ML032390244
| 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: |
| References | |
| TAC MB7945 | |
| Download: ML032390244 (5) | |
Text
TABLE OF CONTENTS (Cont'd) 3.4 and 4.4 3.5 and 4.5 3.6 and 4.6 3.7 and 4.7 Standby Liquid Control System A.
System Operation B.
Boron Solution Requirements C.
3.4 and 4.4 Bases Core and Containment/Spray Cooling Systems A.
ECCS Systems B.
RHR Intertie Return Line Isolation Valves C.
Containment Spray/Cooling System D.
RCIC E.
Cold Shutdown and Refueling Requirements F.
Recirculation System 3.5 and 4.5 Bases Primary System Boundary A.
Reactor Coolant Heatup and Cooldown B.
Reactor Vessel Temperature and Pressure C.
Coolant Chemistry D.
E.
Safety/Relief Valves F.
Deleted G.
Jet Pumps H.
Snubbers 3.6 and 4.6 Bases Containment Systems A.
Standby Gas Treatment System C.
Primary Containment Isolation Valves E.
Combustible Gas Control System 3.7 Bases 4.7 Bases Paue 93 93 95 96 99 101 101 103 104 105 106 107 110 121 121 122 123 126 127 I
128 129 145 156 156 166 169 170 172 175 183 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 2120F.
- 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, 15,-120, 137
a 3.0 LIMITING CONDITIONS FOR OPERATION j_4.0 SURVEILLANCE REQUIREMENTS I
D. Reactor Coolant System (RCS)
- a.
Any time irradiated fuel is In the reactor vessel and coolant temperature is above 212'F, reactor coolant system (RCS) leakage, shall be limited to:
- 1) s5 gpm Unidentified Leakage
- 2) c 2 gpm increase in Unidentified Leakage 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,
- 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
- 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 />.
D. Reactor Coolant System (RCS)
- 1. Operational Leakage Any time irradiated fuel is in the reactor vessel ai coolant temperature is above 21 20F, every 12 hc verify the following:
- a. Unidentified Leakage is within limits,
- b.
Unidentified Leakage Increase is within limits and
- c.
Total Leakage is within limits.
urs 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
- a. Any time irradiated fuel is in the reactor vessel and reactor water temperature is above 2120F the Drywell Floor Drain Sump Monitoring System shall be operable.' If the Drywell Floor Drain Sump Monitoring System is not operable, then:
- 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 />.
- b. Any time irradiated fuel is in the reactor vessel and reactor water temperature is above 21 20F the drywell particulate radioactivity monitoring system shall be operable.* If the drywell particulate radioactivity monitoring system is not operable, then:
- 2.
RCS Leakage Detection Instrumentation RCS leakage detection instrumentation shall be demonstrated OPERABLE by:
- a. Primary containment atmosphere particulate monitoring system - 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 channel functional test at least monthly and a channel calibration at least once per cycle.
- 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 channel functional test'* (flow instruments only) at least monthly, and a channel calibration test at least once per cycle.
I I
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 mode change is allowed when this system Is inoperable.
I
- A functional test of this instrument means Injection of a simulated signal into the instrument (not primary sensor) to verify the proper instrument channel response alarm 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 2120F 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
- 1. During power operating conditions and whenever reactor coolant pressure is greater than 110 psig and temperature is greater than 3450 F the safety valve function (self actuation) of seven safety/relief valves shall be operable (note: Low-Low Set and ADS requirements are located in Specification 3.2.H. and 3.5.A, respectively).
Valves shall be set as follows:
8 valves at 51120 psig
- 2. If Specification 3.6.E.1 is not met, initiate an orderly shutdown and have reactor coolant pressure and temperature reduced to 110 psig or less and 3450 F or less within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
E. Safety/Relief Valves
- 1. a. Safety/relief valves shall be tested or replaced each refueling outage in accordance with the Inservice Testing Program.
- b. At least two of the safety/relief valves shall be disassembled and inspected each refueling outage.
- c. The integrity of the safety/relief valve bellows shall be continuously monitored.
- d. The operability of the bellows monitoring system shall be demonstrated each operating cycle.
- 2. Low-Low Set Logic surveillance shall be performed in accordance with Table 4.2.1.
127 Amendment No. 30, 62, 76, 92, 93, 111, 122, 128, 137 3.6/4.6