Text

Proposed Tech Specs Affecting Requirements for low-temp Overpressure Protection
	ML20249B396
Person / Time
Site:	Catawba
Issue date:	06/15/1998
From:	; DUKE POWER CO.
To:	;
Shared Package
ML20249B394	List: ML20249B393; ML20249B396;
References
	NUDOCS 9806230025
	Download: ML20249B396 (130)
	v • d • e

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Attachment la Revised Current Technical specification 88 r Cata h Unit 1 l

9906230025 990615 PDR ADOCK 05000413 P PDR L - - - - - - - _ _

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION ILA91 TABLE 4.4-5 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM WITHDRAWAL SCHEDULE .................. 3/4 4-34 P re s s u ri z e r . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-35 Overpressure Protection Systems . . . . . . . . . . . . . . 3/4 4-36 ,

! i 3/4.4.10 STRUCTURAL INTEGRITY ................... 3/4 4-38 i l 3/4.4.11 REACTOR COOLANT SYSTEM VENTS ............... 3/4 4-39 !

i I 3/4.5 EMERGENCY CORE COOLING SYSTEMS l

l 3/4.5.1 ACCUMULATORS 1

Cold Leg Injection . . . . . . . . . . . . . . . . . . . . 3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - T,y, t 350*F . . . . . . . . . . . . . . 3/4 5-4 '

3/4.5.3 ECCS SUB5YSTEMS - T,y, < 350*F . . . . . . . . . . . . . . 3/4 5-8 3/4.5.4 REFUELING WATER STORAGE TANK ............... 3/4 5-10' 3/4';6 CONTAINMENT' SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT l Containment Integrity . . . . . . . . . . . . . . . . . . . 3/4 6-1 Containment Leakage . . . . . . . . . . . . . . . . . . . . 3/4 6-2 TABLE 3.6-1 SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS . . . . . . . 3/4 6-5 l

Containment Air Locks . . . . . . . . . . . . . . . . . . . 3/4 6-8 !

I n t e rna l P re s s u re . . . . . . . . . . . . . . . . . . . . . 3/4 6-10 Air Temperature . . . . . . . . . . . . . . . . . . . . . . 3/4 6-11 Containment Vessel Structural Integrity . . . . . . . . . . 3/4 6-12 Reactor Building Structural Integrity . . . . . . . . . . . 3/4 6-13 l Annulus Ventilation System ................ 3/4 6-14 Containment Purge Systems . . . . . . . . . . . . . . . . . 3/4 6-16 TA&E 1 +- 3 RsAcroA ctcuyer fvFf 00UATW6 RsnRicTwI Fvll Low Tw fillATv6 *owtfessivec l'Reitchani. .. 1/4 if-);

CATAWBA - UNIT 1 VIII Amendment No. K s

REACTOR COOLANT SYSTEM V RPRESSURE PROTECTION SYSTEMS LIMI NG CONDITION FOR OPERATION 3.4.9.3 t least one of the following Overpressure Protection Syste

' shall .

be OPERABL -

a. Two wer operated relief valves (PORVs) with a lift s ing of less than o equal to 450 psig, or

b. The React Coolant System depressurized with a Re tor Coolant System ven< of greater than or equal to 4.5 squar inches.

h

} APPLICABILITY: MODE 4 hen the temperature of any Rea or Coolant System cold J leg is less than or equ to 285'F, MODE 5 and MODE hen the head is on the reactor vessel.

ACTION:

} a. With one PORV inoperab in MODE 4, store the inoperable PORV to OPERABLE status within ays or c )lete depressurizatior and venting of the Peactor Co ant Sy em through at least a 4.' square inch vent within the next our .

b. With one PORV inoperable in ES 5 or 6, restore the inoperable PORV to OPERABLE status within ho s or complete depressurization and venting of the Reactor Co ant S tem through at least a 4.5 square inch vent within the ne 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

c. With both PORVs inop ble, complete pressurization and venting of the Reactor Coolant ystem through at est a 4.5 square inch vent within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

d. In the event e' er the PORVs or the Reacto CoolantSystemvent(s) are used to ;igate a Reactor Coolant Syste ressure transient, a Special Rep t shall be prepared and submitte o the Commission pursuant Specification 6.9.2 within 30 days. The report shall describe he circumstances initiating the transie ., the effect of the P0 s or Reactor Coolant System vent (s) on the ransient, and any l corre ive action necessary to prevent recurrence.

e. T provisions of Specification 3.0.4 are not applicab

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CATAWBA - UNIT 1 3/4 4-36 Amendment No.

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REACTOR COOLANT SYSTEM I

OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.9.3 A Low Temperature Overpressure Protection System shall be OPERABLE with a maximum of one charging pump or one safety injection pump capable of injecting into the Reactor Coolant System, the cold leg accumulators isolated *,

Reactor Coolant pump operation limited as specified in Table 3.4-3, and either a or b below:

a. Two power operated relief valves (PORVs)# with a lift setting of less than or equal to 400 psig (as left calibrated), allowable value of less than or equal to 425 psig (as found), or i

b. The Reactor Coolant System depressurized with a Reactor Cuolant System i vent of greater than or equal to 4.5 square inches. l APPLICABILITY: MODE 4 when the temperature of any Reactor Coolant System cold leg is less than or equal to 285*F, MODE 5 and MODE 6 when the head is on the reactor vessel.

ACTION:

a. With one PORV inoperable in MODE 4, restore the inoperable PORV to OPERABLE status within 7 days or complete depressurization and venting of the Reactor Coolant System through at least a 4.5 square inch vent within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

b. With one PORV inoperable in MODES 5 or 6, restore the inoperable PORV to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or complete depressurization and venting of the Reactor Coolant System through at least a 4.5 square inch vent within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

c. With both PORVs inoperable, complete depressurization and venting of l the Reactor Coolant System through at least a 4.5 square inch vent I within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . j i

l

Accumulator isolation is only required when accumulator pressure is greater than or equal to the maximum Reactor Coolant System pressure for the existing Reactor Coolant System cold leg temperature allowed by the pressure / temperature limit curves provided in Specification 3/4.4.9.

l # When using the PORVs to meet the requirements of this Specification, each Reactor Coolant System cold leg temperature shall be greater than or equal to 65'F. When the Reactor Coolant pumps are secured, this temperature shall be measured at the residual heat removal heat exchanger outlet.

l l CATAWBA - UNIT 1 3/44-36 Amendment No.

E T_0R COOLANT SYSTEM ACTION (Contirgf)

d. In the event either the PORVs or the Reactor Coolant System vent (s) are used to mitigate a Reactor Coolant System pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to . Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs or Reactor Coolant System vent (s) on the transient, and any corrective action necessary to preYent recurrence.

e. The provisions of Specification 3.0.4 are not applicable.

f. With more than the specified number of charging pumps and/or safety injection pumps capable of injecting into the Reactor Coolant System *,

intnediately initiate action to verify a maximum of one charging pump or one safety injection pump is capable of injecting into the Reactor Coolant System.

g. With a cold leg accumulator not isolated as specified, within one hour, isolate the affected accumulator. If the affected accumulator is not isolated within one hour, within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , either increase Reactor Coolant System cold leg temperature to greater than 285'F, or depressurize the affected accumulator to less than the maximum Reactor Coolant System pressure for the existing cold leg temperature allowed by Specification 3/4.4.9.

h. With Reactor Coolant pump operation not in accordance with the requirements of Table 3.4-3, intnediately initiate action to limit pump l operation as specified in Table 3.4-3.

TABLE 3.4-3 REACTOR COOLANT PUMP OPERATING RESTRICTIONS FOR LOW TEMPERATURE OVERPRESSURE PROTECTION l

1 Reactor Coolant System Maximum Number of Pumos Cold Leo Temperature Allowed in Ooeration 1 67*F 1 2 68*F 2' 2 73*F 4 l

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Two charging pumps may be capable of injecting into the Reactor Coolant System I during pump swap operation for less than or equal to 15 minutes.

l CATAWBA - UNIT 1 3/44-36a Amendment No.

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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.9.3.1 Each PORY shall be de'monstrated OPERABLE by:

a. Performance of an ANALOG CHANNEL OPERATIONAL' TEST on the PORV actuation channel, but excluding valve operation, at least once per 31 days; f b. Performance of a CHANNEL CALIBRATION on the PORY actuation channel at l 1 east once per 18 months; and l

l c. Verifying the PORY isolation valve is open at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months when the PORY l's being used for overpressure protection.

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4.4.9.3.2 The Reactor Coolant System vent (s) shall be verified to be open at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

when the vent (s) is being used for overpressure protection.

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Except when the vent pathway is provided with a valve which is locked, -

sealed, or otherwise secured in the open position, then verify these valves open at least once per 31 days. .

CATAWBA - UNIT 1 3/4 4-37 Amendment No. l

EMERGENCY CORE COOLING SYSTEMS 3/4.5.3- ECCS SUBSYSTEMS - T,y, < 350*F LINITING CONDITION FCR OPERATION

3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE

a. One OPERABLE centrifugal charging pump,f l b. One OPERABLE residual heat removal heat exchanger, l c. One OPERABLE residual' heat removal pump, and

d. An OPERABLE flow path capable of taking suction from the refueling water storage tank upon being manually realigned and transferring suction to the containment sump during the recirculation phase of operation.

APPLICABILITY: MODE 4.

ACTION:-

4.. With no ECCS subsystem OPERABLE because of the inoperability of either the centrifugal charging pump or the flow path from the refueling water storage tank, restore at least'one ECCS subsystem to OPERABLE status within I hour or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .

b. With no ECCS subsystem OPERABLE because of the inoperability of either the residual heat removal heat exchanger or residual- heat removal pump, restore at least one ECCS subsystem to 0PERABLE status or maintain the Reactor Coolant System T,y, less-than 350*F by use of alternate heat removal methods,

c. In the event the ECCS is actuated and injects water into the Peactor-Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describ-ing the circumstances of the actuation and the total accumulated actuation cycles to date. . The current value of the usage factor for ,

each affected Safety Injection nozzle shall be provided in this i Special- Report whenever its value exceeds 0.70. !

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A maximum of one O N charging pump one Safety Injection pump ,

shall be OPERABLE whenever the temperature o one or more of the Reactor 'j Coolant System cold -legs is less than or equal to 285'F.

- CATAWBA.- UNIT.1~ 3/4 5-8 Amendment No.

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1 Attachment ib j Revised Current Technical Specifications Pages for Catawba l i

Unit 2 l

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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE l TABLE 4.4-5 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM 1

WITHDRAWAL SCHEDULE .................. 3/4 4-35 P re s s u ri z e r . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-36 y Overpressure Protection Systems . . . . . . . . . . . . . . 3/4 4-37

( 3/4.4.10 STRUCTl!RAL INTEGRITY . . . . . . . . . . . . . . . . . ... 3/4 4-39 i 3/4.4.11 REACTOR COOLANT SYSTEM VENTS ............... 3/4 4-40 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS Cold Leg Injection . . . . . . . . . . . . . . . . . . . . 3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - T,y, t 350*F ............... 3/4 5-4 3/4.5.3 ECCS SUBSYSTEMS - T,yg < 350*F ............... 3/4 5-8 3/4.5.4 REFUELING WATER STORAGE TANK ............... 3/4 5-10 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Containment Integri ty . . . . . . . . . . . . . . . . . . . . 3/4 6-1 Containment Leakage . . . . . . . . . . . . . . . . . . . . 3/4 6-2 TABLE 3.6-1 SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS . . . . . . . 3/4 6-5 !

Containment Ai r Locks . . . . . . . . . . . . . . . . . . . 3/4 6-8 I n t e rnal P re s s u re . . . . . . . . . . . . . . . . . . . . . 3/4 6-10 Air Temperature . . . . . . . . . . . . . . . . . . . . . . 3/4 6-11 Containment Vessel Structural Integrity . . . . . . . . . . 3/4 6-12 Reactor Building Structural Integrity . . . . . . . . . . . 3/4 6-13 Annulus Ventilation System ................ 3/4 6-14 Containment Purge Systems . . . . . . . . . . . . . . . . . 3/4 6-16 T/16tE $4-3 RGAcTg coouwr faMf 0fuAnnC KritucTwM M LbH TTM(USTUG OVi/fitUSuRE fitOT6c'nobl . . *

3l'$ 'f ~37q CATAWBA - UNIT 2 VIII Amendment No. %

REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS l

\1MITINGCONDITIONFOROPERATION I 3.4. 3 At least one of the following Overpressure Protection Sys ms shall be OP BLE:

a. o power operated relief valves (PORVs) with a lift etting of less t or equal to 450 psig, or

b. The ctor Coolant System depressurized with a actor Coolant System nt of greater than or equal to 4.5 sq re inches. -li APPLICABILITY: MO 4 when the temperature of any R' ctor Coolant System cold leg is less than or ual to 285*F, MODE 5 and MOD a when the head is on the ,

reactor vessel.

l ACTION:

a. With one PORV inope ale in MODE 4 restore the inoperable PORV to I OPERABLE status withi 7 days or mplete depressurization and venting of the Reactor olant stem through at least a 4.5 square , ,

inch vent within the nex 8 ho s.

b. With one PORV inoperable i ODES 5 or 6, restore the inoperable PORV to OPERABLE status within 4 urs or complete depressurization and venting of the Reactor C lant stem through at least a 4.5 square inch vent within the n t 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

c. With both PORV; ino rable, complet pressurization and venting of the Reactor Coola System through at east a 4.5 square inch vent within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

d. In the event ther the PORVs or the React CoolantSystemvent(s) are used to tigate a Reactor Coolant Syst pressure transient, a Special Re rt shall be prepared and submitte to the Commission >

pursuant Specification 6.9.2 within 30 days. The report shall de',cri b the circumstances initiating the transi t, the effect of the P0 s or Reactor Coolant System vent (s) on the ransient, and any !

corr tive action necessary to prevent recurrence. )

e. T provisions of Specification 3.0.4 are not applicab .

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i CATAWBA - UNIT 2 3/4 4-37 Amendment No. 1

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REACTOR COOLANT SYSTEM hk(( h OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.9.3 A Low Temperature Overpressure Protection System shall be OPERABLE with a maximum of one charging pump or one safety injection pump capable of injecting into the Reactor Coolant System, the cold leg accumulators isolated *, Reactor Coolant pump operation limited as specified in Table 3.4-3, and either a or b below: I

a. Two power operated relief valves (PORVs)# with a lift setting of less than or equal to 400 psig (as left calibrated), allowable value of 1 less than or equal to 425 psig (as found), or l

b. The Reactor Coolant System depressurized with a Reactor Coolant System vent of greater than or equal to 4.5 square inches.

APPLICABILITY: MODE 4 when the temperature of any Reactor Coolant System cold leg is less than or equal to 285*F, MODE 5 and MODE 6 when the head is on the reactor vessel.

ACTION:

a. With one PORV inoperable in MODE 4, restore the inoperable PORV to OPERABLE status within 7 days or complete depressurization and venting of the Reactor Coolant System through at least a 4.5 square inch vent within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ,

b. With one PORV inoperable in MODES 5 or 6, restore the inoperable PORV to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or complete depressurization and venting of the Reactor Coolant System throagh at least a 4.5 square inch vent within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

c. With both PORVs inoperable, complete depressurization and venting of the Reactor Coolant System through at least a 4.5 square inch vent

within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

1 l

Accumulator isolation is only required when accumulator pressure is greater i than or equal to the maximum Reactor Coolant System pressure for the existing )

Reactor Coolant System cold leg temperature allowed by the '

pressure / temperature limit curves provided in Specification 3/4.4.9.

When using the PORVs to meet the requirements of this Specification, each Reactor Coolant System cold leg temperature shall be greater than or equal to 65 F. When the Reactor Coolant pumps are secured, this temperature shall be measured at the residual heat removal heat exchanger outlet.

CATAWBA - UNIT 2 3/44-37 Amendment No. l j

REACTOR COOLANT SYSTEM ACTION (Continued)

d. In the event either the PORVs or the Reactor Coolant System vent (s) are used to mitigate a Reactor Coolant System pressure transient, a Special Report shall be prepared and submitted to the Conmission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs or Reactor Coolant System vent (s) on the transient, and any corrective action necessary to prevent recurrence,

e. The provisions of Specification 3.0.4 are not applicable.

f. With more than the specified number of charging pumps and/or safety injection pumps capable of injecting into the Reactor Coolant System *, immediately initiate action to verify a maximum of one charging pump or one safety injection pump is capable of injecting into the Reactor Coolant System.

g. With a cold leg accumulator not isolated as specified, within one hour, isolate the affected accumulator. If the affected accumulator is not isolated within one hour, within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , either increase Reactor Coolant System cold leg temperature to greater than 285'F, or depressurize the affected accumulator to less than the maximum Reactor Coolant System pressure for the existing cold leg temperature allowed by Specification 3/4.4.9.

h. With Reactor Coolant pump operation not in accordance with the requirements of Table 3.4-3, immediately initiate action to limit pump operation as specified in Table 3.4-3.

TABLE 3.4-3 REACTOR COOLANT PUMP OPERATING RESTRICTIONS FOR LOW TEMPERATURE OVERPRESSURE PROTECTION Reactor Coolant System Maximum Number of Pumos Cold Leo Temperature Allowed in Operation 2 67'F 1 2 73*F 2 l 2 95'F 4 l

i I

Two charging pumps may be capable of injecting into the Reactor Coolant System during pump swap operation for less than or equal to 15 minutes.

CATAWBA - UNIT 2 3/44-37a Amendment No. l l ;

REACTOR COOLANT SYSTEM I SURVEILLANCE RE0UIREMENTS 4.4.9.3.1 Each PORV shall be demonstrated OPERABLE by: 4 l

! a. Performance of an ANALOG CHANNEL OPERATIONAL TEST on the PORV

} actuation channel, but excluding valve operation, at least once per 31 days;

b. Performance of a CHANNEL CALIBRATION on the PORV actuation channei at least once per 18 months; and l c. Verifying the PORY isolation valve is open at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months l when the PORY is being used for overpressure protection.

i 4.4.9.3.2 The Reactor Coolant System vent (s) shall be verified to be open at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

when the vent (s) is being used for overpressure protection.

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Except when the vent pathway is provided with a valve which is locked, sealed, or otherwise secured in the open position, then verify these valves open at least once per 31 days.

Cf.iAWBA - UNIT 2 3/4 4-38 Amendment No.

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't $r y4 dQT 4F y 4g 3 EMERGENCY CORE COOLING SYSTEMS 3/4.5.3 ECCS SUBSYSTEMS - T,yg < 350*F LIMITING CONDITION FOR OPERATION 3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:

a. One OPERABLE centrifugal charging pump,#

b. One OPERABLE residual heat removal heat exchanger, 1 c. One OPERABLE residual heat removal pump, and

d. An OPERABLE flow )ath capable of taking suction from the refueling water storage tan c upon being manually realigned and transferring suction to the containment sump during the recirculation phase of operation.

} APPLICABILITY: MODE 4.

ACTION:

a. With no ECCS subsystem OPERABLE because of the inoperability of either the centrifugal charging pump or the flow path from the refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .

b. With no ECCS subsystem OPERABLE because of the inoperability of either the residual heat removal heat exchanger or residual heat removal pump, restore at least one ECCS subsystem to OPERABLE status or maintain the Reactor Coolant System T,yg less than 350*F by use of alternate heat removal methods.

c. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describ-ing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the usage factor for each affected Safety Injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.

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A maximum of one @Auni'b charging pump one Safety Injection pump shall be OPERABLE whenever the temperature o one or more of the Reactor Coolant System cold legs is less than or equal to 285*F.

CATAWBA - UNIT 2 3/4 5-8 Amendment No.

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l Attachment 2a j Reprinted Current Technical Specifications Pages for l

Catawba Unit 1 1

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I LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS

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SECTION MGE TABLE 4.4-5 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM '

WITHDRAWAL SCHEDULE .................. 3/4 4-34 l Pressurizer . . . . . . . . . . . . . . . . . . . . . . . . 3/44-35 Overpressure Protection Systems . . . . . . . . . . . . . .

