ML20149E451

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Proposed Tech Specs Re Containment Purge Isolation Valves
ML20149E451
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 01/12/1988
From:
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20149E446 List:
References
NUDOCS 8801130352
Download: ML20149E451 (28)
v • d • e


Text

.

.[hD11 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PJ_GE j 1/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION 3/4 9-1 3/4.9.2 INSTRUMENTATION 3/4 9-2 3/4.9.3 DECAY TIME 3/4 9 3 3/4.9.4 CONTAINMENT PENETRATIONS 3/4 9-4 3/4.9.5 COMMUNICATIONS 3/4 9-5 3/4.9.6 REFUELING MACHINE OPERABILITY 3/4 9-6 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORAGE POOL BUILDING 3/4 9 7 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION 3/4 9 8 3/4.9.9 DELETED 3/4 9-9 3/4.9.10 WATER LEVEL - REACTOR VESSEL 3/4 9-10 3/4.9.11 SPENT FUEL POOL WATER LEVEL 3/4 9 11 3/4.9.12 SPENT FUEL P0OL VENTILATION SYSTEM 3/4 9-12 3/4.9.13 SPENT FUEL CASK HANDLING CRANE 3/4 9-16 3/4.9.14 CONTAINMENT VENT ISOLATION VALVES 3/4 9-17 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN 3/4 10-1 3/4.10.2 MODERAT0P TEMPERATURE COEFFICIENT, CEA INSERTION AND POWER DISTRIBUTION LIMITS 3/4 10 2 3/4.10.3 NO FLOW TESTS 3/4 10-3 3/4.10.4 CENTER CEA MISALIGNMENT 3/4 10 4 3/4.10.5 COOLANT CIRCULATION 3/4 10-5

$011$UM 0 d7 CALVERT CLIFFS UNIT 1 VI!! Amendment No. JJ//J5//ES,

lEQU BASES SECTION BGE -

3/4.9.5 COMMUNICATIONS B 3/4 9-1 3/4.9.6 REFUELING MACHINE OPERABILITY B 3/4 9-2  !

3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING B 3/4 9-2 l 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION B 3/4 9-2 3/4.9.9 DELETED B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND SPENT FUEL POOL WATER LEVEL B 3/4 9-3 -

3/4.9.12 SPENT FUEL POOL VENTILATION SYSTEM B 3/4 9-3 3/4.9.13 SPENT FUEL CASK HANDLING CRANE B 3/4 9-3 3/4.9.14 CONTAINMENT VENT ISOLATION VALVES B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS B 3/4 10-1 3/4.10.3 NO FLOW TESTS B 3/4 10-1 3/4.10.4 CENTER CEA MISALIGNMENT B 3/4 10-1 3/4.10.5 COOLANT CIRCULATION B 3/4 10-1 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS B 3/4 11-2 3/4.11.3 SOLID RADI0 ACTIVE WASTE B 3/4 11-5 3/4.11.4 TOTAL DOSE B 3/4 11-5 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM B 3/4 12-1 3/4.12.2 LAND USE CENSUS B 3/4 12-1 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM B 3/4 12 2 CALVERT CLIFFS - UNIT 1 XIII Amendment No. l#l/E5//E81 1991/195,

9 TAfME 't.3-3 (Continumi)

Q

-t FNGIMffRfD SAFETY FIATtRE ACTUATION SYSTFM INSTRIMFNTATION -

.s I~

Q MINIMtM

] 10TAL NO. DIANNELS OtANNELS APPLICABLE

, FtWCil0NAI tmIT Of CHANNftS TO TRIP OPfRADIE N0 DIS ACTION C

3

-4

6. CONTAINitNT PIRE VALVES ISOLATION
a. Manual (Purge Valve ControlSwitches) 2/ Penetration 1/ Penetration 2/ Penetration 6** 8
b. Containment Radiation -

High Area Monitor 4 2 3 6** 8 w 7. LOSS Of POW R l N 4 l w 4. 4.16 kw Er.ergency Bus j Undervoltage (Loss of W Voltage) 4/ Bus 2/ bus 3/ Bus 1, 2, 3 7*

1

b. 4.16 kw Energency Bus Undervoltage (Degraded Voltage) 4/ Bus 2/ Bus 3/ Bus 1, 2. 3 7* I

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c.

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2 ** Must be OPERABLE only in MODE 6 when the valves are required OPERABLE and they are open.

