ML20034H064
| ML20034H064 | |
| Person / Time | |
|---|---|
| Site: | Shoreham, Limerick File:Long Island Lighting Company icon.png |
| Issue date: | 03/08/1993 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20034H063 | List: |
| References | |
| NUDOCS 9303150196 | |
| Download: ML20034H064 (2) | |
Text
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(4)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or t
associated with radioactive apparatus or componer,; and (5)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility, and to receive-
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and possess, but not separate, such cource, byproduct, and special nuclear materials as contained in the fuel assemblies and fuel channels from the Shoreham Nuclear Power Station.
C.
This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I (except as exempted from compliance in Section 2.D.
below) and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional' conditions i :
specified or incorporated below:
(1)
Maximum Power Level l
I Philadelphia Electric Company is authorized to operate the facility at reactor core power levels of 3293 megawatts thermal (100 percent rated power) in accordance with the conditions l
specified herein.
(2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, and i
hereby incorporated into this license. PECo shall operate the
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facility in accordance with the Technical-Specifications and the Environmental Protection Plan.
(3)
Fire Protection (Section 9.5, SSER-2)*
1 The licensee shall maintain in effect all provisions of the
-,i approved fire protection program as described in the Final Safety Analysis Report for the facility through Revision 58 and y
as approved in the SER through Supplement 9, and in the-Fire i
Protection Evaluation Report through Revision 12, subject to the followino provisions a and b below-s t
- The parenthetical notification following the title of license conditions denotes
]i the section of the Safety Evaluation Report and/or its supolements wherein the license condition is discussed.
9303150196 930308 PDR ADOCK 05000352 p
PDR i
a.
The licensee shall make no changes to features of the approved fire protection program which would decrease the level of fire protection in the plant without prior approval of the Commission. To make such a change the licensee must submit an application for license amendment pursuant to 10 CFR 50.90.
b.
The licensee may make changes to features of the approved fire protection program which would decrease the level _ of fire protection without prior Commission approval after such features have been installed as approved, provided.
such changes do not otherwise involve a change in a license condition or technical specification or result in an unreviewed safety question (see 10 CFR 50.59). However, the licensee shall maintain, in an auditable form, a current record of all such changes including an evaluation of the effects of the change on the fire protection program and shall make such records available to NRC inspectors upon request. All changes to the approved program made without prior Commission approval shall be reported to the Director of the Office of Nuclear Reactor Regulation, together with supporting analyses, annually.
(4)
Physical Security and Safeouards The licensee shall fully implement and maintain in effect all provisions of the physical security, guard training and qualification and safeguards contingency plans previously approved by the Commission and all amendments and revisions to such plans made pursuant to the-authority of 10 CFR.50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled:
" Limerick Generating' Station, Units 1 & 2, Physical Security Plan," with revisions submitted through October 31, 1988; " Limerick Generating Station, 4
Units 1 & 2, Plant Security Personnel Training and Qualification Plan," with revisions submitted through October 1,1985; and -
" Limerick Generating Station, Units 1 & 2, Safeguards Contingency Plan," with revisions submitted through November 15,-1986.
D The facility requires exemptions from certain requirements of 10 CFR Part 50 and 10 CFR Part 70. These include (a) exemption from the requirement of paragraph III.D.2.(b)(ii) of Appendix J, the testing of containment air locks at times when the containment integrity is not required (Section 6.2.6.1 nf the SER and SSER-3)
(b) exemption from the requirements of paragraphs II.H.4 and'III.C.2 of Appendix J, the leak rate testing of the Main Steam Isolation Valves (MSIVs) at the peak calculated containment pressure, Pa, and
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exemption from the requirements of paragraph III.C.3 of Appendix J that the measured MSIV leak rates be included in the summation for the local leak rate test (Section 6.2.6.1 of SSER-3), (c) exemption from the requirement of paragraphs II.H.1 and III.C.2 of Appendix J, 1
)