ML17059A105
| ML17059A105 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 11/10/1993 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17059A106 | List: |
| References | |
| NUDOCS 9311180243 | |
| Download: ML17059A105 (10) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555.0001 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-410 NINE MILE POINT NUCLEAR STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
52 License No.
NPF-69 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated March 22,
- 1993, as supplemented July 14,
- 1993, and September 14,
- 1993, 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 1;
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. NPF-69 is hereby amended to read as follows:
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(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached
- hereto, as revised through Amendment No. 52
. are hereby incorporated into this license.
Niagara Mohawk Power Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of 'the date of its issuance to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 10, 1993 Robert A.. Capra, Director Project Directorate I-I Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
AMENDMENT NO.
ATTACHMENT TO LICENSE AMENDMENT TO FACILITY OPERATING LICENSE NO. NPF-69 DOCKET NO. 50-410 Revise Appendix A as follows:
Remove Pa es 6-23 B 3/4 2-4 I sert Pa es 6-23 B 3/4 2-4
R L
R RATIN LIMIT RE RT 6.9.1.9 (Continued) 2)
The GESTR-LOCA and SAFER Models of the Evaluation of the Loss-ofCoolant Accident - SAFER/GESTR Application Methodology, NEDE-23785-1-PA, latest approved revision.
3)
General Electric Standard Application for Reactor Fuel, NEDE-24011-P-A-US, latest approved revision.
C.
The core operating limits shall be determined such that all applicable limits (e.g fuel thermalmechanical limits, core thermal*ydraulic limits, ECCS limits, nuclear limits such as shutdown margin, transient analysis limits, and accident analysis limits) of the safety analysis are met.
d.
The CORE OPERATING LIMITS REPORT, including any midwycle revisions or supplements shall be provided, upon issuance for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
IA R
RT 6.9.2.
Special reports shall be submitted in accordance with 10 CFR 50,4 within the time period specified for each report.
1 RE RD RETENTI N
6.10.1 In addition to the applicable record retention requirements of Title 10, of the Code of Federal Regulations (10 CFR), the following records shall be retained for at least the minimum period indicated.
6.10.1.1 The following records shall be retained for at least 5 years:
a, Records and logs of unit operation covering time interval at each power level b,
Rexeh and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety c.
AI.REPORTABLE EVENTS submitted to the Commission d.
Records of surveillance activities, inspections, and calibrations required by these Technical Specifications e.
Records of changes made to the procedures required by Specification 6.8.1 f.
Records of radioactive shipments Amendment No.
g.
Records of sealed source and fission detector leak tests and results h.
Records of annual physical inventory of all sealed souce material of record NINE MILE POINT - UNIT 2 6-23
P WER D RIB TI N LIMIT BA E
4.2.
MINIM M RITI AL POWER RATI 3/4.2.3 (Continued) while still allotting time for the power distribution to stabilize.
The requirement for calculating MCPR, after initiallydetermining that a LIMITINGCONTROL ROD PATTERN exists, ensures MCPR will be known following a change in THERMAL POWER or power shape and therefore> operation while exceeding a thermal limit will be avoided.
4.2 4 LINEAR HEAT GENERATION RATE This specification assures that the linear heat generation rate (LHGR) in any rod is less than the design linear heat generation rate even if fuel pellet densification is postulated.
The daily requirement for calculating LHGR when THERMAL POWER is greater than or equal to 25/ of RATED THERMAL POWER is sufficient, since power distribution shifts are very slow when there have not been significant power or control rod changes.
The requirement to calculate LHGR within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the completion of a THERMAL POWER increase of at least 15% of RATED THERMAL POWER ensures thermal limits are met after power distribution shifts while still allotting time for the power distribution to stabilize.
The requirement for calculating LHGR, after initially determining a LIMITING CONTROL ROD PATTERN exists, ensures that LHGR will be known following a change in THERMAL POWER or power shape and therefore, operation while exceeding a thermal limitwill be avoided.
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- 1. General Electric Company Analytical Model for Loss-of-Coolant Analysis in Accordance with 10 CFR 50, Appendix K, NEDE-20566, latest approved revision.
- 2. General Electric Standard Application for Reactor Fuel, NEDE-24011-P-A, latest approved revision.
- 3. The GESTR-LOCA and SAFER Models of the Evaluation at the Loss-of-Coolant Accident - SAFER/GESTR Application Methodology, NEDE 23785-1-PA, latest approved revision.
NINE MILE POINT - UNIT 2 B3/4 2-4 Amendment No.~~
52