ML20062D683

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Proposed Tech Specs Correcting Inconsistencies,Providing Clarifications & Supplemental Requirements & Incorporating Updated Bases Re Containment Integrity
ML20062D683
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 11/07/1990
From:
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20062D681 List:
References
NUDOCS 9011150079
Download: ML20062D683 (18)
v • d • e


Text

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'[ 4' ATTACERENT 1 UNIT 1 REVISED

+c TECHNICAL' SPECIFICATION AND BASES'PAGES 4

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ELECTRICAL POWER Sv5TEMS SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a. One circuit between the offsite transmission network and the onsite Class 1E distribution system, and
b. One diesel generator with: ,
1. A day fuel tank containing a minimum volume of 375 gallons of fuel,
2. A fuel storage system containing a minimum volume of 18,250 gallons of fuel, and
3. A fuel transfer pump.

APPLICABILITY: MODES 5 and 6.

AC ' ION _:

With less than the above minimum required A.C. electrical power sources OPERAB.LE.;..:r-  :-f :"3':: : :t'_: 4-

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fa. kmmediately* suspend all operations involving CORE ALTERATIONS, positive reactivity changes, movement of over irradiated fuel and movement of heavy loads )

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irradiated fuel, and q Establish containment penetration closure as identified j

[b.

i in Specification 3.9.4 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and k' c. Initiate corrective actions within one hour to restore the minimum A.C. electrical power sources to OPERABLE st_atus. _ _

SUR.'EILLANCE REQUIREMENTS

4. 8.1. 2 The above required A.C. electrical power sources shall be demonstrated OPERABLE by the performance of each of the Surveillance Requirements of 4.8.1.1.1 and 4.8.1.1.2 except for requirement 4.8.1.1.2a 5.

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  • Performance of Action a. shall not preclude completion of actions to establish a safe conservative position.

CALVERT CLIFFS-UNIT 1 3/4 8-5

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

ELECTRICAL POWER SYSTEMS A.C. O!$TRIBUTION - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.2.2 As a minimum, the following A.C. electrical busses shall be OPERABLE and energized from sources of power other than a diesel gene-rator but aligned to an OPERABLE diesel generator: ,

1 4150 volt Emergency Bus 1 - 480 volt Emergency Bus 2 - 120 voit A.C. Vital Busses .

APPLICABILITY: MODES 5 and 6 ACTION:

With less than the above complement of A.C. busses OPERABLE and energized; x;_Z : . .

^"~':"__:::7 : 'T::::?" J ;r '- 0 5;.. ..

l-( Immediately*

ALTERATIONS, suspend all positive reactivity changes, operations involving movement of CORE i-I i irradiated fuel and movement of heavy' loads over irradiated

'f i fuel, until the minimum required A.C. busses are restored to  ;

OPERABLE and energized status, and }

I

b. Establ.'ah containment penetration closure as identified in

.- Specification 3.9.4'within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and [I

c. Initiate corrective actions within one hour to restore the <

I minimum A.C. electrical busses to OPERADLE and energized  ;.

status. ^

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p SURVEILLANCE RE0VIREMENT5~

1 L 4.8.2.2 The specified A.C. busses shall be determined OPERABLE and energized from A.C. sources other than the diesel generators at least once per 7 days by verifying correct breaker alignment and indicated power availability. ___

  • Performance of Action a. shall not preclude completion of actions to establish a safe con. servat.ve position.

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CALVERT CLIFFS-UNIT 1 3/4 8-7 J

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I IELECTRICAL COWER SYSTEMS 0.C. O!STR:30 TION SHUTDOWN ,

i LIMITING CON 0! TION FOR OPERATION 3.3.2.4 As a minimum, the following 0,C. electrical equipment and busses

shall
e energized anc OPERABLE:

2 - 125-volt D.C. busses, and J I

2 - 125-volt battery banks, one of wnich may be the Reserve Battery, and one associated charcer per bank supplying tne above O.C. busses.

APPLICABit.!TY: MODES 5 and 6.

ACTION:  ;

With less than the above complement of D.C. equipment and busses OPERABLE!

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- _ __ - , l b Immediately* suspend all operations involving CORE
h. ALTERATIONS, positive reactivity changes, movement of (

j irradiated fuel, and movement of heavy loads over [i i irradiated fuel until the minimum required D.C.