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i TAllt f 3.3-4 (Continmil ,

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30 2>

[NGINEERfD SAffTY ffATtlRE ACTUATION SYSTIN INSTRt9f MTATION TRIP VAltf5 f~Q mm .

u :;o a ,

Oo ALLOWABLE r r- t

  • ~ (UNCTIONAl ImIT TRIP VAltE VAltf5 }

mm

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<n tn S. CONTAINNI SlMP RECIRCIA All0N (RAS) cc [

ZZ a. Manual RAS (Trip Button:) Not Applicable Not Applicable 4

N c-* b. Refueling Water Tank - Low 1 24 inches above 1 24 inches above tank bottom I tank bottom

6. CONTAIINENT PtRE VALVES ISOLATION  ;
a. Manual (Purge Valve Control Switches) Not Applicable Not Applicable I i

(a Containment Radiation - High

[ } b. f

Area Monitor 1 220 mr/hr 1 220 mr/hr CD 7. LOSS OF POWR .

t i

a. 4.16 kv Emergency Bus Undervoltage 2450 1 105 volts with a 2450 + 105 volts with a_

j (Loss of Voltage) 2 1 0.2 second time delay 210.2 second time delay [

b. 4.16 kw Emergency Bus undervoltage 3628 1 25 volts with a 3628 1 25 volts with a 3f

=. m C1 Q.

(Degraded Voltage) 8 1 0.4 second time delay 8 1 0.4 second time delay BB mm t 33 l c+ &

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TAlllE 4.3-? (Ccatinued)

INGINffRfD SAffTY FIATIRf ACTtlATION SYSTfM INSTRtMf MTATION StRVfill ANCF Rf0t!!RfMINIS Q

G g CHANNEL. MODES IN )AlIDI ,

H CliANNE'. DIANNEL FUNCTIONAL StRVEILUueCE p FUNCTIONAL llNIT DifCK CAIIIWATION TFST Rf0tIIRfD y 5. CONTAI M NT StMP RECIRCtLATION (R.b)

4. Manual RAS (Trip Buttons) NA NA R NA 2 b. Refueling Water Tank - Low NA R H 1, 2, 3 H c. Automatic Actuation Logic NA NA M(1) 1. 2, 3

~

6. CONTAIMNT PtRE VALVES ISOLATION  !
a. Manual (Purge Valve Control Switches) M NA R NA
b. Containment Radiation - High S R M 6 Area Monitor u

} 7. LOSS Of POWER w

a. 4.16 kw Emergency Bus Undervoltage NA R M 1, 2, S 4

w (toss of Voltage) i b. 4.16 kw Emergency Bus Undervoltage (DegradedVoltage) NA R M 1. 2, 3 i

4

8. CVCS ISOLATION M>

Mg West Penetratton Room / Letdown 3 Heat Exchanger Room Pressure - High NA R M 1, 2, 3, 4 5

3 9. AUKILIARY FEEDWATER e

2

,o a. Manual (Trip Buttons) NA NA R NA
b. Steet Generator Level - Low $ R - M 1, 2, 3 g c. Steam Generator a P - High S R M 1, 2, 3 g , d.

Automatic Actuation Logic NA NA M(1) 1, 2, 3 s

ba N

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CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) .

4.6.4.1.2 Each isolation valve specified in Table 3.6-1 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per refueling interval by: l

a. Verifying that on each containment isolation Channel A or Channel B test signal, each required isolation valve actuates to its isolation position,
b. Verifying that on each Safety Injection Actuation Channel A or ~~~

Channel B test signal, each required isolation valve actuates to its isolation position.

4.6.4.1.3 The isolation time of each power operated or automatic valve of Table 3.6-1 shall be Jetermined to be within its limit when tested pursuant to Technical Specification 4.0.5.

e f' CALVERT CLIFFS - UNIT 1 3/4 6-18 Amendment No. E//7E//JE,

n T_Alli F 3.Er1 (Contimwwi) r-

< CONTAINMfMT 1501ATION VAlVfS S

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m ITNEIRA! the ISOLAll0N ISOLATION VALVE ISOLATION G1 NiMIf R CitANNf I $ IDF NTIFICATION NO. IUNCTION TIW (SFCDNDS}

C 7A NA Blind Flange ILRT NA NA ILRT-1 NA 78 NA Blind Flange ILRT NA N.* ILRT-2 NA 8 SIAS A EAC-5462-HOV Contaiment Norcul Sump i 13 y SIAS B EAO-5463-H0V 1 13 4

G SI-340 Containment Spray h 9 NA NA SI-326 NA NA 10 NA SI-330 Containment Spray NA NA SI-316 NA e

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I TAHIE 3.6-1 (Cnntirral) .