3/44-36 TABLE 3.4-3 REACTOR COOLANT PUMP OPERATING RESTRICTIONS FOR LOW TEMPERATURE OVERPRESSURE PROTECTION ........ 3/44-36a 3/4.4.10 STRUCTURAL INTEGRITY ................... 3/4 4-38 3/4.4.11 REACTOR COOLANT SYSTEM VENTS ............... 3/44-39 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS '

Cold Leg Injection . . . . . . . . . . . . . . . . . . . . 3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - T,,it 350"F . . . . . . . . . . . . . . . . 3/4 5-4 I 3/4.5.3 ECCS SUBSYSTEMS - T.,, < 350"F . . . . . . . . . . . . . . . 3/4 5-8 3/4.5.4 REFUELING WATER STORAGE TANK ............... 3/4 5-10 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Contai nment Integri ty . . . . . . . . . . . . . . . . . . . . 3/4 6-1 i i

Containment Leakage . . . . . . . . . . . . . . . . . . . . . 3/46-2 TABLE 3.6-1 SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS . . . . . . . 3/4 6-5 Containment Ai r Locks . . . . . . . . . . . . . . . . . . . 3/4 6-8 i

Internal Pressure . . . . . . . . . . . . . . . . . . . . . 3/4 6-10 4 Air Temperature . . . . . . . . . . . . . . . . . . . . . . 3/4 6-11 Containment Vessel Structural Integrity . . . . . . . . . . 3/46-12 i Reactor Building Structural Integrity . . . . . . . . . . . 3/4 6-13 l

Annulus Ventilation System ................ 3/46-14 Containment Purge Systems . . . . . . . . . . . . . . . . . 3/4 6-16 l CATAWBA - UNIT 1 VIII Amendment No.

i

l REACTOR COOLANT SYSTEM ,

l OVERPRESSURE PROTECTION SYSTEMS i LIMITING CONDITION FOR OPERATION 3.4.9.3 A Low Temperature Overpressure Protection System shall be OPERABLE with a maximum of one charging pump or one safety injection pump capable of injecting into the Reactor Coolant System, the cold leg accumulators isolate P ,

Reactor Coolant pump operation limited as specified in Table 3.4-3, and either a or b below: j

a. Two power operated relief valves (PORVs)# with a lift setting of less than or equal to 400 psig (as left calibrated), allowable value of l less than or equal to 425 psig (as found), or

b. The Reactor Coolant System depressurized with a Reactor Coolant System vent of greater than or equal to 4.5 square inches.

APPLICABILITY: MODE 4 when the temperature of any Reactor Coolant System cold leg is less than or equal to 285*F, MODE 5 and MODE 6 when the head is on the reactor vessel.

ACTION:

a. nith one PORV inoperable in MODE 4, restore the inoperable POP.V to OPERABLE status within 7 days or complete depressurization and venting of the Reactor Coolant System through at least a 4.5 square inch vent within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

b. With one PORV inoperable in MODES 5 or 6, restore the inoperable PORV to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or complete depressurization and venting of the Reactor Coolant System through at least a 4.5 square inch vent within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

c. With both PORVs inoperable, complete depressurization and venting of the Reactor Coolant System through at least a 4.5 square inch vent within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Accumulator isolation is only required when accumulator pressure is greater than or equal to the maximum Reactor Coolant System pressure for the existing Reactor Coolant System cold leg temperature allowed by the pressure / temperature limit curves provided in Specification 3/4.4.9.

l

When using the PORVs to meet the requirements of this Specification, each Reactor Coolant System cold leg temperature shall be greater than or equal to 65*F. When the Reactor Coolant pumps are secured, this temperature shall be measured at the residual heat removal heat exchanger outlet.

l CATAWBA - UNIT 1 3/44-36 Amendment No.

i 1

REACTOR COOLANT SYSTEM ACTION (Continued)

d. In the event either the PORVs or the Reactor Coolant System vent (s) are used to mitigate a Reactor Coolant System pressure transier t, a l Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report shall l describe the circumstances initiating the transient, the effect of the l PORVs or Reactor Coolant System vent (s) on the transient, and any corrective action necessary to prevent recurrence.

l

e. The provisions of Specification 3.0.4 are not applicable,

f. With more than the specified number af charging pumps and/or safety injection pumps capable of injecting into the Reactor Coolant System *,

imediately initiate action to verify a maximum of one charging pump or one safety injection pump is capable of injecting into the Reactor Coolant System.

9 With a cold leg accumulator not isolated as specified, within one hour, isolate the affected accumulator. If the affected accumulator is not isolated within one hour, within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , either >

increase Reactor Coolant System cold leg temperature to greater than 285*F, or depressurize the affected accumulator to less than the maximum Reactor Coolant System pressure for the existing cold leg temperature allowed by Specification 3/4.4.9.

h. With Reactor Coolant pump operation not in accordance with the requirements of Table 3.4-3, immediately initiate action to limit pump operation as specified in Table 3.4-3.

TABLE 3.4-3 REACTOR C0OLANT PUMP OPERATING RESTRICTIONS FOR LOW TEMPERATURE OVERPRESSURE PROTECTION Reactor Coolant System Maximum Number of Pumos Cold Leo Temperature Allowed in Ooeration 1 67*F 1 2 68*F 2 1 73*F 4 l

l *Two charging pumps may be capable of injecting into the Reactor Coolant System during pump swap operation for less than or equal to 15 minutes.

l CATAWBA - UNIT 1 3/44-36a Amendment No.

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.9.3.1 Each PORV shall be demonstrated OPERABLE by:

a. Performance of an ANALOG CHANNEL OPERATIONAL TEST on the PORV l actuation channel, but excluding valve operation, at least once per 31 days;

b. Performance of a CHANNEL CALIBRATION on the PORV actuation channel at least once per 18 months; and

c. Verifying the PORV isolation valve is open at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months when the PORV is being used for overpressure protection.

4.4.9.3.2 The Reactor Coolant System vent (s) shall be verified to be open at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

when the vent (s) is being used for overpressure protection.

4.4.9.3.3 A maximum of one charging pump or safety injection pump shall be verified to be capable of injecting into the Reactor Coolant System at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4.9.3.4 Each cold leg accumulator shall be verified to be isolated at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when accumulator isolation is required.

1 l

l

Except when the vent pathway is provided with a valve which is locked, sealed, or otherwise secured in the open position, then verify these valves open at l- least once per 31 days.

{

( :

I. CATAWBA - UNIT 1 3/44-37 Amendment No. l )

l l

e__-______-_____-___-_-___ __ _

1 1'

i EMERGENCY CORE COOLING SYSTEMS 3/4.5.3 ECCS SUBSYSTEMS - T , < 350"F LIMITING CONDITION FOR OPERATION 3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:

a. One OPERABLE centrifugal charging pump,#

b. One OPERABLE residual heat removal heat exchanger,

c. One OPERABLE residual heat removal pump, and

d. An OPERABLE flow path capable of taking suction from the refueling water storage tank upon being manually realigned and transferring suction to the containment sump during the recirculation phase of operation.

APPLICABILITY: MODE 4.

ACTION:

a. With no ECCS subsystem OPERABLE because of the inoperability of either the centrifugal charging pump or the flow path from the refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .

b. With no ECCS subsystem OPERABLE because of the inoperability of either the residual heat removal heat exchanger or residual heat removal pump, restore at least one ECCS subsystem to OPERABLE status or

, maintain the Reactor Coolant System T ., less than 350*F by use of alternate heat removal methods.

c. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describ-ing the circumstances of the actuation and the total accumulated

. actuation cycles to date. The current value of the usage factor for I

each affected Safety Injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.

l #A maximum of one charging pump or one Safety Injection pump shall be OPERABLE whenever the temperature of one or more of the Reactor Coolant System cold legs is less than or equal to 285 F.

l CATAWBA - UNIT 1 3/4 5-8 Amendment No.

r

Attachment 2b Reprinted Current Technical specifications Pages ft.r l Catawba Unit 2 l

1 l

l l

l L

l l

L______-___-________--_____-____. . _ - - . _ _- - __ ________________ __- _ _ _ _ _ _ _ _ _ _ _ _

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS l SECTION g TABLE 4.4-5 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM WITHDRAWAL SCHEDULE .................. 3/44-35 P re s s u ri z e r . . . . . . . . . . . . . . . . . . . . . . . . 3/44-36 Overpressure Protection Systems . . . . . . . . . . . . . . 3/44-37 TABLE 3.4-3 REACTOR COOLANT PUMP OPERATING RESTRICTIONS FOR LOW TEMPERATURE OVERPRESSURE PROTECTION ........ 3/44-37a 3/4.4.10 STRUCTURAL INTEGRITY ................... 3/44-39 3/4.4.11 REACTOR COOLANT SYSTEM VENTS ............... 3/44-40 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS Cold Leg Injection ..................... 3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - T,,, > 350*F . . . . . . . . . . . . . . . . 3/4 5-4 :

3/4.5.3 ECCS SUBSYSTEMS - T.,, < 350 F . . . . . . . . . . . . . . . . 3/4 5-8 )

3/4.5.4 REFUELING WATER STORAGE TANK ............... 3/45-10 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Contai nment Integri ty . . . . . . . . . . . . . . . . . . . . 3/46-1 Containment Leakage . . . . . . . . . . . . . . . . . . . . 3/4 6-2 TABLE 3.6-1 SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS . . . . . . . 3/4 6-5 Containment Air Locks . . . . . . . . . . . . . . . . . . . 3/4 6-8 Internal Pressure . . . . . . . . . . . . . . . . . . . . . 3/46-10 Ai r Tempe ra t u re . . . . . . . . . . . . . . . . . . . . . . 3/46-11 l

Containment Vessel Structural Integrity . . . . . . . . . . 3/46-12 i

Reactor Building Structural Integrity . . . . . . . . . . . 3/46-13 Annulus Ventilation System ................ 3/4 6-14 Containment Purge Systems . . . . . . . . . . . . . . . . . 3/4 6-16 1

l CATAWBA - UC f 2 VIII Amendment No.

REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.9.3 A Low Temperature Overpressure Protection System shall be OPERABLE with a maximum of one charging pump or one safety injection pump capable of injecting into the Reactor Coolant System, the cold leg accumulators isolated *, Reactor Coolant pump operation limited as specified in Table 3.4-3, and either a or b below:

a. Two power operated relief valves (PORVs)# with a lift setting of less than or equal to 400 psig (as left calibrated), allowable value of less than or equal to 425 psig (as found), or

b. The Reactor Coolant System depressurized with a Reactor Coolant System vent of greater than or equal to 4.5 square inches.

APPLICABILITY: MODE 4 when the temperature of any Reactor Coolant System told l leg is less than or equal to 285'F, MODE 5 and MODE 6 when the head is on the reactor vessel.

l l ACTION:

a. With one PORV inoperable in MODE 4, restore the inoperable PORV to OPERABLE status within 7 days or complete depressurization and venting of the Reactor Coolant System through at least a 4.5 square

! inch vent within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

b. With one PORV inoperable in MODES 5 or 6, restore the inoperable PORv to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or complete depressurization and venting of the Reactor Coolant System through at least a 4.5 square inch vent within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

c. With both PORVs inoperable, complete depressurization and venting of the Reactor Coolant System through at least a 4.5 square inch vent within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Accumulator isolation is only required when accumulator pressure is greater than or equal to the maximum Reactor Coolant System pressure for the existing Reactor Coolant System cold leg temperature allowed by the pressure / temperature limit curves provided in Specification 3/4.4.9.

When using the PORVs to meet the requirements of this Specification, each Reactor Coolant System cold leg temperature shall be greater than or equal to 65'F. When the Reactor Coolant pumps are secured, this temperature shall be measured at the residual heat removal heat exchanger outlet.

CATAWBA - UNIT 2 3/44-37 Amendment No. l L______________________

REACTOR COOLANT SYSTEM ACTION (Continued)

d. In the event either the PORVs or the Reactor Coolant System vent (s) are used to mitigate a Reactor Coolant System pressure transient, a Special Report shall be prepared and submitted to the Commission

, pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs or Reactor Coolant System vent (s) on the transient, and any corrective action necessary to prevent recurrence,

e. The provisions of Specification 3.0.4 are not applicable.

f. With more than the specified number of charging pumps and/or safety injection pumps capable of injecting into the Reactor Coolant !

System *, immediately initiate action to verify a maximum of one l charging pump or one safety injection pump is capable of injecting !

into the Reactor Coolant System. l

g. With a cold leg accumulator not isolated as specified, within one hour, isolate the affected accumulator. If the affected accumulator is not isolated within one hour, within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , either

! increase Reactor Coolant System cold leg temperature to greater than 285"F, or depressurize the affected accumulator to less than the maximum Reactor Coolant System pressure for the existing cold leg temperature allowed by Specification 3/4.4.9.

h. With Reactor Coolant pump operation not in accordance with the requirements of Table 3.4-3, immediately initiate action to limit pump operation as specified in Table 3.4-3.

TABLE 3.4-3 REACTOR COOLANT PUMP OPERATING RESTRICTIONS FOR LOW TEMPERATURE OVERPRESSURE PROTECTION 1

1 Reactor Coolant System Maximum Number of Pumos Cold Lea Temperature Allowed in Operation 2 67'F 1 2 73 F 2 2 95*F 4 l

Two charging pumps may be capable of injecting into the Reactor Coolant System during pump swap operation for less than or equal to 15 minutes.

CATAWBA - UNIT 2 3/44-37a Amendment No. l

REACTOR COOLANT SYSTEM SURVEILLANCE RE0VIREMENTS 4.4.9.3.1 Each PORV shall be demonstrated OPERABLE by:

a. Performance of an ANALOG CHANNEL OPERATIONAL TEST on the PORV actuation channel, but excluding valve operation, at least once per 31 days;

b. Performance of a CHANNEL CALIBRATION on the PORV actuation channel at least once per 18 months; and

c. Verifying the PORV isolation valve is open at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months when the PORV is being used for overpressure protection.

4.4.9.3.2 The Reactor Coolant System vent (s) shall be verified to be open at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

when the vent (s) is being used for overpressure protection.

4.4.9.3.3 A maximum of one charging pump or safety injection pump shall be verified to be capable of injecting into the Reactor Coolant System at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4.9.3.4 Each cold leg accumulator shall be verified to be isolated at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when accumulator isolation is required.

Except when the vent pathway is provided with a valve which is locked, sealed, or otherwise secured in the open position, then verify these valves open at least once per 31 days.

l CATAWBA - UNIT 2 3/44-38 Amendment No.

EMERGENCY CORE COOLING SYSTEMS 3/4.5.3 ECCS SUBSYSTEMS - T.,, < 350*F LIMITING CONDITION FOR OPERATION

'3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:

a. One OPERABLE centrifugal charging pump,#

b. One OPERABLE residual heat removal heat exchanger,

c. One OPERABLE residual heat removal pump, and

d. An OPERABLE flow path capable of taking suction from the refueling water storage tank upon being manually realigned and transferring suction to the containment sump during the recirculation phase of operation.

APPLICABILITY: ' MODE 4.

ACTION:

a. With no ECCS subsystem OPERABLE because of the inoperability of either the centrifugal charging pump or the flow path from the refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .

b. With no ECCS-subsystem OPERABLE because of the inoperability of either the residual heat removal heat exchanger or residual heat L

removal pump, restore at least-one ECCS subsystem to OPERABLE status or maintain the Reactor Coolant System T. , less than 350*F by use of alternate heat removal methods.

c. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Comission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumu-lated actuation cycles to date. The current value of the usage

' factor for each affected Safety Injection rozzle shall be provided in this Special Report whenever its value exceeds 0.70.

l #A maxim' um of one charging pump or one Safety Injection pump shall be OPERABLE whenever the temperature of one or more of the Reactor Coolant System cold legs is less than or equal to 285"F.

l CATAWBA - UNIT 2 3/45-8 Amendment No.

Attachment 2c Revised TJRproved Technical specifications conversion Subunittal Documentation for Catawba Unit 1 i

]

1 1

l l

l l Revised Current Technical Specifications Marked-up Pages (NOTE: DUKE'S 9/15/97 ORIGINAL ANENDNENT REQUEST DID NOT

INCLUDE REVISED CURRENT TECHNICAL SPECIFICATIONS NARKED-UP PAGES; THEREFORE, REVISED PAGES ARE BEING INCLUDED FOR ALL ~

CHANGES PROPOSED BOTH IN THE ORIGINAL ANENDNENT REQUEST AND THIS SUPPLENENT,)

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l MATERIAL PROPERTY BASIS UMITING MATERIAL; LCPNER SIELL FORGING 04 UMfTING ART AT15 dFeY: 1/4-T, 43*F 3/4T, 26*F o

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FIGURE Y. .I-REACTOR COOLANT SYSTEM HEATUP LIMITATIONS (Heatup rates up to 60'F/hr)

APPLICABLE FOR THE FIRST 15 EFPY (Without Margins For Instrumentation Errors)

' CATAWBA - UNIT 1 3/4 4-32 Amendment No.

K bt ttcee,n,e m k J Adrl 9-l5-97

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1 REACTOR COOLANT SYSTEM C00LDOWN LIMITATIONS (Cooldown rates up to 100*F/hr)

APPLICABLE FOR THE FIRST 15 EFPY (Without Margins For Instrumentation Errors) j CATAWBA - UNIT 1 3/4 4-33 Amendment No.

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[ 3.M R_EACTOR COOLANT SYSTEM pfgp; f (tssa Tvgrafu]g 3t/,/pJUVLTPREssURL~FROTECTIONSYSTEMS

([MITINGCONDITIONFOROPERATION LCp 3.4C ow wmnararure overoressuoe rrotec System shall be OPERABLE with a maxTmum of one char

/).l hnjecting into the Eea&ging pump or Syeteifb one safety injectionaccumulators pump capable of#A/>P coq)mt the CEDF%b isolated *, Reactor Coolant pump operation limited as specified in Table -

and either a or b below:

a. Two_ power operated relief valves (PORVs)# with a lift setting of w*~b r i

(' _ an-or counAB400 psig (as left calibrated), allowable value of art or eiiiEF Tth 425 psig (as found)), or

b. The freactorT6 Ment-5wrtes ssm11* zed with3eactor Coe7 KtID (syug ven rearse tpaeror equait tD 4.5 square inches. j l

APPLICABILITY: et0DE 4 when GDem6ecatufhof Cogletft SuteiD cold a leg is(TET Uthan g eacal tG 285'F, MODE 5 and MODE 6 when tne head is on the i reactor vessel.

ACTION:

Cest////coE h With one PORV inoperable in MODE 4, restore the inoperable PORV to OPERABLE status within 7 days or complete depressurization and venting of the Reactor Coolant System through at least a 4.5 square fad ///*nO inch vent within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Mw////o# @ With one PORV inoperable in MODES 5 or 6, restore the inoperable PORV i to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or complete depressurization and gjjjg venting of the Reactor Coolant System through at least a 4.5 square ;

inch vent within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . I With both PORVs inoperable,[ complete depressurization and venting of the Reactor Coolant System through at least a 4.5 square inch vent cord 63G@/within8 hours.

Rherd kidn m'assWs/ed Confl e/ tin %e of ^

Cedil/dn /,b,Ep f Rc naf met.

Accumulator solation is on1 required when accumulator pressure is greater fo than or equal to the maximu e]pitt>r CoetantTV4T61D pressure for t e existing tillMBET50t3 T.~5fstiih cold leg temperature allowed by the

~

-L ,

LPOP 5s/t/plh.

pressure / temperature limit rurves provided in Specification ,A:

he art reason , Mn kcs) 8thec Ytan f Whgus99 the PpRVsitoA1~ e et the'Fenuiremarrfi nf thic. frffarifir2 Mon. eath1 csdiff,g4,c, (Ras torfoolant Sfstenfcold leg temperature shall be grea'er t than or eqifal to)

D, E,e F. ,"rNual emo h eat 1 gerOut I- A 1 5 CATAWBA - UNIT 1 3/a 4-36 Amendment No.

Propaed License Amendinent hded bl ee

Specification 3.M.11 INSERT 10 not used. l

$r'c r.1ft k*M6rbl4 f f),{c c/ d-IE-4$

Catawba I Page 2. of f

i spei A M .4.it i

REACTOR COOLANT SYSTEM ACTION (Continued)

. In t e event either the PORV r the Reactor Coolant Sys mvent(s) are u d to mitigate a Reactor oolant System pressure tra ient, a l Specia Report shall be prepare nd submitted to the Commi ion -

(A.t pursuant o Specification 6.9.2 w hin 30 days. The report s all describe t e circumstances initiati the transient, the effec of the PORVs o Reactor Coolant System v nt(s) on the transient, a any corrective a tion necessary to prevent ecurrence.

J

(%O @ Qhe pronsions oL,&pecifipatiorb .0.4 h Nplicable.

ag;, A O With more than the specified number of charging pumps and/or safety injection pumps capable of injecting into the Reactor Coolant System *, immediately initiate action to verify a maximum of one charging pump or one safety injection pump is capable of injecting into the Reactor Coolant System.

MMC $ With a cold leg accumulator not isolated as specified, within one hour, isolate the affected accumulator. If the affected accumulator Agg_ D is not isolated within one hour, within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , either increase Reactor Coolant System cold leg temperature to greater than 285'F, or depressurize the affected accumulator to less than the maximum Reactor Coolant System pressu the existin cold leg temperature allowed by Specification 3/ . 3 .3 9 3 Ag QLMA @ With Reactor Coolant pum operation not in accordance with the requirements of Table intnediately initiate action to limit pump operation as specified in Table .

4.r2.-l TABLE A-REACTOR COOLANT PUMP OPERATING RESTRICTIONS FOR LOW TEMPERATURE OVERPRESSURE PROJECTION Reactor Coolant System Maximum Number of Pumm Cold Leo Temperature Allowed in Ooeration 2 67'F 1 2 68'F 2 2 73*F 4

Two charging pumps may be capable of injecting into the Reactor Coolant System during pump swap operation for less than or equal to 15 minutes.

CATAWBA - UNIT 1 3/4 4-36a Amendment No.

