ML20138C846

Proposed Tech Spec 3.4.6.2,authorizing Temporary Extension of Allowed Time in Mode 3 W/Identified RCS Leakage Greater than 1 Gpm

ML20138C846
Person / Time
Site:	Catawba
Issue date:	10/18/1985
From:	DUKE POWER CO.
To:
Shared Package
ML20138C835	List: ML20138C832 ML20138C846
References
NUDOCS 8510230064
Download: ML20138C846 (3)

Text

Proposed Amendment to Catawba Unit 1 Technical Specification 3.4.6.2 Concerning -

Reactor Coolant System Unidentified Leakage 8510230064 851018 PDR ADOCK 05000413 p PDR

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REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE

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LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System leakage shall be limited to:

a. No PRESSURE BOUNDARY LEAKAGE,

b. 1 gpm UNIDENTIFIED LEAKAGE, c.

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

10 gpm I0ENTIFIED LEAKAGE from the Reactor Coolant System, e.

40 gpm 2235 CONTROLLED 1 20 psig, and LEAKAGE at a Reactor Coolant System pressure of

- s f.

I gpm leakage at a Reactor Coolant System pressure of from any Reactor Coolant System Pressure Isolation Valve specified2235 1 20 p in Table 3.4-1.

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

ACTION: s, g

a.

With any PRESSURE BOUNDARY 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 />, b.

With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE and leakage from Reactor Coolant System Pressure Isolation Valves, 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 l within 30 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 hours.*

c.

With any Reactor Coolant System Pressure Isolation Valve leakage greater than 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 deactivated automatic valves, or be in at least SHUTDOWN within HOT STANDBY the following within 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. 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 r*Until 0048 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, October 23, 1985, operation in Mode 3 and 4 is permitt e d with the Reactor Coolant System unidentified leakage rate Mgpm but 45gpm . If the be placed in COLD SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. unide CATAWBA - UNIT 1 3/4 4-20

m JUSTIFICATION AND ANALYSIS OF NO SIGNIFICANT HAZARDS CONSIDERATION The Proposed Amendment is a result of 1.3 GPM unidentified leakage from the Reactor Coolant System of Catawba Unit One. This leakage exceeds the allowed Technical Specification 3.4.6.2 unidentified leakage of 1 GPM. Leakage calculations first identified this problem on the 18th of October, 1985 and the Action Statement was entered at 1448 hours0.0168 days <br />0.402 hours <br />0.00239 weeks <br />5.50964e-4 months <br />. It is anticipated that an Unusual Event will be declared, and the unit shutdown to Mode 3 (Hot Standby) as required within the next 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. Efforts to identify the source of the leakage have not yet been successful and additional time is needed to accomplish this task.

It is felt that because of the low rate.of Leakage it will be difficult to identify the source if plant pressure and temperature are further reduced as required under the Technical Specification Action Statement (be 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 />). Providing an additional 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> at Hot Standy to scarch Containment Areas will increase the likelyhood that leakage paths are identified for correction and not masked to resurface on the next Start-up.

10 CFR 50.92 states that a proposed amendment involves no significant hazards considerations if operation 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 dif ferent kind of accident from any accident previously evaluated; or

3. Involve a significant reduction in a margin of safety.

The proposed amendment does not incrense the probability or consequences of an accident previously evaluated, it does not create the possibility of a new or different kind of accident and it does not involve a significant reduction in a margin of safety.

Since the leakage is not extensive, and only barely exceeds Technical Specifica-tion Limits, it poses no challenge to the ability of the Reactor Coolant Make-up system to maintain system water inventory. Activity 1cvels have remained within acceptable limits and do not indicate any gross leakage of Reactor Coolant. All other Technical Specification requirements are being met and the plant is in a stable condition. The safety margins contained in the LOCA Analysis described in the FSAR are unaffected by this level of leakage and no new accident scenarios are created.

Based upon the above analysis, the proposed amendment is determined to involve no significant hazard considerations.

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