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'q PfMEIRAIION ISOLATICII ISOLATI001 VALVE ISOLATION

] INOGWR CHANNIlS IDINTIFICATION NO. FtlNCTION Tiff (SFCONDS) c 1S' 51AS A RE-S291-CV Purge Air Monitor 17 Z

. SIAS B RE-S292-CV 17 4

16 CIS A CC-3832-CV Component Cooling Vater Inlet i 18 18 CIS B CC-3833-CV Conponent Cooling Water Outlet i 18 w

} 19A NA IA-337 Instrument Air NA CIS A IA-2080-MOV i 13 to 198 fiA PA-1040* Plant Air NA NA PA-1044* NA 20A NA N -344 Nitrogen Supply NA 2

, g NA N -612-CV*

2 NA 1

8 NA N -622-CV* NA 2

g NA N -632-CV*

2 NA 3 NA N -642-CV* NA 2

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4 4

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Tant E 3.6-1 (Continual) m 3=

E rri CONTAIN>fMT IS0tATION VAlVFS

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Q PfhEIRATION ISOLATION ISOLATION VALVE ISOLA) ION

] Nt Mii R CHANNftS IDIhTIFICATION NO. F1MCTION TI W (STCON05) c 44 NA FP-141-A F tre Protectton NA Z NA FP-141-B NA H NA FP-6200-MOV* NA w

47A NA PS-6540A-SV* Hydrajen Sample Outlet NA NA PS-6507A-SV* NA w 47B NA PS-6540E-SV* Hydrvjen Sample Outlet NA

) NA PS-6507E-SV* NA

?

to W 47C NA PS-6540F-SV* Hydrogen Sample Outlet NA NA PS-6507F-SV* NA y 470 NA PS-6540G-SV* Hydrogen Sample keturn NA Q NA PS-6507G-SV* NA a

a a

2 48A SIAS-B HP-6900-MOV(3) Containment Vent Isolation i 15 P SIAS-A HP-6301-MOV(3) i 15 w

ba M .

A m

A

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S

. m r

1 TAIMF 3.6-1 (Contir m f) -

n 3>

_ Q rri CONTAINE NT IS0tATION VAlVf5

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!$0iATION ISOLATION Q PENE1 RATION ISOLAll0N VALVE  ;

TI E (SICONDS)

] NiseFR CHANNFtS JOINTIFICATION NO. FilNCTION i

61 NA SFP-176 Refueling Pool Outlet NA Z NA SFP-174 NA H NA SFP-172 NA

  • NA SFP-189 NA 62 SIAS A PH-6S79-MOV Containment Heating Outlet < 13 g g 64 NA PH-376 Containment Heating Inlet NA l

1, N

4 m

l 4

  • May be open on an intermittent basis under adninistrative control.

! m (1) Manual or remote valve which is closed during plant operation.

(2) May be opened below 300 F to establish shutdown cooling flow.

y (3) Contatrunent vent isolation valves shall be opened for containment pressure control, airborne radioactivity control, and surveillance g testing purposes only.

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I REFUELING OPERATIONS CONTAINMENT PENETRATIONS LIMITING CONDITION FOR OPERATION I I

3.9.4 The containment penetrations shall be in the following status:

a. gy uipment door closed and held in place by a minimum of four
b. A miniaum of one door in each airlock is closed *, and
c. Each penetration providing direct access ' rom the containment ,

atmosphere to the outside atmosphere shall be either: j

1. Closed by an isolation valve, blind flange, or manual valve, or
2. Be capable of being closed by an OPERABLE automatic containment purge valve.

APPLICABILITY: Durina CORE ALTERATIONS or movement of irradiated fuel witnin the containment.

ACTION:

above specifgcat on not satisfied g immediately WithtgegyquirementsofthyNSn I N!bSat d f !$ $ $ N c $$a T p WV S n$ of h !$hication 3.0.3 are not applicab e.

