ML071590185

Units, 1 and 2, Tech Spec Pages for Amendment 265 Relocation of Technical Specification Requirements for the Movable Incore Detectors and Radioactive Gaseous Effluent Oxygen Monitoring Instrumentation

ML071590185
Person / Time
Site:	Salem
Issue date:	06/06/2007
From:	NRC/NRR/ADRO/DORL/LPLI-2
To:
Ennis R, NRR/DORL, 415-1420
Shared Package
ML071200374	List: ML071200393 ML071590185 ML071590189
References
TAC MD2506
Download: ML071590185 (5)

Text

(2) Technical Specifications and Environmental Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.265 . 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 criteriaý 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. 265

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE ..................... ............ 3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR .............. ............ 3/4 2-5 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR ........ .... 3/4 2-9 3/4.2.4 QUADRANT POWER TILT RATIO ................. ............ 3/4 2-13 3/4.2.5 DNB PARAMETERS ............................ ............ 3/4 2-16 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION ....... ............ 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION ........................... ............ 3/4 3-14 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation ...... ..3/4 3-38 Remote Shutdown Instrumentation ........... .. 3/4 3-43 Accident Monitoring Instrumentation ....... .. 3/4 3-50 Radioactive Liquid Effluent Monitoring Instrumentation ........................... .. 3/4 3-53 Power Distribution Monitoring System ...... ............ 3/4 3-65 3/4.3.4 DELETED 265 SALEM - UNIT 2 IV 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) Main Steamline S M R Q 1, 2, 3 & 4 Discharge (Safety Valves and Atmospheric Dumps)

4) 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 3-42 Amendment No265 I

Pages 3/4 3-57 through 3/4 3-64 Deleted SALEM - UNIT 2 3/4 3-56 Amendment No.265

RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the waste gas hol1dup system shall be limited to less than or equal to 2% by volume.

APPLICABILITY: At all times.*

ACTION:

a. With the concentration of oxygen in the waste gas holdup system greater than 2% by volume but less than or equal 4% by volume, reduce the oxygen concentration to the above limits within 48 hours2 days <br />0.286 weeks <br />0.0658 months <br />.

b. With the concentration of oxygen in the waste gas holdup system greater than 4% by volume immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to 2% by volume without delay.

C. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.5 The concentration of oxygen in the waste gas holdup system shall be determined to be within the above limits by continuously"* monitoring the waste gases in the waste gas holdup system with the oxygen monitor. If hydrogen is not measured, the concentration of hydrogen shall be assumed to exceed 4% by volume.

• Not applicable to portions of the Waste Gas System removed from service for maintenance provided that, the portions removed for maintenance are isolated, and purged of hydrogen to less than 4% by volume.

• • Note: If the oxygen monitoring instrumentation is inoperable, operation of the waste gas holdup system may continue provided grab samples are collected at least once per 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> and analyzed within the following 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br />.

SALEM - UNIT 2 3/4 11-15 - UIT SALE 23/4 1-15Amnendmient No.265