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MONTHYEARLR-N06-0233, Request for Change to Technical Specifications Containment Ventilation System, Containment Isolation Valves2006-08-0404 August 2006 Request for Change to Technical Specifications Containment Ventilation System, Containment Isolation Valves Project stage: Request ML0703301782007-02-0202 February 2007 Draft Request for Additional Information Project stage: Draft RAI LR-N07-0032, Response to RAIs on LCR S06-06 Request for Change to Technical Specifications Containment Ventilation System Containment Isolation Valves2007-02-20020 February 2007 Response to RAIs on LCR S06-06 Request for Change to Technical Specifications Containment Ventilation System Containment Isolation Valves Project stage: Request ML0707101782007-03-19019 March 2007 License Amendment, Containment Purge System Project stage: Other ML0708104172007-03-19019 March 2007 Technical Specifications, Consolidate the Containment Isolation Requirements by Moving the Requirements of TS 3/4 6.1.7, Containment Ventilation System, to TS 3/4 6.3, Containment Isolation Valves. Project stage: Acceptance Review ML0708104152007-03-19019 March 2007 Technical Specifications, Consolidate the Containment Isolation Requirements by Moving the Requirements of TS 3/4 6.1.7, Containment Ventilation System, to TS 3/4 6.3.1, Containment Isolation Valves. Project stage: Other 2007-02-02
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Text
-4 -(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 No277 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. 277 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)3/4.5.1 ACCUMULATORS
.. .........................................
3/4.5.2 ECCS SUBSYSTEMS
-Tavg 350 .F ...........................
3/4 .5.3 ECCS SUBSYSTEMS
-Tavg < 350°F ...........................
3/4.5.4 SEAL INJECTION FLOW .....................................
3/4.5.5 REFUELING WATER STORAGE TANK ............................
PAGE 3/4 3/4 3/4 3/4 3/4 5-1 5-3 5-6 5-6b 5-7 3/4.6 3/4.6.1 CONTAINMENT SYSTEMS PRIMARY CONTAINMENT Containment Integrity
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Containment Leakage ..............
Containment Air Locks ............
Internal Pressure ................
Air Temperature
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Containment Structural Integrity.
3/4 3/4 3/4 3/4 3/4 3/4 6-1 6-2 6-5 6-6 6-7 6-8 3/4.6.2 3/4. 6.3 3/4.6.4 DEPRESSURIZATION AND COOLING SYSI Containment Spray System ........Spray Additive System ...........
Containment Cooling System ......CONTAINMENT ISOLATION VALVES ....COMBUSTIBLE GAS CONTROL Hydrogen Analyzers
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Electric Hydrogen Recombiners...
3/4 3/4 3/4 3/4 6-9 6-10 6-11 6-12.. ......................
3/4 6-18........................
3/4 6-19 SALEM -UNIT 1 VI Amendment No. 277 This page left intentionally blank.Note that the elements of TS 3.6.1.7 and 4.6.1.7 were relocated to TS 3/4.6.3.SALEM -UNIT 1 3/4 .6-8a Amendment No.2 7 7 CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3.1 Each containment isolation valve shall be OPERABLE.APPLICABILITY:
MODES 1, 2, 3 and 4.ACTION: NOTE 1 Penetration flow paths, except for the containment purge valves, may be unisolated intermittently under administrative controls.Note 2 A containment purge valve is not a required containment isolation valve when its flow path is isolated with a testable blind flange tested in accordance with SR 4.6.1.2.b.
The required containment purge supply and exhaust isolation valves shall be closed. (Valves immobilized in shut position with control air to valve operators isolated and tagged out of service).NOTE 3 The containment pressure-vacuum relief isolation valves may be opened on an intermittent basis, under administrative control, as necessary to sati!fy the requirement of Specification 3.6.1.4.1. With one or more of the isolation valve(s) inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and either: a. Restore the inoperable valve(s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or b. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or c. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange; or d. Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.2. With one required containment purge supply and/or exhaust isolation valve open, close the open valve(s) within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.SURVEILLANCE REQUIREMENTS 4.6.3.1.1 DELETED SALEM -UNIT 1 3/4 6-12 Amendment No.277 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.1.2 Each containment isolation valve shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by: a. Verifying that on a Phase A containment isolation test signal, each Phase A isolation valve actuates to its isolation position.b. Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation position.c. Not used.d. Verifying thaL on a Containment Purge and Pressure-Vacuum Relief isolation test signal, each required Purge and each Pressure-Vacuum Relief valve actuates to its isolation position.e. Verifying that the Containment Pressure-Vacuum Relief Isolation valves are limited to 60%opening angle.4.6.3.1.3 4.6.3.1.4 4.6.3.1.5 4.6.3.1.6 At least once per 18 months, verify that on a main steam isolation test signal, each main steam isolation valve actuates to its isolation position.The isolation time of each power operated or automatic containment isolation valve shall be determined to be within its limit when tested pursuant to Specification 4.0.5.Each required containment purge isolation valve shall be demonstrated OPERABLE within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after each closing of the valve, except when the valve is being used for multiple cyclings, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, by verifying that when the measured leakage rate is added to the leakage rates determined pursuant to Specification 4.6.1.2.b for all other Type B and C penetrations, the combined leakage rate is less than or equal to 0.60La.A pressure drop test to identify excessive degradation of resilient valve seals shall be conducted on the: a. Required Containment Purge Supply and Exhaust Isolation Valves at least once per 6 months.b. Deleted.4.6.3.1.7 The required containment purge supply and exhaust isolation valves shall be determined closed at least once per 31 days.SALEM -UNIT 1 3/4 6-13 Amendment No.277