SURVEILLANCE RE0VIREMENTS b

5 dr eb k Oe e $h  ! 5k! So ehSk$ a$ c H07 58P 8 P 1:[e of being Yo t th a h $$ e !$ "h N Sys b $n klTERATSONSormovementofirrabiate0fu!$inthecontainmentby:

a. Verifying the penetrations are in their closed / isolated condition, or j
b. Demonstrating that the containment purge valves are OPERABLE by: l
1. l VerifyinS18 or Chann test sianalthat on each Con mentRadiationimentpurgeHigh requir d centa Channel A i valves actuate to thsir Is ion pos tion, an '

2.

g gi g + g gntainment purge valve isolation occurs on 4.9.4.2 The isolation tim gegminedtobes7seconbs of hen eachtested containment pursuanku tSe valvicagall bSpecification Techn 4.9.4.3 "he c ntai ment pur e val es sha 1 be demonstrated OPERABLE rior to eturn'ng t e va ves to a tomat c serv ce fter maintenanc repai or l rep ac e on the tua g {ement o gwork is perc, orgy per orma er c rcult a cycg g gva ve ver gng testonanitsassocite o

The emergency escape hat:h temporary closure device is an acceptable replacement Tor that air ock door.

l CALVERT CLIFFS - UNIT 1 3/4 9-4 Amendment No. JpE,

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l

. 1 Technical Specification 3.9.9 was deleted by Amendment No.

CALVERT CLIFFS - UNIT 1 3/4 9-9 Amendment No. 61,

3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 BORON CONCENTRATION The limitations on minimum boron concentration (2300 ppm) ensure that:

1) the reactor will remain subcritical during CORE ALTERATIONS, and 2) a uniform boron concentration is maintained for reactivity control in the water volumes having direct access to the reactor vessel. The limitation on Keff f no greater than 0.95 which includes a conservative allowance for uncertainties, is sufficient to prevent reactor criticality during refueling operations. . _ .

3/4.9.2 INSTRUMENTATION The OPERABILITY of the source range neutron flux monitors ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core.

3/4.9.3 DECAY TIME The minimum requirement for reactor subcriticality prior to movement of irradiated fuel assemblies in the reactor pressur e ves:ci cr.:urc: th:t sufficient time has elapsed to allow the radioactive decay of tne short lived fission products. This decay time is consistent with the assumptions used in the accident analyses.

3/4.9.4 CONTAINMENT PENETRATIONS The OPERABILITY of the containment purge valves ensures these valves will be automatically isolated upon detection of high radiation levels within the containment. The requirements on containment penetration closure and OPERABILITY ensure that a release of radioactive material within containment will be restricted from leakage to the environment. The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization potential while in the REFUELING MODE.

3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity condition during CORE ALTERATIONS.

CALVERT CLIFFS - UNIT 1 Amendment No. A8, l Amendment No. II, CALVERT CLIFFS - UNIT 2 B 3/4 9-1

REFUELING OPERATIONS BASES 3/4.9.6 REFUELING MACHINE OPERABILITY ,

The OPERABILITY requirements for the refueling machine ensure that: (1) the refueling machine will be used for movement of CEAs and fuel assemblies, (2) the refueling machine has sufficient load capacity to lift a CEA or fuel assembly, and (3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel assembly and CEA over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array.

This assumption is consistent with the activity release assumed in the accident analyses.

3/4.9.8 COOLANT CIRCULATION The requirement that at least one shutdown cooling loop be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140 F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification.

The requirement to have two shutdown cooling loops OPERABLE when there is less than 23 feet of water above the core ensures that a single failure of the operating shutdown cooling loop will not result in a complete loss of decay heat removal capability. With the reactor vessel head removed and 23 feet of cater above the core, a large heat sink is available for core cooling, thus in the event of a failure of the opecating shutdown cooling loop, adequate time is provided to initiate emergency procedures to cool the core.

3/4.9.9 Technical Specification 3/4.9.9 was deleted by Amendment No. .