[l equipment and busses are restored to OPERABLE status,

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b. Establish containment penetration closure as identified in Specification 3.9.4 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and p  ;

, c. Initiate corrective actions within one hour to restore the minimum D.C. equipment and busses to OPERABLE j}

I status.

SURVEILLANCE REQUIREMENTS 1

4.8.2.4.1 The above required 125-volt D.C. busses shall be determined OPERABLE and energi:ed 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 OPERA 3LE per Surveillance Requirement 4.8.2.3.2.

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  • Performance of Action a. shall not preclude completion of actions to establish a safe conservative position.

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CALVERT CLIFFS - UN!T I 3/4 3-11 Amendment No.114 l l

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A REFUELING OPERATIONS 4

CONTAINMENT PENETRATIONS ,

LIMITING CONDITION FOR OPERATION 3.9.4 The containment penetrations shall be in the following status:-

a. The equipment door closed and held in place by a mininam of four bolts, i
b. A minimum of one door in each airlock is closed.* and
c. Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either:
1. Closed by an isolation valve, blind flange, or manual j valve, or 1

, 2. Be capable of being closed by an OPERABLE automatic contain- l ment purge valve. -

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a. Verifying the penetrations are In their closed / isolated condition, or
b. Testing the containment purge valves per the applicable portions of Specification 4.6.4.1.2.
  • The emergency escape hatch temporary closure device is an acceptable replace-

_ ment for_ that airlock door. -- _

(en _REPI3C [WITH INSERT ON FOLLOUING PAGE.

CALVERT CLIFFS - UNIT 1 3/4 9-4 - Amendment No 108 .

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4 1

1 INSERT FOR LCO 3.9.4 ACTION l 1

CONTAINMENT PENETRATIONS '

l i

l APPLICABILITY: During CORE ALTERATIONS, positive reactivity changes, movement of irradiated fuel within the containment, movement of heavy loads over irradiated fuel within the containment building, and electrical power distribution  ;

system degradation as required by Specification 3.8.2.2 and 3.8.2.4.  !

ACTION:

-a.

With the requirements of the above specification not satisfied, .immediately** suspend all operations involving CORE ALTERATIONS, positive reactivity changes, movement of irradiated fuel within the containment and movement of heavy loads over irradiated i' fuel.within the containment building.-

b. The provisions of Specification 3.0.3 are not applicable.

L t

i. SURVEILLANCE REQUIREMENTS i

.4.9.4 Each of the above required containment l

penetrations shall be determined to be either in its L closed / isolated condition or . capable of being closed by an l ^ OPERABLE automatic containment purge valys within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to.the-start of and at least once per 7 days during l

CORE ALTERATIONS, positive reactivity changes, movement of n . irradiated fuel in the' containment, movement of heavy loads

  • i over irradiated fuel within the containment building, or electrical power distribution system degradation by: ,

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    • Performance of A tion a. shall not preclude completion l of actions to es.ablish a safe conservative position.

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3/4.6 CONTA!W4ENT $YSTEMS l-L

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3/4.6.1 PRIMARY CONTA!W4ENT I:

3/4.6.1.1 CONTA!W4ENT INTESRITY

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[In Modes 1, 2, 3, and 4, primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the  ;

[I containment atmosphere will- be restricted to those leakage (

( paths and associated leak rates assumed in the accident }

l I analyses. This restriction, in conjunction with the leakage 4 rate will limit the site boundary radiation l 4' doses - to withinlimitation, the limits of 10 CFR 100 during accident p ,

l conditions. In Modes 5 and 6, the probability and q l I

consequences of these events are reduced because of the l Reactor Coolant. System (RCS) pressure and temperature <

)

[, . limitations of these modes, by preventing operations which {

i-could lead to a need for containment isolation, and by i

providing containment isolation through penetration closure, j
  • i 3/4.6.1.2 CONTAINNENT LEAXASE The limitations on containment leakage rates ensure that the total containment leakage vol me will not exceed the value assumed-in the accident analyses at the peak accident pressure. Pa . As an added con-

- servatism, the measured overall integrated leaks rete is further limited to < 0.75 L or = 0 during perforsence of the periodic tests to accoun.75 t fof' p(asL applicableossiple degradation of the contain ment leakage barriers between leakage tests.