Paoeosco Ltcmse AMe44mT BArto 4I-/5'-9f f

l Pag 3 oc>

Q f';*t 0CJ h9n 3, V /p l REACTOR COOLANT SYSTEM SilRVET81ANCE RE0VIREMENTS p w: w r

~

(43[9.3.1 Each PORV~sEiTDe_demqns{ rated QPEfA'Bil]iy? I"* "*'jJ a'5 >N"rD, a wrej e t a

,q y - eunums cod /m teyvny rRS . '/,g,5 r[f feriormance:nLarrRfAL0GCHANNEL OPERATIONAL TEST on the PM S ##V actuation channel, but excluding valve operation, at least once per 31 days; 6f S, 4, ,% G (9 Performance of a CHANNEL CALIBRATION on the PORV actuation channel at

~

-~

least once per 18 months; and tbj n-e "pO' Y' /E Y p' Verifying the PORV 61stN N51ve is open at least once per 72 hourFQ/

WKe~n2hejPORV KJefnfy or'0verpMsiure protettjdiP. f

~

p, , ,,,,

'@r?s:hre,ple])

< p.a "' $/ , /4' ". o /f.4.973.FTffReactor Coolant _ System venth)_Sha1Lhe_reriffed to be onen a? j 1 IIdit once psr 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months *

(Pfotectfon. _ _ _,_.,_ffisn the vint(s) is being used for overprgjisyng) d

-~ p'o y /p, / @

A maximum of one charging pump or safety injection pump shall be veriffis to be capable of injecting into the Reactor Coolant System at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . 4,[ "

s# B.M /O.R 64v9'33 Each cold leg accumulator shall be verified to be isolated at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when accumulator isolation is required.

l 4,90

( *Except when the vent pathway is provided with a valve which is locked, sealed, g,g g or otherwise secured in the open position, then verify these valves open at least once per 31 days.

W frct4fnf v/ CATAWBA - UNIT 1 3/4 4-37 Amendment No.

$ l Pectox/ beesse.

l .4medm ui Dadd C M cye 4 of 2

[fe?$tetftGn?.Y,/A__ l EMERGENCY CORE COOLING SYSTEMS 3/4.5.3 ECCS SUBSYSTEMS - T., < 350*F LIMITING CONDITION FOR OPERATION 3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:

l

a. One OPERABLE centrifugal charging pump,#

l

b. One OPERABLE residual heat removal heat exchanger,

c. One OPERABLE residual heat removal pump, and k

d. An OPERABLE flow path capable of taking suction from the refueling water storage tank upon being manually realigned and transferring suction to the containment sump during the recirculation phase of k operation.

See1%eryg i of /75 APH ICABILITY: MODE 4.

ACTION:

a. With no ECCS subsystem OPERABLE because of the inoperability of either the centrifugal charging pump or the flow path from the refueling water storage tank, restore at least one ECCS subsystem to OPERABLE .

status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .

{

b. With no ECCS subsystem OPERABLE because of the inoperability of either the residual heat removal heat exchanger or residual heat removal 1 pump, restore at least one ECCS subsystem to OPERABLE status or '

maintain the Reactor Coolant System T., less than 350*F by use of alternate heat removal methods.

c. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Connission pursuant to Specification 6.9.2 within 90 days describ-ing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the usage factor for each affected Safety Injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.

b!pVC Vo *

(COL Vol)

~

e y, k'Sech hj \,

l (w(A maximum of one charging pump or one Safety Injection pump flIa'llf be O

/1096 IO (is less than or equal to 285'F. ./

S, % /2 jg l CATAWBA - UNIT 1 3/45-8 Amendment No. f l

ff'Cft:Ek b/CCMSf.

/kah rot' Zkdl Y

\

' \

/ujt 7 , :F P l l

i

l l

Reprinted Improved Technical Specifications Pages '

i I

i i

RCSP/TLimits 3.4.3 i I

l l MATERIAL PROPERTY BASIS ,

i UMITING MATERIAL: LOWER SHELL FORGING 04 l UMITING ART AT15 EFPY: 1/4-T, 43*F l 3/4-T, 26*F 2,500 a i i i i i i i i i i ! > >

I 1 LEAK TEST UMIT- .Q l L

[

2,250

/ / o l !l i i i 2,000 '

f / l

. - , I l

I I

i

' I c2. 1 ,7 5 0 ----

UNACCEPTABLE / l

OPERATION I I

@ / /

$ 1,500 ,' ,

,, l g

U)

HEATUP RATE '- x UP TO 60 F/HR ,

/ '

/ ACCEPTABLE '

t OPERATION l 2 1,250 ; / / , ,

j G

> i li o l l V 1,000 O

w ,

i 5 '

l

.9 750 -l V l C i

+

500 '

L , , ,

NCRITICAUTY UMIT BASED ON ::::

INSERVICE HYDROSTATIC TEST 250 ---

TEMPERATURE (176*F) FOR THE ----

j l SERVICE PERIOD UP TO 15 EFPY ::::

l liliI:Ii'IIiiiI IIIIlIli 1

0 l

0 50 100 150 200 250 300 350 400 450 500 a

l Indicated Temperature (Deg. F) !

l l I L

Figure 3.4.3-1 RCS Heatup Limitations l i

l l !

Catawba Unit 1 3.4-10 7/2/97 L- ----- - - - - - - - - - - - - - - - - - - - - - - - -----------------------------J

l l RCS P/T Limits 3c4.3 l

MATERIAL PROPERTY BASIS ,

' LIMfTING MATERIAL: LOWER SHELL FORGING 04 LIMITING ART AT 15 EFPY: 1/4 T, 43*F 3/4 T, 26*F l 1

2,500 l

l 2,250 / l 2,000 /

D) 2: UNACCEPTABLE 1

'5 :: OPERATION /

o.-1,750 I

/

@ l

$ 1,500 /

crj j ACCEPTABLE CfJ i r OPERATION 2 1,250 '

/ ,

Q 4

/ .!

"O 1,000 i ,

i COOLDOWN ! -

ES 'FQR. l l l c 750 ----

o

'g :::: 20 '

40 i

l i

E 500 :::: ioo l

250 :

i .

I i i 0 - ' ' '

O 50 100 150 200 250 300 350 400 450 500 '

Indicated Temperature (Deg. F) i Figure 3.4.3-2 RCS Cooldown Limitations Catawba Unit 1 3.4-11 7/2/97

1 l LTOP System 3.4.12 I- . .

3.4 REACTOR COOLANT SYSTEM (RCS).

'3.4.12 Low Temperature Overpressure Protection (LTOP) System l

LCO 3.4.12 An LTOP System shall be OPERABLE with a maximum'of one charging pump or one safety injection pump capable of injecting into .the RCS, the accumulators isolated, reactor coolant pump oper2 tion limited as specified in Table 3.4.12-1 and either a or b below.

L

a. Two power operated relief valves- (PORVs) with lift setting s 400 psig (as left calibrated), allowable value s 425 psig (as found), with RCS cold leg temperature 2

-65'F; or

b. The RCS depressurized and an RCS vent of 2 4.5 square inches.

APPLICABILITY:. MODE 4 when any RCS cold leg temperature is s 285"F, MODE 5, MODE 6 when- the reactor vessel head is on.

l

NOTE--------------------- .------

Accumulator isolation is only required when accumulator pressure is greater than or equal to the maximum RCS pressure for the existing RCS cold leg temperature allowed by the P/T limit curves provided in Specification 3.4.3.

l l

\-

l l

Catawba Unit 1 3.4-31 5/11/98

L19P System 3.4.12 ACTIONS

NOTE------------------..------__----

LCO 3.0.4 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Two or more charging ----------NOTE--------------

pumps capable of Two charging pumps may be injecting into the capable of injecting into the RCS. RCS during pump swap operation for s 15 minutes.

g ..________ ..________________

One charging pump and A.1 Initiate action to Immediately one safety injection verify a maximum of pump capable of one charging pump or injecting into the one safety injection RCS. pump is capable of injecting into the M RCS.

Two or more safety injection pumps capable of injecting into the RCS.

B. Reactor coolant pump B.1 Initiate action to Imediately operation not limited limit pump operation as specified in Table as specified in Table 3.4.12-1. 3.4.12-1.

l C. An accumulator not C.1 Isolate affected I hour isolated when the accumulator.

accumulator pressure is greater than or equal to the maximum RCS pressure for existing cold leg temperature allowed in Specification 3.4.3.

(continued)

Catawba Unit 1 3.4-32 5/11/98

LTOP System l I

3.4.12 ACTIONS (continued)

CONDITION REQi' IRED ACTION COMPLETION TIME j l D. Required Action and 0.1 Increase RCS cold leg 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months l associated Completion temperature to Time of Condition C > 285"F. l not met.

E D.2 Depressurize affected 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months l accumulator to less than the maximum RCS pressure for existing

, cold leg temperature allowed by Specification 3.4.3.

1 E. One PORV inoperable in E.1 Restore PORV to 7 days l MODE 4. OPERABLE status.

F. One PORV inoperable in F.1 Restore PORV to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months l l MODE 5 or 6. OPERABLE status. j G. Two PORVs inoperable. G.1 Depressurize RCS and 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months l establish RCS vent of !

QR lt 4.5 square inches. l Required Action and 1 associated Completion !

Time of Condition A, ;

D, E, or F, not met. l !

M LTOP System inoperable for any reason other !

than Condition A, C, '

D, E, or F.

Catawba Unit 1 3.4-33 5/11/98 l

l.

l- LTOP System 3.4.12 Table 3.4.12-1 (Page 1 of 1) 1 Reactor Coolant Pump Operating Restrictions for Low Temperature Overpressure Protection Reactor Coolant System Cold Leg Maximum Number of Pumps Allowed in Temperature Operation 1

2 67*F 1

, i l

2 68*F 2 2 73*F 4 i

l j Catawba Unit 1 3.4-36 5/11/93

. _ _ _ _ _ _ _ - . _ _ . _ . _ _ . . .__. __. __. _. __-. - _- a

RCS Operational LEAKAGE 3.4.13 3.4' REACTOR COOLANT SYSTEM (RCS) 3.4.13 RCS Operational LEAKAGE LC0 3.4.13 RCS operational LEAKAGE shall be limited to:

a. No pressure boundary' LEAKAGE;

.b. 1 gpm unidentified LEAKAGE;

c. 10 gpm identified LEAKAGE;

d. 576 gallons per day total primary to secondary LEAKAGE through all steam generators (SGs);.and

e. 150 gallons per day primary to secondary LEAKAGE through any one SG.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. :RCS LEAKAGE not within A.1 Reduce LEAKAGE to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months limits for reasons- within limits.

Other than pressure boundary LEAKAGE.

I I

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months l associated Completion Time of Condition A A!E!

not met.

l B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

! gg

' Pressure boundary LEAKAGE exists.

Catawba Unit 1 3.4-37 5/11/98

RCS Operational LEAKAGE 3.4.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.13.1 -------------------NOTE-------------------- -----NOTE------

Not required to be perforned in MODE 3 or 4 Only required until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of steady state operation. to be perforned

during steady state operation Verify RCS Operational LEAKAGE within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months limits by performance of RCS water inventory balance.

l SR 3.4.13.2 Verify steam generator tube integrity is in In accordance accordance with the Steam Generator Tube with the Steam Surveillance Program. Generator Tube Surveillance Program I

l l

Catawba Unit 1 3.4-38 5/11/98

1 RCS PIV Leakage 3.4.14 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage LCO 3.4.14 Leakage from each RCS PIV shall be within limit.

APPLICABILITY: MODES 1, 2, and 3, MODE 4, except valves in the residual heat removal (RHR) flow path when in, or during the transition to or from, the RHR mode of operation.

ACTIONS

NOTES------------------------------------

1. _ Separate Condition entry is allowed for each flow path.

2.- Enter applicable Conditions and Required Actions for systems made inoperable by an inoperable PIV.

4 CONDlIION REQUIRED ACTION COMPLETION TIME A. One or more flow paths ------------NOTE-------------

with leakage from one Each valve used to satisfy or more RCS PIVs not Required Action A.1 must have within limit. been verified to meet SR 3.4.14.1 and be in the reactor coolant pressure boundary or the high pressure portion of the system.

(continued) l l

l Catawba Unit 1 3.4-39 5/11/98 l

L. . _ _ . _ _ _ _ _ . _ _ _ . . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _

RCS PIV Leakage 3.4.14 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.1 Isolate the high 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months pressure portion of the affected system from the low pressure portion by use of one closed manual, deactivated I automatic, or check l valve.

AND A.2 Restore RCS PIV to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months within limits.

l B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time for Condition A AEQ not met. 4 B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months l l

1 C. RHR System interlock C.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months function inoperable. penetration by use of one closed manual or deactivated automatic valve. !

Catawba Unit 1 3.4-40 5/11/98

RCS PIV Leakage 3.4.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.1 -------------------NOTES--------------___--

1. Not required to be performed in MODES-3 and 4.

2. Not required to be performed on the RCS PIVs located in the RHR flow path when in the shutdown cooling mode of operation.

I

3. RCS PIVs actuated during the performance of this Surveillance are not required to be_ tested more than once if a repetitive testing loop cannot be avoided.

Verify leakage from each RCS PIV is In accordance equivalent to s 0.5 gpm per nominal inch of with the valve size up to a maximum of 5 gpm at an Inservice RCS pressure 1 2215 psig and s 2255 psig. Testing Program, and 18 months AND Prior to entering MODE 2 whenever the unit has been in MODE 5 for )

7 days or more, i if leakage ;

testing has not been performed in the previous 9 nonths AMD (continued)

Catawba Unit 1 3.4-41 5/11/98 i

l

l RCS PIV Leakage 3.4.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY l

i SR 3.4.14.1 (continued) Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months l following valve actuation due to autelatic or manual action )

or flow through !

the valve SR 3.4.14.2 Verify RHR system interlock prevents the 18 months valves from being opened with a simulated or actual RCS pressure signal 2 425 psig.

l l

l 1

l l

Catawba Unit 1 3.4-42 5/11/98

RCS Leakage Detection Instrumentation 3.4.15 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.15 RCS Leakage Detection Instrumentation LCO 3.4.15 The following RCS leakage detection instrumentation shall be OPERABLE:

a. One containment floor and equipment sump level monitor;

b. One containment atmosphere radioactivity monitor (gaseous or particulate); and

c. One containment ventilation unit condensate drain tank level monitor.

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

ACTIONS

NOTE------------------------------

LC0 3.0.4 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Required containment A.1 Perform SR 3.4.13.1. Once per !

floor and equipment 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months sump level monitor AHQ inoperable.

A.2 Restore required 30 days containment floor and equipment sump level monitor to OPERABLE status. .

l (continued) j 1

l l

l I

l Catawba Unit 1 3.4-43 5/11/98 l

RCS Leakage Detection Instrumentation 3.4.15 I

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required containment B.1 Analyze grab samples Once per atmosphere of the containment 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months radioactivity monitor atmosphere.

inoperable.

B.2 Perform SR 3.4.13.1. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months C. Required containment C.1 Perform SR 3.4.15.1. Once per ventilation unit 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months condensate drain tank E level monitor inoperable. C.2 Perform SR 3.4.13.1. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months l

D. Required containment D.1 Restore required 30 days atmosphere containment radioactivity monitor atmosphere inoperable. radioactivity monii.or to OPERABLE status.

]

E .

Required containment !

' ventilation unit D.2 Restore required 30 days condensate drain tank containment level monitor ventilation unit !

inoperable. condensate drain tank level monitor to OPERABLE status.

l l

o E. Required Action and E.1 Be in-MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. E E.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

Catawba Unit 1 3.4-44 5/11/98

1. RCS Leakage Detection Instrumentation 3.4.15 ACTIONS (continued) l CONDITION REQUIRED ACTION COMPLETION TIME

' F. All' required monitors F.1 Enter LC0 3.0.3. Immediately inoperable.

r SURVEILLANCE REQUIREMENTS

l. SURVEILLANCE FREQUENCY y

SR 3.4.15.1- Perform CHANNEL CHECK of the required 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months containment atmosphere radioactivity monitor.

l SR 3.4.15.2 Perform COT of the required containment 92 days atmosphere radioactivity monitor.

-SR 3.4.15.3 . Perform CHANNEL CALIBRATION of the required. 18 months containment floor and equipment sump level monitor.

SR 3.4.15.4- Perform CHANNEL CALIBRATION of the required. 18 months containment atmosphere radioactivity monitor.

v- . -

SR 3.4.15.5 Perform CHANNEL CALIBRATION of the required 18 months containment ventilation unit condensate drain tank level monitor.

I L

Catawba Unit 1l 3.4-45 5/11/98.

RCS Specific Activity 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 The specific activity of the reactor coolant shall be within limits.

APPLICABILITY: ~ MODES 1 and 2, MODE 3 with RCS average temperature (T.,,) a 500*F.

ACTIONS-1

. CONDITION -REQUIRED ACTION COMPLETION TIME A. DOSE' EQUIVALENT I-131 ------------Note------------

> 1.0 Ci/gm. LC0 3.0.4 is not applicable.

A.1 Verify DOSE Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months EQUIVALENT I-131 within the acceptable region of 1 Figure 3.4.16-1.

M A.2 Restore DOSE- 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months EQUIVALENT I-131 to within limit.

B. Gross specific B.1 Be in MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

-activity of the T.,, < 500*F.

reactor coolant not within limit.

(continued) i i

1

.)

. i Catawba Unit 1 3.4-46 5/11/98

L RCS Specific Activity 3.4.16 l

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion T.,, < 500*F.

, Time of Condition A

-not met.

1

[8 DOSE EQUIVALENT I-131 in the unacceptable region of

-Figure 3.4.16-1.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1- Verify reactor coolant gross specific 7 days activity s'100/E Ci/gm.

SR 3.4.16.2 -------------------NOTE--------------------

Only._ required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT 14 days I-131 specific activity s 1.0 Ci/gm.

AM!

Between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after a THERMAL l POWER change of a 15% RTP within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period (continued)

-Catawba Unit 1 3.4-47 5/11/98

RCS Specific Activity 3.4.16 1

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR -3.4.16.3 -------------------NOTE-------------------- ,

j Not required to be performed until 31 days l after a minimum of 2 effective full power days and 20 days of MODE 1 operation have elapsed since the' reactor was last l subcritical for 2 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

l Determine E from a sample taken in MODE 1 184 days 3 after a minimum of 2 effective full power I days and 20 days of MODE 1 operation have elapsed since the reactor was last subcritical for a 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

l Catawba Unit-1 3.4-48 5/11/98 l

1 l

l RCS Specific Activity 3.4.16 i

300 l

250

\

l U

2 200 ik UNACCEPTABLE OPERATION kg5 81 o,g350

!l N2

\

IE i E

n 100 8

w E ACCEPTABLE 8 OPERATION 50 0

20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER Figure 3.4.16-1 (page 1 of 1)

Reactor Coolant DOSE EQUIVALENT I-131 Specific Activity Limit Versus Percent of RATED THERMAL POWER l

Catawba Unit 1 3.4-49 5/11/98 i

l

RCS Loops-Test Exceptions 3.4.17 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.17 RCS Loops-Test Exceptions

)

LC0 3.4.17 The requirements of LC0 3.4.4, "RCS Loops-MODES I and 2,"

may be suspended, with THERMAL POWER < P-7.

I APPLICABILITY: MODES 1 and 2 during startup and PHYSICS TESTS.

{

l ACTIONS

' CONDITION REQUIRED ACTION COMPLETION TIME l'

l A. THERMAL POWER 2 P-7. A.1 Open reactor trip Innediately breakers.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.17.1 Verify THERMAL POWER is < P-7 . I hour SR 3.4.17.2 Perform a COT for each power range neutron Prior to flux-low and intermediate range neutror, initiation of flux channel and P-7. startup and PHYSICS TESTS l

l l

-Catawba Unit 1 3.4-50 5/11/98 l

l

RCSP/TLimits B 3.4.3 BASES )

ACTIONS C.1 and C.2 (continued)

Condition C is modified by a Note requiring Required Action C.2 to be completed whenever the Condition is entered. The Note emphasizes the need to perform the evaluation of the effects of the excursion outside the allowable limits. Restoration alone per Required Action C.1 is insufficient because higher than analyzed stresses may have occurred and may have affected the RCPB integrity.

SURVEILLANCE SR 3.4.3.1 REQUIREMENTS Verification that operation is within the specified limits is required every 30 minutes when RCS pressure and temperature conditions are undergoing planned changes. This Frequency is considered reasonable in view of the control room indication available to monitor RCS status. Also, since temperature rate of change limits are specified in hourly increments, 30 minutes permits assessment and correction for minor deviations within a reasonable time.

Surveillance for heatup, cooldowr., or ISLH testing may be discontinued when the definition given in the relevant plant procedure for ending the activity is satisfied.

This SR is modified by a Note that only requires this SR to be performed during system heatup, cooldown, and ISLH testing. No SR is given for criticality operations because LCO 3.4.2 contains a more restrictive requirement.

REFERENCES 1. . 10 CFR 50, Appendix G.

2. ASME, Boiler and Pressure Vessel Code,Section III, Appendix G.

l '3. ASTM E 185-73, 1973.

