ML18102A838

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Proposed Tech Specs 3/4.4.3 Re Relief Valves
ML18102A838
Person / Time
Site: Salem  PSEG icon.png
Issue date: 01/31/1997
From:
Public Service Enterprise Group
To:
Shared Package
ML18102A837 List:
References
NUDOCS 9702190051
Download: ML18102A838 (5)
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Text

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REACTOR COOLANI SYSTEM 3/4.4.3 RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.3 Two power relief valves (PORVs) and their associated block valves shall be OPERABLE.

APPLICABILIIY: MODES l, 2, and 3.

ACTION:

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a. With one or both PORVs inoperable and eapaele ef aeing maa\::lillly eyeledl, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV(s) to OPERABLE status or close the associated block valve(s) with power maintained to the block valve(s); otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

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b. With one PORV inoperable aaa ast eapasle ef aeiag maaYally eyClea, within 1 ~-**r either restore the PORV to OPERABLE status or close its associated block valve and remove power from the block valve; restore the PORV* to OPERABLE. status .. within the following 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT STANDBY within the next* 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

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c. With both PORVs inoperable ana net eapeele ef being martttall' c'cled, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either restore at least one PORV to OPERABLE status or close the associated block valves and remove power from the block valves and be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Restore the remaining PORV to.OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from failure of that valve to meet the Limiting Condition for Operation.
d. With one block valve inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> restore the block valve to OPERABLE status or place the associated PORV in manual controL; restore the block valve to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
e. With both block valves inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> restore the block valves to OPERABLE status or place the associated PORVs in manual control; restore at least one block valve to OPERABLE status within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Restore the remaining block valve to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from failure of that valve to meet the Limiting Condition for Operation.

1-- 9702190051 97013{ ____ _

't PDR ADOCK 05000272 P PDR SALEM - UNIT 1 N4 4-5 Amendment No. 150

I I

I UACIOR COOLANI SYSTEM BASES 3/4.4.2 SAfEIY VALVES The pressurizer code safety valves operate to prevent the RCS from being pressurized above its Safety Limit of 2735 psig. Each safety valve is designed to r3lieve 420,000 pounds per hour of saturated steam at the valve setpoint.

The relief capacity of a single safety valve is adequate to relieve any overpressure concF ion which could occur during shutdown. In the event that no safety valves are OPERABLE, an operating RHR loop, connected to the RCS, provides overpressure relief capability and will prevent RCS overpressurization. In addition, the Overpressure Protection System provides a diverse means of protection against RCS overpressurization at low temperature.

While in Mode 5 the safety valve requirement may be met by establishing a vent path of equivalent relieving capacity when no code safety valves are OPERABLE.

During operation, all pressurizer code safety valves must be OPERABLE to prevent the RCS from being pressurized above its safety limit of 2735 psig .

....._a combined r*' *~f capacity of all of these valves is greater than the maximum surge rate resulting from a complete loss of load assuming no reactor trip until the first Reactor Protecti .. e System trip setpoint is reached (i.e.,

no credit is taken for a. direct reactor* trip on. the, loss . of load) and also assuming no operation of the power operated relief valves or steam dump valves.

Demonstration of the safety valves lift settings will occur only during shutdown and will be performed in accordance with the provisions of Section XI of the ASKE Boiler and Pressure Code.

3/4.4.3 RELIEF VALVES relief SALEM - UNIT 1 B 3/4 4-la Amendme.1t t1u. 150

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. REACTOR COOL\NT SYSTEM 3/4.4.5 RELIEF VALVES LIMITING CONI5ITION°FOR OPERATION 3.4.5 Two power relief valves (PORVs) and their associated block valves shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

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a. With one or .both PORVs inoperable aaEl eapaele ef 'BeiBg mtH!:'l:iB:lly eyelea, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV(s) to OPERABLE status or close the associated block valve(s) with power maintained to the block valve(s); otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

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b. With one PORV inoperabl~ aa~ aet; eapable ef~ag IYft\:J:ally eyefJ!G, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV to OPERABLE status or close its associated block valve and remove power from the block valve; restore the PORV to OPERABLE status within tha following 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT STANDBY within the .1ext 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT S:tiUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

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c. With both PORVs inoperable aaa fl:a!: eapable ef eeiag maR1:1-ally ~;(

within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either restore at least one PORV to OPERABLE status ~

or close the associated block valves and remove power from the block' valves and be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Restore the remaining PORV to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from failure of that valve to meet the Limiting Condition for Operation.

. d. With one block valve inoperable, within l hour restore the block valve to OPERABLE status or place the associated PORV in manual control; restore the block valve to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

e. With both block valves inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> restore the block valves to OPERABLE status or place the associated PORVs in manual control; restore at least one block valve to OPERABLE status within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Restore the remaining block valve to OPERABLE sta~ within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from failure of that valve to meet the Limiting Condition for Operation.

