ML032390244

Technical Specification, Revise Drywell Leakage and Sump Monitoring Detection Section of the Current Plant Technical Specification

ML032390244
Person / Time
Site:	Monticello
Issue date:	08/21/2003
From:	Padovan L NRC/NRR/DLPM/LPD3
To:	Denise Wilson Nuclear Management Co
Shared Package
ML032390249	List: ML031980275 ML032390244
References
TAC MB7945
Download: ML032390244 (5)

Text

TABLE OF CONTENTS (Cont'd)

Paue 3.4 and 4.4 Standby Liquid Control System 93 A. System Operation 93 B. Boron Solution Requirements 95 C. 96 3.4 and 4.4 Bases 99 3.5 and 4.5 Core and Containment/Spray Cooling Systems 101 A. ECCS Systems 101 B. RHR Intertie Return Line Isolation Valves 103 C. Containment Spray/Cooling System 104 D. RCIC 105 E. Cold Shutdown and Refueling Requirements 106 F. Recirculation System 107 3.5 and 4.5 Bases 110 3.6 and 4.6 Primary System Boundary 121 A. Reactor Coolant Heatup and Cooldown 121 B. Reactor Vessel Temperature and Pressure 122 C. Coolant Chemistry 123 D. Reactor Coolant System (RCS) 126 I E. Safety/Relief Valves 127 F. Deleted G. Jet Pumps 128 H. Snubbers 129 3.6 and 4.6 Bases 145 3.7 and 4.7 Containment Systems 156 A. Primary Containment 156 B. Standby Gas Treatment System 166 C. Secondary Containment 169 D. Primary Containment Isolation Valves 170 E. Combustible Gas Control System 172 3.7 Bases 175 4.7 Bases 183 ii Amendment No. 0,35,17, 71, 77,7-9,102,10V1, 137

I Y. Shutdown - The reactor is in a shutdown condition when the reactor mode switch is in the shutdown mode position and no core alterations are being performed. In this condition, a reactor scram is initiated and a rod block is inserted directly from the mode switch. The scram can be reset after a short time delay.

1. Hot Shutdown means conditions as above with reactor coolant temperature greater than 212 0F.

2. Cold Shutdown means conditions as above with reactor coolant temperature equal to or less than 2120F.

Z. Simulated Automatic Actuation - Simulated automatic actuation means applying a simulated signal to the sensor to actuate the circuit in question.

AA. Transition Bgfling - Transition boiling means the boiling regime between nucleate and film boiling, also referred to as partial nucleate boiling. Transition boiling is the regime in which both nucleate and film boiling occur intermittently with neither type being completely stable.

AB. Pressure Boundary Leakage - Pressure boundary leakage shall be leakage through a non-isolable fault in the reactor coolant system pressure boundary.

AC. Identified Leakage - Identified leakage shall be:

1. Leakage into the drywell, such as that from pump seals or valve packing leaks, that is captured and conducted to a sump or collecting tank, or

2. Leakage into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be Pressure Boundary Leakage.

AD. Unidentified Leakage - All leakage into the drywell that is not Identified Leakage.

AE. Total Leakage - Sum of the Identified and Unidentified Leakage.

AF. through AH. (Deleted)

Al. Purging - Purging is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

AJ. Venting - Venting is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required.

1.0 5 Amendment No. 14, 1 5,-120, 137

a 3.0 LIMITING CONDITIONS FOR OPERATION j_4.0 SURVEILLANCE REQUIREMENTS I D. Reactor Coolant System (RCS) D. Reactor Coolant System (RCS)

1. Operational Leakage 1. Operational Leakage

a. Any time irradiated fuel is In the reactor vessel Any time irradiated fuel is in the reactor vessel ai and coolant temperature is above 212'F, coolant temperature is above 21 20F, every 12 hc urs reactor coolant system (RCS) leakage, shall be verify the following:

limited to:

a. Unidentified Leakage is within limits,

1) s5 gpm Unidentified Leakage

b. Unidentified Leakage Increase is within limits

2) c 2 gpm increase in Unidentified Leakage and within the previous 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period while in the run mode,

c. Total Leakage is within limits.

3) < 25 gpm Total Leakage averaged over the previous 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, and

4) no pressure boundary leakage

b. With reactor coolant system leakage greater than 3.6.D.1.a.1) or 3.6.D.1.a.3) above, reduce the leakage to within limits within four hours, or be in 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c. With an increase in Unidentified Leakage in excess of the rate specified in 3.6.D.1.a.2) reduce leakage to within limits within four hours, or verify that the source of increased leakage is not service sensitive type 304 or type 316 austenitic stainless steel within four hours, or be in 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.6/4.6 126 Amendment No. 14, 17, 87, 404, 137

I, 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS

d. If any Pressure Boundary Leakage exists, be in 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2. RCS Leakage Detection Instrumentation 2. RCS Leakage Detection Instrumentation I

a. Any time irradiated fuel is in the reactor vessel RCS leakage detection instrumentation shall be and reactor water temperature is above 2120F demonstrated OPERABLE by:

the Drywell Floor Drain Sump Monitoring System shall be operable.' If the Drywell Floor a. Primary containment atmosphere particulate Drain Sump Monitoring System is not operable, monitoring system - perform a sensor check then: 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 monthly and a channel calibration at least

1) Restore the Drywell Floor Drain Sump once per cycle.

Monitoring System to operable status within 30 days. b. Required leakage detection instrumentation -

perform a sensor check once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a

2) Otherwise, be in Hot Shutdown within the channel functional test'* (flow instruments only) 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 at least monthly, and a channel calibration test the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. at least once per cycle.

b. Any time irradiated fuel is in the reactor vessel and reactor water temperature is above 21 2 0F the drywell particulate radioactivity monitoring I system shall be operable.* If the drywell particulate radioactivity monitoring system is not operable, then:

I 1) Analyze grab samples of the primary containment atmosphere once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. ** A functional test of this instrument means Injection of a simulated signal into the instrument (not primary sensor)

A mode change is allowed when this system Is to verify the proper instrument channel response alarm I inoperable. and/or initiating action.

3.6/4.6 126a Amendment No. 17, 8-7, 137

t 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS

2) Otherwise, be in 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c. Any time irradiated fuel is in the reactor vessel and reactor water temperature is above 2120 F at least one channel of the required leakage detection instrumentation shafl be operable. If all channels of both systems (Drywell Floor Drain Sump Monitoring System and drywell particulate radioactivity monitoring system) are inoperable, restore at least one channel of the required leakage detection instrumentation to operable status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, or be in 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

E. Safety/Relief Valves E. Safety/Relief Valves

1. a. Safety/relief valves shall be tested or replaced

1. During power operating conditions and whenever each refueling outage in accordance with the reactor coolant pressure is greater than 110 psig Inservice Testing Program.

and temperature is greater than 3450 F the safety valve function (self actuation) of seven safety/relief b. At least two of the safety/relief valves shall be valves shall be operable (note: Low-Low Set and disassembled and inspected each refueling ADS requirements are located in Specification outage.

3.2.H. and 3.5.A, respectively).

Valves shall be set as follows: c. The integrity of the safety/relief valve bellows shall be continuously monitored.

8 valves at 51120 psig

d. The operability of the bellows monitoring system

2. If Specification 3.6.E.1 is not met, initiate an orderly shall be demonstrated each operating cycle.

shutdown and have reactor coolant pressure and temperature reduced to 110 psig or less and 3450 F 2. Low-Low Set Logic surveillance shall be performed or less within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. in accordance with Table 4.2.1.

3.6/4.6 127 Amendment No. 30, 62, 76, 92, 93, 111, 122, 128, 137