ML20072T773

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Proposed Tech Specs Re Leakage Detection Sys & Operational Leakage
ML20072T773
Person / Time
Site: River Bend Entergy icon.png
Issue date: 04/11/1991
From:
GULF STATES UTILITIES CO.
To:
Shared Package
ML20072T770 List:
References
NUDOCS 9104180250
Download: ML20072T773 (6)
v • d • e


Text

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l l APPLICABILITY

( SURVEILLANCE REQUIREMENTS (Continued)

ASME Boiler and Pressure Vessel Required frequencies Code and applicable Addenda for performing inservice terminology for inservice inspection and testing inspection and testing activities activities ,

Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 montns At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days

c. The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities.
d. Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements,
e. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.

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i 9104180250 910411 PDR ADOCK 05000458 l P PDR RIVER BEND - UNIT 1 3/4 0-3

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b.

The drywe11 atmeschere particulate radioactivity , Senit '

The drywell systems. and pedestal fleer se drain flew senttoring c.

er the arywell atmosphere gaseous radioac A_pp(!CA8!LITY: QPERAT!0NAL CCN0!TIONS 1, 2 and 3.

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tien may ctwo of the above reeutred leakage detecties systems CPERA

,g .h.re ar. e tained and anto 30 days provided grab

.ywe 1 ataes-gaseous and/or.particuli urs . hen ta. r uir.d Y 00WN within the neat u is inoperable; other*

l SHUT 00WN SUAvt!LLANCE At0UIREMENf5

4. A. 3.1 strated CPERA8LE The reacter by: cesi.nt syste. ieawage d.tection syste.s shan ne d an-a.

Drywell atmosehere particulate and gaseeve monitor *ng systems-performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a CHANN(L FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 senths.

D.

The sumo drain flow monitoring systems performance at a CHANNEL FUfeCTIONAL 7tlT at least once per J1 days and a CHANNEL CALIBRATICN '

TEST at.least once per la months,

c. Crywell air coolees condensate flew rate monitoring systen-performance of-a CHANNEL FUNCTICMAL Tlif at least once per 31 days . I and a CHANNEL CAL!lRAT!CN st least once per la sentns.
d. Now testing the drywell fleer drata sump Inlet piping for blockage at least once per 18 months.~

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_ REACTOR COOLANT $YSTfM OPERATIONAL LEAKAGE L1HITING CONDITION FOR OPERATION 3.4.3.2 Reactor coolant system leakage shall be limited to:

a. No PRESSURE BOUNDARY LEAKAGE.
b. 5 ppa UNIDENTIFIED LEAKAGE.
c. 25 gpa total leakage (averaged over any 24-hour period).
d. 0.5 gpm per nominal inch of valve size up to a maximum of 5 ppm leakage at a reactor coolant system pressure of 1025 t 15 psig from any reactor coolant system pressure isolation valve specified in In s ed ~111,r---

7 Table 3.4.3.2-1.

7 APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

a. With any PRES $URE BOUNDARY LEAKAGE, be in at 169t HOT SPUTDOW within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOW within the next 24 nours.'
b. With any reactor coolant system leakage greater than the limits in b and/or c, above, reduce the leakage rate to within the Itaits 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 SHUTDOW within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOW within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

' 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 other closed sanual, deactivated automatic or check" valves, or be. in at least HOT SHUTDOW within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOW within 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 pressure intciface valve leakage pressure monitors shWn in Table 3.4.3.2-2 inoperable, restore the inoperable monitor (s) to OPERABLE status within 7 days or verify the pressure to be less than the alare point at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; restore the inoperable monitor (s) to OPERABLE status within 30 days or be in at least HOT SHUTDOW 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The provisions of Speciff-RECEIVED cation 3.0.4 are not appitcable.

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AUG 131987 Insut. EL soc

  • Which have been verified not to exceed the allowable leakage Itait at the last refueling outage or after the last tire the valve was disturbed, <

whichever is more recent.

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l l

REACTOR COOLANT SYSTDi

$URVE!LLANCE REQUIREMENTS _

i 4.4.3.2.1 The reactor coolant system leakage shall be demonstrated to be within I each of the above limits by:

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

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b. ( Monitoring the sump 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 />, AUC 2g eB1 w 4 Monitoring the drywell air coolers condensate flow rate at least once
/.*;,w,,.n..* *"'/ per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and Watt to d. Monitoring the reactor vessel head flange leak detection system at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. .

4.4.3.2.2 Each reactor coolant system pressure isolation valve specified in leak testing pursuant to Table Specification 3.4.3.2-1 shall 4.0.5 be demonstrated including paragraph IWOPERABLE 3427 by(B) of the ASME Code andI verifying the leakage of each valve to be within the specified limit  ;

'a . At least once per 18 months /, and *'l

b. Prior to returning the valve to service following maintenance.

L repair or replacement work on the valve which could affect its L leakage rate. i

. The provisions of $pecification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 3.

4.4.3.2.3 The high/ low pressere. interface valve leakage pressure monitors shall be demonstrated OPERABLE with alam setpoints per Tabl,e 3.4.3.2-2 by perfomance of at .

a. CHANNEL FUNCTIONAL TEST at least once per 31 days, and
. b. CHANNEL CALIBRATION at least once per 18 months.

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ENCLOSURE II 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 invol transmitters food 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.

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REACTOR COOLANT SYSTEM

, 3/4.4 REACTOR COOLANT SYSTEM BASES SAFETY / RELIEF VALVES (Continued)

Demonstration of the safety-relief valve lift settings will occur only during shutdown and will be performed in accordance with the provisions of -

Specification 4.0.5.

The low-low set system ensures that safety / relief valve discharges are minimized for a second opening of these valves, following any overpressure transient. This is achieved by automatically lowering the closing setpoint of 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 duty cycle is substantially reduced. Sufficient redundancy is provided for the low-low set system such that failure of any one valve to open or close at its reduced setpoint does not violate the design basis.

3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.3.1 LEAKAGE DETECTION SYSTEMS The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the reactor coolant pressure i boundary. These detection systems are consistent with the recomendations of Regulatory Guide 1.45, " Reactor Coolant Pressure Scundary Leakage Detection Systems", May 1973. In conformance with Regulatory Guide 1.45, the atmospheric seous radioactivity system will have a sensitivity of 10 8 pCi/cc.

4.4.3.2 OPERATIONAL LEAKAGE i

The allowable leakage rates from the reactor coolant system have been based on the predicted and experimentally observed behavior of cracks in pipes. The normally expected background leakage, due to equipment design and the detection capability of the instrumentation for determining system leakage, was also considered. The evidence obtained from experiments suggests that, for Isakage somewhat greater than that specified for UNIDENTIFIED LEAKAGE, the probability is small that the imperfection or crack associated with such leakage would grow rapidly. However, in all cases, if the leakage rates exceed the values specified I

or the leakage is located and known to be PRESSURE B0UNDARY LEAKAGE, the reactor will be shut down to allow further investigation and corrective action.

l The Surveillance Requirements for RCS pressure isolation valves provide

! added assurance of valve integrity, thereby reducing the probability of gross valve failure'and consequent intersystem LOCA. Leakage from the RCS pressure isolation valves is IDENTIFIED LEAKAGE and will be considered as a portion of the allowed limit.

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l RIVER BEND - UNIT 1 8 3/4 4 3

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