4. 10 CFR 50, Appendix H.

l (continued)

I Catawba Unit 1 B 3.4-16 9/9/97 l

w-__-__-___________---_-____ _ _ _ _ _ _ _ _ _ _ _ _ - - _ i

LTOP System B 3.4.12 B 3.4 REACTOR COOLANT SYSTEM (RCS)

B 3.4.12 Low Temperature Overpressure Protection (LTOP) System BASES BACKGROUND The LTOP System controls RCS pressure at low temperatures so the integrity of the reactor coolant pressure boundary (RCPB) is not com temperature (P/T)limits promised by violating of 10 CrR the pressure 50, Appendix G (Ref. and 1).

The reactor vessel is the limiting RCPB component for demonstrating such protection. This specification provides the maximum allowable actuation logic setpoints for the power operated relief valves (PORVs) and LC0 3.4.3, "RCS Pressure and Temperature (P/T) Limits," provides the maximum RCS pressure for the existing RCS cold leg temperature during cooldown, shutdown, and heatup to meet the Reference 1 requirements during the LTOP MODES.

The reactor vessel material is less tough at low temperatures than at normal operating temperature. As the !

vessel neutron exposure accumulates, the material toughness ;

decreases and becomes less resistant to pressure stress at '

low temperatures (Ref. 2). RCS pressure, therefore, is maintained low at low temperatures and is increased only as temperature is increased.

The potential for vessel overpressurization is most acute when the RCS is water solid, occurring only while shutdown; a pressure fluctuation can occur more quickly than an j operator can react to relieve the condition. Exceeding the RCS P/T limits by a significant amount could cause brittle l cracking of the reactor vessel. LC0 3.4.3 requires administrative control of RCS pressure and temperature ;

during heatup and cooldown to prevent exceeding the j specified limits. '

This LC0 provides RCS overpressure protection by having a minimum coolant input capability and having adequate pressure relief capacity. Limiting coolant input capability requires all but one charging pump or one safety injection i pump incapable of injection into the RCS, isolating the ;

accumulators, and limiting reactor coolant pump operation at low temperatures. The pressure relief capacity requires 1

either two redundant PORVs or a depressurized RCS and an RCS

, vent of sufficient size. One PORV or the open RCS vent is the overpressure protection device that acts to terminate an (continued)

Catawba Unit 1 B 3.4-59 5/11/98 l l

LTOP System B 3.4.12 BASES BACKGROUND increasing pressure event.

(continued)

With minimum coolant input capability, the ability to l provide core coolant addition is restricted. The LC0 does not require the makeup control system deactivated or the safety injection (SI) actuation circuits blocked. Due to the lower pressures in the LTOP MODES and the expected core i decay heat levels, the makeup system can provide adequate flow via the makeup control valve. If conditions require the use of more than one charging pump for makeup in the event of loss of inventory, then pumps can be made available through manual actions.

The LTOP System for pressure relief consists of two PORVs with reduced lift settings or a depressurized RCS and an RCS vent of sufficient size. Two PORVS are required for redundancy. One PORV has adequate relieving capability to keep from overpressurization for the required coolant input capability.

PORV Requirements As designed for the LTOP System, each PORV is signaled to open if the RCS pressure reaches 400 psig (as left calibrated), allowable value s 425 psig (as found), when the PORVS are in the "lo-press" mode of operation. If the PORVs are being used to meet the requirements of this Specification, then RCS cold leg temperature is limited to 2 65*F in accordance with the LTOP analysis. When all Reactor Coolant Pumps are secured, this temperature is measured at the outlet of the resiciual heat removal heat exchanger.

This location will provide the most conservative (lower) temperature measurement of water capable of being delivered into the Reactor Coolant System. The LTOP actuation logic monitors both RCS temperature and RCS pressure. The signals used to generate the pressure setpoints originate from the wide range pressure transmitters. The signals used to generate the temperature permissives originate from the wide range RTDs. Each signal is input to the appropriate NSSS protection system cabinet where it is converted to an ,

internal signal and then input to a comparator to generate an actuation signal. If the indicated pressure meets or exceeds the calculated value, a P0RV is signaled to open.

This Specification presents the PORV setpoints for LTOP.

Having the setpoints of both valves within the limits (continued) l Catawba Unit 1 B 3.4-60 5/11/98

LTOP System B 3.4.12 l

BASES BACKGROUND PORV Requirements (continued) ensures that the Reference 1 limits will not be exceeded in any analyzed event. ;

When a PORV is opened in an increasing pressure transient, the release of coolant will cause the pressure increase to l

slow and reverse. As the PORV releases coolant, the RCS L i pressure decreases until a reset pressure is reached and the j valve is signaled to close. The pressure continues to decrease below the reset pressure as the valve closes.

1

! RCS Vent Requirements Once the RCS is depressurized, a vent exposed to the containment atmosphere will maintain the RCS at containment ambient pressure in an RCS overpressure transient, if the relieving requirements of the transient do not exceed the capabilities of the vent. Thus, the vent path must be l capable of relieving the flow resulting from the limiting LTOP mass or heat input transient, and maintaining pressure below the P/T limits. The required vent capacity may be provided by one or more vent paths. The vent path (s) must.

be above the level of reactor coolant, so as not to drain l the RCS when open.

~ APPLICABLE Safety analyses (Ref. 3) demonstrate that the reactor vessel l SAFETY ANALYSES is adequately protected against exceeding the Reference.1 P/Tlimits. In MODES 1, 2, and 3, and in MODE 4 with RCS cold leg temperature exceeding 285*F, the pressurizer safety valves will prevent RCS pressure from exceeding the Reference 1 limits. At about 285*F and below, overpressure prevention falls to two OPERABLE PORVs or to a depressurized RCS and a sufficient sized RCS vent. Each of these means has a limited overpressure relief capability.

The actual temperature at which the pressure in the P/T limit curve falls below the pressurizer safety valve !

setpoint increases as the reactor vessel material toughness l decreases due to neutron embrittlement. Each time the P/T i

curves 'are revised, the LTOP System must be re-evaluated to I ensure its functional requirements can still be met using the PORV method or the depressurized and vented RCS condition.

(continued) l Catawba Unit-1 B 3.4-61 5/11/98 l ;

I

{ -___ ____-_-__ ___

l LTOP System B 3.4.12 BASES APPLICABLE Any change to the RCS must be evaluated against the SAFETY ANALYSES Reference 3 analyses to determine the impact of the change (continued) on the LTOP-acceptance limits.

Transients that are capable of overpressurizing the RCS are categorized as either mass or heat input transients, examples of which follow:

Mass Inout Tvoe Transients

a. Inadvertent safety injection; or l i

b. Charging / letdown flow mismatch.

]

Heat Inout Tvoe Transients

a. Inadvertent actuation of pressurizer heaters;

b. Loss of RHR cooling; or

c. Reactor coolant pump (RCP) startup with temperature asymmetry within the RCS or between the RCS and steam ,

generators.

The following are required during the LTOP MODES to ensure j that mass and heat input transients do not occur, which i either of the LTOP overpressure protection means cannot handle:

a. Rendering all but one charging pump or one safety injection pump incapable of injection;

b. Deactivating the accumulator discharge isolation

'l valves in their closed positions; l l

c. Limiting RCP operation based on the existing )

temperature in the RCS cold legs; and

d. Disallowing start of an RCP if secondary temperature is more than 50 F above primary temperature in any one loop. LCO 3.4.6, "RCS Loops -MODE 4," and LC0 3.4.7, l "RCS Loops-MODE 5, Loops Filled," provide this protection.

The Reference 3 analyses demonstrate that either one PORV or the depressurized RCS and RCS vent can maintain RCS pressure l

(continued) l Catawba Unit 1 B 3.4-62 5/11/98 i

l l l I

l l LTOP System l

8 3.4.12 BASES APPLICABLE Heat Inout Tvoe Transients (continued)

SAFETY ANALYSES below limits when only one charging pump or one safety injection pump is actuated. Thus, the LC0 allows only one charging pump or one safety injection pump OPERABLE during the LTOP MODES. Since neither one PORV nor the RCS vent can handle the pressure transient from accumulator injection when RCS temperature is low, the LC0 also requires the accumulators isolation when accumulator pressure is greater than or equal to the maximum RCS pressure for the existing RCS cold leg temperature allowed in LC0 3.4.3.

The isolated accumulators must have their discharge valves closed and the valve power supply breakers fixed in their open positions.

The restrictions on the number of RCPs in operation at a given temperature ensures that during a LTOP mass injection event that the pressure / temperature (P/T) limits of 10 CFR 50, Appendix G to protect the reactor vessel are not exceeded. During startup and shutdown, when the RCPs are '

operated, their induced flows create a pressure drop across the vessel. This pressure drop along with the difference in elevation between the beltline region and the instrumentation locations are additive to the peak pressure from the mass injection event.

The amount of the pressure at the reactor vessel beltline region from the RCPs is dependent on the number of RCPs operated. AdequatemargintopreventexceedingtheP/T limits is assured by restricting the number of RCPs operated. Since LTOP events are basically. acknowledged as being steady-state events, these RCP operating restrictions are designed to work with the LTOP setpoint to provide protectionfromexceedingthesteady-stateAppendixGP/T limits.

Fracture mechanics analyses established the temperature of LTOP Applicability at 285'F.

The consequences of a small break loss of coolant accident (LOCA) in LTOP MODE 4 conform to 10 CFR 50.46 and 10 CFR 50, Appendix K (Refs. 4 and 5), requirements by having a maximum of one charging pump OPERABLE and SI actuation enabled.

i (continued) l Catawba Unit 1 B 3.4-63 5/11/98 l l

l l

_ . _ _ _ _ _ ._J

LTOP System B 3.4.12

' BASES APPLICABLE PORV Performance SAFETY ANALYSES (continued) The fracture mechanics analyses show that the vessel is protected when the PORVs are set to open at or below the s)ecified limit. The setpoints arc derived by analyses t1atmodel the performance of the LTOP System, assuming the limiting LTOP transient of one charging pump or one safety injection pump injecting into the RCS. These analyses consider pressure overshoot and undershoot beyond the PORV opening and closing, resulting from signal processing and valve stroke times. The PORV setpoints at or below the derived limit ensures the Reference 1 P/T limits will be net.

)

The PORV setpoints will be updated when the revised P T limits conflict with the LTOP analysis limits. The P T limits are periodically modified as the reactor vesse material toughness decreases due to neutron embrittlement i caused by neutron irradiation. Revised limits are '

determined using neutron fluence projections and the results of examinations of the reactor vessel material irradiation surveillance specimens. The Bases for LC0 3.4.3, "RCS Pressure and Temperature (P/T) Limits," discuss these examinations.

The PORVs are considered active components. 'Thus, the failure of one PORV is assumed to represent the worst case, single active failure.

RCS Vent Performance With the RCS depressurized, analyses show a vent size of 4.5 square inches is capable of mitigating the allowed LTOP overpressure transient. The capacity of a vent this size is greater than the flow of the limiting transient for the LTOP configuration, one charging pump or one safety injection pump OPERABLE, maintainin RCS pressure less than the maximum pressure on the P T limit curve.

The RCS vent size will be re-evaluated for compliance each time the P/T limit curves are revised based on the results ;

of the vessel material surveillance. '

The RCS vent is passive and is not subject to active 1 failure.

The LTOP System satisfies Criterion 2 of 10 CFR 50.36 )

l (Ref. 6). ,

i (continued) l Catawba Unit 1 B 3.4-64 5/11/98 I i

l LTOP System l B 3.4.12 BASES-(continued) l LC0 This LC0 requires that the LTOP System is OPERABLE. The l LTOP System is OPERABLE when the minimum coolant input and pressure relief capabilities are OPERABLE. Violation of this LC0 could lead to the loss of low temperature overpressure mitigation and violation of the Reference 1 limits as a result of- an operational transient.

l To limit the coolant input capability, the LC0 permits a maximum of one charging pump or one safety injection pump capable of injecting into the RCS and requires all accumulator discharge isolation valves closed and immobilized when accumulator pressure is greater than or equal to the maximum RCS pressure for the existing RCS cold leg temperature allowed in LC0 3.4.3. The LC0 also limits RCP operation based on existing RCS cold leg temperature as required by the LTOP analysis.

The elements of the LC0 that provide low temperature overpressure mitigation through pressure relief are:

a. Two OPERABLE PORVs (NC-32B and NC-34A); or A PORV is OPERABLE for LTOP when its block valve is j open, its lift setpoint is set to the specified limit and testing proves its ability to open at.this setpoint, and motive power is available to the valve and its control circuit.

b. A depressurized RCS and an RCS vent.

An RCS vent 1s OPERABLE when open with an area of 2 4.5 square inches. )

Each of these methods of overpressure prevention is capable '

of mitigating the limiting LTOP transient.

APPLICABILITY This LC0 is applicable in MODE 4 when any RCS cold leg temperature is s 285*F, in MODE 5, and in MODE 6 when the reactor vessel head is on. The pressurizer safety valves provide overpressure protection that meets the Reference 1 P/Tlimitsabove285*F. When the reactor vessei head is off, overpressurization cannot occur. !

(continued) 4 Catawba Unit 1 B 3.4-65 5/11/98 l i

LTOP System B 3.4.12 BASES APPLICABILITY LC0 3.4.3 provides the operational P/T limits for all MODES.

(continued) LC0 3.4.10. " Pressurizer Safety Valves," requires the OPERABILITY of the pressurizer safety valves that provide overpressure protection during MODES 1, 2, and 3, and MODE 4 above 285"F.

Low temperature overpressure prevention is most critical during shutdown when the RCS is water solid, and a mass or heat input transient can cause a very rapid increase in RCS pressure when little or no time allows operator action to mitigate the event.

The Applicability is modified by a Note stating that j accumulator isolat .on is only required when the accumulator j pressure is more than or at the maximum RCS pressure for the j existingtemperature,asallowedbytheP/Tlimitcurves. .

This Note permits the accumulator discharge isolation valve Surveillance to be performed only under these pressure and temperature conditions.

1 I

. ACTIONS LC0 3.0.4 is not applicable for entry.into LTOP operation.

L.1 With two or more charging pumps, two safety injection pumps,

, or one safety injection pump and one charging pump capable l of injecting into the RCS, RCS overpressurization is possible.

1 i To immediately initiate action to restore restricted coolant input capability to the RCS reflects the urgency of removing the RCS from this condition.

Required Action A.1 is modified by a Note that permits two charging pumps capable of RCS injection for s 15 minutes to allow for pump swaps.

I L1 With RCP operation not limited in accordance with Table l 3.4.12-1, RCS overpressurization is possible.

To immediately initiate action to limit pump operation reflects the urgency of removing the RCS from this condition.

(continued) j I

l Catawba Unit 1 B 3.4-66 5/11/98

LTOP System B 3.4.12 l

BASES l ACTIONS C.1. D.1. and D.2 l (continued)

An unisolated accumulator requires isolation within I hour.

This is only required when the accumulator pressure is at or more than the maximum RCS pressure for the existing temperatureallowedbytheP/Tlimitcurves.

If isolation is needed and cannot be accomplished in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , Required Action D.1 and Required Action D.2 provide two l options, either of which must be performed in the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . By increasing the RCS temperature to > 285'F, an accumulator pressure of 678 psig cannot exceed the LTOP limits if the accumulators are fully injected.

Depressurizing the accumulators below the LTOP limit also gives this protection.

The Completion Times are based on operating experience that these activities can be accomplished in these time periods ,

and on engineering evaluations indicating that an event j requiring LTOP is not likely in the allowed times. '

Ed I In MODE 4 when any RCS cold leg temperature is s 285'F, with one PORV inoperable, the PORV must be restored to OPERABLE status within a Completion Time of 7 days. Two PORVs are required to provide low temperature overpressure mitigation l while withstanding a single failure of an active component.

The Completion Time considers the facts that only one of the PORVs is required to mitigate an overpressure transient and that the likelihood of an active failure of the remaining valve path during this time period is very low, f_d l

-The consequences of operational events that will overpressurize the RCS are more severe at lower temperature (Ref. 7). Thus, with one of the two PORVs inoperable in MODE 5 or in MODE 6 with the head on Completion Time to restore two valves to OPERABLE status is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The Completion Time represents a reasonable time to investigate and repair several types of relief valve failures without exposure to a lengthy period with only one OPERABLE PORV to protect against overpressure events. l (continued) i Catawba Unit 1 B 3.4-67 5/11/98 l l

1

l l

LTOP System B 3.4.12 i BASES l l l ACTIONS ful (continued)

The RCS must be depressurized and a vent must be established within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months when:

a. Both PORVs are inoperable; or j

b. A Required Action and associated Completion Time of I l Condition A, D, E, or F is not met; or

c. The LTOP System is inoperable for any reason other l than Condition A, C, D, E, or F.

The vent must be sized :t 4.5 square inches to ensure that the flow capacity is greater than that required for the worst case mass input transient reasonable during the applicable MODES. This action is needed to protect the RCPB from a low temperature overpressure event and a possible 4 brittle failure of the reactor vessel.

The Completion Time considers the time required to place the plant in this Condition and the relatively low probability of an overpressure event during this time period due to increased operator awareness of administrative control requirements.

SURVEILLANCE SR 3.4.12.1 and SR 3.4.12.2 REQUIREMENTS To minimize the potential for a low temperature overpressure event by limiting the mass input capability, all but one charging or safety injection pump is verified incapable of injecting into the RCS and the accumulator discharge isolation valves are verified closed and locked out.

The pumps are rendered incapable of injecting into the RCS through removing the power from the pumps by racking the breakers out under administrative control. An alternate method of LTOP control may be employed using at least two independent means to prevent a pump start such that a single failure or single action will not result in an injection into the RCS. This may be accomplished through two valves i in the discharge flow path being closed.

The Frequency of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is sufficient, considering other (continued) <

l Catawba Unit 1 B 3.4-68 5/11/98 l

l u_____ _

LTOP System B 3.4.12 BASES l

l SURVEILLANCE SR 3.4.12.1 and SR 3.4.12.2 (continued)

REQUIREMENTS l

(continued) indications and alarms available to the operator in the control room, to verify the required status of the equipment.

SR 3.4.12.3

~The RCS vent of 2 4.5 square inches is proven OPERABLE by verifying its open condition either:

a. Once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for a valve that cannot be locked.

b. Once every 31 days for a valve that is locked, sealed, or secured in position. A removed pressurizer safety valve fits this category, i The passive vent arrangement must only be open to be OPERABLE. This Surveillance is required to be performed if the vent is being used to satisfy the pressure relief requirements of the LC0 3.4.12b.

SR 3.4.12.4 The PORV block valve must be verified open every 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to provide the flow path for each required PORV to perform its function when actuated. The valve must be remotely verified open in the main control room. This Surveillance is performed if the PORV satisfies the LCO.

The block valve is a remotely controlled, motor operated valve. The power to the valve operator is not required removed, and the manual operator is not required locked in the inactive position. Thus, the block valve can be closed in the event the PORV develops excessive leakage or does not close (sticks open) after relieving an overpressure i

situation.

l The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Frequency is considered adequate in view of i other administrative controls available to the operator in the control room, such as valve position indication, that verify that the PORV block valve remains open.

l (continued) l Catawba Unit 1 B 3.4-69 5/11/98 l l

LTOP System B 3.4.12 BASES

. SURVEILLANCE SR 3.4.12.5 REQUIREMENTS (continued) Performance of a COT is required within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after decreasing RCS temperature to s 285'F and every 31 days on each required PORV to verify and, as necessary, adjust its lift setpoint. = The COT will verify the setpoint is within the allowed maximum limits. PORV actuation could depressurize the RCS and is not required.

The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Frequency considers the unlikelihood of a low temperature overpressure event during this time.

A Note has been added indicating that this SR is required to be met 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after decreasing RCS cold leg temperature to

-; 285'F. The COT cannot be performed until in the LTOP MODES when the PORV lift setpoint can be reduced to the LTOP setting. The test must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering the LTOP MODES.

SR 3.4.12.6 Performance of a CHANNEL CALIBRATION on each required PORV actuation channel is required every 18 months to adjust the whole channel so that it responds and the valve opens within the required range and accuracy to known input.

l REFERENCES 1. 10 CFR 50, Appendix G.

! 2. Generic Letter 88-11.

! 3. UFSAR, Section 5.2 !

4. 10 CFR 50, Section 50.46.

5. 10 CFR 50, Appendix K.

l

6. 10 CFR 50.36. Technical Specifications, (c)(2)(ii). l

7. Generic Letter 90-06.

l l Catawba Unit ' B 3.4-70 5/11/98

Discussien of Changes l Ssetien 3.4 - R:acter Coolant System 1

TECHNICAL CHANGES - MORE RESTRICTIVE 1

on plant operation since a limit of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of steady state operation has been included which the CTS does not include. This change is consistent with NUREG-1431.

M.14 A note has been added to CTS 3.4.6.2 action c which indicates valves used to isolate a leaking RCS PIV must have been verified to meet the same leakage limit requirements. This is more restrictive since the CTS does not require the valves to actually be leak tested. The note, retained in ITS 3.4.14, is consistent with NUREG-1431.

M.15 Not used.

M.l6 Nof USed.c.r.e. ..a.n...,

, 4... . __m.4. ,. _ a 4. .- 4.. ., ., m. ..J .-

, 13 m r. ...t. _

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RCS, : =c11 :: requiring the i:clation of the ::cumulater;.