(

SAI.Eh - _ UNIT 2 1

/4 4-8 Amendment No. 130

REACTOR COOLANI SYSTEM BASES 3/4.4.2 and 3/4.4.3- SAfETY VALVES The pressurizer code safety valves operate to prevent the RCS from being pressurized above its Safety Limit of 2735 psig. Each safety valve is designed to ~clieve 420,000 pounds per hour of *saturated steam at the valve setpoint. The relief capacity of a single safety valve is adequate to relieve any overpressure condition which could occur during shutdown. In the event that no safety valves are OPERABLE, an operating RHR loop, connected to the RCS, provides overpressure relief capability and will prevent RCS overpressurization. In addition, the Overpressure Protection System provides a diverse means of protection against RCS overpressurization at low temperature. While in Mode 5 the safety valve requirement may be met by establishing a vent path of equivalent relieving capacity when no code safety valves are OPERABLE.

During operation, all pressurizer code safety valves must be OPERABLE to prevent the RCS from being pressurized above its safety limit of 2735 psig.

The combined relief capacity of all of these valves is greater than the maximum surge rate resulting from a complete loss of load assuming no reactor trip until the first Reactor Protective System trip setpoint is reached (i.e.,

no credit is taken for a direct reactor trip on the loss of load) and also assuming no operation of the power operated relief valves or steam dump valves.

Demonstration of the safety valves lift settings will occur only during .

shutdown and will be performed in accordance with the provisions of Section Xl<

of the ASME Boiler and Pressure Code.

3/4.4.4 PR£SSVRIZER.

- The limit on the maximum water volume in the pressurizer assures that the parameter is maintained within the normal steady-state envelope of operation assumed in the SAR. The limit is consistent with the initial SAR assumptions.

The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surveillance is sufficient to ensure that the parameter is restored to within its limit following expected transient operation. The maximum water volume also ensures that a steam bubble is formed and thus the RCS is not a hydraulically solid system. The requirement that a minimum.

number of pressurizer heaters be OPERABLE enhances the capability of the plant to control RCS pressure and establish natural circulation.

3/4.4.5 BELIEF VALVES SALl..'i - UNIT 2 3 3/4 4-2 Amendment No. 130

'/ -

REACTQB COOLANT SYSTEM BASES 3/4. 4. 5 RELIEF-VALVES ---(continued)

J:1~me~~design function. PORV inoperability may be leakage, ion problems, automatic control proble , ot er causes that do not prevent manua d do not c possibility for R small break LOCA. The Action State the block valve be closed, and power 11&intai PORV is still

_ __.c~t-atrree of being manually 3/4.4.6 STEAK GElfERATOR5 The Surveillance Requirements for iru1pection of the steam generator tubes ensure that the structural integrity of thia portion of the RCS will be maintained. The program for inservice inspection of steam generator tubes is based on a 112dification of Regulatory Guide 1.83, Revision 1. Inservice inspection of steam generator tubing is essential in order to 11&intain surveillance of the conditions of the tubes in the event that there is -

evidence of mechanical damage or progressive dagradation due to design, manufacturing errors, or inservice conditions that lead to corrosion.

Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that -corrective measures -can .. be. *talten*; ..

The plant is expected to be operated in a manner such that the secondary coolant vill be maintained within those cheaiatry limit* found to result in negligible corrosion of the steam generator tubes. If the secondary coolant ch. .istry is not maintained within these liaita, localized corroaion DAY likely result in stress corrosion cracking. The extent of cracking during plant operation would be liaited by th* liai.tation of steaa generator tube leakage between th* primary coolant system and the* secondary coolant system (primary-to-secondary leakage - 500 gallon.S per day per steam generator).

Cracks having a primary-to-secondary leakage less than thia liait during operation will have an adequate nargin of safety to withstand the loads imposed during normal operation and by postulated accidents. Operating plants have demonstrated that priaary-to-secondary leakage of 500 gallons per day per steam generator can readily be detected by radiation 110nitora of *team _

generator blovdovn. Leakage in exceH of thia limit will require plant shutdown and an unscheduled inspection, during which the leaking tubes will be located and plugged.

Vaatage-type defect* are unlikely with proper ch. .iatry treataent of the secondary coolant. However, even if a defect should develop in service, it will be found during scheduled inservice ate- generator tube examinations.

Plugging will be required for all tubes with imperfections exceeding the plugging limit of 40* of the tube nominal wall thickneH. Steam generator cube inspections of operating plants have deaonstrated the capability to reliably detect degradation that has penetrated 20* of the original tube wall thickness. -

SAJ.EM - UNIT 2 8 3/4 4-3 Amendment No. 130

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