I 1

l l

I l

CALVERT CLIFFS - UNIT 1 Amendment No. EE, i CALVERT CLIFFS - UNIT 2 B 3/4 9-2 Amendment No. ES,  ;

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION PAGE 3/4.9.4 CONTAINMENT PENETRATIONS 3/4 9-4 ',

3/4.9.5 COMMUNICATIONS 3/4 9-5 i 3/4.9.6 REFUELING MACHINE OPERABILITY 3/4 9-6 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORAGE P00L BUILDING 3/4 9-7 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION 3/4 9-8 3/4.9.9 DELETED 3/4 9-9 3/4.9.10 WATER LEVEL - REACTOR VESSEL 3/4 9-10 3/4.9.11 SPENT FUEL P0OL WATER LEVEL 3/4 9-11 3/4.9.12 SPENT FUEL P0OL VENTILATION SYSTEM 3/4 9-12 3/4.9.13 SPENT FUEL CASK HANDLING CRANE 3/4 9-16 3/4.9.14 CONTAINMENT VENT ISOLATION VALVES 3/4 9-17 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN 3/4 10-1 3/4.10.2 MODERATOR TEMPERATURE C0 EFFICIENT, CEA INSERTION AND POWER DISTRIBUTION LIMITS 3/4 10-2 3/4.10.3 NO FLOW TESTS 3/4 10-3 3/4.10.4 CENTER CEA MISALIGNMENT 3/4 10-4 3/4.10.5 COOLANT CIRCULATION 3/4 10-5 CALVERT CLIFFS - UNIT 2 VIII Amendment No. E//JJ//EE/

7E,

INDEX BASES SECTION PAGE 3/4.9.5 COMMUNICATIONS B 3/4 9-1 B 3/4 9-2  ;

3/4.9.6 REFUELING MACHINE OPERABILITY 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING B 3/4 9-2 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION B 3/4 9-2 3/4.9.9 DELETED B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND SPENT FUEL P0OL WATER LEVEL B 3/4 9-3 3/4.9.12 SPENT FUEL P00L VENTILATION SYSTEM B 3/4 9-3 3/4.9.13 SPENT FUEL CASK HANDLING CRANE B 3/4 9-3 3/4.9.14 CONTAINMENT VENT ISOLATION VALVES B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS B 3/4 10-1 3/4.10.3 N0 FLOW TESTS B 3/4 10-1 3/4.10.4 CENTER CEA MISALIGNMENT 3 3/4 10-1 3/4.10.5 COOLANT CIRCULAlION B 3/4 10-1 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS B 3/4 11-1 3/4.11.2 GASE0US EFFLUENTS B 3/4 11-2 3/4.11.3 SOLID RADI0 ACTIVE WASTE B 3/4 11-5 3/4.11.4 TOTAL DOSE R 3/4 11-5 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM B 3/4 12-1 3/4.12.2 LAND USE CENSUS B 3/4 12-1 3/4.12.3 INTERLABORATORY COMPARIS0N PROGRAM B 3/4 12-2 CALVERT CLIFFS - UNIT 2 XIII Amendment No. $//JJ//JEl E21/EE,

r l

Q T m E 3.3-3 fContinurd) r-l g INGINffRED SAFETY FIATtRE ACTUATION SYSTEM INSTRtMfMTATION

--t n

r-

~ MINIltM n

OtANNELS APPLICABLE

, ] TOTAL NO. CHAlmELS IUNCTIGNAl tali 0F OtAlmf t S ' TO TRIP OPIRABtE Mn0FS ACTION c

2 6. CONIAllNENT PLRff VALVES ISOLATI0ft

-e N a. Manual (Purge Valve Control Switches) 2/ Penetration 1/ Penetration 2/ Penetration 6** 8

b. Containment Radiation -

! Eigh Area Monitor 4 2 3 6** 8

+

g 7. LOSS OF POE R N

, 4 g a. 4.16 kw Emergency Bos L Undervoltage (Loss of W Voltage) 4/ Bus 2/ Bus 3/ Bus 1, 2. 3 7*  !

b. 4.16 kv Emergency Bus 2

Undervoltage (Degraded Voltage) 4/ Bus 2/ Bus 3/ Bus 1, 2. 3 7*

Dk Nm N3

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I et

    • Must be OPERABLE only in MODE 6 when the valves are required OPERABLE and they are open.

