ML20066H095

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Proposed Tech Specs 3/4.4.3 Re Limiting Conditions for Operation & Surveillance Requirements for RCS Leakage & Leakage Detection Sys
ML20066H095
Person / Time
Site: River Bend Entergy icon.png
Issue date: 02/13/1991
From:
GULF STATES UTILITIES CO.
To:
Shared Package
ML20066H094 List:
References
NUDOCS 9102200166
Download: ML20066H095 (5)
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Text

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REACTOR COOLANT SYSTEM 3/4.a.3 4EACTOR COOLANT _ SYSTEM LEAKAGE 4

, LEAKAGE OETECTION SYSTEMS

.19!TINGCONDITIONFOROPERAT!0N '

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I 3.4.3.1 ee OPERABLE: The follcwing' *eactor coolant system leakage ostection systems sh a.

The drywell atmosohere particulate radioactivity monitoring' syste b.

The drywell systems, and pedestal-floor sump drain flow monitoring c.

Either the drywell air coolers condensate flow rate monitoring system-or the drywell atmosphere gaseous radioactivity monitoring system.

APPLICA8ILITY

(

OPERATIONAL-CON 0!TIONS 1, 2 and 3.

ACTION:

  • tion may cotwo of the aboveto -

required leakage detection systems OPERA 8 30 days *provided grab sam gg phere are obtained and ana gaseous and/or particula M aours when the rywell: atmos-required Y wise, be in ve so SHUT 00WH within'the.next 12 hou em i's inoperable; other-LO.SHUTOOWN e following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. .

1,U,RVEILLANCEREQUIREMENTS 4.4.3.1 The reactor coolant sy. stem leakage detection systems shall be demon-  :

strated OPERA 8LE by:

a.

Drywell atmosphere particulate and gaseous monitoring systems -

performance of a CHANNEL CHECK at11 east'once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, 4. CHANNEL

FUNCTIONAL TEST at least once-per 31 days and a CHANNEL CALIBRATION at least once par 18 sonths,
b. The sump drain flow' monitoring systems performance af a CHANNEL FUNCTIONAL TE51 at least once per 31 days and a . CHANNEL CALIBRATION .

TEST at.least cnce per 18 months,

c. Orywell air coo er.: candensate -flow rate monitoring system-

' performance of a CHANhel FUNCTIONAL TEST at least once per 31 days and a CHANNEL CAL!BRATION st' least once per 18 montns. -

d. F1ow testing the drywell floor-drain sump inist piping for blockage at least once per 18 months. " .

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LIMITING CONDITION FOR OPERATION ' '

l 3.4.3.2 Reactor coolant system leakage _ shail be' limited' to:. i
a. No PRESSURE B0UNDARY LEAKAGE.
b. 5 gpa UNIDENTIFIED LEAKAGE.
c. 25gpatotalleakage-(averaged.overfany24-hourperiod$:
1 d."' O.5 gpa per nominal inch of valve l size up to' a-maximum of:5 gpa leakage at a reactor: coolant system pressure of 1025 t 15.psig from any reactor coolant: system pressure isolation valve specified'in.

3 Table 3.4.3.2 .1.; *

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ITY: OPERATIONAL CONDITIONS 1,. 2 and 3.

ACTION:

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a.

With any PRESSURE 800NDARY LEAKAGE,<be in at least'H0T-SHUTDOWN within.. ,

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTD0WN'withincthe.nexti24" hours.t

b. With any reactor coolant system'1eakagej greater than the limits in' b ~

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and/or c above, reduce theileakage' rate'to sithin the limits within--

4' hours o,r be in at least NOT SNUTDOWN within the next?l2~ hours'and in-COLD SHUTDOWN within the following 241 hours0.00279 days <br />0.0669 hours <br />3.984788e-4 weeks <br />9.17005e-5 months <br />'.

' c.

With any reactor coolant system pressurelisciation valve leakage greater ,

than the.above limit . isolate the highipressure: portion of. the Laffacted 1 systes fron' the low' pressure portion within 4(hours by uselof  : at least two other closed manual,' deactivated automatic or: check

  • valves, or:

be.in at ler t HOT' SHUTDOWN within'the nekt 12' hours and in' COLD SHUTDOWN wiu.in-the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.# .

d.

.With one or more of the high/ low pressur'e interface valve leakage L 8 l

pressure monitors. shown in-Table 3;4.3.2-2 inoperable, restore the  :

i inoperable monitor (s) to 0PERA8LE status within'7 days'ordvarify the-  !

' pressure to be less'than.the alarm point 'at lea' st once per.12: hours; restore the inoperable monitor (s)<to:0PERABLE.. status within 30 days or be in at least-HOT: SHUTDOWN within' the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and COLD : .

SHUTDOWN within the following 24: hours. The-provisions. ^of Specifi-'

NECEiVED cation:3.0.4-are not applicable. <

a RUG 131987 INsr.nr III

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" Which have been verified not to exceed the allowable ' leakage. limit-at the 11ast: refueling outage or after.the-last time the valve was-disturbed.1 a Lwhichever is more recent.

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REACTOR C001. ANT SYSTEM 51)RVillLANCE RIOUIR(MENTS l

4.4.3.2.1 -;

each of: the above'Italts by:The reactor coolant system leakag

a.  !

, Monitoring the drywell atmospheric particulate radioactivity once per ' 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, b.

Monitoring the sung flow rates at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.-

c.