The surveillance testing for measuring leakage rates are consistent with the requirements of Appendix 'J" of 10 CFR 50. ,

3/4.6.1.3 CONTAINMENT AIR LOCKS ,

l' 1he 11mitations on closure and leak rate for the containment air locks am required to meet the restrictions on CONTAINMENT INTEGRITY and cor.tainment leak rate. Surveillance testing of the air lock seals

  • provi6es assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.

CALVERT CLIFFS - UNIT 1 8 3/4 6-1 c - . - - - .c ~.- , , . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

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

1) the reactor will remain suberitical 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 K

ff of no greater than 0.95 which includes a conservative allowance for uIncertainties, is sufficient to prevent reactor criticality during refueling operations.

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

3/4.9.3 DECAY TIME The minimum requirement for reactor suberiticality prior to movement of irradiated 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 cons 4 stent with the assumptions used in the accident analyses. .

REPIACE WITH INSERT ON FOLLOWING PAGE.

3/4.9.4 CONTAINMENT PENETRATIONS _

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

CALVERT CLIFFS - UNIT 1 B 3/4 9-1 Amendment No. 48

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t l INSERT FOR BASES 3/4.9.4 CONTAINMENT PENETRATIONS During CORE ALTERATIONS or movement of irradiated fuel within containment, a release of fission product radioactivity to the environment must be prevented. During Modes 1, 2, 3, and 4, this is accomplished by maintaining CONTAINMENT INTEGRITY as described in LCO 3.6.1. In other situations, the potential for containment pressurization as a result of an accident is not present, therefore, less stringent requirements are needed to isolate the containment from the outside atmosphere.

The containment structure serves to contain fission product radioactivity which may be released from the reactor core following a Design Basis Accident (DBA), such that offsite radiation exposures are maintained within the requirements

- of 10 CFR 100. Additionally, this structure provides radiation shielding from the fission products which may be presor.t in the containment atmosphere following accident conditions.

4 ATTACHMENT 2 UNIT 2 REVISED TECHNICAL SPECIFICATION AND BASES PAGES i

3/4 8-5 3/4 8-7 3/4 8-11 3/4 9-4 B3/4 6-1 B3/4 9-1

ELECTRICAL POWER S,Y,, STEMS

+

SHUTDOWN *

~

LIMITING CONDITION FOR OPERATION

3. 8.1. 2 As a minimum, the folloding A.C. electrical power sources she.11 be OPERABLE: .
a. One' circuit between the offsite transE.ission network and the onsite Class 1E distribution system, and
b. One diesel generator with:
1. A day fuel tank containing a minimum volume of 375 gallons of fuel, i 2. A fuel storage system containing a minimum volume of 18,250 gallons of fuel, and  ;
3. A fuel transfer pump.

I L APPLICABILITY; MODES 5 and 6.

.e ACTION:

g- .

!' With less than the above minimum recuiret A.C. electrical power sources

" "* ^

OPERABLE;  :-M':^^ ' '

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Immediately* suspend all operations involving CORE ]

[a~. ALTERATIONS, positive reactivity changes, movement' of j

{

irradiated fuel and movement of heavy loads over (

p-I irradiated fuel,.and j

[) b. -Establish containment penetration closure as identified Ill l in Specification 3.9.4 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and

'>c. Initiate correctiveelectrical actions within one hour to restore power sources to OPERABLE lI the minimum A.c. l status.

SURVE!LLANCE REQUIREMErlTS

.S.1.2 The 'above required A.C. electrical power sources shall be I

demonstrated OPERABLE by the performance of each of tha Surveillance Requirements of 4.5.1.1.1 and 4.8.1.1.2 except for requirement 4.8.1.1.2a.5.

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  • Performance of Action a. shall not preclude completion J l

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of actions to establish a safe conservative position.

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( li ;ALs'ERT CLIFFS-Uh'IT 2 , 3/4 E 5

1 ELECTRICAL POWER SYSTEMS A.C. DISTRIBUTION - SHUTDOWN I

LIMITING CONDITION FOR OPERATION

)

3.8.2.2 As a minimum, the following A.C. electrical busses shall be ,

OPERABLE and energized from sources of power other than a diesel gene- l rator but aligned to an OPERABLE diesel generator:

1 - 4160 volt Emergency Bus -

1 - 480 volt Emergency Bus 2 - 120 volt A.C. Vital Busses APPLICABILITY: MODES 5 and 6 ACTION:

