ML080670064

Tech Spec Pages for Amendment 288, Surveillance Requirements for Containment Building Penetrations

ML080670064
Person / Time
Site:	Salem
Issue date:	03/13/2008
From:	NRC/NRR/ADRO/DORL/LPLI-2
To:
Ennis R, NRR/DORL, 415-1420
Shared Package
ML080670042	List: ML080670052 ML080670064 ML080670082
References
TAC MD8219
Download: ML080670064 (2)

Text

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() Maximum Power Level PSEG Nuclear LLC is authorized to operate the facility at a 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. 288, are hereby incorporated in the license. The licensee shall operate the facility in accordance I

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 appr oval for less than four loop operation at power levels above P-7 has been granted by the Commis~ion 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 t-hose changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

Amendment No. 288

REFUELING OPERATIONS CONTAINMENT BUILDING PENETRATIONS LIMITING CONDITION FOR OPERATION 3.9.4 The containment building penetrations shall be in the following status:

a. The equipment hatch inside door is capable of being closed and held in place by a minimum of four bolts, or an equivalent closure device installed and capable of being closed,

b. A minimum of one door in each airlock is capable of being closed C. Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either:

1. closed by a manual or automatic isolation valve, blind flange, or equivalent, or

2. capable of being closed by the Containment Purge and Pressure-Vacuum Relief Isolation System.

Note: Penetration flow path(s) providing direct access from the containment atmosphere to the outside atmosphere may be unisolated under administrative controls.

APPLICABILITY: During movement of irradiated fuel within the containment.

ACTION:

With the requirements of the above specification not satisfied, immediately suspend all operations involving movement of irradiated fuel in the containment building. ýThe provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.4.1lEach of the above required containment building penetrations shall be determined to be either in its required condition or capable of being closed by a manual or automatic containment isolation valve at least once per 7 days.

4.9.4.2 Once per refueling prior to the start of movement of irradiated fuel assemblies within the containment building, verify the capability to close, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, the equipment hatch inside door or an equivalent closure device. Applicable only when the equipment hatch is open. during movement of irradiated fuel in the containment building.

4.9.4.3Verify, once per 18 months, each required containment purge isolation valve actuates to the isolation position on a manual actuation signal.

SALEM - UNIT I 3/4 9-4 SALE

- UIT 3/49-4Amendment No. 288