ML20134B002
| ML20134B002 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 01/22/1997 |
| From: | Pickett D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20134B006 | List: |
| References | |
| NPF-62-A-113 NUDOCS 9701290214 | |
| Download: ML20134B002 (5) | |
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t UNITED STATES s
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30806-0001
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ILLINDIS POWER COMPANY. ET AL.
DOCKET NO. 50-461 CLINTON POWER STATION. UNIT NO. 1 AMENDMSTT0-FACILITYOPERATINGLICENSE Amendment No.113 License No. NPF-62 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Illinois Power Company * (IP), and Soyland Power Cooperative, Inc. (the licensees) dated August 15, 1996, and as supplemented on October 28, and November 15, 1996, and January 7, 1997, 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; 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 Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-62 is hereby 1
amended to read as follow::
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- Illinois Power Company is authorized to act as agent for Soyland Power Cooperative, Inc. and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
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i 9701290214 970122 i
DR ADOCK 050004 1 1
2-(2)
Technical Snecifications and Environmental Protection Plan i
The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.113, are hereby incorporated into this license.
Illinois Power 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.
FOR THE NUCLEAR REGULATORY COMMISSION j
V E*b4 h[e.
Douglas V. Pickett, Project Manager Project Directorate III-3 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 22, 1997 1
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ATTACHMENT TO LICENSE AMENDMENT NO.113 FACILITY OPERATING LICENSE NO. NPF-62 DOCKET NO. 50-461 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Paaes Insert Paaes 1
2.0-1 2.0-1
.5 5.0-19 5.0-19 i
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SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs d
2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam done 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 2 785 psig and core flow 210% rated core flow:
NOTE---------------------------
Only applicable for Cycle 7 operation.
4 MCPR shall be 21.09 for two recirculation loop operation or 21.10 for single recirculation loop operation.
2.1.1.3 Reactor vessel water level shall be greater than the top j
of active irradiated fuel.
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2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be s 1325 psig.
2.2 SL Violations With any SL violation, the following actions shall be completed:
4 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 i
2.2.2.2 Insert all insertable control rods.
1 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 corporate executive responsible for overall plant nuclear safety, i
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CLINTON 2.0-1 Amendment No. -943 113 i
RCporting. Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LINITS REPORT (COLR)
(continued) b.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in General Electric Standard Application for Reactor Fuel (GESTAR), NEDE-24011-P-A, except that the MCPR Safety Limits for Operating Cycle 7 shall be determined as described in Illinois Power letters (to the NRC) U-602624 dated August 15, 1996; U-602651 dated October 28, 1996; and U-602662 dated November 15, 1996.
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 midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the
-NRC.
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CLINTON 5.0-19 Amendment No. 4Gr, 113
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