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TARtE 3.3-4 (Continued) .

nn 2n 2D (NGINffRfD SAffiY ffAltstf ACTilATION SYSTEM INSTRISfMTATION TRIP VAltifS QQ mm -

i NM

-4 mn ALLadABLE r r-

-~ fuMCT100tAl (NilT TRIP VAX(E val (KS mn mn

<n tn

5. CONIAlletNT StMP RECIRCLA.All0N (RAS)

CC

a. Manual RAS (Trip Buttons) Not Applicable Not Applicable 23 4

to - b. Refueling Water Tank - Low 1 24 inches above 3 24 inches above tank bottom tank bottom k

6. CONIAIINENT Plate VALVES ISOLATION
a. Manual (Purge Valve Control Switches) Not Applicable Not Applicable a

(A) g b. Containment Radiation - High Area Monitor 1 220 mr/hr 1 220 mr/hr i 5 7. LOSS OF POWR

a. 4.16 kw Emergency Bus Undervoltage 2450 1 ?OS volts with a 2450 1 105 volts with a (Loss of Voltage) 2 1 0.2 second time delay 2 1 0.2 second time delay
b. 4.16 kw Emergency Bus Undervoltage 3678 1 25 volts with a 3628 1 25 volts with a gg (Degraded Voltage) 8 1 0.4 second time delay 810.4 second time delay 3 3 CL CN 33 i em 4*

33 G to

! 22

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IN D NTN

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TAREE 4.3-7 (Continuni)

O INGINffRID SAffTY FTAltRE ACTilATION SYSTEM INSTRIMfMTATION StRVfill ANCE Rf0tifRENfMTS G

$ OtANKL M00ES IN WHIOt .

OlANNEL OlANKL IUNCTIONAL StRVEILLANCE h ftlNCTIONAl llNIT OffCK CAtIIRATION TFST RIOUIRfD

$ S. CONTAINK NT SlMP RECIRC11ATION (RAS) c- a. Manual RAS (Trip Buttons) NA NA R NA 3 b. Refueling Water Tank - Low NA R H 1, 2, 3

c. Autanatic Actuation Logic NA NA M(1) 1, 2, 3 ru
6. CONTAINENI PtRE VALVES ISOLATION
a. Manual (Purge Valve Control Switches) NA NA R NA
b. Containnent Radiation - High S R M 6 Area Monitor w

) 7. LOSS OF POWER w

4

s. 4.16 kw Emergency Bus Undervoltage NA R H 1, 2, 3 (Loss of Voltage)
b. 4.16 kw Energency Bus Undervoltage (DegradedVoltage) NA R H 1, 2, 3
8. CVCS ISOLATION ha g D en West Penetration Room / Letdown D S. Heat Exchanger Roan Pressure - High NA R H 1, 2, 3, 4

%B

- to fo 9. AtRILIARY IEEDWATIR i z

? a. Manual (Trip Buttons) NA NA R NA ba b. Stean Generator Level - Low S R M 1, 2, 3 Q c. Stean Generator A P - High S R H 1, 2, 3 D

A

. d. Autanatic Actuation Logic NA NA M(1) 1, 2, 3 N

< ha

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.6.4.1.2 Each isolation valve specified in Table 3.6-1 shall be demonstrated OPERABLE during the COLD SHUTD0WN or REFUELING MODE at least once per refueling interval by:

a. Verifying that on each containment isolation Channel A or Channel B test signal, each required isolation valve actuates to its isolation position.
b. Verifying that on each Safety Injection Actuation Channel A or Channel B test signal, each required isolation valve actuates to its isolation position. .

4.6.4.1.3 The isolation time of each power operated or automatic valve of Table 3.6-1 shall be determined to be within its limit when tested pursuant to Technical Specification 4.0.5.

CALVERT CLIFFS - UNIT 2 3/4 6-18 Amendment No. ,47// S// S ,

i

. TARIf 3.6-1 (Continrwi) -

4 n

30 E

m CONTA110EfMT IS0l?lil0N VAlVfS

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n t r <

Q PfhEIRATION ISOLATION ISOLATION VALVE ISOLATION

] $ INeefR OiAINeft S 10fMIIFICATION NO. FllNCTION TIIE (SFCONDS) 1A NA Blind Flange ILRT NA 4

3

~

NA ILRT-1 NA N

I 18 NA Bilnd Flange ILRT NA NA ILRT-2 NA

! 8 SIAS A EAD-5462-MOV Containment Normal Sump 1 13 1

w SIAS B EAD-5463-MOV i 13 N

4 m

k 9 NA S1-340 Containment Spray NA O- NA SI-326 NA i

10 NA $1-330 Containment Spray NA NA SI-316 NA 3

i E B

i (D

3

,t o t

w N.

