ML20206B419
| ML20206B419 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 04/08/1999 |
| From: | Clifford J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20206B423 | List: |
| References | |
| NUDOCS 9904290240 | |
| Download: ML20206B419 (6) | |
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UNITED STATES l
,j NUCLEAR REGULATORY COMMISSION
't WASHINGTON. D.C. 205SHm01
,o N_ORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 wilLLSTONE NUCLEAR POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPEMTING LICENSE Amendment No.232 License No. DPR-65
- 1..,1e Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee) dated December 28,1998, as supplemented March 1 and 29,1999, 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; 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 regulathns; 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.
9904290240 990400 PDR ADOCK 05000336 p
. 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-65 is hereby amended to read as follows:
(2) Igchnical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 232, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of issuance, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION iM/d P
Ja es W. Clifford, hief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: April 8,1999
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f ATTACHMENT TO LICE'ME AMENDMENT NO. 232 FACILITY OPERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 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 areas of change.
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1 LIMITING SAFETY SYSTEM SETTINGS
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Steam Generator Water Level - Low The Steam Generator Water Level-Low Trip provides core protection by preventing operation with the steam generator water level below the minimum volume required for adequate heat remeval capacity and assures that the design pressure of the reactor coolant system will not be exceeded.
i local Power Densitv-Hiah The Local Power Density-High trip, functioning from AXIAL SHAPE INDEX monitoring, is provided to ensure that the peak local power density in the fuel which corresponds to fuel centerline melting will not occur as a conse-quence of axial power ma1 distributions.
A reactor trip is initiated whenever the AXIAL SHAPE INDEX exceeds the allowable limits of Figure 2.2-2.
The AXIAL SHAPE INDEX is calculated from the upper and lower ex-core neutron detector channels.
The calculated setpoints are generated as a function of THERMAL POWER level.
The trip is automatically bypassed below 15 percent power.
The maximum AZIMUTHAL POWER TILT and maximum CEA misalignment permitted for continuous operation are assumed in generation of the setpoints. In addition, CEA group sequencing in accordance with the Specifications 3.I.3.5 and 3.1.3.6 is assumed.
Finally, the maximum insertion of CEA banks which can occur during any anticipated operational occurrence prior to a Power Level-High trip is assumed.
Thermal Marain/ Low Pressure The Thermal Margin / Low Pressure trip is provided to prevent operation when the DNBR is less than 1.17.
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MIgLSTONE-UNIT 2 8 2-6 AmendmentNo.77,ff.77.71.177.232 l
I 4
LIMITING SAFETY SYSTEM SETTINGS BASES Thermal Marcin/ Low Pressure (Continued)
The trip is initiated whenever the reactor coolant system pressure signal drops below either 1865 psia or a computed value as described below, whichever I
is higher. The computed value is a function of the higher of AT power or neutron power, reactor inlet temperature, the number of reactor coolant pumps operating and the AXIAL SHAPE INDEX. The minimum value of reactor coolant flow rate, the maximum AZIMUTHAL POWER TILT and the maximum CEA deviation permitted for continuous operation are assumed in the generation of this trip function.
In addition, CEA group sequencing in accordance with Specifications 3.1.3.5 and 3.1.3.6 is assumed.
Finally, the maximum insertion of CEA banks which can occur during any anticipated operational occurrence prior to a Power Level-High trip'is assumed.
Thermal Margin / Low Pressure trip setpoints are derived from the core safety limits through application of appropriate allowances for equipmant response time measurement uncertainties and processing error. A safety margin is provided which includes:
an allowance of 5% of RATED THERMAL POWER to compensate for potential power measurement error; an allowance of 2.25'F to compensate for potential temperature measurement uncertainty; and a further allowance of 74 psi to compensate for pressure.neasurement error, trip system processing error, and time delay associated with providing effective termina-tion of the occurrence that exhibits the most rapid decrease in margin to the safety limit.
The 74 psi allowance is made up of a 5 psi bias, a 19 psi pressure measurement allowance and a 50 psi time delay allowance.
Loss of Turbine A Loss of Turbine trip causes a direct reactor trip when operating above 15% of RATED THERMAL POWER. This trip provides turbine protection, reduces the severity of the ensuring transient and helps avoid the lifting of the main steam line safety valves during the ensuing transient, thus extending the service life of these valves.
No credit was taken in the accident analyses for operation of this trip.
Its functional capability at the specified trip setting is required to enhance the overall reliability of the Reactor Protec-tion System.
MILLSTONE - UNIT 2 B 2-7 Amendment No. 77, pg,177 Jp7,239 om lip,