ML20205G499
| ML20205G499 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 04/01/1999 |
| From: | Emch R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20205G503 | List: |
| References | |
| NUDOCS 9904070262 | |
| Download: ML20205G499 (9) | |
Text
p UNITED STATES
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.c. 20555-0001 4
o 9.....g SOUTHERN NUCLEAR OPERATING COMPANY. INC.
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION 1
MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA DOCKET NO. 50-321 EDWIN 1. HATCH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 215 l
License No. DPR-57
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit 1 (the facility)
Facility Operating License No. DPR-57 filed by Southern Nuclear Operating Company, Inc. (Southern Nuclear), acting for itself, Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated Decembei 4,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and rafety of the public; and E. The iscuance 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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9904070262 990401 PDR ADOCK 05000321 p
PDR C 90'l0 70 24 2 i
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. 2. Accordingly, the license is hereby amended by page 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-57 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 215,
are hereby incorporated in the license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This hcense amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Richard L. Emch, Jr., Section Ch:ef, Section 1 Project Directorate 11 Division of Licensing Project Management Office of Nuclear Reactor Regulation At*achment:
Technical Specification Changes Date of issuance:
April 1,1999
ATTACHMENT TO LICENSE AMENDMENT NO. 215 FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed j
pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove Paaes insert Paaes -
2.0-1 2.0-1 5.0-19
-5.0-19 i
l
l SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor r eam dome pressure < 785 psig or core flow < 10% rated core flow:
THERMAL POWER shall be s 25% RTP.
2.1.1.2 With the reactor steam dome pressure a 785 psig and core flow 210% rated core flow:
{
MCPR shall be 21.10 for two recirculation loop operation or a 1.12 for single recirculation loop operation.
l 1
2.1.1.3 Reactor vesse's water level shall be greater than the top of active irradiated fuel.
2.1.2 Reactor Coolant System (RCS) Pressure SL Re.ctor steam dome pressure shall be s 1325 psig.
l 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 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the plant manager, the corporate executive responsible for overall plant nuclear safety, and the offsite review committee.
(continued)
HATCH UNIT 1 2.0-1 Amendment No. 215
is i.
I 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 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 Specification 3.2.2.
j b.
The analytical methods used to determine the core operating j
limits shall be those previously reviewed and approved by the NRC, specifically those described in NEDE-24011-P-A,
" General Electric Standard Application for Reactor Fuel,"
1 (applicable amendment specified in the COLR).
c.
The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits and accident analysis limits) of the safety analysis are met.
d.
The COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
(continued)
HATCH UNIT 1 5.0-19 Amendment No. 215
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UNITED STATES -
NUCLEAR REGULATORY COMMISSION g
I *g WASHINGTON, D.C. 2055M001 s
%...../
SOUTHERN NUCLEAR OPERATING COMPANY. INC.
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA DOCKET NO. 50-366 EDWIN 1. HATCH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Ar;iendment No.156 License No. NPF 1. The Nuclear Regulatory Commission (the Commission) has found that:
i A. The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit 2 (the facility)
Facility Operating License No. NPF-5 filed by Southern Nuclear Operating Company, Inc. (Southern Nuclear), acting for itself, Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated December 4,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in cor,: mity with the application, the provisions of the Act, and the rt.!es and regulations of it,i. ',ommission; 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 set forth in 10 CFR Chapter I; 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 al, applicable requirements have been satisfied.
- 2. Accordingly, the license is hereby amended by page changes to the Technical l
Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-5 is hereby amended to read as follows:
(2) ' Technical Soecifications The Technical Specifications contained in Appendix A and the Environ,vntal Protection Plan contained in Appendix B, as revised through Amendmer, No.156 are hereby incorporated in the license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection l
Plan.
- 3. This license amendment is effective as of its date of issuance and shall be implemented i
within 30 days from the date of issuance.
FOR THE NUCLEAi4 REGULATORY COMMISSION
]
Richard L. Emch, Jr., Section Chief, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reac!or Regulation j
Attachment:
Technical Specification Changes Date of issuance:
April 1, 1999 4
e
ATTACHMENT TO LICENSE AMENDMENT NO.156 FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-3G6 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains vertical lines indicating the areas of change.
Remove Paae Insert Paae I
5.0-19 5.0 19 j
l
Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.5 CORE OPERATI(4G LIMITS REPORT (COLR)
Core operating limits shall be established prior to each a.
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 Rat'o for Specification 3.2.2.
b.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described.n NEDE-240ll-P-A,
" General Electric Standard Application for Reactor Fuel,"
(applicable amendment specified in the COLR).
c.
The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits and accident analysis limits) of the safety analysis are met, d.
The COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
4 (continued) i HATCH UNIT 2 5.0-19 Amendment No.156