ML20072M805

Proposed Tech Specs Re Leak Rate Testing Criteria

ML20072M805
Person / Time
Site:	Farley
Issue date:	07/08/1983
From:	ALABAMA POWER CO.
To:
Shared Package
ML20072M800	List: ML20072M795 ML20072M805
References
NUDOCS 8307150099
Download: ML20072M805 (4)

Text

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ATTACHMENT Revised Unit 2 Technical Specifications Pages 3/4 4-17 3/4 4-17a 3/4 4-19b B307150099 830708 PDR ADOCK 05000348 p

PDR

. REACTOR C0_0LA_NT SYST_EM CPERATIONAt LEAKAGE LIMITING _CCNDITION FOR CPERATION

.3.4 7.2 Reactor _foolant System leakage shall be limited to:

a.

No PRESSURE BOUNDARY LEAKAGE, b.

1 GPM UNIDENTIFIED LEAGGE, c.

1 GPM total primary-to-secondary leakage through all steam generators and 500 gallons per day through any one steam generator, d.

10 GPM IDENTIFIED LEAXAGE from the Reactor Coolant System, and e.

31 GPM CONTROLLED LEAXAGE at a Reactor Coolant System pressure of 2235

• 20 psig.

• f 1 G2M leakage frem any Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1 at a Reactor Coolant System pressure of 2235

• 20 psig.

APPLICABILITY:

MODES 1, 2, 3 and 4 ACTION:

1 a.

With any PRESSURE SOUNCARY LEAXAGE, be in at least HOT STANCBY within 6 heurs 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 />.

b.

With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE SOUNDARY LEAXAGE, 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 NOT 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 />.

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c.

With any Reactor Coolant System Pressure Isolation Valve leakage greater that the above limit, isolate the high pressure portion of the affected system from the 1cw 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 NOT 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 SHUTDCW within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.-

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SURVEILL)NCE REOUIREMENTS 4.4.7.2.1 Reactor Coolant Syseem leakages shall be demonstrated to be within each of the above limits by; a.

Monitoring the containment atmosphere particulate radioactivity monitor at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b.

Monitoring the containment air cooler condensate level system or containment atmosphere gaseous radioactivity monitor at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

FARLEY-UNIT 2 -

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REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.7.2 Reactor Coolant System leakage shall be limited to:

a.

No PRESSURE BOUNDARY LEAKAGE, b.

1 GPM UNIDENT! Ilio LEAKAGE, 1 GPM total primary-to-secondary leakage through all steam c.

generators and 500 gallons per day through any one steam generator, d.

10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System, and 31 GPM CONTROLLED ' LEAKAGE at a Reactor Coolant System pressure of e.

2235 + 20 psig.

• f.

The maximum allowable leakage of any Reactor Coolant System Pressure Isolation Valve shall be as specified in Table 3.4-l a at a pressure of 2235 1 20 psig.

9 APPLICABILITY: MODES 1, 2, 3 and 4 ACTION:

With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY a.

within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and 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 />.

b.

With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY 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 that the above limit, 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 deactiviated 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 />.

• SURVEILLANCE REQUIREMENTS 4.4.7.2.1 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by; a.

Monitoring the containment atmosphere particulate radioactivity monitor at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b.

Monitoring the containment air cooler condensate level system or containment atmosphere gaseous radioactivity monitor at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

rADIFY - IINIT ?

3/4.4-17a

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• These leakage rates apply only to startup tests following the'sedond: refueling outage. Allowable leakage rates for this one time exception are contained in Table 3.4-1b

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L TABLE 3.4-lb REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES Q2E11V016A Q2E21V062A Q2E11V001A Q2E21V062B Q2E11V016B Q2E21V062C Q2E11V001B Q2E21V066A Q2E21V066B Q2E11V051A Q2E21V066C Q2E11V051B Q2E21V077C Q2E11V051C Q2E21V078A Q2E11V021A Q2E21V0788 Q2E11V021B Q2E21V078C Q2E11V021C Q2E21V079A Q2E11V042A Q2E21V079B Q2E11V0428 Q2E21V079C Q2E21V077A*

Q2E21V032A*

Q2E21V077B*

Q2E21V032B*

Q2E21V076A*

Q2E21V032C*

Q2E21V076B*

Q2E21V037A*

Q2E21V037B*

Q2E21V037C*

ALLOWABLE LEAKAr,E RATES:

1.

Leakage rates less than or equal to 1.0 gpm are considered acceptable.

However, for initial tests, or tests following valve repair or replacement, leakage rates less than or equal to 5.0 gpm are considered acceptable.

2.

Leakage rates greater than 1.0 gpm but less than or equal to 5.0 gpm are considered acceptable if the latest measured rate has not exceeded the rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the maximum permissible rate of 5.0 gpm by 50% or greater.

3.

Leakage rates greater than 1.0 gpm but less than or equal to 5.0 gpm are considered unacceptable if the latest measured rate exceeded the rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the maximum permissible rate of 5.0 gpm by 50% or greater.

4.

Leakage rates greater than 5.0 gpm are considered unacceptable.

Minimum differential test pressure shall not be less than 150 psid.

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l FARLEY - UNIT 2 3/4 4-19b l

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