ML19343D551

Revised Tech Specs Per Order Modifying License Requiring Periodic Surveillance Over Life of Plant & Specifying Limiting Conditions for Operation of Primary Coolant Sys Pressure Isolation Valves

ML19343D551
Person / Time
Site:	Robinson
Issue date:	04/20/1981
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML19343D531	List: ML19343D530 ML19343D539 ML19343D544 ML19343D551
References
NUDOCS 8105050206
Download: ML19343D551 (6)

Text

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3.1 -19a j>l j 4.1-10 4.1-10

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i 3.1.5 1.eakage 3.1. 5.1 If the prirary system leakage exceeds 1 gpm and the source of leakage is not identified within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, the reactor j

shall be placed in the hot shutdown condition utilizing j

normal operating procedures.

If the source of leakage exceeds 1 gpm and is not identified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the 1

reactor shall be placed in the cold shutdown condition utilizing normal operating procedures.

3.1. 5. 2 '

If the sources of leakage have been identified and it is evaluated that continued operation is safe, operation of the reactor with a total leakage rate not exceeding 10 gpm shall I

be permitted.

If leakage exceeds 10 gpm, the reactor shall be placed in the hot shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> utilizing normal operating procedures.

If the leakage exceeds 10 gpm for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the reactor shall be placed in the cold shutdown condition utilizing normal operating procedures, 1

3.1. 5. 3 If the leakage is determined to be primary to secondary steam generator leakage in excess of 0.35 gpm in any steam generator, or in excess of 1 spm total for all three steam generators, the L

reactor shall be shutdown and the plant placed in the cold f

shutdown condition utilizing normal procedures within 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> i

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after detection.

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During reactor operation and hot shutdown conditions all 3.5.4 a.

pressure isolation va'Ives liste'd in Table 3.1-1 shalf l

be functional as a pressure isolation device, except as l

specified in 3.1.5.4.b.

Valve leakage shall not exceed the amounts indicated, b.

In the event that integrity of any pressure isolation valve specified in Table 3.1-1 cannot be demonstrated, reactor operation may continue, provided that at

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least two valves in each high pressure line having a non-functional valve are in, and remain,in the mode corresponding to the isolated condition. ( Manual valves shall be locked in the closed position; motor cperated valves shall be placed in the closed position and power supplies deenergized ).

c.

If Specifications 3,1.5.4a and b cannot be met, an orderly shutdown shall be initiated and the reactor shall be in hot shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in the cold shutdown condition within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, f

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3;-16 Order dated April 20, 1981 e

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I Basis Leakega fenm the Reactor Coolant System is collected in the containment or by the other closed systems.

These closed systems are: the Steam and Feedwater System, the Waste Disposal System, and the Component CooHng System. Assuming the existence of the maximum allowable activity in the reactor coolant, the rate of 1 gpm unidentified leakage is a conservative limit on what is allowable before the guidelines of 10 CFR Part 20 would be exceeded. This is shown as follows:

If the reactor I

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T AJ L E, 3.1 -1 PRIMARY COOLANT SYSTEM PRESSURE ISOLATION VALVES a)

Maximum System Valve No.

Allowable Leakage Low-Pressure Safety

-< 5.0 GPM for each-valve i

Injection / Residual Heat--Removal Loop 1, cold leg 875A 876A Loop 2, cold leg 8759 876B Loop 3, cold leg,,,

875C 876C High-Pressure Injection 1.oop 2, hot leg 8748 Loop 3, hot leg 874A

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(a)l, Leakage rates less than or equal to 1.0 gpm are considered acceptable.

2.

Leakage rates greater than 1,0 gpm but less than or equal to 9,0 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.

3.1 -19a Order dated April 20, 1981

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TABLE 4.1-3 (Continued) flaximum Time Check Frequency Between Tests 6 vears

13. Turbine inspection l'isual,..agnaflux Every five years and Die Penetrant

14. Fans and Associated-Fans functioning, Once per operating cycle NA Charcoal and AL,so-Laboratory tests on lute Feilters for charcoal must show Control P.oon and

_99 iodine removal.

R(sidual Heat in-place test must P.emoval Compart-show : 99" removal of

.ments (HVF-19, polyd'ispersed 00r HVE-5a and 5b particics by the HEPA respectively) filters and Frenn by the charcoal filters.

15. Isolation Seal Functioning Each refuleing shutdown NA Water System

16. Overpressure Functioning.,

Each refueling shutdown -

NA Protection System

1. Periodic leakage testing (a)(b)'

17. Primary Coolant Functioning on each valve listed System check in Table 3.1-1 shall valves be accomplished prior to entering reactor operation condition after every time the plant is placed in the cold shutdown condition for refueling, after each time the plant is placed in a cold shutdown condition for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if testing has not been accomplished in the pre-ceding 9 months, and prior to service after maintenance, repair or replacenent work is perforned.

(a)To satisfy ALARA requirements, leakage may be measured indirectly (as from.the performance of pressure indicators) if accomplished in accordance with approved procedures and supported by computations showing that the method is capable of demonstrating valvc compliance with ? 5e leakage criteria.

(b} Minimum test ditterential pressure anali not be lest, than 150 psid.

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4.1-10 Order dated April 20, 1981

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TABLE 4.1-3 (Continued)

Maximum limt L Check Frequency Between Tes!

2, Whenever integrity of a pressure isolation valve listed in Table 3.1-1 cannot be demonstrated the integrity of the remaining valve in each high pressure line having a leaking valve shall be determined and recorded daily.

In addition, the position of the other closed valve located in the high pressure piping shall be recorded daily.

t P00R ORIGINA 4.1 -10a Order dated April 20, 1981

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