With less than the above complement of A.C. busses OPERABLE and energized;

l.  ::r$ :' 00"T".:. .;,J * :~::"'"' i;!.'.. C h r :.

fa . Immediately* suspend all operations involving CORE ALTERATIONS, positive reactivity changes,

' movement of r

irradiated fuel and movement of heavy loads over irradiated fuel, until the minimum required A.C. busses are rsstored to '

. OPERABLE and energized status, and j i

'b. Establish containment penetration closure f i

' as identified in

~ Specification 3.9.4 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and j

}

I; c.

i Initiate corrective minimum A.C. electrical actions within one-hour to restore thei

"

  • i busses to OPEkABLE and d I g

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status, r energizej .

l SURVEILLANCE REQUIREMENTS '

l t

4.8.2.2 The specified A.C. busses shall be determined OPERABLE and energized from A.C. sources other. than the diesel generators at least once per 7 days by verifying correct. breaker alignment and indicated power availability.

7 - - -- _

4

  • Performance of Action a. shall not ;3reclude completion of l  !

actions to establish a safe conservatnve position.

i (

CALVERT CLIFFS-UNIT 2 3/4 8-7

a

, i llELECTRICALPOWERSYSTEMS 1

1 l0.C.DISTRIBUT!ON-SHUTDOWN i LIMITING CONDITION FOR OPERATION i

3.8.2.4 As a minimum, the following 0.C. electrical equipment and bussas shall be energized and OPERABLE:

2 - 125-volt D.C. ousses, and 2 - 125-volt battery banks, one of whien may be the Reserve Battery, and one associated charger per bank supplying the above O.C. busses.

APPLICABILITY: MODES S and 6.

ACTION: ',

With n

..._ le.ss tha.n.t.he abov.e. complemen.t of D.C. equiement and busses OPERABLEj n ..

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a. Immediately* suspend all operations involving CORE j ALTERATIONS, positive reactivity changes, movement of 4

{ irradiated fuel, and movement of heavy loads over d

) irradiated fuel until the minimum required D.C. I I

I equipment and busses are restored to OPERABLE status, and I) i

b. Establish containment penetration closure as identified l) in specification 3.9.4 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and I

[t

c. Initiate corrective actions within one hour to restore I> the minimum D.C. equipment and busses to OPERABLE status.

j i SURVEILLANCEREQUiREMENTS 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 recuired 125-volt battery banks and chargers shall be demonstrated OPERABLE per Surveillance Requirement 4.8.2.3.2.

l

  • Performance of Action a. shall not preclude completion

/L_ _

of actions to establish a safe conservative position.

CALVERT CLIFF 3 - UNIT 2 3/4 8-11 Amendment No. 97 1.

1,.x , _ _ . . - . _ . . . . - . . _ - . . . - , . _ - , . , . . . - . . . . . , . , . _ .. _. -_ - _ , . - . --

. _ _ - - _ _ _ _ _. __.___ _ __ _ -. ~ ___ ___ _. _ _ _ __ _ _ _ _

REFUELING OPERATIONS CONTAINMENT PENETRATIONS LIMITING CONDITION FOR OPERATION _

3.9.4 The containment penetrations shall be in the following status:~

a. The equipment door closed and held in place by a minimum of four bolts,
b. A minimum of one door in each airlock is closed *, and
c. Each penetration providing direct access from the containment atmosphere to the outside atmosphern shall bu either:
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.  ;

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1 j REPLACE WITH INSERT ON FOLI4WINC PAGE. d I h i i

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a. Verifying the penetrations are 1n their closed / iso 19 ted condition, or
b. Testing the containment purge valvec per the applicable portions of Specification 4.6.4.1.2.
  • The emergency escape hatch temporary closure device is an acceptable replacement for tnat airlock door. _

p _- __

~ _ - , _

44 REPLACE WITH INSERT ON FOLI4 WING PAGE.

__ /

CALVERT CLIFFS - UNIT 2 3/4 9-4 Amendment No. 91 l

e

INSERT FOR LCO 3.9.4 ACTION i CONTAINMENT PENETRATIONS APPLICABILITY: During CORE ALTERATIONS, positive reactivity changes, movement of irradiated fuel within the containment, movement of heavy . loads over irradiated fuel within the containment building, and electrical power distribution I system degradation as required by Specif:. cation 3.8.2.2 and 3.8.2.4.

