ML20043D306

From kanterella
Jump to navigation Jump to search
Proposed Tech Specs 4.0.5,3.4.3.1 & 3.4.3.2 to Address IGSCC Concerns
ML20043D306
Person / Time
Site: River Bend 
Issue date: 06/04/1990
From:
GULF STATES UTILITIES CO.
To:
Shared Package
ML20043D305 List:
References
NUDOCS 9006070351
Download: ML20043D306 (6)
v • d • e


Text

,___

APPLICABILITY SURVEILLANCE REQUIREMENTS (Continued)

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

inspection and-testing activities

_ activities Weekly At least once per 7 days l

Monthly At.least once per 31-days

- Quarterly or every 3 months At least once per 92 days Semiannually or every 6 mnnths At least_once per 184 days Every 9 months At least once per 276 days Yearly _or annually At least once per 366 days i

The provisions of Specification 4.0.2 are applicable to the above 1

c.

required frequencies for performing inservice inspection and testing activities.

i d.

Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements..

l Nothing in the ASME Boiler and Pressure Vessel Code shall be construed e.

to supersede the requirements of any Technical Specification.

ASM 1 i

i e

RIVER SEND - UNIT 1 3/4 0-3

{9006070331ADOCK 0300o43g DR 900604 PDC

REACTOR COOLANT SYSTEM'

\\

3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR DPERATION i

3.4.3.1 The following reactor coolant system leakage detection systems shall be OPERABLE:

i i

The drywell atmosphere particulate radioactivity monitoring system, I

a.

b.

The drywell and pedestal floor sump drain flow monitoring

systems, Either the drywell air coolers condensate flow rate monitoring system c.

or the drywell atmosphere gaseous radioactivity monitoring system.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2 and 3.

i

-ACTION:

two of the above required leakage detection systems OPE tion may co to-30 days provided grab sam' rywell atmos-

'g g phere are obtained and ana 1ours when the required gaseous and/or particula ea tem is inoperable; other-Y wise, be i

. SHUTDOWN within the next 12 hou LD' SHUTDOWN d

+

e following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.4.3.1 The reactor coolant system leakage detection systems-shall be demon-strated OPERABLE by:

Drywell atmosphere particulate and gaseous monitoring systems-a.

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

The sump drain flow monitoring systems-performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a. CHANNEL CALIBRATION-TEST at least once per 18 months, Orywell air coolers condensate flow rate monitoring system-c.

performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATI0t,1 at least once per 18 montns.

d.

F10w testing the drywell floor drain sump inlet piping for blockage at least once per 18 months."""

i

^nu6 g...'v....J...ti l,,. :

1;, ;t;.c t4 f;11 = h; n t ; f = ! "C

..y u...u w

v.

RIVER BEND - UNIT 1 3/4 4-10 I

_ REACTOR COOLANT $YSTEM OPERATIONAL LEAKAGE-LINITING CONDITION FOR OPERATION 3.4.3.2 Reactor coolant system leakage shall be limited to:-

a.

No PRES $URE BOUNDARY LEAKAGE.

b.

5 gpa UNIDENTIFIED LEAKAGE.

c.

25 gpe total leakage (averaged over any 24-hour period),

d."

0.5 gpa per nominal inch of valve 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 L Table 3.4.3.2-1.

IiwURT III +

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3..

ACTION:

With any PRESSURE BOUNDARY LEAKAGE, be in at least HDT SHUTDOWN within a.

12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> nd in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

With a actor coolant system leakage greater than the limits in b ci 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> o,'r be in at least HOT SHUTDOWN within the next 12 and/or f above, reduce the leakage rate to within the limits withi i

3 in 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 />.

' 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 leut two other closed manual, deactivated automatic or check

  • valves, 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 in COLD SHUTDOWN within the following 24' hours,

d.

With one or more of the high/ low pressure interface valve leakage pressure monitors shown in Table 3.4.3.2-2 inoperable, restore the inoperable monitor (s) to CPERABLE status within 7 days or verify the pressure to be less than the alarm 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 CPERABLE 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The provisions of Specifi-RECEIVED cation 3.0.4 are not applicable.

AUG 131987 i

soe i

" Which have been verified not to exceed the allowable leakage limit at the 4

last refueling cutage or after the last time the valve was disturbed, whichever is more recent.

R7VER RFWD - ffwTT {

1/A A 'M

REACTOR COOLANT $YSTER SURVEILLANCE' REQUIREMENT $

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

Monitoring the drywell. atmospheric particulate radioactivity at least s.

i once.per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. -

i l

b.

