ML20217B426
| ML20217B426 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 10/05/1999 |
| From: | Clifford J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217B411 | List: |
| References | |
| NUDOCS 9910120248 | |
| Download: ML20217B426 (5) | |
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NUCLEA 9 REGULATORY COMMISSION
'4 WASHINGTON, D.C. 2055M001
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PECO ENERGY COMPANY PUB lC SERVICE ELECTRIC AND GAS COMPANY DELMARV.A POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO,3 i
l AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 233 License No. DPR-56 i
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by PECO Energy Company, et al..(the licensee) dated July 12,1999 and supplemented August 30,1999, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; i
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Cornmission; C.
There is rease,re' le assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and cafety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations:
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and i
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.
j 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 Operating License No. DPR-56 is hereby amended to read as follows:
I 9910120248 991005 DR ADOCK 05000278 p
. l (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 233, are hereby incorporated in the license. PECO Energy Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of date of issuance and shall be implemented prior to the start of Peach Bottom Atomic Power Station Unit No. 3, Cycle 13 operation.
FOR THE NUCLEAR REGULATORY COMMISSION mes W. Cliffor, Chief, Section 2 Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 5, 1999 l
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.o 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow:
THERMAL POWER shall be s 25% RTP.
l 2.1.1.2 With the reactor steam dome pressure a 785 psig and core l flow a 10% rated core flow:
MCPR shall be a 1.09 for two recirculation loop operation or i 1.11 for single recirculation loop operation.
2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.
2.1.2 Reactor Coolant System Pressure SL l
Reactor steam dome pressure shall be s 1325 psig.
2.2 SL Violations With any SL violation, the following actions shall be completed:
2.2.1 Within I hour, notify the NRC Operations Center, in accordance with 10 CFR 50.72.
2.2.2 Within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
2.2.2.1 Restore compliance with all SLs; and 2.2.2.2 Insert all insertable control rods.
2.2.3 Within 2t. hours, notify the Plant Manager and the Vice President-Peach Bottom Atomic Power Station.
(continued)
PBAPS UNIT 3 2.0-1 Amendrnent No. 225,233
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1 ATTACHMENT TO OCENSE AMENDMENT NO. 233
. FACit.lTY OPERATING LICENSE NO. DPR 56 -
DOCKET NO. 50-278 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of changes.
Remove Las_g_r1 2.0-1 2.0-1 5.0-21 5.0-21
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f 5.6.5 CORE OPERATING LIMITS REPORT (COLR) a.
Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be_ documented in the COLR for the following:
1.
The Average Planar Linear Heat Generation Rate for Specification 3.2.1; 2.
The Minimum Critical Power Ratio for Specifications 4
3.2.2 and 3.3.2.1; 3.
The Linear Heat Generation Rate for Specification 1
3.2.3; and 4.
The Control Rod Block Instrumentation for Specification j
3.3.2.1.
b.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by J
the NRC, specifically those described in the following documents:
1.
NEDE-240ll-P-A, " General Electric Standard Application for Reactor Fuel" (latest approved version as specified l
in the COLR);
2.
NEDC-32162P, " Maximum Extended Load Line Limit and ARTS Improvement Program Analyses for Peach Bottom Atomic l
Power Station Units 2 and 3," Revision 2, March, 1995; 3.
PEco-FMS-0001-A, " Steady-State Thermal Hydraulic Analysis of Peach Bottom Units 2 and 3 using the FIBWR Computer Code";
4.
PEco-FMS-0002-A, " Method for Calculating Transient critical Power Ratios for Boiling Water Reactors (RETRAN-TCPPECo)";
i 5.
PEco-FMS-0003-A, " Steady-State Fuel Performance Methods L
Report";
6.
PECo-FMS-0004-A, " Methods for Performing BWR Systems Transient Analysis";
(continued)
PBAPS UNIT 3.
5.0-21 Amendment No. 225, 233