ML071090619

Tech Spec Pages for Amendment 263 Accident Monitoring Instrumentation and Source Check Definition

ML071090619
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: ML070920317 ML071090619 ML071090633
References
TAC MD1654, TAC MD1655, TAC MD1656, TAC MD1657
Download: ML071090619 (6)

Text

(2) Technical Specifications and Environmental Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.263 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Special Low Power Test Program PSE&G shall complete the training portion of the Special Low Power Test Program in accordance with PSE&G's letter dated September 5, 1980 and in accordance with the Commission's Safety Evaluation Report "Special Low Power Test Program",

dated August 22, 1980 (See Amendment No. 2 to DPR-75 for the Salem Nuclear Generating Station, Unit No. 2) prior to operating the facility at a power level above five percent.

Within 31 days following completion of the power ascension testing program outlined in Chapter 13 of the Final Safety Analysis Report, PSE&G shall perform a boron mixing and cooldown test using decay heat and Natural Circulation. PSE&G shall submit the test procedure to the NRC for review and approval prior to performance of the test. The results of this test shall be submitted to the NRC prior to starting up following the first refueling outage.

(4) Initial Test Program PSE&G shall conduct the post-fuel-loading initial test program (set forth in Chapter 13 of the Final Safety Analysis Report, as amended) without making any major modifications of this program unless modifications have been identified and have received prior NRC approval. Major modifications are defined as:

(a) Elimination of any test identified in Chapter 13 of the Final Safety Analysis Report, as amended, as essential; (b) Modification of test objectives, methods or acceptance criteria for any test identified in Chapter 13 of the Final Safety Analysis Report, as amended, as essential; (c) Performance of any test at a power level different by more than five percent of rated power from there described; and Amendment No. 263

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 or 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 intLerval iLto (n) equal subintervals.

SALEM - UNIT 2 1-6 Amendment No.263

TABLE 3.3-6 (Continued)

RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE ALARM/TRIP MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION

2. PROCESS MONITORS

b. Noble GasiEffluent Monitors 2 3

1) Medium Range Auxiliary 1 1,2, 3&4 .3. Oxl 0-2Ci/cm 10-3_101 OCi/cm3 26 Building Exhaust System (Alarm only)

,'Plant Vent) 3 3

2) High Range Auxiliary 1 1,2, 3&4 1. Oxl 02Ci/cm 10--105 LCi/cm 26 Building Exhaust System (Alarm only)

(Plant Vent)

3) Condenser Exhaust 1 1,2, 3&4 *7.12x10 4 cpm 1-106 cpm 26 System (Alarm only)

3. CONTROL ROOM 3

a. Air Intake - 2/Intake## ** .2.48x10 cpm 101_10 7 CPM 27,28 Radiation Level

1. 1. Control Room air intakes shared between Unit 1 and 2.

• ALL MODES and during movement of irradiated fuel assemblies and during CORE ALTERATIONS.

26 3 SALEM - UNIT 2 3/4 3-39a Amendment No.

TABLE 4.3-3 (Continued)

RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNELS SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECKS CHECKS CALIBRATION TEST REQUIRED

2. PROCESS MONITORS

b. Noble Gas Effluent Monitors

1) Medium Range Auxiliary S M R Q 1, 2, 3 & 4 Building Exhaust System' (Plant Vent)

2) High Range Auxiliary S M R Q 1, 2, 3 & 4 Building Exhaust System (Plant Vent)

3) Condenser Exh. Sys. S M R Q 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 2 3/4 3-41a Amendment No.263

TABLE 3.3-11 (Continued)

ACCIDENT MONITORING INSTRUMENTATION REQUIRED MINIMUM NO. OF NO. OF INSTRUMENT CHANNELS CHANNELS ACTION

13. PORV Block Valve Position Indicator 2/valve** 1 1, 2

14. Pressurizer Safety Valve Position 2/valve** 1 1, 2 Indicator

.15. Containment Pressure - Narrow Range 2 1 1, 2

16. Containment Pressure - Wide Range 2 1 7, 2

17. Containment Water Level - Wide Range 2 1 7, 2

18. Core Exit Thermocouples 4/core quadrant 2/core quadrant 1, 2

19. Reactor Vessel Level Instrumentation 2 1 8, 9 System (RVLIS)

20. Containment High Range Accident 2 2 10 Radiation Monitor

21. Main Steamline 1/ 1/ 10 Discharge (Safety MS Line MS Line Valves and Atmospheric Steam Dumps) Monitor

(**) 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.

263 SALEM - UNIT 2 3/4 3-51a Amendment No.

TABLE 4.3-11 (Continued)

SURVEILLANCE REQUIREMENTS FOR ACCIDENT MONITORING INSTRUMENTATION CHANNEL CHANNEL CHANNEL FUNCTIONAL INSTRUMENT CHECKS CALIBRATION TEST

12. PORV Position Indicator M N.A. R

13. PORV Block Valve Position Indicat :or M N.A. Q*

14. Pressurizer Safety Valve Positior 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. Core Exit Thermocouples M R N.A.

19. Reactor Vessel LevellInstrumentation M R N.A.

System (RVLIS)

20. Containment High Range Accident S R Q Radiation 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 3.4.5.

SALEM - UNIT 2 3/4 3-52a Amendment No.263