O l..________________ ___ _ _ _ _ . . -

s n TABIF 3,6-1 (Conttrams) ,

3D r-

% CONTAllNE NT IS0t ATION VAlVr5 5 -

n r-i PENEIRATION ISOLATION ISOLAll0N VALVE ISOLATION l M IR9WIR CHANNflS IDINTIFICATION NO, FtBICTION TI E (SFCONDS) >

g 15 SIAS A RE-5291-CV Purge Air Monitor 17 q S!AS B RE-5292-CV 17 ro 16 CIS A CC-3832-CV Component Cooling Water Inlet 1 18 1

18 CIS B CC-3833-CV Component Cooling Water Outlet i 18 l

! w N

'!

  • 19A NA IA-175 Instrument Air NA f.

f ro CIS A IA-2080-Mov s 13 1 W 198 NA PA-137* Plant Air NA NA PA-1044* NA

'g 20A NA N -347 2

Nitrogen Supply NA g

RA N -612-CV* NA 2

g NA N -622-CV*

2 NA g NA N -632-CV*

2 NA

" NA N -642-CV* NA 2

  • z 4 o i

i N N

N h

  • h.

e N

. . , . . ~ = =

--. _ - _ _ _ _ _ _ - _ _ . _ _ _ - _ __ _ _ _ - - - - - - - = _ -- - - -_ __ _ __ _ -

n IAH1f 3.6-1 (Ccatinm 1)

  • 3D r-M CONIAINT NT IS0tATION VAlVf_S N
  • n C

M PfMEIRAll0N ISOLATION ISOL ATION VALVE ISOLATION MMtf R CilANNilS IOfMTIFICATION NO. FINCil0N TIMF (SFCONOS)

E 44 NA FP-141-A Fire Protection NA N NA FP-141-B NA m NA FP-6200-H0V" NA 47A NA PS-6S40A-SV* Hydrogen Sample Outlet NA NA PS-6507A-SV* NA N #

478 NA PS-SS40E-SV* Hydrogen Sample Outlet NA NA PS-6507E-SV* NA Y

5 47C NA PS-SS40F-SV* Hydrogen Sample Outlet NA NA PS-6507F-SV* NA u$ 470 NA PS-6S40G-SV" Hydrogen Sample Return NA D$

ua NA PS-6507G-SV* NA ba 9 o m s

r+

o 48A SIAS-B HP-6900-H0V(3) Containment Vent Isolation < IS SIAS-A HP-6901-MOV(3) -< IS w

N A

M b

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1 f

n TAatE 3.6-1 (Cotinued) 3D -

CONTAINIf MT IS0t ATION VALVES w

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]M PENEIRAliDet ISOLATION ISOLATION VALVE ISOLATION InseMR OtAlmef t S IDf ulIFICAT1018 NO. FUNCTION Tilf (SFCONDS)

C 61 NA SFP-184 Refueling Pool Outlet NA 2

Q NA SFP-182 NA y NA SFP-180 NA j NA SFP-186 NA i

1 il 62 SIAS A PH-6579-MOV Containment Heating Outlet < 13 a

(a 64 NA PH-387 Containment Heating Inlet NA c.h y

  • May be open on an intennittent basis under adninistrative control.

1 (1) Manual or remote valve which is closed during plant operation.

(2) May be opened below 300 F to establish shutdown cooling flow.

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gg (3) Containment vent isolation valves shall be opened for contalrnent pressure control, airborne radioactivity control, and surveillance Q 80 testing purposes only.

o Ma h9

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to i 2 w -

N A

i N 1

N i M

  • e N -

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% r- e --un i- r ?m-- W .m-e e- ,e'%'- m w a bi r - + ~ - - - - - -

1 REFUELING OPERATIONS l CONTAINMENT PENETRATIONS l LIMITING CONDITION FOR OPERATION I

3.9.4 The containment penetrations shall be in the following status:

l

a. gy uipment door closed and held in place by o minimum of four
b. A minimum of one door in each airlock is closed *, and
c. Each penetration providing direct access from the containment I atmosphere to the outside atmosphere shal be either: i
1. Closed by an isolation valve, blind flange, or manual valve, or
2. Be capable of being closed by an OPERABLE automatic i containment purge valve. l APPLICABILITY: Durina witnin tne containment. CORE ALTERATIONS or movement of irradiated fuel ACTION-above s not satisfied WithtegquirementsofthyvinaCORpecificatiogSormovemento,fimmediately suspen a perations invo ALTERATIO irradiated f el in the containment. The provisions of Specification 3.0.3 are l not applicab e. .

