ML20094M416

Proposed Tech Spec Pages 3/4 4-17 & B3/4 4-3a in Support of Interim Plugging Criteria

ML20094M416
Person / Time
Site:	Farley
Issue date:	03/27/1992
From:	SOUTHERN NUCLEAR OPERATING CO.
To:
Shared Package
ML20094M414	List: ML20094M412 ML20094M416
References
NUDOCS 9203310216
Download: ML20094M416 (3)

Text

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ATTACHMENT Revised Farley Unit 2 Technical Specification Pages 3/4 4-17 .

83/4 4-3a D

920331021,6 920327 PDR ADOCK 05000364 PDR

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o 4

. ELACTOR COOLANT SYSTEM

. '0PERATIONAL LEAKAGE 1.lMITING CONDITION FOR OPERATION m ................. ............................................................

3.4,7.2 Reactor Coolant System leakage shall be limited to:

a. No PRESSURE BOUNDARY LEAKAGE,

b. 1 GPM VNIDENTIFIED LEAKAGE,

c. For the Ninth Goerating Cycle oniv. orimary-t.9-secondary leakaae throuah all steam generators shg]l be limited to 4]iQ gallons per day and 150 aallons Der day throuah any one steam generator, for subsequent cycles,1 GPM total primary-to-secondary l leakage through all steam generators and 500 gallons per day through any one steam generator,

d. 10 GPM UN10ENTlf!ED LEAKAGE from the Reactor Coolant System, and

e. 31 GPM CONTROLLED LEAKAGE at a Reactor Coolant System pressure of 2235 i 20 psig,

f. The maximum allowable leakage of any Reactor Coolant System Pressure Isolation Valve shall be as specified in Table 3.4-1 at a pressure of 2235

• 20 psig.

APPLIC.A_RI! ill: MODES 1, 2, 3 and 4 DOM:

t With any PRESSURE B0UNDARY LEAKAGE, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />,

i. With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE B0UNDARY LEAKAGE, reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

c. With any Reactor Coolant System Pressure Isolation Valve leakage greater than the limit specified in Table 3.4-1, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least two closed manual or deactivated automatic valves, 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

FARLEY-UNIT 2 3/4 4-17 AMENDMENT NO.

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o RE&CTOR COOLANT SYSTEM

' BASES a- Mechanical

1. Indications of degradation in the entire length of the sleeve must be evaluated against the sleeve plugging limit.

2. Indication of tube degradation of any type including a complete guillotine break in the tube between the bottom of the upper joint and the to) of the lower roll expansion does not require that the tube se removed f rom service.

3. The tube plugging limit continues to apply to the portion of the tube in the entire upper joint region and in the lower roll expansion. As noted above the sleeve plugging limit applies to these areas also.

4. The tube plugging limit continues to apply to that portion of the tube above the top of the upper joint,

b. Laser Welded

1. Indications of dearadation in the length of the sleeve between the weld joints must be evaluated against the sleeve plugging limit.

2. Indication of tube degradation of any type including a complete break in the tube between the upper weld joint and the lower weld joint does not require that the tube be removed from service.

3. At the weld joint, degradation must be evaluated in both the sleeve and tube.

4. In a joint with more than one weld, the wald closest to the end of the sleeve represerts the joint to be inspected and the limit of the sleeve inspection.

5. The tube plugging limit continues to apply to the portion of the tube above the upper weld joint and below the lower weld joint.

F* tubes do not have to be plugged or repaired provided the remainder of the

tube within the tubesheet that is above the F* distance is not degraded. The F* distance is equal to 1.79 inches and is measured down from the top of the tubesheet or the bottom of the roll transition, whichever is lower in elevation. Included in this distance is an allowance of 0.25 inch for eddy current elevation measurement uncertainty.

Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect wastage type degradation that has penetrated 20%

of the original tube wall thickness.

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l FARLEY-UNIT 2 B3/4 4-3a AMENDMENT NO.

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