Th ;; requirc ^nt; have been : t in the p :t with :dmini;trativ:

ntr:1; and in :::crd nce with TS requirement; lo: ted in varica;

...4. u. ._ _. ,.r..

_ _ _ 4. r. 4. ,.., 4 4. .- _. ,. ,

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n :b r Of chargir.; p; p; :nd ;;fety injceti:n p; p; c:hich ::n bc

, 4_,4 T..L.. 4. e. .L...,_.,.,

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,mm 4 ., 4. ._. . .J 4.... T.T. .c, 3.'.'2, i con f; tent with :::umpti:n: ::dc in the analy:::

___<___ .u-

r. . . . . - .a 4. -.., 4.

.. ., u , 4. ,. u. . . . . .._____,,..___444._.,44..__..

...r......m y ,m,4.-_-.

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. ... , _. n...,._,._m._.4.,,

....4.,4.-_.4 .. ._

. . 4 4. .L. 1 the new LCO requirc=ent and ;y;te : Operati:n. The ::ve::nt Of )

existing requirement; is admini:trative, h wever th Overall change; cre =:re restrictive. The change; are : n;i; tent with unner sa,s n.n.. +7 4 e M.17 The frequency of CTS SR 4.1.2.3.2 and 4.1.2.4.2 has been changed )

from 31 days to verify all but one charging pump is inoperable to

.12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to verify a maximum of one charging pump is capable of l injection. This change, retained in ITS SR 3.4.12.1, is more l restrictive, however, it is appropriate since the pump no longer ;

I will specifically require that power be removed or that valves be locked into position as described in a Less Restrictive-Removal of Detail change (LA. 9) Administrative controls to ensure that the pumps are not capable of injection are still required, however. ,

This change is consistent with NUREG-1431. !

Catawba Units 1 and 2 Page M - 45 5/11/985/20/97-l l

6 _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Discussi:n of Ching;s S;cticn 3.4 - R; actor Coolant System TECHNICAL CHANGES - RFMOVAl 0F DFTAll and cooldown limitations are contained in CTS 3.4.9.2. This clarification is not necessary for inclusion within the LCO and is relocated to the Bases for ITS 3.4.3. This change does not affect the requirements for RCS heatup and cooldown which are retained in LCO 3.4.3. Changes to the Bases are controlled in accordance with the administrative requirements in ITS Chapter 5. This change is consistent with NUREG-1431.

LA.15 The details in a footnote to CTS LCO 3.4.9.3.a regarding how the RCS temperature measurement is obtained when using the PORVs have been moved to the Bases for ITS 3.4.12. Details of where temperature measurements are taken are more appropriate for the Bases and are not necessary for inclusion in the TS. Changes to the Bases are controlled in accordance with the administrative requirements in ITS Chapter 5. This change is consistent with NUREG-1431.

l I

Catawba Units 1 and 2 Page LA - 443 Supplement 55/20/97l

l t

l I

Revised NUREG-1431 Marked-up Pages (NOTE: DUKE's 9/15/97 ORIGINAL ANENDNENT REQUEST DID NOT l znCLETDE REVXsED NUREG-1431 NARKED-Ur rAQsBf THERErORE, RuvxsmD rAQss ARs mzzm xaczUDsD rOR Att cnAnass rROrOszD BOTH IN Tax ORIGINAL AnxNDencNT REQUssT AND THrs SUrPLauxNT.)

)

l l

i

-l

. j l I L-____---___________- _ _ _ _. --

INSERT 5 (Unit 1) 6 MATERI.4L PROPERTY BASIS ,

UMITING MATERIAL LOWER SHELL FORGING 04 l LIMTING ART AT15 EFPY: 1/4-T, ?3*F 3/4-T, 26*F i

2,500 i i i i i i i i i i i i ,. ,

i LEAK TEST LIMIT-- / 1

/ 7 2,250 l l :'

l .] , 1

~r i

/-- -J L

i i

i ,

_--4 2,000 ' ' '

i, ,

Q em il I I _

j

(/) ._.-_._ f '

l cl. 1 ,7 5 0 ----

UNACCEPTABLE ,/ / l

OPERATION il / -

O I / '

/ !

hi 1,500 '

/ ,

1, i y) HEATUP RATE ' k- ---

ACCEPTABLE y) , UP TO 60 F/HR -U r/ '! !

OPERATION l

2 1,250 .

--T7_ -/- :

e --_-.

y ; l i

l

/ s ,

V 1,000 /:

O , ,

w

, i i

, , i (U i

.9 750 _ 1 l

t l l ! l :

c: i i i .

1 i i.

500 '

L ,

l, , . ,,, ,, ,

-, t i , , ,a g___ 1

' CRITICALITY LIMIT BASED ON ----

INSERVICE HYDROSTATIC TEST 250 TEMPERATURE (176 F) FOR THE

! SERVICE PERIOD UP TO 15 EFPY _ ___

iii;;; i: :iiiiiiii'i'iii o

0 50 100 150 200 250 300 350 400 450 500 Indicated Temperature (Deg. F)

Figure 3.4.3-1 RCS Heatup Limitations Catawba 1 INSERT Page 3.4-6 l

INSERT 6 (Unit 1)

)

~7 MATERIAL PROPERTY BASIS ,

LIMITING MATERIAL: LJOWER SHELL FORGING 04 LIMITING ART AT 15 EFPY: 1/4-T, 43*F 3/4-T, 26*F 2,500 i l

) ____

2,250 /

2,000 ' ~~~~~'

D) 2: UNACCEPTABLE >

OPERATION

@ n.

c.1,750 '; ,

l D

/

~~ i 1

!:5 1 ,5 0 0

/ '

(/) j ACCEPTABLE .-_

(/) r OPERATION 2 1,250 / .

Q / ,! i ___..

7 ,

V 1,000 , . .

i

@ COOLDOWN i +

RATES *F/HR.

II: o P

)

' 0 750 g: :~

'5 --] ~_L._. _ _

c , ,

ggg go .

____+

,gg ,

+_.

I r I O

O 50 100 150 200 250 300 350 400 450 500 Indicated Temperature (Deg. F)

Figure 3.4.3-2 RCS Cooldown Limitations 1

Catawba 1 INSERT Page 3.4-6 l

w_ - - --- _ - - -

M8

N NT 4.

LTOP System d.f S f55O In *TAk *),ggg 3.4.12 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12 Low Temperature Overpressure Protection (LTOP) System LCO 3.4.12 An LTOP System shall be OPERABLE with a maximum ofM

[thigypreswre in.irction ()se1>J pdte ta#d one charging _

g 'T capane or. m.

isolat ofnd injecting either ainto or btne KL3. y the accumulators below S4h hjnM];

~

a. P%p #

[ Res relief vptves a Two pcnver operated relief valves (PORVs) with lift g '+00 yn,'

(s.:.I]t+ , nrsettingsqq.pq _wumn = -m <=cified in the em @ 9 C'cl } ra d aNag ' , T2. Two res uiil heat 7uiiiiival ( ) suction relief' valve with setpoints 2 [ 6.5] psig and Vgk g gp+

s [4 .5] psig. or]

(O/ W ,W 'M4 AC.J ~

[3. O ~PORV with a lift jfied in the P tting sithin the li its C#lN IE .and one RHR suctio relief i valve with a set 80 2 (,50 s f463.5] psig]'po t n [436.5] psig an The RCS depressurized and an RCS vent of h P.47] square inches.

4.5 APPLICABILITY

H00E 4 when RCS oldlegtemperatureissGIQ'F.

H00E 5, l H0DE 6 when the reactor vessel head is on.

wp l

............................ NOTE - - - - - ..

Accumulator isolation is only required when accumulator pressure is greater than or equal to the maximum RCS pressure for the existing RCS cold leg t rature allowed by the P/T limit curves provided in .

....................................(.......................

'sP.wa.D s.43 j S 3.4 27 Rev 1. 04/07/95 t

~

Y n g g,sl (o T V t l cento AmW N

l

,,__ _ . -- yog. - - - LTOP System LLO 3.0.4 n. - - -Q9pc4k . _ 5 3.4.12 ACTIONS REQUIRED ACTION COMPLETION TIME A.. Two or more [HPI] \

A.1 In iate action to Immediately Jeps Capable of Veri a maximum of ecting into the- [one] PI] pump is l

RC capable f injecting into the S. .

1

- i-w -

N -

K Two or more charging I.1 ........N0TE.....-.-.

@ pumps capable of Two charging pumps injecting into the QA may be capable of 4 RCS. injecting into the l RCS during pump swap f2!!: operation for en de,y g p o.Jore

s; 15 minutes.

..................... 3 g j S&

Initiate action to Immediately veriff a maximum of _

Ti . te Iajnk pump .pfoney charging pump gr y . e. p p f Mt * '"jacks M O' nj in o the >

=-

RCS.

1 An accumulator not . Isolate affected I hour '

isolated when the accumulator.

aceunulator pressure is greater than or equal to the maximum RCS pressure for existing cold leg temperature allowed in See , iM3]

(continued) b . kta t.h etbIu'tf Umf 0.l T. dtM ac.Non "h

.Tmndshb(y 6tta% n& hk~tet '

h4 f umpstes%

a.t spect6M i ~r kte at t pd fw2 ,.

3W .I A-1 ~Dilft. 7.t.IL-f.

)D83TS 3.4 28 Rev 1, 04/07/95 em I

W t ieuse mLi Ac+tA l- !r-9 S' w_________________

LTOP System 3.4.12 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME Required Action and N Y Increase RCS cold leg 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Comple t ture to Time of Conditioq > 'F.

not set. F I

( k

\ . Depressurize affected 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months accumulator to less than the maximum RCS pressure for existing _

a , b S 8"bS f O M snr pnv f gg7 Lv One jaj \ .

Restrey M 7 days inoperable in MODE 4. OPERABLE status.

l' redAGS 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

DE inoperable in MODE 5 a OPERABLE status.

or 6.

(continued)

M 3.4 29 Rev 1, 04/07/95 s

Q g)g K $

LTOP System 3.4.12 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

[PoRV5) 'g 9 inoperable.

e afs n f h square inc s. .

Required Action and associated Completion of Condit n A.

not

errr E

LTOP System inoperable for any reason o than Cond ion CD see W

SURVEILLANCE REQUIREMENTS SURVLILLANGL ggy SR 3.4.12.1 V f a maxistan of [one] I] pum '

apabfe of injecting in)d the RCS. p i [

@ (ov o.e d 43 6.ht b r= " P] _

SR3.4.12/ Verif a maximum of one charging pumplis 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months y_ capab e of injecting into the RCS A SR 3.4.12 Verify each accumulator is isolated. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (continued)

M 3.4 30 Rev 1, 04/07/95 catwL

' pc6 ame,dmt AcM 5'Mf

(.

l LTOP System 3.4.12 SURVEILLANCE REQUIPIHENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.12 Perform CHANNEL CALIBRATION for each required PORV actuation chanrel. ' A18[ months

)

S[stnr TABLv s.slp &

l l

M 3.4 32 Rev 1. 04/07/95 m

~

bee,vse Awa/So/

1 kW Gu=n _

INSERT l Table 3.4.12-1 (Page 1 of 1) l l

l Reactor Coolant Pump Operating Restrictions for Low l Temperature Overpressure Protection l I

Reactor Coolant System Cold Leg Maximum Number of Pumps Allowed in Temperature Operation I

2 67*F 1 l l

l 2 68'F 2 l l

2 73*F 4 l i

l l

l l l

l l

Catawba 1 INSERT Page 3.4-32 l Ltts,4e AMewtMNT DMeb 4-i.r-7f l

RCS P/T Limits B 3.4.3 i

BASES l

ACTIONS C.1 and C.2 (continued) ,

l Condition C is modified by a Note requiring Required Action C.2 to be completed whenever the Condition is entered. The Note emphasizes the need to perform the evaluation of the effects of the excursion outside the allowable limits. Restoration alone per Required Action C.1 is insufficient because higher than analyzed stresses may

, have occurred and may have affected the RCPB integrity.

SURVEILLANCE SR 3.4.3.1 REQUIREMENTS Verification that operation is within the P b.

inits is required every 30 minutes when RCS pressur @e and temperature conditions are undergoing planned changes. This Frequency is considered reasonable in view of the control room indication available to monitor RCS status. Also since temperature rate of change limits are specified in hourly increments. 30 minutes permits assessment and correction for minor deviations within a reasonable time.

Surveillance for heatup, cooldown, or ISLH testing m$y be discontinued when the definition given in the relevant plant procedure for ending the activity is satisfied. '

This SR is modified by a Note that only requires this SR to be performed during system heatup, cooldown, and ISLH -

testing. No SR is given for criticality operations because '

LCO 3.4.2 contains a more restrictive requirement.

REFERENCES _ y e nzy A. Apr y 1975 D Q2' '10 CFR 50. Appendix G.

@. ASME, Boiler and Pressure Vessel Code. Section NI, Appendix G. g .

@ .4'. ASTN E 185-[. C1^'".

@)5. 10 CFR 50. Appendix H.

(continued)

B 3.4 15 Rev 1. 04/07/95 m v ,:, t s I

4 6-ibm., etembe.d Amitk 7-/5 97

LTOP System B 3.4.12 8 3.4 REACTOR COOLANT SYSTEM (RCS)

B 3.4.12 Low Temperature Overpressure Protection (LTOP) System BASES BACKGROUND The LTDP System controls RCS pressure at low temperatures so the integrity of the reactor coolant pressure boundary

(RCPB) is not compromised by violating the pressure and temperature (P/T) limits of 10 CFR 50. Appendix G (Ref.1).

The reactor vessel is the limitino RCP3 compotent for demonstrating such protection. m sr a(provides the f maximum allowable actuation logic setpoints for the power'y pq operated relief valves (PORVs) anothe maximum RCS pressure for the existi cold leg ature during cooloown.

NT 843 and o meet the ference I requirements

'*')Q[fh p

The reactor vessel material is less tough at low temperatures than at normal operating temperature. As the vessel nectron exposure accumulates, the saterial. toughness decreases and becomes less resistant to pressure stress at low temperatures (Ref. 2). RCS pressure, therefore, is maintained low at low temperatures and is increased,only as temperature is increased. .

I The potential for vessel overpressurization is most acute when the RCS is water solid, occurring only while shutdown; a pressure fluctuation can occur more quickly than an operator can react to relieve the condition. Exceeding the I g d b m %. RCS P/T limits by a significant amount could cause brittle fMr C44(ad -

crackina of the reactor vessel. LCO 3.4.30 iaer reissurel ena Temperatuw tr/W L1mits D requires administrate' We M W

control of HC5 pressure and t r fuMp aptab i cooldown to prevent exceeding during heatup and gt-( v6'jg This LCO provides RCS overpressure protection by having a minimum coolant input capability and having adequate

} pressure relief cyacity. Limitino coolant ' nnut eebility res all butfrar=a un- ompere inect on inrJ rA g isolatino the accu)mulators.one eTheof iniaction charging intorelier

_surepump theRncapa) gN t ; uty rwquun em pres two redundanton,s renanalvet or or w g g a depressurized RCS and an RCS vent of sufficient s' ze. eg g p. ,,, p 1:e.nevvalve or the open RCS vent is the overpressure P0AW protection device that acts to terwinate an increasing pressure event.

(continued)

B 3.4 58 Rev 1. 04/07/95 m

ub am6t .hteA b 'N

I i

LTOP System

! B 3.4.12 BASES l

BACKGROUND (continued)

With minimum coolant input capability, the ability to provide core coolant addition is restricted. The LCO does not require the makeu safety injection the lower pressure (SI)p actuation control circuits blocked.system Due to s in the LTOP NODES and the expected core deactivated or the l

decay heat levels, the mak system can provide adequate flow via the ma cont If conditions require the use of more t n one charging pump for makeup in the event of loss of inventory, then pumps can be made available through manual acticts.

The LTOP System for pressure relief consists of two PORVs

l. with reduced lif: settingsc~or 6 RHR) s re' lief 4ralves, or esidual heat femoval 3 l lief PORY and no6 RHR suction) veJor a aceryssurized RCS and an RCS vent of sutticient size.

redundancy. One w,3 Twom -wrmiven.are re11mf"vaTh has adequate required relievino for Q apability to keep from overpressurization for the requiredM J{-tk foGsa]s,

^

coolant input capability. s%0 Po. 6s lef+ cdde gg, ,', yMe , West V b afIeeUQ PORV Requirements N87 bSM 1 $

4

%* *g

j% n Aswidesigned L

for the LTOP System each PORV is signaled to qf N or<: oreecuev .. - .

- aA4an t *r-, .o neo or - k ,,, mge d JC t.4b8$ UP N1= '~'ie.TThe LTOP actuation logic monitorsggu,, , ^ y%

HCS temperature and RCS pressurayana ermines when al woui6 ion no ' .Mc ' n Lic. J.K limit is approached.

A.Cf% wive.

{ gg / rhe wide r m.$"t R

to select he lowest t 6ture i ication are auctioneered rature signal.

~

MT

. The 1 st temperatu signal is proc sed through a b 88440 484 , M funct generator )

at calculates a ressure limit for hat t rature. The alculated press e limit is then ared i L.,,pgfg',.M..'g* .. wi the ndicat RCS pressure f a wide range pre ure ; j L annel. If the tr,aicated pressure meets or exceeas the - ;

calculated value, t. PORY is signaled to oper.

This g ,(Speedkk hMIDpresents the PORV setpoints for LTOP.;The Ipo s u6.

ing a uvmally sta temperature so only rora m e tr valve g 1en aving the setpoints oT DoEn vaives within the limitijfon me PJDn ensures any analyzed that event.

the Reference 1 limits will not be exceeded in (continued)

B 3.4 59 Rev 1. 04/07/95 e

c,a Ant h+O- C- ! M8'

LTOP System B 3.4.12 I

BASES l

APPLICABLE Heat Inout Tvoe Transients SAFE 1Y ANALYSES (continued) a. Inadvertent actuation of pressurizer heaters:

l b. Loss of RfR cooling: or

c. Reactor coolant ptmp (RCP) startup with temperature asymmetry within the RCS or between the RCS and steam generators.

.. The following are required during the LTOP MODES to ensure C. Limd% {thattg,of mass and heat input transients do not occur, which wL .m.CfR aparek 4, the LTOP overpressure protection means cannot et,A %.A

.w - "

g & *Ri M @ L P * * "* charSins @

b. Deactivating the accumulator discharge isolation valves in their closed positions: @ g r o, one s4 sjdep.-[se )( Disallowing start,of an RCP if secondary temperature 4

t .

ismorethag503"Faboveprimarytemperature'inany one loop. 3.4.6, *RCS Loo I LCO 3.4.7. *RCS Loops-MODELoops 5.ps-MODE Filled *4.* and' provide this protection.

The Reference lyses demonstrate that either one @ k O O'e uvra>9 or the depressurized RCS and RCS ven n ma' ntain RCS pressure belst limits when only one i A4na)o5e cnarging WE)is r&O actuated. Tius, t L W allows only ievi nir jERABLE during @the LTOP MUDES.M : N charging A Since neither one cene3.-var 12e nor the RCS vent can handle the pressure POR'd 04 transient ($iiiB from accumulator injectiongwhen RCS i temperature is low, the LCO also requires the accumulators I isolation when accumulator pressure is greater than or equal to the maximum RCS pres the existing RCS cold leg temperature all in

! 4 o 5. Q h The isolated accumulators must have their discharge valves

. closed and the valve power supply breakers fixed in their open positions.JThe a lyses s the effect accumulator (discharg(eAsovera rower RCS emperature r nge ([175]*F (andbelp)thantha of the ([275]'F and low).

h M (continued)

B 3.4 62 Rev 1. 04/07/95 M

4 g,4 ek

INSERT l

^ l l

l l The restrictions on the number of RCPs in operation at a given temperature ensures that during a LTOP mass injection event that the pressure / temperature (P/T) limits of 10 CFR 50, Appendix G to protect '

the reactor vessel are not exceeded. During startup and shutdown, when l the RCPs are operated, their induced flows create a pressure drop across l the vessel. This pressure drop along with the difference. in elevation between the beltline region and the instrumentation locations are additive to the peak pressure from the mass injection event.

l The amount of the pressure at the reactor vessel beltline region from the RCPs is dependent on the number of RCPs operated. Adequate margin to prevent exceeding the P/T' limits is assured by restricting the number l of RCPs operated. Since LTOP events are basically adnowledged as being ,

steady-state events, these RCP operating restrictions are designed to work with the LTOP setpoint to provide protection from exceeding the steady-state Appendix G P/T limits.

l f

l l

l 1

l l

l Catawba INSERT Page B 3.4-62 l LtCS/Id AMfNDMtur DA100hlf-f f

l 1

l LTOP System B 3.4.12 l BASES I

APPLICABLE RCS Vent Performance (continued)

SAFETY AHALYSES The LTOP System satisfies Criterion 2 of{heARCM112h l

QDCFE 3D.% (llef.M

! LCO l This LCO requires that the LTOP System is OPERABLE. The LTOP System is OPERABLE when the minista coolant input and l

pressure relief capabilities are OPERABLE. Violation of this LCO could lead to the loss of low temperature overpressure mitigation and violation of the Reference 1 limits as a result of an operational transient.

