ML20003G343
| ML20003G343 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/20/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20003G328 | List: |
| References | |
| NUDOCS 8104290078 | |
| Download: ML20003G343 (5) | |
Text
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ATTACHMENT 3 TECHNICAL SPECIFICATION CHANGES O
Remove Pages Insert Pages IV IV 3/4 4-16a 3/4 4-16b 3/4 4-16c 1
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION Pace 3/4.2 POWER DISTIRBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE......................................
3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACT 0R...............................
3/4 2-5 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACT 0R........................ 3/4 2-9 3/4.2.4 QUADRANT P0HER TILT RATI0..................................
3/4 2-11 3/4.2.5 D N S P AR AM ET E RS............................................. 3/4 2-13 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEV INSTRUMENTATION........................
3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION............................................
3/4 3-14 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation.......................
3/4 3-35 Mova bl e Inco re Det ectors................................... 3/4 3-39 Seismic Instrumentation....................................
3/4 3-40 Meteorological Instrumentation............................. 3/4 3-43 Remote S hutdown Instrumentation............................ 3/4 3-46 Fire Detection Instrumentation.............................
3/d 3-49 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS Normal Operation...........................................
3/4 4-1 3/4.4.2 SAFETY VALVES - SHUTDOWN...................................
3/4 4-4 3/4.4.3 SAFETY VALVES - 0PERATING..................................
3/4 4-5 3/4.4.4 PRESSURIZER................................................
3/4 4-6 3/4.4.5 STEAM GENERATORS...........................................
3/4 4-7 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE
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Leakage Detection Systems..................................
3/4 4-14 Operational Leakage........................................
3/4 4-15 Pressure Isolation Valves..................................
3/4 4-16a SALEN - UNIT 1 IV Order dated Aoril 20, 1981
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i REACTOR COOLANT SYSTEM PRIMARY COOLANT SYSTEM PRESSURE ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.4.6.3 P.eact'or Coolant,5ystem Pressure Isolation Valves shall be operational.
- a. ~ The integrity of all pressure isolation valves listed in Table 4.4 4 shall have been demonstrated, except as specified in "b".
Valve leakage shall not. exceed the amounts indicated, b.
In the evert that the " integrity of any pressure isolation
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valve specified in Table 4.4 4 cannot be,cemonstrated...
reactor operation may continue, provided that,at
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least two valves ~ in each high; pressure line havind: a non-functional valve are in and emain in,the mode corresponding to the isolated conditi,on.ta(i AFFliCAEILITY:
MODES 1, 2, 3, and 4.
ACTION:
If neither Condition "a" nor."b" can be met, an orderly shutdown shall be initiated within one hour and the reactor shall 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 />.
SU:VIILLANCE REOUIREMENTS Periedic leakagii testing (b) on each valve listed in Table 4.4.6.3 a.
4.4-4 shall be accomplished.
1.
Each time the plant is placed in COLD SHUTDOWN condition for refueling.
2.
Each time the plant is placed in 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 preceding 12 months.
(a) Motor operated valves shall be placed in the closed posit 4n and power supplies deenergized.
(b) 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 valve c:mpliance with the leakage
'70 BRBML -
Order dated April 20, 1981 3/4 4-16a
3.
Prior to returning the valve to service following maintenance, repair, or replacement work on -the valve.
4 The provision of specification 4.0.4 is not appliedble for entry into Mode 3 or.4 b.
Whenever integrity of a pres'sbre isolation valve lis' tied in Table 4.4-4 cannot be t'emonstrated, the integrit)'of the remaining valve in each high pressure line having 'a leaking valve shall be determiaed and recorded daily.
In addition,
.the position of one other val ~ve located in the-high pressure line shall be recsrded daily.
s 3/4 4-16b Order dated April 20,1581 P00R ORGINA'
P00R BRBINM
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REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES Maximum (a) (b)
System
' Valve No.
Allowable Leakaoe
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45.0 GPM each' Elve '
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Low Pressure Safety Injection Loop 11, cold leg 11SJ56
-[5 0.GPM each vai$e 11SJ43 5,5.0 GPM each valve
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Loop 12., cold leg 12SJ56 5 0 GPM each valve 12SJ43 15.0 GPM each valve 15.d GPM each valve Loop 13, cold leg 13SJ56 135J43 15.0 GPM each valve Loop 13, hot leg 13SJ156 15.0 GPM each valve 13RH27 15 0 GPM each valve Loop 14, cold leg 14SJ56
- 15. 0 GPM each valve 15.0 GPM each valve 14SJ43 15.0 GPM each valve Loop 14, hot leg 14SJ156 15.0 GPM each valve 14RH27 Intermediate Pressure Safety Injection 15.0 GPM each valve Loop 11, cold leg llSJ144 25.0 GPM each valve Lo:p.11, not leg 11SJ156 15.0 GPM each valve 11SJ139 15.0 GPM each valve Locp l'. cold leg 12SJ144 15.0 GPM each valve Lo:p 12, hot leg 12SJ156 15.0 GPM each valve 12SJ139 15.0 GPM each valve 15.0 GPM each valve Loop 13, cold leg 135'J144 15.0 GPM each valve Lo:p 13, hot leg 13SJ156 15.0 GPM each valve 13SJ139
- 15. 0 GPM each valve Lc:p 14, cold leg 14SJl#4 15.0 GPM each valve Loop 14. hot leg 14SJ156 15.0 GPM each valve 14SJ139
( * )1.
Leakage rates less than or equal to 1.0 sp are cor.sidered acceptable.
However, for initial tests, or tests following valve repair or replace-ment leakage rates less than or equal to 5.0 gpm are considered acceptable.
2.
Leakage rates greater than 1.0 g:n b. less than or equal to 5.0 gpm are considered acceptable if the lat.st measured rate has not exceeded the rate determined by the previcus test by an amount that reduces the margin between reasured leakage rate and the maximum permissible rate of 5.0 gpm by 5C% cr greater, i
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Leakage rates greater than 1.0 spm but less than or e:ual to 5.0 epe are considered ur. acceptable if the latest measured rate exceeded the l'
rate determined by the previous test by an amount that reduces the margin between measured leaka;e rate and the maximum pernissible rate cf 5.0 gpm by 50% or greater.
4 Leakage rates greater than 5.0 g:. a-censidered ur. acceptable.
N Minimum differential test pressure shall n:t be less th'an 150 psid.
{ALEM-l' NIT 1 Order dated April 20, 1981 3/4 4-16C