ML20206R779
| ML20206R779 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 01/12/1999 |
| From: | Bill Dean NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20206R783 | List: |
| References | |
| NUDOCS 9901200250 | |
| Download: ML20206R779 (5) | |
Text
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UNITED STATES r
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NUCLEAR REGULATORY COMMISSION p
WASHINGTON, D.C. 2006H001 PECO ENERGY COMPANY aI DOCKET NO. 50-353 7
LIMERICK GENERATING STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 94 License No. NPF-85 1.
The Nuclear Regulatory Commission (the Commission) has found that:
i A.
The application for amendment by PECO Energy Company (the licensee) dated j
September 14,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and i
regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the pnnisions cf the Act, i
and the rules and regulations of the Commission-1 C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii)
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that such activities will be conducted in compliance with the Commission's regulations; 4
i D.
The issuance of this amendment will not be inimical to the common defense and j
security or to the health and safety of the public; and i
4 E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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c 9901200250 990112 PDR ADOCK 05000353 P
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility i
Operating License No. NPF-85 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 94, are i
hereby incorporated into this license. PECO Energy Company shall operate the facility In accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION i
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William M. Dean, Director Project Directorate 1-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: January 12, 1999 t
ATTACHMENT TO LICENSE AMENDMENT NO. 94 FACILITY OPERATING UCENSE NO. NPF-85 DOCKET NO. 50-353 Replace the following pages of the Appendix A Technical Specifications with the attached page. The revised pages are identified by Amendment nun.ber and contain vertical lines indicating the area of change.
Remove Insert 3/4 4-19 3/4 4-19 i
3/4 4-21 3/4 4-21 l
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REACTOR COOLANT SYSTEM SURVEILLANCE RE0VIREMENTS (Continued) 4.4.6.1.2 The reactor coolant system temperature and pressure shall be determined to be to the right of the criticality limit line of Figure 3.4.6.1-1 curve C and curve C_' within 15 minutes prior to the withdrawal of control rods to bring the reactor to criticality and at least once per 30 minutes during system heatup.
4.4.6.1.3 The reactor vessel material surveillance specimens shall be removed I
and examined, to determine changes in reactor pressure vessel material properties, as required by 10 CFR Part 50, Appendix H in accordance with the schedule in Table 4.4.6.1.3-1.
The results of these examinations shall be used to update 4
the curves of Figure 3.4.6.1-1.
4.4.6.1.4 The reactor flux wire specimens located within the surveillance capsules i
shall be removed and examined to determine reactor pressure vessel fluence as a
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function of time and power level and used to modify Figure B 3/4 4.6-1 in accordance with the schedule in Table 4.4.6.1.3-1.
The results of these fluence determinations shall be used to adjust the curves of Figure 3.4.6.1-1, as required.
4.4.6.1.5 The reactor vessel flange and head flange temperature shall be verified to be greater than or equal to 70*F:
In OPERATIONAL CONDITION 4 when reactor coolant system temperature a.
is:
1.
s 100*F, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
2.
s 90*F, at least once per 30 minutes.
I b.
Within 30 minutes prior to and at least once per 30 minutes during tensioning of the reactor vessel head bolting studs.
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LIMERICK - UNIT 2 3/4 4-19 Amendment No. 94
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TABLE 4.4.6.1 3-1 I
i REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM-WITHDRAWAL SCHEDULE Cz E
CAPSULE i
VESSEL LEAD WITHDRAWAL TIME y
NUMBER
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LOCATION FACTOR *
(EFPY) 131C 7717 G003 30' j
1.20 15 l
zZ 131C 7717 G002 I
120' l.20 30 l
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131C 7717 G001 300*
1.20 Spare i
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