."-

v INSTRUMENTATION BASES '

by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.

I MRT 3/4.3.3.2 INCORE DETECTORS The OPERABILITY of the incore detectors with the specified min'imum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core.

3/4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that suffi-cient capability is available to promptly detemine the magnitude of a seismic event and eva? sate the response of those features important to safety. This capabili'y is required to permit comparison of the measured s response to that used th the design basis for the facility and is consistent with the recommendations of Regulatory Guide 1.12. " Instrumentation for Earthquakes", April 1974.

3/4.3.3.4. METEOROLOGICAL INSTRUMENTATION Yhe OPERABILITY of the meteorological instrumentation ensures that s.afficient meteorological data is available for estimating potential radiation doses to the public as a result of routine orThis accidental capability is release cf radioactive materials to the atmosphere.

required to evaluate the need for initiating protective measures to protect tre health and safety of the public and is consistent ~ with the recommendations of Regulatory Guide 1.23 "Onsite Meteorological Programs",

February 1972.

3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION _

l The OPERABILITY of the remote shutdown instrumentation ensures tha i

sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room.

This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.

B 3/4 3-2 AUG 1 3 SN CALVERT CLIFFS - UNIT 2 t

f INSTRUMENTATION BASES 3/4.3.3.6 POST-ACCIDENT INSTRUMENTATION sufficient infomatian is available on selected plant paramete monitor and assess these variables following an accident. 1 is consistent with the recomendations of Regulatory Guide 1.97, "Instru-This ca l mentation for Light-Water-Cooled Nuclear Plants to Assess Plant Conditions During and Following an Accident," December 1975, and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Tem Recomendations."

3/4.3.3.7 FIRE DETECTION INSTRUMENTATION adequate fires.

OPERALILITY of theis fire warning capability detection available for the instrumentation prompt detection ofensures that in their early stages,.This capability is required in order to detect and locate fires tial for damage to safety related equipment and is an integral el in the overall facility fire protection program.

In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to operability.

3/4.3.Li>""HADIDACTIVE GAS 3Nf!P1FFLUENT MONUmwimaINSTRU rIODNVE AND PAATICULATEEPP.ER N

[

Th Iodi ERABI of the dine Particul e Samp nd Par ulate Sa es ca ensur th foll ing ' ccident. su e obtained or an sis du ng degre 111ance requi n availability. ensure i 11 z c o.n e n a v a a m a r*z s

nove To Item The samplenway installed to meet the requirements of NUREG-0737 II.,F.1.

i3 sfy,3s4 analysis. The sarlipledg operation was not assumed in any accident

~

. . i k

E

?

E 1' y

~

m CALVERT CLIFFS - UNIT 2 B 3/4 3-3 i

.endment No. JJ, 36,81 E E

E E

E.

l .

<~~txvt T*Aftettr*5 A rt.f fWtFon M44 o u aieJ C,~~

~~-r w - -ryrt A c. ora,u w r wa u n a =.4rc <ests , c u s. . m ur- m ,-tw 1~~

~~- -r u Sra a <., + rmeinay 1~zer.~~

~~AUG 1 3 375 CAL'IERT CLIFFS - UNIT 2 8 3/4 6-2~~

~~. - - _.-. -...._.-..- ._ .-, --~~

ML20117B346

Text

Navigation menu

Search