To limit the cool mt input capability, the LCO

I @ n ana vi Hu< ==r arizb one charcina pump]Iltapable of inaecting into the o and La isolation valves clo<.ed and r an 55111zedgalfhen accumulator C'"r *e salt #h'-pressure f** P . is greater than or equal1 acm = "=t ? d % roa M @

to thi maximm RCS pressure for the_existino RCS cold leg temperature allowed f ag, s O(e in (t__ie#TM&--(Lto mg The elements of the LCO that provide low temperature s[ 4 ,

g g .

overpressure mitigation through pressure relief aret ACf ggg I a. T Two

_ re11erp61ves, as fol)6wsD l % g thdy ((p r Two OPERABLE PORV l-3tgu)ge,.3pf) h l Af A PORV is OPERABli for LTOP when its block valve l is open. its lift setpoint is set to theilimit ft.g r qg [ g g feau1ree ny tm PIMDand testing proves its r$E@

ability to open at this setpoint, and motive i

power is available to theag)valvagf and M 2 p#64Wthr,)

I control circuitg

. [2. RlR suction relief y Two es: or]'

~

]

l An RHD uction relief valve is ERABLE for LTOP i

ts RfR suction isolati valve and its RtR / l s ion valve are open its etpoint is at or 1

3 t testing

% [436.51 psig its and .5J psig, and i has proven ility to open at this j ~ setpoint.

~) i (continued)

B 3.4 65 Rev 1. 04/07/95 m

$ Lt L, K4kmk*f ksY

LTOP System B 3.4.12 bl co 3.oM is nd app!<Me 4e@

BASES (continued)f A (_ top opw Mn. @

(e_ _

gag ACTIONS ' l A.1 Iran 6BA1] C e With two or more etel + usAcapable or injecting into tne RCS. RCS overpressurization is possible. I To insediately initiate action to restore restricted coolant input capability to the RCS reflects the urgency of removing the RCS from this condition.

h Required Action .1 is modified by a Note that reits two charging pumps capable of RCS injection for s ihminutes to

([ allow for ptmp swaps.

r -x U Yb 1.anh2f-OGV k s Y g^-

SCNSm*4 Vd An unisolated accumulator requires isolation within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

This is only required when the accumulator pressure is at or Wk 2'4* M . i . I more than the maximum RCS pressure for the existing temperature allowed by the P/T limit curves. l II.Cf

dWa#/etJuri s.

If isolation i and cannot be in I hour, t J f 4 f8 adit. . Required Acti L and Required Acti provide two a

options, ett which must be perfo in the lK 1 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . By increasing t S temperature to > t h

late tabbt fasY.a h an accumulator pressure of (

9g 5' I

. )Dsio cannot er limits if the accumulators are fully injected. ~ LTOP &~8 M*0e N l# mat [vm/ s urizing the acetasulators below the LTOP limit @

also gives this protection.

OM #A. (OtY k W64mtf AI fameg/sst The Completion Times are based on operating experience that these activities can be accomplished in these time peridds k /,(f k d. -[ i and on' engineering evaluations indicating that an event requiring LTOP is not likely in the allowed times.

Ce ben. .

g In H00E 4 when any RCS cold leg temperature is s PblLV witn oneirsuirgp.to reiwr valve inoserable, t s el.valvi>must )e restored to OPERARI status wi in a

'F, h Cons >1etion "ine of 7 days. Twolno rel*M valves tiyanyT gT 5%1natiojvor Ine rukvyana the RHRguction reliervalves])

are required to provice low t w ature overpressure mitigation while withstanding a single failure o" an active

+ ent.

1 (continued)

M W B 3.4 67 Rev 1. 04/07/95

I LTOP System B 3.4.12 BASES

[g T

ACTIONS (continued)

The Comoletion Time considers the facts that only one of the C5Mef M1ves)is required to mitigate an overpressure transient and that the likelihood of an active failure of l

the low. remaining valve path during this time period is very

The consequences of operational events that will overpressurize the RCS are more severe at lower t rature (Ref.,7). Thus, with one of the two RCSMief ve inoperable in MODE 5 or in MODE 6 with the head on. the Completion Time to restore two valves to OPERABLE status is l 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The Completion Time represents a reasonable time to investigate and repair several types of relief valve .

failures without exposure to a lengthy period with only one OPERABLE gch.sefiefp61velto protect against overpressure i events.

Oh The RCS must be depressurized and a vent must be established within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months when:

a MOR4)

Q/

a. Both@guicee xcd reuer valve 9are inoperable: or

b. A Required nd associated Completion Time of 1 Condition A is met; or g !

I O

c. The LTOP System i rab reason other than Condition A C. 0

499T h The vent must be sized 2: s the flow capacity is greater than that inches r to ensure that red for the i worst case mass input transient reasonabl during the applicable MODES. This action is needed to protect the RCPB from a low temperature overpressure event and a possible brittle failure of the reactor vessel.

(continued)

M B 3.4 68 Rev 1. 04/07/95

[

& Q 1. . t h

1 W f o -

LTOP System B 3.4.12 I

ACTIONS (continued)

The Completion Time considers the time required to place the plant in this Condition and the relatively low probability of an overpressure event during this time period due to increased operator awareness of administrative control requirements.

l SURVEILLANCE REQUIREMENTS SR 3.4.12.1C ~ ISR' 3.4 d 2_2't and SR 3.4.12.2'@ h To minimize the potential for a low temperature overpressure event by limitino the mass inout capsbility, m ==r=='oM4Il buO )

/Fonel DIPIl nuen radd amrima ODone Chargi veriffed inca ble of injecting into the RCS a )

accumulator d scharge isolation valves are verified clos ocy and locked out, byt w h The DfXounf>Is1Antb6hardini)pumpks[are render.ed incapab' e of injecti into the RCS through removing the power from the pumps y racking the breakers out under administrative control. An alternate method of LTOP control may be employed using at least two independent means to prevent a pump start such that a single failure or single action will not result in an injection into the RCS. _This may be acen=n14shed throuohrEne (cleenVin rniW tn inew $ad = *ast co roi swuen utngr Lyalve in tie discharge' Dow path being closed. D*

The Frequency of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is sufficient, considering other i

indications and alarms available to the operator in the control room, to verify the requfced status of the equipment.

SR 3.4.12.4 Each required suction relief valve 11 be demonstrated i'

OPERABLE by rifying its RHR suction alve and RHR suction isolation lves are open and by te ing it in accordance ,

with t nservice Testing Progr (Refer to SR 3.4.12.7 i

for Rm suction isolation y ve Surveillance.) This Su 11ance is only requ red o be performed if the ion relief valve is i used to meet this LCO.

(continued)

% B.3.4 69 Rev 1. 04/07/95

" u k os A c L+el 6-tf 7f

I Attachment 2d Revised Improved Technical Specifications Conversion Suhan4 ttal Documentation for Catawba Unit 2 l

t I

l i

I

Revised Current Technical specifications Marked-up Pages (NO Ms D WErs 9/15jgy gg3yyy,L ,ugynggyp pgggg,,g, NCBNICAL SPECIFICATIONS MAgggp_yy PAGEBt ' TREREFORE, REVIBRD PAGES ARE BRING ~ INCLUDED'POR ALL l CHANGES PROPOSED BOTH IN THE ORIGINAL ANENDNENT REQUEST AND TRIB BUPPLRNENT.)

l l

&3cohn yon 3, W, )

MATERIAL PROPERTY BASIS l IDGIING MATERIALS: INTERMEDIATE WFf L B8605 2 IDGTING ART AT 15 EPPY: 1/4-t,112.6 7 3/44, 96.0 7 2.,500 ,,,,,,,,,,,,, , ,

LEAK TEST LIMIT- ._ '

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I

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2.,250 ' '

l n '

n 0 2.,000 ' ' '

i i

([] I I h 1s750 UNACCEPTABLE OPERATION f I I y 1.,500 l / ,

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m M CEPTABLE 2222

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g 1,250- HEATUP RATE w ,

g Up To so *F/HR "r, r Q. l '

l y 1.,000 /

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] 500

\ CRITICALITY LIMIT BA!ED ON- ,

250 INICE NATIC MST TEMPERATURE (245 *F) FOR THE ,

SERVICE PER100 UP TO 15 EFPT' ,

' iIiiiiiIIiiIIIIIIiiiiII D

O 50 100 150 200 250 300 350 400 450 500 Indicated Temperature CDeg. F)

FIGURE . 2 REACTOR COOLANT SYSTEM HEATUP LIMITATIONS (lleatup rates up to 60*F/hr)

APPLICABLE FOR THE FIRST 15 EFPY (Without Margins For Instrumentation Errors)

CATAWBA - UNIT 2 3/4 4-33 Amendment No. %

k 4 fC64VE,, a mYa Y~~ I- % pgg.T6 . [~ -

$# M 04 7,4,7 l 1

Y MA11RL% PROPERTY BASIS IlMITING MATERIALS: INTERMEDIATE wrr. B8605-2 IJMrI1NG ART AT 15 EFPY: 1/4-t.1124 7 3/4-t, 96.0 7 2,500 i

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0 50 100 150 200 250 300 350 400 450 500 l

I nd i cated Temperature (Deg . F)

FIGURE -

I' '3~ '

REACTOR COOLANT SYSTEM C00LDOWN LIMITATIONS (Cooldown rates up to 100'F/hr)

APPLICABLE FOR THE FIRST 15 EFPY (Without Margins For Instrumentation Errors)

CATAWBA - UNIT 2 3/4 4-34 Amendment No. [

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. 3.f/24 OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION de Wb 4co 3.4. HoW TemocratureMerpreefure PJdttcliF3 System shall be OPERABLE with a maximum of one charging pump or one safe h injecting into the~Eganne coeTant W h the htinjection pump capable o

'T @ accumulators isolated *, Reactor Coolant pump operation limited as specified in Table

//./ and either a or b below:

a. Two power operated relief valves (PORVs)# with a lift setting of@

hanfor #cHEID 400 psig (as lef t calibrated), allowable value of

'< @n Af~NissTTo 425 psig (as foundW

b. The mewror cnnarnt syste with a feacMF Ce6'rgwd

@ vent o W~ pbressurize an orsmual t 4.5 square inches.

APPLICABILITY: MODE 4 when fhe mer2tbrf.)of any esettf CoolarSvstRD cold leg is Es7tMa~ri 3PeduiT~4 285'F, MODE 5 and MODE 6 when the head is on the i reactor vessel. g ACTION:

Cm////rvi d- /)) With one PORY inoperable in M0DE 4, restore the inoperable PORY to OPERABLE status within 7 days or complete depressurization and conde.hoo G venting of the Reactor Coolant System through at least a 4.5 square {

inch vent within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

poed///dn F $ With one PORY inoperable in MODES 5 or 6 restore the inoperable PORV to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or complete depressurization and coodihoo c' venting of the Reactor Coolant System through at least a 4.5 square inch vent within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Con /// Ion 2 @ With both_ PORVs inogerable,7 complete depressurization and venting of he Reactor Coolant System through at least a 4.5 square inch vent 0.2S within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . f

\

bga&ed Addo and assediafed consp i ehin be of Condhen All g g g, or' f not oce t'. ,

I 2$ (?cS \

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Accumulator isolation is nly required when accumulator pressure is greater for aer f"#

than_or equal to the maximummeactorToolae5vstMbpressure for the existing o#er 9 Mil RelGMFrnnwir lynes cold leg temperature allowed by the condihen A,C, r. y,3 pressure /temperaturelimitcurvesprovidedinSpecification

10. Oor A -

@ e3Arsing PONY

W

..w o Uie rJ!iiisiFements ofAhis Specification. ear.!P

! - Reacror Eco at Vste il tg l

j

@ en TF'RNtio d lea temperature bTant shall b.t_

pump 3 W secured, oreater than_o_r e@Wb'h nia Lmperaturt6Ea dngalured at the residual heat removal heat exchanger outlety---

I CATAWBA - UNIT 2 3/44-37 Amendment No.

Proposed License Aniendmed bdecl h /SW$

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mye lof s> l

Specification 3.1.l'L INSERT 10 not used. l 1

i l

l btcfrist h k /gn f

$9 bro l h /P98 Catawba 2 Page 2_ of #

L_______-__.

Syc iJg REACTOR COOLANT SYSTEM l

i ACTION (Continued)

(d. In the event eith the PORVs or'the Reac CoolantSystemvent(s l are used to mi '[ ate a Reactor Coolant tem pressure Sa transient Qg Special Rep shall be prepared and s mitted to the Commissio pursuant Specification 6.9.2 with 30 days. The report s 1 descri the circumstances initiat g the transient, the eff t of I the Vs or Reactor Coolant Sys vent (s) on the transien , and any l ective action necessary to evan+ rar"rrence.

b @ The crowtstons opspecifir/tio 0.4 ot applicable.

CodM A $ With more than the specified number of charging pumps and/or safety l injection pumps capable of injecting into the Reactor Coolant System *, immediately initiate action to verify a maximum of one charging pump or one safety injection pump is capable of injecting

( into the Reactor Coolant System.

l C* b t (d) With a cold leg accumulator not isolated as specified, within one l hour, isolate the affected accumulator. If the affected accumulator is not isolated within one hour, within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , either b". increase Reactor Coolant System cold leg temperature to greater than 285'F, or depressurize the affected accumulator to less than the maximum Reactor Coolant System pressure for the existing cold leg temperature allowed by Specification C4dMd @ With Reactor Coolant peration not in accordance with the requirements of Table l, immediately initiate action to limit pump operation as spec TinTable.

TN.12-i[A-TABLE b REACTOR COOLANT PUMP OPERATING RESTRICTIONS FOR LOW TEMPERATURE OVERPRESSURE PROTECTION Reactor Coolant System Maximum Number of Pumos Cold Leo Temperature Allowed in Ooeration 2 67'F 1 2 73*F 2 1 95'F 4

Two charging pumps ma. he capable of injecting into the Reactor Coolant System during pump swap operation for less than or equal to 15 minutes.

CATAWBA - UNIT 2 3/44-37a Amendment No.

l Ibpo40 I uccnse ntnCNom.w

%1G hlS 9g pse s J 2 s

$/>rh l/C0 ltlL 3, f /3 REACTOR COOLANT SYSTEM 2./

SURVEILLANCE REQUIREMENTS -

g./ $(y__.IAch. PORVihall be demopstJited OPERAbill wd//r.r /A6ts:Aoye3 g4,.,/eff 7,;j%?mIaske gg 3, g g, g fa? PerformEnf~1iCMtfJ. ELOPERATIONAiTE o t P b $[ gor actuation channel, but excluding valve operation, at least once per 31 days;

.s g 3. 9. /0, /p /f) Performance of a CHANNEL CALIBRATION on the PORY actuation channel at least once per 18 months; a block 5#3, v. /2. / 'j Verify

@ wh&TEilib PORY 15~ fig, tag USECf0CGVerprEisilrEpret!!ctid. s S/f 3.Y/2 3 (1JQ2 4 tor Coolant least e once per 12 Ee5~t eh 1(1)JttalLheJerified to be_open is being used for overpressure $ a3 (protecf1Ni~_""~~ Jours*'

S,7 3.WA ,/ 4% A maximum of one charging pump or safety injection pump shall be veriffEd to L: rapabic of injecting into the Reactor Coolant System at least or.ce per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , y 3,f fg.g hjQ3 Each cold leg accumulator shall be verified to be isolated at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when accumulator isolation is required.

A@

/0DW N N *Except when the vent pathway is provided with a valve which is locked.

FN #ug sealed, or otherwise secured in the open position, then verify these valves open at least once per 31 days.

l CATAWBA - UNIT 2 3/44-38 Amendment No.

l hofosd(l b/C8/fSC thnedad bd/hfY !

pp fol ?

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EMERGENCY CORE COOLING SYSTEMS 3/4.5.3 ECCS SUBSYSTEMS - T ., < 3',0Y

~ N~%_'~m N

'N LIMITING CONDITION FOR OPERATION h 3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:

a. One OPERABLE centrifugal charging pump,#

7

b. One OPERABLE residual heat removal heat exchanger,

c. One OPERABLE residual heat removal pump, and g d. An OPERABLE flow path capable of taking suction from the refueling J C j;gy water storage tank upon being nenually rea'ligned and transferring

[ fg suction to the containment sump during the recirculation phase of operation.

APPLICABILITY: MODE 4.

ACTION:

a. With no ECCS subsystem OPERABLE because of the inoperability of either the centrifugal charging pump or the flow path from the refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .

b. With no ECCS subsystem OPERABLE because of the inoperability of either the residual heat removal heat exchanger or residual heat removal pump, restore at least one ECCS subsystem to OPERABLE status or naintain the Reactor Coolant System T ., less than 350*F by use of alternate heat removal methods.

c. In the event the ECCS is actuated and injects water into the React:

Coolant System, a Special Report shall be prepared and submitted tc the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumu-lated actuation cycles to date. The current value of the usage factor for each affected Safety Injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.

w_ __

/~~-~~_ _

blCR YO Ce gjk o mlECN,

/ o V/r NE LCb 3. i . O ]

l #A maximum of one charging pump or one Safet In ection pump s h M BM XB D f henever the temperature of one or more~of I actorCoolantsyst~ei11 tota]

I legs is less than or equal to 285'F.

ggpig /c l CATAWBA - UNIT 2 3/4 5-8 Amendment No.

l 3.e/, /.R AppNaNUj

/%pned, & mice

&wdauf 24Uf-64]

page ?of P

i Reprinted Improved Technical Specifications Pages

RCSP/TLimits 3.4.3 l

l MATERIAL PROPERTY BASIS LIMITING MATERIALS INTERMEDIATE SHEIL, B8605-2 LIMITING ART AT 15 EPPY: 1/4-t,112.6 7 3/4-t, 96.0 7 2,500 ,,,,,,,,,,,,, ,

--~ --

LEAK TEST LlWIT-m l i

'H I I 2,250 ' '

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y 1.,750 L M CCEPTAnt.E OPERATION f l f l

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g} ; , ACCEPTABLE '----

'~~~~

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' (f) > I OPERATION '~""~~

1,250 HEATUP RATE O ;

UP TD 80 'F/HR\"r, y r j C1- l '

l \

l y 1,.000 /

l e .

o '

e 750

~

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- /

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l [ 500 ,

, CRITICALITY LIMIT BASED ON 250 '"55"V'CE moRosTAT:C Test TE W ERATURE (245 *F) FOR THE !

SERVICE PERIOD UP TO 15 EFPr j 0 - iiiiiiiiiiiiiiiiiiiiiii 0 50 100 150 200 250 300 350 400 450 500 Indicated Temperature CDeg. F) l 1

i I

Figure 3.4.3-1 RCS Heatup Limitations Catawba Unit 2 3.4-10 7/2/97

l' l

RCSP/TLimits 3.4.3 l

MATTERIAL PROPERTY BASIS LIMITING MATHt1ALS: INTERMEDIATE SHELL,B8605-2 LIMrrING ART AT 15 EPPY: 1/4 t,112.6 7 3/4-t, %.0 T 2,500 , , i i i .

I 2,250 n s' G 2,000 s==

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h 1,750 ::::: ----.

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$ 1,250 j

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DPERATION l

y 1,000 /

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(d 750 rates *F/HR. d O :::: u

$3;1 a

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[ 500 l 60 / l

____ po_.

250 i

0 D 50 100 150 200 250 300 350 400 450 500 Indicated Temperature (Deg. F) l Figure 3.4.3-2 RCS Cooldown Limitations l

1 1

h' L

l Catawba Unit 2 3.4-11 7/2/97 u______. __-__ __-_ - _

LTOP System 3.4.12 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12 Low Temperature Overpressure Protection (LTOP) System LC0 3.4.12 An LTOP System shall be OPERABLE with a maximum of one charging pump or one safety injection pump capable of injecting into the RCS, the accumulators isolated, reactor coolant pump operation limited as specified in Table 3.4.12-1 and either a or b below.

a. Two power operated relief valves (PORVs) with lift setting s 400 psig (as left calibrated), allowable value s 425 psig (as found), with RCS cold leg temperature a 65'F; or

b. The RCS depressurized and an RCS vent of a 4.5 square inches.

APPLICABILITY: MODE 4 when' any RCS cold leg temperature is s 285'F, MODE 5, MODE 6 when the reactor vessel head is on. .

NOTE----------------------------

Accumulator isolation is only required when accumulator pressure is greater than or equal to the maximum RCS

% pressure for the existing RCS cold leg temperature allowed by the P/T . limit curves provided in Specification 3.4.3.

i I

i i

Catawba Unit 2 3.4-31 5/11/98

LTOP System 3.4.12 ACTIONS

NOTE--------------------------------

LC0 3.0.4 is not applicable.

CONDITION l REQUIRED ACTION COMPLETION TIME 1

A. Two or more charging ----------NOTE--------------

pumps capable of Two charging pumps may be j injecting into the capable of injecting into the '

RCS. RCS ouring pump swap operation for s 15 minutes.

g ___....... ____________......

