ML071150358

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Technical Specifications Elimination of Requirements for Hydrogen Recombiners and Hydrogen Analyzers Using the Consolidated Line Item Improvement Process
ML071150358
Person / Time
Site: Salem PSEG icon.png
Issue date: 04/19/2007
From: Richard Ennis
NRC/NRR/ADRO/DORL/LPLI-2
To:
Shared Package
ML070930262 List:
References
TAC MD2328
Download: ML071150358 (4)


Text

(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. 281 , are 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. 281

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 ACCUMULATORS .................. ......................... 3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - T avg Ž 350cF... ......................... 3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS - Tavg < 350FF... ......................... 3/4 5-6 3/4.5.4 SEAL INJECTION FLOW ..................................... 3/4 5-6b 3/4.5.5 REFUELING WATER STORAGE TANK ............................ 3/4 5-7 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Containment Integrity ............... 3/4 6-1 Containment Leakage ................. 3/4 6-2 Containment Air Locks ............... .3/4 6-5 Internal Pressure ................... .3/4 6-6 Air Temperature ..................... .3/4 6-7 Containment Structural Integrity .... 3/4 6-8 Containment Ventilation System ...... 3/4 6-8a 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray System ............ . 3/4 6-9 Spray Additive System ............... .3/4 6-10 Containment Cooling System .......... .3/4 6-11 3/4.6.3 CONTAINMENT ISOLATION VALVES ............................. 3/4 6-12 SALEM - UNIT 1 VI Amendment No.281

INDEX BASES SECTION PAGE 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4'5.1 ACCUMULATORS ............ ................... B 3/4 5-1 3/4.5.2 and ECCS SUBSYSTEMS ........... ................ B 3/4 5-1 3/4.5.3 3/4.5.4 SEAL INJECTION FLOW ........... .............. B 3/4 5-2 3/4.5.5 REFUELING WATER STORAGE TANK (RWST) .... ...... B 3/4 5-2 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT ........... .............. B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS ... ...... B 3/4 6-3 3/4.6.3 CONTAINMENT ISOLATION VALVES ...... .......... B 3/4 6-3 28 1 SALEM - UNIT 1 XiII Amendment No.

PAGES 3/4 6-14 THROUGH 3/4 6-19 ARE INTENTIONALLY LEFT BLANK SALEM - UNIT 1 3/4 6-14 through 19 Amendment No.281