Monitoring per the 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, anddrpell air coolers condensate flow rate at least on ,

d.

Monitoring the 24 least once per reactor hours. vessel head flange leak detection system at 4.4.3.2.2 - fech reactor coolant system pressure isolation valve specified in Table 3.4.3.2 1 shall be demonstrated CPERA8LE b leak testing pursuant to Specification 4.0.5 including paragraph IW 3427 l) of the A5ME Code and verifying the leakage of each valve to be within the specified limit:

a. LAt least once per 18 monthd and b.

prior to returning the valve to service' following maintenance, l repair or replacement work on the valve which could affect its leakage rate.

. The provisions of- Specification 4.0.4 are not applicable Lfer entry into OPERATIONAL CONDITION 3.

4.4.3.2.3 The high/ low pressure interface valve leakage pressure monitors shall be demonstrated performance of as CPERA8LE with alarm setpoints per Table 3.4.3.2-2 by

a. CHANNEL FUNCTIONAL TEST at least once per 31 days, and l . b'. CHANNEL CALIBRAT!0N at least once per 18 months.

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1 ENCLOSURE II t

INSERT Basis of Specification 3/4.4.3.1 The drywell and pedestal floor sump drain flow monitoring systems consist of 2 sumps with one level transmitter and two 100% pumps each. The level transmitters feed Main Control Room level indicators as well as various automatic control systems. Each of the automatic systems calculate leakage, control pumps and provide annunciation. The leak rate may be determined by the automatic system or a manual procedure through the use of the -level indication and pump control switches located'in the main control room. The substitution of grab samples for the' drywell particulate and gaseous monitors is to allow for continued monitoring of the function -

while normal components are inoperable.

Basis of Specification 3/4.4.3.2 The use of the drywell= radiation monitors as alternate means to monitor a change in the leakage while the sump f. low monitoring system is inoperable is to continue to provide the-operator with drywell leakage information during system outages. The new LCO. 3.'4.'3.2.0 is intended to address Intergranular Stress Corrosion Cracking- (IGSCC) concerns cf propagating a crack due to these effects. . Leakage whicit continues to increase at a rate of greater than or equal to 2; gpm in a period of.24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> may be' indicative of IGSCC and entry into the appropriate action'is required. Increases in leakage resulting from normal plant activities that stabilize and are no longer increasing at the above rate within the allowed LCO action time (e.g. a packing leak) are not intended-to be addressed by this LCO but continue to be included in the total unidentified leakage limit of 5 gpm.

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g .3 MEACTOR COOLANT SYSTEN

.V a 3/4.4 ' REACTOR COOLANT SYSTEM L BASES j

SAFETY / RELIEF VALVES (Continued)-

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Demonstration of the safety-relief valve' lift settirags will occur only during shutdown and willibe-performed in accordance withlthe' provisions of 4

. Specification _4.0.5.- >"

The low-low set system ensures that safety / relief valve 1 discharges are minimized for a second opening of these~ valves, following any overpressure-

' transient.- This. is_ achieved by automatically. lowering thesclosing s'atpoint ofl a 5 valves and lowering the opening setpoint of 2 valves following!the\ initial opening. 'In-this way, the frequency and magnitude of the' containment blowdown a duty cycle is substantially reduced.1 Sufficient redundancy 11s provided_ fori ,  ;

the low-low set system such that failure of any one valve to;cpen or close at >

its reduced setpoint does:not violate =the design basis..  ;

3/4.4.3 REACTOR C00LANT' SYSTEM LEAKAGE

  • a 3/4.4.3.1 LEAKAGE DETECTION-SYSTEMS- "

The RCS lea'kage-detection syptoms; required by'this1 specification;ars s.

provided to monitor and detect leakage from the; reactor < coolant pressure .

J

' boundary. -' These detection syste'es are consistent with-the' recommendations of- '

' Regulatory Guide 1.45,1" Reactor. Coolant Pressure _ Boundary: Leakage: Detection d Systems", May 1973. ;In conformance with; Regulatory Guide 1;45, the atmospheric '

UEEIU seous radioactivity system will:have aisensitivity.of;10 8.pC1/cc.; -t

" 4.4.3.2 OPERATIONAL LEAKAGE E J

The allowable leakage > rates from the-reacto_r coolant' system:have been based- j on the predicted and experimentally 1 observed behavior of cracks .in pipas., Ther l normally-expected background: leakage, due'to: equipment; design and:the c'etection!

. ;e I capability.of the1 instrumentation:for; determining; system;1eakage, wasfalso considered. The evidence 'obtained from- experiments suggests that,lfor leakagen '

a somewhat greater than-thathspecifind for UNIDENTIFIEDJLEAKAGE, the' probability-is small that the imperfection:or crack. associated ~withisuch leakage would growl rapidly.

However, in a11 Leases,11f _the leakage Lrates exceed the1 values Lspecified or t_he leakage'is located and-knowntto be PRESSURE B0UNDARY LEAKAGE,ithe reactor: #

. will be shut down totallow furtheriinvestigationiand: corrective action.

l. '

l The Surveillance Requirements forJRCS pressure!isoiation valves provide-added assurance of valveEintegrity,1thereby- reducing thenprobability of gross valve failure and consequentiintersystem;LOCA.: Leakage;from the RCS pressure-isolation valves is IDENTIFIED' LEAKAGE and will;be: considered asta portion of  :

he allowed limit. "

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