One charging pump and A.1 Initiate action to Immediately one safety injection verify a maximum of 4 pump rapable of one charging pump or )

injecting into the one safety injection 1 RCS. pump is capable of I injecting into the i M RCS.

Two or more safety injection pumps capab'e of injecting i into the RCS. i B. Reactor coolant pump B.1 Initiate action to Immediately operation not limited limit pump operation as specified in Table as specified in Table 3.4.12-1. 3.4.12-1.

l C. An accumulator not C.1 Isolate affected I hour isolated when the accumulator, accumulator pressure is greater than or equal to the maximum RCS pressure for existing cold leg temperature allowed in Specification 3.4.3.

(continued)

Catawba Unit 2 3.4-32 5/11/98

LTOP System 3.4.12 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Increase RCS cold leg 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months l associated Completion temperature to Time of Condition C > 285*F. l not met.

M D.2 Depressurize affected 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months l accumulator to less than the maximum RCS !

pressure for existing cold leg temperature allowed by Specification 3.4.3.

E. One PORV inoperable in E.1 Restore PORV to 7 days l MODE 4. OPERABLE status. ,

F. One PORV inoperable in F.1 Restore PORV to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months l 1 MODE 5 or 6. OPERABLE status. l G. Two PORVs inoperable. G.1 Depressurize RCS and 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months l establish RCS vent of M 2 4.5 square inches.

Required Action and associated Completion Time of Condition A, D, E, or F, not met. l M

LTOP System inoperable for any reason other than Condition A, C, D, E, or F.

Catawba Unit 2 3.4-33 5/11/98

LTOP System 3.4.12 Table 3.4.12-1 (Page 1 of 1)

Reactor Coolant Pump Operating Restrictions for Low Temperature Overpressure Protection j Reactor Coolant System Cold Leg Maximum Number of Pumps Allowed in Temperature Operation 2 67"F 1 2 73*F 2 2 95*F 4 Catawba Unit 2 3.4-36 5/11/98 l

RCS Operational LEAKAGE

.3.4.13 3.4' REACTOR COOLANT SYSTEM (RCS) 3.4.13'1RCS Operational: LEAKAGE LCO 3.4.13 RCS operational LEAKAGE shall be limited to:

.a. No pressure boundary LEAKAGE; b .- 1 gpm unidentified LEAKAGE;

c. 10 gpm identified LEAKAGE; '

d. 576 gallons per day total primary to secondary LEAKAGE through all steam generators (SGs); and

e. 150 gallons per day primary to secondary LEAKAGE through any one SG.

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

i

ACTIONS L CONDITION REQUIRED ACTION COMPLETION TIME i

A. RCS LEAKAGE not within A.1 Reduce LEAKAGE to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months limits Ter reasons within~11mits.

other tw a pressure boundary LEAKAGE. j B.. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A AM not met.

! B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E

i:

L Pressure boundary LEAKAGE exists.

Catawba Unit 2 3.4-37 5/11/98 l i

l

RCS Operational LEAKAGE 3.4.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.13.1 -------------------NOTE-------------------- -----NOTE------

Not required to be perforned in MODE 3 or 4 Only required until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of steady state operation. to be perforned

during steady state operation Verify RCS Operational LEAKAGE within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months limits by performance of RCS water inventory balance. )

SR 3.4.13.2 : Verify steam generator tube integrity is in In accordance accordance with the Steam Generator Tube with the Steam Surveillance Program. Generator Tube Surveillance Program I

l I

l l l 1

l 1,

Catawba Unit 2 3.4-38 5/11/98 l

RCS PIV Leakage 3.4.14 3.4 REACTOR COOLANT SYSTEM (RCS). 1 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage '

L LC0 -3.4.14 Leakage from each RCS PIV shall be within limit.

I APPLICABILITY: MODES 1, 2, and 3, MODE 4, .except valves in the residual heat removal (RHR) flow path when in, or during the transition to or from, the RHR mode of operation.

I L

ACTIONS

NOTES-----------------------------------.

1. . Separate Condition entry is allowed for each flow path.

2. Enter applicable Conditions and Required Actions for systems made.

inoperable by an inoperable PIV.

wnDmon

. REQUIRED ACTION COMPLETION TIME A. One or more flow paths ---------_--NOTE-------------

with leakage from one Each valve used to satisfy-or:more RCS PIVs not Required Action A.1 must have within limit, been verified to meet SR 3.4.14.1 and be in the-reactor coolant pressure boundary or the high pressure-portion of the system.

l (continued)

Catawba Unit 2- 3.4-39 5/11/98 l

RCS PfV-Leakage 3.4.14 ACTIONS

. CONDITION REQUIRED ACTION COMPLETION' TIME l

l A. (continued) A.1 Isolate the high 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months l

pressure portion of the affected system from the low pressure portion by use of one closed manual, deactivated automatic, or check valve.

A!H1 A.2 Restore RCS PIV to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months within limits.

'B. Required Action and B.1. Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months l associated Completion J Time for Condition A Atul i

- not met.

B.2 Pe in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C. RHR System interlock C.1 Isolate-the affected. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months {

function inoperable. penetration by use of one closed manual or.

deactivated automatic valve.

1 1

l Catawba Unit 2 3.4-40 5/11/98

RCS PIV Leakage 3.4.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.1 -------------------NOTES-------------------

1. Not required to be performed in MODES 3 and 4.

2. Not' required to be performed on the RCS PIVs located in the RHR flow path when in the shutdown cooling mode of operation.

3. RCS PIVs actuated during the performance'of this Surveillance are not required.to be' tested more than once if a repetitive testing loop cannot be avoided.

Verify leakage from each RCS PIV is .

In accordance equivalent to s 0.5 gpm per nominal inch of with the valve size up to a maximum of 5 gpm at'an Inservice RCS pressure 2 2215 psig and s 2255 psig. Testing Program, and 18 months M

Prior to entering MODE 2 whenever the unit has been in MODE 5'for 7 days or more, if leakage testing has not been performed in the previous 9 months M

(continued) l l

Catawba Unit 2 3.4-41 5/11/98

RCS PIV Leakage 3.4.14 i SURVEILLANCE REQUIREMENTS.

SURVEILLANCE FREQUENCY SR 3.4.14.1 (continued) Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following valve actuation due to automatic or manual action or flow through the valve SR 3.4.14.2 Verify RHR system interlock prevents the 18 months valves from being opened with a simulated or actual RCS pressure signal 2 425 psig.

f I

i l

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l Cat'awba Unit 2 3.4-42 5/11/98

- - - - _ _ _ _ _ . _________m__.__,_______ _______

RCS Leakage Detection. Instrumentation 3.4.15 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.15 RCSl Leakage' Detection Instrumentation LCO 3.4.15- The following RCS leakage detection instrumentation shall be OPERABLE:

a.. One containment floor and equipment sump level monitor; i

b. One containment atmosphere radioactivity monitor (gaseous or particulate); and

c. One containment ventilation unit condensate drain tank level monitor.

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

ACTIONS

_--------_---------NOTE------------------------------ .

.LC0 3.0.4 is not applicable..

CONDITION REQUIRED ACTION. COMPLETION TIME A. Required containment.- A.1 Perform SR 3.4.13.1. Once per floor and equipment 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months i sump level monitor AM inoperable.

A.2 Restore required. 30 days containment floor and equipment sump level monitor-to OPERABLE status.

(continued)

I i

Catawba Unit 2 3.4 43 5/11/98 ]

RCS Leakage Detection Instrumentation 304.15 ACTIONS (continued) l CONDITION REQUIRED ACTION COMPLETION TIME B. Required containment B.1 Analyze grab samples Once per atmosphere of the containment 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months radioat.tivity monitor atmosphere.

inoperable.

DE B.2 Perform SR 3.4.13.1. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

-C.

Required containment C.1 Perform SR 3.4.15.1. Once per ventilation unit 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months condensate drain tank DR level monitor inoperable. C.2 Perform SR 3.4.13.1. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1

D. . Required containinent D.1 Restore required 30 days atmosphere containment radioactivity monitor atmosphere

. inoperable. radioactivity monitor to OPERABLE status.

AND QR Required containment ventilation unit D.2 Restore required 30 days condensate drain tank containment i level monitor ventilation unit -

inoperable. condensate drain tank level monitor to OPERABLE status. i l

l E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion l j

l Time'not met. AHQ l

l l

E.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

Catawba Unit 2- 3.4-44 5/11/98 ,

l

RCS Leakage Detection Instrumentation 3.4.15 ACTIONS (continued)

CONDITION REQUIRED ACTION- COMPLETION TIME F. '_All required monitors F.1 Enter LC0 3.0.3. Immediately inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.15.1 Perform CHANNEL CHECK of the required 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months containment atmosphere radioactivity monitor.

SR 3.4.15.2 Perform COT of the required containment 92 days

atmosphere radioactivity monitor.

1 SR 3.4.15.5 Perform CHANNEL CALIBRATION of the required 18 months containment floor and equipment sump level monitor.

l: SR 3.4.15.4 Perform CHANNEL CALIBRATION of the required' 18 months containment atmcsphere radioactivity monitor..

L SR 3.4.15.5 ierform CHANNEL CALIBRATION of the required 18 months

! containment ventilation unit-condensate l drain tank level monitor.

l l

l. Catawba Unit 2. 3.4-45 5/11/98 l

___=___________:_______-__ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _

l l RCS Specific Activity l 3.4.16 l

l 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LC0 3.4.16 The specific activity of the reactor coolant shall be within limits.

l l APPLICABILITY: MODES 1 and 2, l MODE 3 with RCS average temperature (T.,,) a 500*F.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT I-131 ------------Note------------

> 1.0 Ci/gm. LCO 3.0.4 is not applicable.

A.1 Verify DOSE Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months EQUIVALENT I-131 l within the acceptable

! l region of i Figure 3.4.16-1.

l Afill A.2 Restore DOSE 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months EQUIVALENT I-131 to within limit.

t B. Gross specific B.1 Be in MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months l activity of the T.,, < 500*F.

reactor coolant not within limit.

(continued) l l Catawba Unit 2 3.4-46 5/11/98 l

l

RCS Specific Activity 3.4.16 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion T y < 500*F.

Time of Condition A not met.

OE l 1

DOSE EQUIVALENT I-131 '

l in the unacceptable region of ,

Figure 3.4.16-1. !

i l

l

-SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR-'3.4.16.1 Verify reactor coolant gross specific 7 days activity s 100/E pCi/gm.

SR 3.4.16.2 -------------------NOTE--------------------

Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT 14 days I-131specificactivitys1.0pC1/gm.

850 Between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after a THERMAL POWER change of

( 2 15% RTP within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months L

period .

i (continued) l Catawba Unit 2 3.4-47 5/11/98

RCS Specific Activity 3.4.16 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.16.3 -------------------NOTE--------------------

Not required to be performed until 31 days after a minimum of 2 effective full power days and 20 days of MODE 1 operation have {

-elapsed since the reactor was last subcritical for a 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Determine E from a sample taken in MODE 1 184 days after a minimum of 2 effective full power days and 20 days of MODE 1 operation have etapacd since the reactor was last subcritical for a 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

i m

1' l-I l

4 Catawba Unit 2- 3.4-48 5/11/98 L__-_-___-_______- . _ _ _ _ _ __ _ - _a

I l '

RCS Specific Activity 3,4016 l

300 i

l )

250

\

t:

i lE

! 3 D

l 5 \ 4 e

o 200 \ '

it i @ UNACCEPTABLE l' $5.-. OPERATION l tI 5*

8i O J150 s N

! oE 5i a:

E 2

E y 100 e ;

5 i O

ACCEPTABLE i

' l OPERATION j i

50 l l

I l

l l

0 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER Figure 3.4.16 '. (page 1 of 1)

Reactor Coolant DOSE EQUIVALENT I-131 Specific Activity Limit'Versus Percent of RATED THERMAL POWER Catawba Unit 2 3.4-49 5/11/98 e

RCS Loops-Test Exceptions 3.4.17

(; 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.17 'RCS Loops-Test Exceptions LCO 3.4.17 The requirements of LCO 3.4,4, "RCS Loops-MODES 1 and 2 "

may be suspended, with THERMAL POWER < P-7.

APPLICABILITY: MODES 1 and 2 during startup and PHYSICS TESTS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME l

A. THERMAL P0'WER ;t P-7. A.1 Open reactor trip Immediately ,

breakers.

SURVEILLANCE REQUIREMENTS l SURVEILLANCE FREQUENCY

.SR 3.4.17.1 Verify THERMAL POWER is < P-7_. I-hour

'SR 3.4.17.2 ' Perform a COT for each power. range neutron Prior to l flux-low and intermediate range neutron initiatun of flux channel and P-7. Startup and PHYSICS TESTS 1

i I

i Catawba Unit 2 3.4-50 5/11/98

i RCSP/TLimits l B 3.4.3 i

BASES ACTIONS C.1 and C.2 (continued)

Condition C is modified by a Note requiring Required Action C.2 to be completed whenever the Condition is entered. The Note emphasizes the need to perform the evaluation of the effects of the excursion outside.the allowable limits. Restoration alone per Required Action C.1

, .is insufficient because higher than analyzed stresses may have occurred and may have affected the RCPB integrity.

i SURVEILLANCE SR 3.4.3.1 REQUIREMENTS Verification that operation is within the specified limits is required every 30 minutes when RCS pressure and temperature conditions are undergoing planned changes. his Frequency is considered reasonable in view of the control room indication available to monitor RCS status. Also, since temperature rate of change limit:; are specified in hourly increments, 30 minutes permits assessment and correction for minor deviations within a reasonable time.

Surveillance for heatup, cooldown, or ISLH testing may be discontinued when the definition given in the relevant plant procedure for ending the activity is satisfied.

This SR is modified by a Note that only requires this SR to be performed during system heatup, cooldown, and ISLH testing. No SR is given for criticality operations because LC0 3.4.2 contains a more restrictive requirement.

REFERENCES 1. 10 CFR 50, Appendix G.

2. ASME, Boiler and Pre sure Vessel Code,Section III, !

Appendix G. ;

l 3. ASTM E 185-82, 1982.

1

4. 10 CFR 50, Appendix H. I i- !

(continued)

Catawba Unit 2 B 3.4-16 9/9/97 i

LTOP System B 3.4.12 l

B 3.4' REACTOR COOLANT SYSTEM (RCS)

B 3.4.12 Low Temperature Overpressure Protection (LTOP) System l \

BASES BACKGROUND The LTOP System controls RCS pressure at low temperatures so the integrity of the reactor coolant pressure boundary (RCPB) is not com '

temperature (P/T) promised by violating the pressure andlimits of The reactor vessel is the limiting RCPB component for i demonstrating such protection. This specification provides the maximum allowable actuation logic setpoints for the

! power operated relief valves (PORVs) and LC0 3.4.3, "RCS l

Pressure and Temperature (P/T) Limits," provides the maximum '

j RCS pressure for the existing RCS cold leg temperature

! during cooldown, shutdown, and heatup to meet the Reference 1 requirements during the LTOP MODES.

The reactor vessel material is less tough at low temperatures than at normal operating temperature. As the vessel neutron exposure accumulates, the material toughness ,

decreases- and becomes less resistant to pressure stress at l

i low temperatures (Ref. 2). RCS pressure, therefore, is maintained low at low temperatures and is increased only as j temperature is increased.

I The potential for vessel overpressurization is most acute

, when the RCS is water solid, occurring only while shutdown; a pressure fluctuation can occur more quickly than an operator can react to relieve the condition. Exceeding the l RCS P/T limits by a significant amount could cause brittle l cracking of the reactor vessel. LC0 3.4.3 requires administrative control of RCS pressure and temperature during heatup and cooldown to prevent exceeding the specified limits.

This LC0 provides RCS overpressure protection by having a minimum coolant input capability and having adequate ;

i pressure relief capacity. Limiting coolant input capability '

i requires all but one charging pump or one safety injection

! pump incapable of injection into the RCS, isolating the accumulators, and limiting reactor coolant pump operation at low temperatures. The pressure relief capacity requires either two redundant PORVs or a depressurized RCS and an RCS vent of sufficient size. One PORV or the open RCS vent is ;

the overpressure protection device that acts to terminate an i (continued)

Catawba Unit 2 B 3.4-59 5/11/98 l l

L

l I LTOP System B 3.4.12 i

BASES l

BACKGROUND increasing pressure event.

(continued)

With minimum coolant input capability, the ability to provide core coolant addition is restricted. The LC0 does not require the makeup control system deactivated or the safety injection (SI) actuation circuits blocked. Due to the lower pressures in the LTOP MODES and the expected core decay heat levels, the makeup system can provide adequate flow via the makeup control valve. If conditions require the use of more than one charging pump for makeup in the event of loss of inventory, then pumps can be made available through manual actions.

The LTOP System for pressure relief consists of two PORVs with reduced lift settings or a depressurized RCS and an RCS vent of sufficient size. Two PORVS are required for i redundancy. One PORV has adequate relieving capability to !

keep from overpressurization for the required coolant input l capability.

PORV Requirements As designed for the LTOP System, each PORV is signaled to open if the RCS pressure reaches 400 psig (as left calibrated), allowable value s 425 psig (as found), when the PORVS are in the "lo-press" mode of operation. If the PORVs are being used to meet the requirements of this Specification, then RCS cold leg temperature is limited to 2 65*F in accordance with the LTOP analysis. When all Reactor Coolant Pumps are secured, this temperature is measured at the outlet of the residual heat removal heat exchanger.

This location will provide the most conservative (lower) temperature measurement of water capable of being delivered into the Reactor Coolant System. The LTOP actuation logic monitors both RCS temperature and RCS pressure. The signals used to generate the pressure setpoints originate from the wide range pressure transmitters. The signals used to generate the temperature permissives originate from the wide range RTDs. Each signal is input to the appropriate NSSS protection system cabinet where 't is converted to an internal signal and then input to a comparator to generate an actuation signal. If the indicated pressure meets or exceeds the calculated value, a PORV is signaled to open.

f l This Specification presents the PORV setpoints for LTOP.

I Having the setpoints of both valves within the limits (continued) l Catawba Unit 2 B 3.4-60 5/11/98 l !

LTOP System B 3.4.12 BASES BACKGROUND PORV Requirements (continued) ensures that the Reference 1 limits will not be exceeded in any analyzed event.

When a PORV is opened in an increasing pressure transient, the release of coolant will cause the pressure increase to slow and reverse. As the PORV releases coolant, the RCS pressure decreases until a reset pressure is reached and the valve is signaled to close. The pressure continues to {

decrease below the reset pressure as the valve closes.

RCS Vent Requirements Once the RCS is depressurized, a vent exposed to the containment atmosphere will maintain the RCS at containment ambient pressure in an RCS overpressure transient, if the relieving requirements of the transient do not exceed the capabilities of the vent. Thus, the vent path must be capable of relieving the flow resulting from the limiting i

LTOP mass or heat input transient, and maintaining pressuie below the P/T limits. The required vent capacity may be provided by one or more vent paths. The vent path (s) must be above the level of reactor coolant, so as not to drain the RCS when open.

1 APPLICABLE Safety analyses (Ref. 3) demonstrate that the reactor vessel SAFETY ANALYSES is adequately protected against exceeding the Reference 1 P/Tlimits. In MODES 1, 2, and 3, and in MODE 4 with RCS cold leg temperature exceeding 285*F, the pressurizer safety valves will prevent RCS pressure-from exceeding the Reference 1 limits. At about 285'F and below, overpressure prevention falls to two OPERABLE PORVs or to a depressurized RCS and a sufficient sized RCS vent. Each of these means has a limited overpressure relief capability.

The actual temperature at which the pressure in the P/T limit curve falls below the pressurizer safety valve

, setpoint increases as the reactor vessel material toughness decreases due to neutron embrittlement. Each time the P/T curves are revised, the LTOP System must be re-evaluated to l ensure its functional requirements can still be met using the PORV method or the depressurized and vented RCS condition.

L j

(continued)

Catawba Unit 2 B 3.4-61 5/11/98 l l

LTOP System B 3.4.12 BASES APPLICABLE Any change to the RCS must be evaluated against the SAFETY ANALYSES Reference 3 analyses to determine the impact of the change I (continued) on the LTOP acceptance limits. i Transients that are capable of overpressurizing the RCS are categorized as either mass or heat input transients, examples of which follow: ,

Mass Inout Tvoe Transients

a. Inadvertent safety injection; or

b. Charging /letdownflowmismatch.

Heat Inout Tvoe Transients

a. Inadvertent actuation of pressurizer heaters;

b. Loss of RHR cooling; or

c. Reactor coolant pump (RCP) startup with temperature asynynetry within the RCS or between the RCS and steam generators.

The following are required during the LTOP MODES to ensure that mass and heat input transients do not occur, which either of the LTOP overpressure protection means cannot handle: ,

a. Rendering all but one charging pump or one safety injection pump incapable of injection; 1

b. Deactivating the accumulator discharge isolation l valves in their closed positions; i

c. Limiting RCP operation based on the existing j temperature in the RCS cold legs; and :

i

d. Disallowing start of an RCP if secondary temperature ;

is more than 50"F above primary temperature in any one loop. LC0 3.4.6, "RCS Loops-MODE 4," and LC0 3.4.7, l l "RCS Loops-MODE 5, Loops Filled," provide this l protection. I The Reference 3 analyses demonstrate that either one PORV or ,

the depressurized RCS and RCS vent can maintain RCS pressure !

