ML20217J557
| ML20217J557 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 10/09/1997 |
| From: | Stolz J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217J548 | List: |
| References | |
| NUDOCS 9710210180 | |
| Download: ML20217J557 (5) | |
Text
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1 UNITED STATES p
,j NUCLEAR REGULATORY COMMISSION
'2 WASHINGTON, D.C. 3046H001 PECO ENERGY COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 225 License No. DPR-56 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by PECO Energy Company, et al. (the licensee) dated June 30, 1997, as supplemented by letter dated September 26, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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) 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 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.
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:
9710210100 971009 PDR ADOCK 0500 0
. (2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 225, 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 its date of issuance, to be implemented prior to startup from Unit 3 refueling outage 3Rll.
FOR THE NUCLEAR REGULATORY COMMISSION l
1 J w F. Stolz, Dire or oject Directorate 1-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Attachmer.t: Changes to the Technical Specifications Date of Issuance: October 9, 1997
ATTACHME4T J LICENSE AMENDMENT NO.??s FACILITY-OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised area is indicated by a marginal line.
Remove Insert 2.0-1 2.0-1 5.0-11 5.0-21 l
l
SLs i
2.0
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2.0 SAFETY LIMITS (SLs) 2.1 -SLs 2.1.1 Reactor Core Sts 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow.
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THERMAL POWER shall be s 25% RTP.
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- 2.1.1.2 With the reactor steam dome pressure a 785 psig and core flow a 10% rated core flow:
MCPR shall be a 1.11 for two recirculation loop operation or a 1.12 for single recirculation loop operation.
2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.
1 2.1.2 Reactor Coolant System Pressure S1 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 Operation:; tenter, in accordance with 10 CFR 50.72.
i 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:
l 2.2.2.1 Restore compliance with all SLs; and j
2.2.2.2 Insert all insertable control rods.
2.2.3 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the Plant Manager and the Vice President-Peach Bottom Atomic Power Station.
i (continued) l *MCPR values in TS 2.1.1.2 are applicable only for Cycle 12 operation i
i PBAPS UNIT 3 2.0-1 Amendment No.225
Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 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 mortion of a reload cycle, and shall be documented in the CO.R for the following:
l.
The Average Planar Lir, tar Heat Generation Rate for Specification 3.2.1; 2.
The Minimum Critical Power Ratio for Specifications 3.2.2 and 3.3.2.1; 3.
The Linear Heat Generation Rate for Specification 3.2.3; and 4.
The Control Red Block Instrumentation for Specification 3.3.2.1.
b.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
1.
NEDE-240ll-P-A, " General Electric Standard Application i
for Reactor Fuel" (latest approved version as specified l
in the COLR);*
2.
NEDC-32162P, " Maximum Extended Load Line limit and ARTS i
Improvement Program Analyses for Peach Bottom Atomic Power Station Units 2 and 3," Revision 1, February, 1993; e
3.
PEco-FMS-0001-A, " Steady-State Thermal Hydraulic l
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)";
5.
PECo-FMS-0003-A, " Steady-State Fuel Performance Methods Report";
6.
PEco-FMS-0004-A, " Methods for Performing BWR Systems Transient Analysis";
(continued)
- For Cycle 12, specific documents were approved in the Safety Evaluation dated (10/9/97) to support License Amendment No. (225) l I
l PBAPS UNIT 3 5.0-21 Amendment No. 225