ML071090633
| ML071090633 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/19/2007 |
| From: | NRC/NRR/ADRO/DORL/LPLI-2 |
| To: | |
| Ennis R, NRR/DORL, 415-1420 | |
| Shared Package | |
| ML070920306 | List: |
| References | |
| TAC MD1654, TAC MD1655, TAC MD1656, TAC MD1657 | |
| Download: ML071090633 (6) | |
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(1)
Maximum Power Level PSEG Nuclear LLC is authorized to operate the facility at a steady state reactor core power level not in excess of 3459 megawatts (one hundred percent of rated core power).
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.280are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
(3)
Deleted Per Amendment 22, 11-20-79 (4)
Less than Four Loop Operation PSEG Nuclear LLC shall not operate the reactor at power levels above P-7 (as defined in Table 3.3-1 of Specification 3.3.1.1 of Appendix A to this license) with less than four (4) reactor coolant loops in operation until safety analyses for less than four loop operation have been submitted by the licensees and approval for less than four loop operation at power levels above P-7 has been granted by the Commission by Amendment of this license.
(5)
PSEG Nuclear LLC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report, and as approved in the NRC Safety Evaluation Report dated November 20, 1979, and in its supplements, subject to the following provision:
PSEG Nuclear LLC may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
Amendment No.280
DEFINITIONS REACTOR TRIP SYSTEM RESPONSE TIME 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until loss of stationary gripper coil voltage.
REPORTABLE EVENT 1.27 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10CFR Part 50.
SHUTDOWN MARGIN 1.28 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical br would be subcritical from its present condition assuming all full length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be FULLY WITHDRAWN.
SITE BOUNDARY 1.29 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee, as shown in Figure 5.1-3, and which defines the exclusion area as shown in Figure 5.1-1.
SOLIDIFICATION 1.30 Not Used SOURCE CHECK 1.31 SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to either (a) an external source of increased radioactivity, or(b) an internal source of radioactivity (keep-alive source),
or (c) an equivalent electronic source check.
STAGGERED TEST BASIS 1.32 A STAGGERED TEST BASIS shall consist of:
- a.
A test schedule for (n) systems, subsystems,
- trains, or other designated components obtained by dividing the specified test interval into (n) equal subintervals.
SALEM -
UNIT 1 1-6 Amendment No. 280
TABLE 3.3-6 (Continued)
RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABLE MODES ALARM/TRIP SETPOINT MEASUREMENT RANGE ACTION
- 2.
PROCESS MONITORS
- b. Noble Gas Effluent Monitors
- 1) Medium Range Auxiliary Building Exhaust System (Plant Vent)
- 2)
High Range Auxiliary Building Exhaust System (Plant Vent)
- 3) Condenser Exhaust System 1
1 1
1,2, 3&4 1,2, 3&4 1,2, 3&4 3.0x10-2 Ci/cm3 (Alarm only) 1.0x10 2 Ci/cm 3
- 1.27xi04 cpm (Alarm only)
.2.4 8x10 3 cpm 10-3_101 Ci/cm3 10-1_105 Ci/cm 3
(Alarm only) 1-106 cpm 23 23 23
- 3.
CONTROL ROOM
- a. Air Intake -
Radiation Level 2/Intake##
l101_1O7 CPM 24, 25
- Control Room air intakes shared between Unit 1 and 2.
- ALL MODES and during movement of irradiated fuel assemblies and during CORE ALTERATIONS.
SALEM -
[]NTT I 3/4 3-36a Amendment No.280
TABLE 4.3-3 (Continued)
RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNELS INSTRUMENT CHECKS SOURCE CHECKS CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST MODES IN WHICH SURVEILLANCE REQUIRED
- 2.
PROCESS MONITORS
- b. Noble Gas Effluent Monitors
- 1) Medium Range Auxiliary Building Exhaust System (Plant Vent)
- 2)
High Range Auxiliary Building Exhaust System (Plant Vent)
- 3)
Condenser Exh.
Sys.
S M
S S
M M
R R
R Q
Q Q
1, 2, 3 & 4 1, 2, 3 & 4 1, 2, 3 & 4
- 3.
CONTROL ROOM
- a. Air Intake - Radiation Level S
M R
Q
- ALL MODES and during movement of irradiated fuel assemblies and during CORE ALTERATIONS.
SALEM -
UNIT 13/4 3-38a Amendment No.280
TABLE 3.3-11 (CONTINUED)
ACCIDENT MONITORING INSTRUMENTATION INSTRUMENT
- 13.
PORV Block Valve Position Indicator
- 14.
Pressurizer Safety Valve Position Indicator
- 15.
Containment Pressure -
Narrow Range
- 16. Containment Pressure -
Wide Range
- 17.
Containment Water Level -
Wide Range REQUIRED NO.
OF CHANNELS 2/valve**
2/valve**
2 2
2 MINIMUM NO.
OF CHANNELS 1
1 1
ACTION 1
1, 2 1, 2 1, 2 7,
2 7,
2 1, 2 8,
9 1
- 18.
Core Exit Thermocouples 4/core quadrant 2/core quadrant
- 19. Reactor Vessel Level Instrumentation System (RVLIS)
- 20.
Containment High Range Accident Radiation Monitor 2
1 2
M /
MS Line 2
10 10
- 21.
Main Steamline Discharge (Safety Valves and Atmospheric Steam Dumps) Monitor 1/
MS Line
(**'I Total number of channels is considered to be two (2) with one (1) of the channels being any one (1) of the following alternate means of determining PORV, PORV Block, or Safety Valve position:
Tailpipe Temperatures for the valves, Pressurizer Relief Tank Temperature Pressurizer Relief Tank Level OPERABLE.
SALEM -
UNIT 1 3/4 3-55 Amendment No. 2 8 0
TABLE 4.3-11 (Continued)
SURVEILLANCE REQUIREMENTS FOR ACCIDENT MONITORING INSTRUMENTATION CHANNEL CHANNEL CHANNEL FUNCTIONAL INSTRUMENT CHECK CALIBRATION TEST
- 12.
PORV Position Indicator M
N.A.
R
- 13.
PORV Block Valve Position Indicator M
N.A.
Q*
- 14.
Pressurizer Safety Valve Position M
N.A.
R Indicator
- 15.
Containment Pressure -
Narrow Range M
R N.A.
- 16.
Containment Pressure -
Wide Range M
R N.A.
- 17.
Containment Water Level -
Wide Range M
R**
N.A.
- 18.
R N.A.
- 19.
Reactor Vessel Level Instrumentation M
R N.A.
System (RVLIS)
- 20.
Containment High Range Accident Radiation S
R Q
Monitor
- 21.
Main Steamline S
R Q
Discharge (Safety Valves and Atmospheric Steam Dumps)
Monitor
- Unless the block valve is closed in order to meet the requirements of Action b, or c in specification 3.4.3.
- A one-time extension to this surveillance requirement is granted during fuel cycle thirteen allowing Unit 1 operations to continue to the thirteenth refueling outage (IR13).
The surveillance is to be completed at the appropriate time during the 1R13 outage, prior to the unit returning to Mode 4 upon outage completion.
SALEM -
UNIT 1 3/4 3-57a Amendment No.280