(continued) l Catawba Unit 2 B 3.4-62 5/11/98 l

l LTOP System B 3.4.12 I'

BASES APPLICABLE Heat Inout Tvoe Transients (continued) '

SAFETY ANALYSES below limits when only one charging pump or one safety injection pump is actuated. Thus, the LC0 allows only one charging pump or one safety injection pump OPERABLE during the LTOP MODES. Since neither one PORV nor the RCS vent can ,

handle the pressure transient from accumulator injection '

when RCS temperature is low, the LC0 also requires the accumulators isolation when accumulator pressure is greater than or equal to the maximum RCS pressure for the existing RCS cold leg temperature allowed in LC0 3.4.3.

The isolated accumulators must have their discharge valves l closed and the valve power supply breakers fixed in their open positions.

The restrictions on the number of RCPs in operation at a given temperature ensures that during a LTOP mass injection event that the pressure / temperature (P/T) limits of 10 CFR 50, Appendix G to protect the reactor vessel are not {

exceeded. During startup and shutdown, when the RCPs are operated, their induced flows create a pressure drop across the vessel. This pressure drop along with the difference in elevation between the beltline region and the instrumentation locations are additive to the peak pressure from the mass injection event.

The amount of the pressure at the reactor vessel beltline region from the RCPs is dependent on the number of RCPs operated. AdequatemargintopreventexceedingtheP/T limits is assured by restricting the number of RCPs operated. Since LTOP events are basically acknowledged as I being steady-state events, these RCP operating restrictions are designed to work with the LTOP setpoint to provide protection from exceeding the steady-state Appendix G P/T limits.

Fracture mechanics analyses established the temperature of LTOP Applicability at 285"F.

The consequences of a small break loss of coolant accident (LOCA) in LTOP MODE 4 conform to 10 CFR 50.46 and 10 CFR 50, Appendix K (Refs. 4 and 5), requirements by having a maximum of one charging pump OPERABLE and SI actuation enabled.

l I

, i (continued) l Catawba Unit 2 B 3.4-63 5/11/98 l i

LTOP System B 3.4.12 BASES APPLICABLE PORV Performance SAFETY ANALYSES (continued) The fracture mechanics analyses show that the vessel is protected when the PORVs are set to open at or below the s)ecified limit. The setpoints are derived by analyses t1atmodel the performance of the LTOP System, assuming the limiting LTOP transient of one charging pump or one safety injection pump injecting into the RCS. These analyses consider pressure overshoot and undershoot beyond the PORV opening and closing, resulting from signal processing and valve stroke times. The PORV setpoints at or below the derived limit ensures the Reference 1 P/T limits will be met.

The PORV setpoints will be updated when the revised P T limits conflict with the LTOP analysis limits. The P T limits are periodically modified as the reactor vesse material toughness decreases due to neutron embrittlement caused by neutron irradiation. Revised limits are determined using neutron fluence projections and the results of examinations of the reactor vessel material irradiation surveillance specimens. The Bases for LC0 3.4.3, "RCS Pressure and Temperature (P/T) Limits," discuss these examinations.

The PORVs are considered active components. Thus, the failure of one PORV is assumed to represent the worst case, single active failure.

RCS Vent PerfeliLDra With the RCS depressurized, analyses snow a vent size of 4.5 square inches is capable of mitigating the allowed LTOP overpressure transient. The capacity of a vent this size is greater than the flow of the limiting transient for the LTOP configuration, one charging pump or one safety injection pump OPERABLE, maintainin maximum pressure on theTP/g RCS limit pressure less than the curve.

The RCS vent size will be re-evaluated for compliance each time the P of the ves/T limit curves sel material are revised based on the results surveillance.

The RCS vent is passive and is not subject to active failure.

The LTOP System satisfies Criterion 2 of 10 CFR 50.36 (Ref. 6).

(continued) l Catawba Unit 2 B 3.4-64 5/11/98 1

LTOP System B 3.4.12 BASES (continued)

LC0 This LC0 requires that the LTOP System is OPERABLE. The LTOP System is OPERABLE when the minimum coolant input and pressure relief capabilities are OPERABLE. Violation of this LC0 could lead to the loss of low temperature overpressure mitigation and violation of the Reference 1 l

limits as a result of an operational transient.

To limit the coolant input capability, the LC0 permits a maximum of one charging pump or one safety injection pump capable of injecting into the RCS and requires all accumulator discharge isolation valves closed and immobilized when accumulator pressure is greater than or equal to the maximum RCS pressure for the existing RCS cold leg temperature allowed in LC0 3.4.3. The LC0 also limits RCP operation based on existing RCS cold leg temperature as required by the LTOP analysis.

l The elements of the LC0 that provide low temperature l overpressure mitigation through pressure relief are:

a. Two OPERABLE PORVs (NC-32B and NC-34A); or A PORV is OPERABLE for LTOP when its block valve is open, its lift setpoint is set to the specified limit and testing proves its ability to open at this setpoint, and motive power is available to the valve and its control circuit.

b. A depressurized' RCS and an RCS vent. i An RCS vent is OPERABLE when open with an area of 2 4,5 square inches.

Each of these methods of overpressure prevention is capable of mitigating the limiting LTOP transient.

APPLICABILITY This LC0 is applicable in MODE 4 when any RCS cold leg temperature is s 285'F, in MODE 5, and in MODE 6 when the reactor vessel head is on. The pressurizer safety valves provide overpressure protection that meets the Reference 1 P/T limits above 285'F. When the reactor vessel head is off, overpressurization cannot occur.

(continued)

Catawba Unit 2 B 3.4-65 5/11/98 l l

L_-__________-__-____ _ _ _ _ . .

LTOP System B 3.4.12 BASES APPLICABILITY LC0 3.4.3 'provides the operational P/T limits for all MODES.

(continued) LC0 3.4.10, " Pressurizer Safety Valves," requires the OPERABILITY of the pressurizer safety valves that provide overpressure protection during MODES 1, 2, and 3, and MODE 4 above 285'F.

Low temperature overpressure prevention is most critical during shutdown when the RCS is water solid, and a mass or heat input transient can cause a very rapid increase in RCS pressure when little or no time allows operator action to mitigate the event.

The Applicability is modified by a Note stating that accumulator isolation is only required when the accumulator pressure is more than or at the maximum RCS pressure for the existing temperature, as allowed by the P/T limit curves.

This Note permits the accumulator discharge isolation valve Surveillance to be performed only under these pressure and temperature conditions.

ACTIONS LC0 3.0.4 is not applicable for entry into LTOP operation.

L.1 With two or more charging pumps, two safety injection pumps, or one safety injection pump and one charging pump capable of injecting into the RCS, RCS overpressurization is possible.

To immediately initiate action to restore restricted cnalant input capa'vility to the RCS reflects the urgency of removing the RCS from this condition.

Required Action A.1 is modified by a Note that permits two cnarging pumps capable of RCS injection for s 15 minutes to allow for pump swaps.

l fL1 With RCP operation not limited in accordance with Table 3.4.12-1, RCS overpressurization is possible.

To immediately initiate action to limit pump operation reflects the urgency of removing the RCS from this condition.

2 (continued) l Catawba Unit 2 8 3.4-66 5/11/98

! LTOP System l B 3.4.12 BASES ACTIONS C.1. D.1. and 0.2 l (continued)

An unisolated accumulator requires isolation within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

This is only required when the accumulator pressure is at or more than the maximum RCS pressure for the existing temperature allowed by the P/T limit curves.

If isolation is needed and cannot be accomplished in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , Required Action D.1 and Required Action D.2 provide two l options, either of which must be performed in the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . By increasing the RCS temperature to > 285*F, an l accumulator pressure of 678 psig cannot exceed the LTOP l limits if the accumulators are fully injected.

Depressurizing the accumulators below the LTOP limit also gives this protection.

The Completion Times are based on operating experience that these activities can be accomplished in these time periods and on engineering evaluations indicating that an event requiring LTOP is not likely in the allowed times.

L1 I In MODE 4 when any RCS cold leg temperature is s 285'F, with i one PORV inoperable, the PORV must b( restored to OPERABLE l status within a Completion Time of 7 days. Two PORVs are l required to provide low temperature overpressure mitigation while withstanding a single failure of an active component.

The Completion Time considers the facts that only one of the PORVs is required to mitigate an overpressure transient and that the likelihood of an active failure of the remaining valve path during this time period is very low.

L.1 I l

The consequences of operational events that will overpressurize the RCS are more severe at lower temperature !

(Ref. 7). Thus, with one of the two PORVs inoperable in MODE 5 or in MODE 6 with the head on Completion Time to restore two valves to OPERABLE status is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The Completion Time represents a reasonable time to investigate and repair several types of relief valve failures without exposure to a lengthy period with only one OPERABLE PORV to protect against overpressure events.

(continued) tawba Unit 2 B 3.4-67 5/11/98 l

LTOP System B 3.4.12 BASES l ACTIONS ftd (continued)

The RCS must be depressurized and a vent must be established within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months when:

a. Both PORVs are inoperable; or

b. A Required Action and associated Completion Time of l Condition A, D, E, or F is not met; or c.- The LTOP System is inoperable for any reason other l than Condition A, C, D, E, or F.

The vent must be sized a 4.5 square inches to ensure that the flow capacity is greater than that required for the worst case mass input transient reasonable during the applicable MODES. This action is needed to protect the RCPB from a low temperature overpressure event and a possible brittle failure of the reactor vessel.

The Completion Time considers the time required to place the plant in this Condition and the relatively low probability of an overpressure event during this time period due to increased operator awareness of administrative control requirements.

. SURVEILLANCE SR 3.4.12.1 and SR 3.4.12.2 REQUIREMENTS To minimize the potential for a lo.v temperature overpressure event by limiting the mass input capability, all but one charging or safety injection pump is verified incapable of injecting into the RCS and the accumulator discharge isolation valves are verified closed and locked out.

The pumps are rendered incapable of injecting into the RC5 through removing the power from the pumps by racking the breakers out under administrative control. An alternate method of LT0P control may be employed using at least two independent means to prevent a pump start such that a single failure or single action will not result in an injection into the RCS. This may be accomplished through two valves in the discharge flow path being closed.

The Frequency of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is sufficient, considering other (continued) l Catawba Unit 2 B 3.4-68 5/11/98 l l

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LTOP System B 3.4.12 BASES SURVEILLANCE SR 3.4.12.1 and SR 3.4.12.2 (continued)

REQUIREMENTS (continued) indications and alanns available to the operator in the control room, to verify the required status of the )

equipment.

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SR 3.4.12.3 The RCS vent of :t 4.5 square inches is proven OPERABLE by verifying its open condition either: l

a. Once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for a valve that cannot be locked.

b. Once every 31 days for a valve that is locked, realed, or secured in position. A removed pressurizer safety valve fits this category.

The passive vent arrangement must only be open to be I OPERABLE. This Surveillance is required to be performed if I the vent is being used to satisfy the pressure relief requirements of the LC0 3.4.12b.

SR 3.4.12.4 The PORV block valve must be verified open every 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to provide the flow path for each required PORV to perform its function when actuated. The valve must be remotely verified open in the main control room. This Surveillance is performed if the PORV satisfies the LCO.

The block valve is a remotely controlled, motor operated valve. The power to the valve operator is not required removed, and the manual operator.is not required locked in the inactive position. Thus, the block valve can be closed in the event the PORV develops excessive leakage or does not 1 close (sticks open) after relieving an overpressure l situation. '

The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Frequency is considered adequate in view of other administrative controls available to the operator in l the control room, such as valve position indication, that L verify that the PORV block valve remains open. l l l (continued)

-Catawba Unit 2 B 3.4-69 5/11/98 l t

LTOP System B 3.4.12 1

BASES SURVEILLANCE SR 3.4.12.5 REQUIREMENTS (continued) Performance of a COT is required within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after i decreasing RCS temperature to s 285*F and every 31 days on each required PORV to verify and, as necessary, adjust its lift setpoint. The COT will verify the setpoint is within )

the allowed maximum limits. PORY actuation could depressurize the RCS and is not required.

The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Frequency considers the unlikelihood of a low temperature. overpressure event during this time.

A Note has.been added indicating that this SR is required to be met 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after decreasing RCS cold leg temperature to s 285'F. The COT cannot be performed until in the LTOP MODES when-the PORV lift setpoint can be reduced to the LTOP setting. The test must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering the LTOP MODES.

SR 3.4.12.6 Performance of a CHANNEL CALIBRATION on each required PORV actuation channel is required every 18 months to adjust the whole channel so that it responds and the valve opens within the required range and accuracy to known input.

REFERENCES 1. 10 CFR 50, Appendix G.

2. Generic Letter 88-11.

l

3. UFSAR, Section 5.2

4. 10 CFR 50, Section 50.46. ;

5. 10 CFR 50, Appendix K.

6. 10 CFR 50.36, Technical Specifications. (c)(2)(ii). l l

7 .- Generic Letter 9C 00. !

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l Catawba Unit 2 B 3.4-70 5/11/98

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Revised NUREG-1431 Marked-up Pages (NOTE: DUKE'S 9/15/97 ORIGINAL ANENDIGNT REQUEST DID NOT INCLUDE REVISED NUREG-1431 NARKED-UP PAGES1 THEREFORE, i REVISED PAGES ARE BEING INCLUDED FOR ALL CHANGES PROPOBED BOTH IN THE ORIGINAL ANENDlMNT REQUEST AND THIS SUPPLRNENT.

ONLY THOSE PAGES DIFFERENT FRON UNIT 1 ARE INCLUDED IN THIS TAB.)

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INSERT 5 (Unit 2)

MATERIAL PROPERTY BASE LIMrrING MATERIALS LVrERMEDIATE SHELL.B8605-2 LIMITING ART AT 15 EFPY: 1/4-t, 112.6 'F 3/4-t. %.0 *F 2,500 ,,,,,,,,,,,,, ,

I J l LEAK TEST LIMIT - -- '

I I

% I I 2,250. '

/ f l ) ; , ---

R I I I O 2,000 ' f f i >

(f) l I h 1,750 UNACCEPTABLE OPERATION

,f ,f L 1,500 / /

/ [ ACCEPTABLE 2-22 (J) 1,250 HEATUP FMTE -

/ / OPERATION :::~

c) f ,

( UP TO SO 'F/HR r /

Q. l '

l y 1,000 /

G /

H r (d

O 750

/

[ 500

, CRITICALITY LIMIT BASED ON INsEwicE wDROSTATIC TEST 250 l TEMPERATURE (245 *F) FOR THE l

SEWit,E PERIOD UP TO 15 EFPf 0 ''''''''''''''''''

l l 0 50 100 150 200 250 300 350 400 450 500 I ndicated Temperature (Deg . FJ Figure 3.4.3-1 RCS Heatup Limitations Catawba 2 INSERT Page 3.4-6 L _ __ ___

INSERT 6 (Unit 2)

MA~ERIAL PROPERTY BASIS LIMITING MATEIWdS INTERMEDIA ~m SHEll, B8605 2 LIMITING ART AT 15 EFPY: 1/4 t,112.6 T 3/4-t, %.0 T 2,500 ,

i f

2,250 I J

n l O 2.,000 '

(f) I h 1.,750 ::::: m mAste OPERATION /

O l L. 1,500 a

/

U) i

$ 1,250 / AccenAste OPERATION g j Q. l y 1,000 /

O . I o e n oo ,n x (0 750 AATEs *F/hA. NI O :::: ""

0 ---- >

f 500 _ -}{ N 50 /

_.__. 100 250 f f

)'

O '*-

O 50 100 150 200 250 300 350 400 450 500 I nd i cated Temperature (Deg . F)

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{

Figure 3.4.3-2 RCS Cooldown Limitations Catawba 2 INSERT Page 3.4-6

.\

l INSERT l

l Table 3.4.12-1 (Page 1 of 1) l l Reactor Coolant Pump Operating Restrictions for Low l Temperature Overpressure Protection l l Reactor Coolant System Cold Leg Maximum Number of Pumps Allowed in Temperature Operation l

l 2 67*F 1 l

l 2 73*F 2 l

l 2 95*F 4 l Catawba 2 INSERT Page.3.4-32 LIC60% AMENDMNT DRO grg

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

RCO P/T Limits B 3.4.3 BASES ACTIONS C.1 and C.2 (continued)

Condition C is modified by a Note requiring Required Action C.2 to be completed whenever the Condition is entered. The Note emphasizes the need to perform the evaluation of the effects of the excursion outside the allowable limits. Restoration alone per Required Action C.1 is insufficient because higher than analyzed stresses may have occurred and may have affected the RCPB integrity.

SURVEILLANCE SR 3.4.3.1 REQUIREMENTS b.

Verification that operation is within theMinits is required every 30 minutes when RCS pressure and temperature conditions are undergoing planned changes. This Frequency is considered reasonable in view of the control room indication available to monitor RCS status. Also since l temperature rate of change limits are specified in hourly increments. 30 minutes permits assessment and correction for minor deviations within a reasonable time.

l Surveillance for heatup, cooldown, or ISLH testing mAy be discontinued when the definition given in the relevant plant procedure for ending the activity is satisfied.

! This SR is modified by a Note that only requires this SR to be perfonned during system heatup, cooldown, and ISLH -

testing. No SR is given for criticality operations because LCO 3.4.2 contains a more restrictive requirement.

REFERENCES & . jpw-/wyA. AprJr1975D j

@ 2f '10 CFR 50. Appendix G. ~

@. ASNE. Boiler and Pressure Vessel Code.Section I'II.

Appendix G.

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@ 4. ASTN E 185 82. % 1982. g

@4. 10 CFR 50. Appendix H.

(continued) !

, B 3.4 15 Rev 1. 04/07/95

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.L.tcent, wem Q - Seftk 9-/f-97

l l Attachment 3 No Significant Hazards Consideration Determination l The following discussion is a summary of the evaluation of l the changes contained in this proposed amendment supplement l .against the 10CFR50.92(c) requirements to demonstrate that l all three standards are satisfied. A no significant hazards consideration is indicated if operation of the facility in accordance with the proposed amendment would not:

1. Involve a significant increase in the probability or consequences of an accident previously evaluated, or

2. Create the possibility of a new or different kind of accident from any accident previously evaluated, or

3. Involve a significant reduction in a margin of safety.

l First Standard Implementation of this amendment would not involve a significant increase in the probability or consequences of an accident previously evaluated. The Low Temperature Overpressure Protection System is.not an accident initiating system; it is an accident mitigating system. Therefore, the

addition of supplemental Technical Specification required controls pertaining to this system cannot impact accident initiating probabilities. The Low Temperature Overpressure Protection System will remain fully capable of performing its' design accident mitigation function for the modes in which'it is required. Therefore, no accident consequences will be impacted.

l Second Standard Implementation of this amendment would not create the possibility of a new or different kind of accident from any accident.previously evaluated. As noted previously, the Low Temperature Overpressure Protection System is not an accident initiating system. The addition of the supplemental Technical Specification controls pertaining to this system as specified will not impact any plant systems that are accident initiators. No other modifications are being proposed to the-plant which would result in the creation of new accident mechanisms.

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Third Standard Implementation of this amendment would not involve a significant reduction in a margin of safety. Margin.of safety is.'related to the confidence in the ability of the fission product. barriers to perform their design functions during and following an accident situation. These barriers include the fuel-cladding, the reactor coolant system, and the containment system. The performance of the fission product barriers will not be impacted by implementation of this proposed amendment supplement. The Low Temperature

- Overpressure Protection System will remain fully capable of.

- performing its design function-for the modes in which it is required. Therefore, no safety margin will be significantly impacted.

Based upon the preceding analysis, Duke has concluded'that the proposed amendment supplement does not. involve a significant hazards consideration.

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l Attachment 4 Environmental Assessment Pursuant to 10CFR51.22(b), an evaluation of this license amendment request has been performed to determine-whether or not it meets the criteria for categorical exclusion set forth in 10CFR51.22 (c) (9) of the' regulations.

l This amendment to the Catawba Units 1 and 2 Technical Specifications provides conservative changes to the current

' Technical Specifications for the Reactor Coolant System Low Temperature Overpressure Protection System and Emergency Core Cooling System. Consequently, implementation of this amendment will have no adverse impact on: 1) the low temperature-overpressure protection provisions provided for the Reactor Coolant System, 2) the Emergency Core Cooling Systems, or'3) a contribution to any additional quantity or type of effluent being available for adverse environmental impact or personnel exposure.

It has been determined there is:

1) No 'significant haza.rds consideration (see Attachment 3);

2) No significant change in the types, or significant increase in'the amounts, of any eff.luents that may be released offsite; and

3) No 'significant increase in individual or cumulative occupational radiation exposures involved.

Therefore, this amendment to the Catawba Technical Specifications, meets the criteria of 10 CFR 51.22 (c) (9) for categorical exclusion'from an environmental impact statement.

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ML20249B396

Text

4.5 APPLICABILITY

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