ML19343D552
| ML19343D552 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/20/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19343D534 | List: |
| References | |
| NUDOCS 8105050209 | |
| Download: ML19343D552 (5) | |
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3/4 4-14a 5
3/4 4-14b 3/4 4-14c i
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION Page 3/4.4.2 SAFETY VALVES - SHUTD0WN...............................
3/4 4-5 3/4.4.3 SAFETY VALVES - 0PERATING..............................
3/4 4-6 3/4.4.4 PRESSURIZER............................................
3/4 4-7 3/4.4.5 STEAM GENERATORS.......................................
3/4 4-8 3/4.4.6-REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems..............................
3/4 4-11 Opera tional Lea kage....................................
3/4 4-13
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Pressure Isolation Valves..............................
3/4 J-11a f 3/4.4.7 CHEMISTRY..............................................
3/4 4-15 3/4.4.8 SPECIFIC ACTIVITY......................................
3/4 4-18 3/4.4.9 PRESSURE / TEMPERATURE LIMITS Reactor Coolant System.................................
3/4 4-22 Pressurizer............................................
3/4 4-27 3/4.4.,10 STRUCTURAL INTEGRITY ASME Code Class 1, 2 and 3 Components..................
3/4 4-23 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) l 3/4. 5.1 ACCUMULATORS...........................................
3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - Tavg 350*F.........................
3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS - T
< 350*F.........................
3/4 5-6 avg 3/4.5.4 BORON INJECTION SYSTEM Boron Injection Tank...................................
3/4 5-7 Heat Tracing...........................................
3/4 5-8 3/4.E.5 REFUELING WATER STORAGE TANK...........................
3/4 5-9 l
Order dated April 20,1981 BEAVER VALLEY - UNIT 1 V
Amendment No. 27 l.
REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES LIMIT!NG CONDITION FOR OPERATION 3.4.6.3 Reactor coolant system pressure isolation valves shall be operational.
. APPLICA9ILITY -Modes 1,2, 3 and 4 Action:
1.
All pressure isolation valves listed in Table 4.4-3 shall be functional as a pressure isolation device, except as specified in 2.
Valve leakage shall not exceed the amounts indicated.
2.
In the event that integrity of any pressure isolation valve specified in Table 4.4-3 cannot be demonstrated, reactor operation may continue, provided that at least two valves in each high pressure line having a non-functional valve are in and repafn in, the mode corresponding to the isolated condition.ta?
3.
If Specification 1 and 2 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4 The provision of specification 4.0.4 is not applicable for entry into Mode 3 or 4 (a) Motor operated valves shall be placed in the closed position and powei supplies deenergized.
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6 BEAVER VALLEY - UNIT 1 3/4 4-14a Order dated April 20,1981 I
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REACTOR COOLANT SYSTEMS SURVEILLANCE PEOUIREMENT 4.4.6.3.1 Periodic leakage testing (a) on each valve listed in Table 4.4-3 shall be accomplished prior to entering operational condition 1 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 bera accomplished in the preceedina 9 months, and prior to returning the valve to service after maintenance, repair or replacement work is performed.
4.4.6.3.2 Whenever integrity of a pressure isolation valve listed in Table 4.4-3 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.
O l'ITo 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 computa-tions showing that the method is capable of demonstrating valve compliance with the leakage criteria.
BEAVER VALLEY - UNIT 1 3/4 4-14b Order dated April 20,1981
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t TABl.E 4.4-3 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES Maximum (a) (b)
System Valve No.
Allowable Leakage toop 1, cold leg SI-23
< 5.0 GPM SI-12 5 5.0 GPM
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Loop 2, cold leg SI-24
< 5.0 GPM SI-ll 7 5.0 GPM Loop 3, cold leg SI-25
< 5.0 GPM l
SI-10
'T 5.0 GPM l
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t (a) 1.
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 5.0 gpm i
are considered acceptable if the latest measured rate has not exceeded l
the rate determined by the previous test by an amount that reduces t
- the margin between measured leakage rate and the maximum permissible rate of 5.0 gpm by 50% or greater.
l 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 detennined 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.
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Leakage rates greater than 5.0 gpm are considered unacceptable.
(b) Minimum test differential pressure shall not be less that 150 psid.
3/4 4-14c Order dated April 20,1981 i
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