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

~

3 I

j' c.

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

l 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 Table 3.4.3.2 1 shall be demonstrated OPERA 8LE by leak testing pursuant to I

Specification 4.0.5 including paragraph IWV-3427(B) of the ASME Code and, verifying the leakage of each valve to be within the specified limit:-

)

At least once per 18 monthsd and

-l) a.

b.

Prior to returning the valve to service following maintenance.

repair or replacement work on the valve which could affect'.its-f l

1eakage rate.

j

. The provisions of Specification 4.0.4 are not applicable for entry into' OPERATIONAL CONDITION 3.

i L

4.4.3.2.3 - The high/ low pressure interface valve-leakage pressure monitors shall be demonstrated OPERABLE with alam setpoints per Table 3.4.3.2-2 by perfomance of a:

a.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and b.

CHANNEL CALIBRAT!0N at least once per 18 months.

l I i [ 3 M R $3 i ' N 5 b 9 5 _ U i.' ' [ N "' " " * " " " i "5 s

RIVER BEND - latIT 1 3/4 4 - Amendment No. 7 RECElVED AUG 13 W SDC l

L

ENCWSURE II INSERI' l

Basis of specification 3/4.4.3.1 1

The drywell and pedestal floor sump drain flow nonitoring systme consist of 2 sumps with one level transmitter and two 100% pumps each.

The level transmitters feed Main Control Rocm level indicators as well'-

as various autcmatic control systems. Each of tho' autmatic~ systms calculate leakage, control pumps and provide annunciation. The leak rate may be determined by the autcmatic system or a manual--procedure L

through the use of the level indication and pump control switches-l located in the main control rom. The substitution of grab samples for the drywell particulate and gaseous nonitors is to allow for continued monitoring of the function while normal cmponents are inoperable.

Basis of specification 3/4.4.3.2

'Ihe use of.the drywell radiation monitors as alternate means_ to monitor a change in the leakage rate while the sump flow monitoring system is inoperable is to continue to provide the operators with drywell leakage information during system outages.

The new ICO 3.4.3.2.e is intended to address Intergranular Stress. Corrosion Cracking (IGSCC) concerns of propagating a crack due to these effects.

l Leakage which continues to increase at a rate'of greater than or cqual to 2 gpn in a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> nay be indicative of IGSCC and entry into the appropriate action is required.

Increases in leakage that stabilize and are no longer increasing at the.above rate within the allowed ICO action timo (e.g. a packing leak) are not intended to be addressed by this. ICO but continue to be included in~the total unidentified leakage limit of 5 gpn.

l

?

1 1

-Q :

3 REACTOR M *"Y SYSTEM i

3/4.4 REACTOR'ennUWT SYSTEM SASE5 j

$AFETY/ RELIEF VALVES (Continued)

L Specification 4.0.5.during shutdown and will be rovisions of'

  • 3 The low-low set systes ensures that safety / relief valve d t

etnisited for a second opening of these valv transient.

5 valves and lowering re-opening.

In this way the opening setpoint of E valves following the initial duty cycle is substantially reduced. Sufficient redunda the. low-low set systen such that failure of any one valve to ope provided for.

ita reduced setpoint does not violate the design basis n or close.at 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGEL 3/4.4.3.1 LEAKAGE DETECTION SYSTEMS provided to monitor and detect leakage from the

, boundary.

Systems",y Guide 1.45, " Reactor Coolant Press sure Regulator

.May 1973.

In conformance with Regulatory. Guide 1.45, the atmos gaseous radioactivity system will have a sensitivity of 10.e M

pC1/cc.

/4.4.3.2 OPERATIONAL LEAFAGE on the predicted and experimentally observed I

capability of the instrumentation for determining e

The considered.

on The evidence obtained from experiments s somewhat greater than that specified for UNIDENTIFIEDsts that, for. leakage-is small that the imperfection or crack assoc E,;the probability.

rapidly.

would grow or the leakage is located and known to be PRES 3URE SOUNDARY. LE

-will be shut down to' allow further investigation and corrective actio

, the reactor The Surveillance Requirements for RCS pressure isolation valv added assurance of valve ' integrity, thereby reducing the prob valve faliure and consequent intersysten LOCA.

isolation valves is IDENTIFIED tEAKAGE and will be considered a the allowed limit.

n of

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

-,_,,_~....m._...

-

Retrieved from "https://kanterella.com/w/index.php?title=ML20043D306&oldid=4537065"