i l

l ACTION:

a. With the requirements of - the above specification not satisfied, immediately** suspend all operations involving CORE ALTERATIONS, positive reactivity changes, movement of irradiated fuel within the containment and movement of heavy loads over irradiated i fuel within the containment building.
b. The provisions of Specification 3.0.3 are not ,

applicable. I L

SURVEILLANCE REQUIREMENTS

j. 4.9.4 Each of the above required
  • containment n penetrations ,shall be determined to be either in its closed / isolated condition Jr capable of being closed by an 'l

! OPERABLE automatic containment- purge valve within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the start of and at least once per 7 days during

[@L CORE ALTERATIONS, positive reactivity changes, movement of irradiated fuel in the containment, movement of heavy loads '

over irradiated fuel within the containment building, or ,

electrical power distribution system degradation by:

1 1

    • Performance of Action a. shall not preclude completion I of actions to establish a safe conservative position. l L i L

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3/4.6 CONTAINMENT SYSTEMS

. BASE 5 -

3/4.6.1 PRIMARY CONTAINENT 3/4.6.1.1 CONTAINENT INTEGRITY l- .. _ _ . _ . . . _ _ _ _ _ _ . ___m_. m_ __ . _ _ _ _ s _ m _

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In Modes 1, 2, 3, and 4, primary CONTAINMENT INTEGRITY )

ensures that the release of radioactive materials from'the containment atmosphere will be restricted to those leakage [

paths and associded leak rates assumed in the accident g analyses. This restriction, in conjunction with the leakage 4 rate limitation, will limit the site boundary radiation j 1 doses to within the limits of 10 CFR 100 during accident i I I

conditions. In Modes 5 and 6, the probability and I

[ consequences of these events are reduced because of the h 1 Reactor Coolant System (RCS) pressure and temperature I limitations of these modes, by preventing operations which I

/ could lead to a need for containment isolation, and by h

(( providing containment isolation through penetration closure,- , _

3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containsent leakape volume will not exceed the,value assumed in the accident analyses > at the peak accident pressure, pa . As an added con-servatism, the measured overall integrated leakage rate is further limited to < 0.75 L or < 0 t fof p(as applicable) during perfomance of theperiodictestsloaccoun.75L ossible degradation of the contain-ment leakage barriers between leakage tests.

)

The surveillance testing for measuring leakage rates are consistant l with the requirements of Appendix "J" of 10 CFR 50.

3/4. 6.1.3 CONTAIhMENT AIR LOCK 3 The limitatior.- on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY-and containment leak rate. Surveillance testing of the air lock seals

! - provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock' leakage tests.

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

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EASES 1

3/1.9.1 BCRON CONCENTRATION The limitations on minimum boron concentration (2300 ppm) ensure that
1) the reactor will remain suberitical during CORE ALTERATIONS, and 2) a uniform boren concentration is maintained for reactivity control in the water volumes having direct access to the reactor vessel. The limitation on X,g of no greater than 0.95 which includes a conservative allowance for uncer ainties, 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 monitering 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 I of irradiated fuel assemblies in the reactor pressure vessel ensures the' ,

sufficient time has elapsed to allow the radioactive decay of the short )

lived fissien products. This decay time is cons.istent with the assumptions  !

used in the accident analyses. l 3/a.0.4 CON ~AINMENT PENETRATIONS hEPLACE WITH INSE -

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3/4.9.5 C CtEUNI CAT !ON,S., l The requirement for communications capability ensures that refueling i station personnel can be promptly informed of significant changes in the '

i facility status or core reactivity conditien during CORE ALTERATIONS.

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INSERT FOR BASES 3/4.9.4 CONTAINMENT PENETRATIONS During CORE ALTERATIONS or movement of irradiated fuel within containment, a release of fission product radioectivity to the environment must be prevented. During Modes 1, 2, 3, and 4, this is accomplished by maintaining CONTAINMENT INTEGRITY as described in LCO 3.6.1. In other situations, the potential for containment pressurization as a result of an accident is not present, therefore, less stringent requirements are needed to isolate the containment from the outside atmosphere.

The containment structure serves to contain fission product radioactivity which may be released from the reactor core following a Design Basis Accident (DBA), such that offsite radiation exposures are maintained within the requirements of 10 CFR _100. Additionally, this structure provides radiation, shielding from the fission products which may be present in the -containment atmosphere following accident conditions.

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