1 I

SURVEILLANCE RE0VIREMENTS b

efin ebt b e$h !Sk"cfoe5Sk$anat8aftfofo"SSi[eofbeing c p or o to the $h$ e $"o "h Naysl n lu.TERATIONS or movement of krra$Iate3cfulf in the containment by:

a. Verifying the penetrations are in their closed / isolated condition, or
6. Demonstrating that the containment purge valves are OPERABLE by:
1. Verifyina t1at on each Cont inment Rad ation - High Channel A or Chann61 3 test signal, b th require containment purge valves actuate to their 1so ation posi ion, and
2. g gi g g g ntainment purge valve isolation occurs on 4.9.4.2 The i gmined to golation e 1 7 seconds time when testedcontainment of each pursuan Specification guge valvycgall Techn be 4.9.4.3 The containment pur e valves sha'1 be demonstrated OPERABLE prior fter maintenanc repair or rep ac e on the purge va to$eturningthevalves.toatomaticserv'cefvegritsassocatedpcaton,of tuator g {ement o gwork is pertorgy per ormance er circuit a cyc o ing test an veri The emergency escape hatch temporary closure device is an acceptable replacement Tor that airlock door.

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

i l

l I

Technical Specification 3.9.9 was deleted by Amendment No.

l l

l CALVERT CLIFFS - UNIT 2 3/4 9-9 Amendment No. ff,

3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 BORON CONCENTRATION The limitations on minimur boron concentration (2300 ppm) ensure that:

1) the reactor will remain subcritical during CORE ALTERATIONS, and 2) a uniform boron concentration is maintained for reactivity control in the water volumes having direct access to the reactor vessel. The limitation on Keff I no greater than 0.95 which includes a conservative allowance for uncertainties, is sufficient to prevent reactor criticality during refueling operations.

1' 3/4.9.2 INSTRUMENTATION The OPERABillTY of the source range neutron flux monitors ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core.

3/4.9.3 DECAY TIME The minimum requirement for reactor suberiticality prior to movement of irradjated fuel assemblies in the reactor pressure vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short lived fission products. This decay time is consistent with the assumptions used in the accident analyses.

3/4.9.4 CONT INMENT PEEENATIONS The OPERABILITY of the containment purge valves ensures these valves will be automatically isolated upon detection of high radiation levels within the containment. The requirements on containment penetration closure and OPERABILITY ensure that a release of radioactive material within containment will be restricted from leakage to the environment. The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization potentialwhileintheRffUEl.INGN000 crPWNic/4J0!n s t 1!! $jmi.o,@el qirement for comunications capability ensures that refueling can be promptly informed of significant changes in the -

pliit ;t .m ,

.ro ro d 'icI!y condjtion during CORE ALTERATIONS.

cal d H CLIFFS-Uldti Amendmentpo,#Po CALVLR CLlFFS - Uly 2 B 3/4 9 1 j Amendmentto.jl,

..._1 -- ,

4 REFUELING OPERATIONS BASES 3/4.9.6 REFUELING MACHINE OPERABILITY The OPERABILITY requirements for the refueling machine ensure that: (1) the refueling machine will be usrJ for movement of CEAs and fuel assemblies, (2) the refueling machine has sufficient load capacity to lift a CEA or fuel assembly, and (3) the core internals and pressare vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel assembly and CEA over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array.

This assumption is consistent with the activity release assumed in the accident analyses.

3/4.9.8 COOLANT CIRCULATION The requirement that at least one shutdown cooling loop be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140 F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core co minimize the effects of a boron dilution incident and prevent boron stratification.

The requirement to have two shutdown cooling loops OPERA 8LE when there is less than 23 feet of water above the core ensures that a single failure of the operating shutdown cooling loop will not result in a complete loss of decay heat removal capability. With the reactor vessel head removed and 23 feet of water above the core, a large heat sink is available for core cooling, thus in the event of a failure of the op3 rating shutdown cooling lcip, adequate time is provided to initiate emergency procedures to cool the core.

3/4.9.9 Technical Specification 3/4.9.9 was deleted by Amendment No. .

CM'/fRTCLIFFS-UNII1 Amendment No. EE, f' 441 r'Iffs - UNIT 2 B 3/4 9-2 Amendment No. EE, w

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