ML20098D922
| ML20098D922 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 05/18/1992 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20098D923 | List: |
| References | |
| NUDOCS 9206010105 | |
| Download: ML20098D922 (5) | |
Text
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UNITED STATES
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<E NUCLEAR REGULATORY COMMISSION 4
WAbHINoTON, D.C. 20666 O,
CONS)LMERS POWER COMPANY QQCKET__NO. 50-lM PALISADES PLANT AMENDMENT TO FAClllTY OEBAT!$ CENSE Amendment No.145 License No. DPR-20 1.
The Nuclear Regulatory Commission (the Commission) has fuend that:
A.
The application for amendment by Consumers Power L npany (the licensee) dated May 30, 1991, 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 prov% ions of the Act, and the rules and regulations of the Comm-
- ion; 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 am;ndment will not be inimical to the common defense and security or to the health and safety of the public; 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 iicense is amended by chat,ges to the Technical Spncifications as indicated in the attachment to the license amendment and Paragraph 2.C,2 of Facility Operating License No. DPR-20 is hereby amended to read as follows:
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9206010105 920518 PDR ADOCK 05000255 P
2 Jfchnini Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.145
, 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 its date of issuance.
FOR THE NUCLEAR REGULA10RY COMMISSION i
l gJA^
Ac L. B. Marsh rector Project Directerate !!!-1 Division of Reactor Projects Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Speci ficat t ori Date of issuance:
Ny 18,1992 l
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- TTACHMENT T0 tlCENSE AMENDMENT NO.145 FACILITY OPERATING LICENSE NO. DPR-20 DDCKET NO. 50-255 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages, The revised pages are identified by the amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 2-5 2-5 2-6 2-6 s
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I$LE2.3.1 Reactor Protective System Tric Settina Limits Four Primary Coolant ihreePrimaryCp4olant Egmos Operatina Pumps Operatina 1.
VariableHigh 515% above core power, s15% above core power l
3 Power with a minimum setpoint with a minimum setpoint of $30% of rated power of $15% rated power and a maximum of $106.5%
and a maximum of ::49%
of rated power of rated power 2.
Primary 295% of Primary Coolant 260% of Primary Cool-c2 Coolant flow )
Flow With Four Pumps ant Flow With Four Operating Pumps Operating 3.
High Pressure 52255 Psia s2255 Psia Pressurizer 4.
Thermal Margip*f)
LNts High Power Trip and P
2 Applicable Replaced by Variable Low Pressure 1750 Psia Minimum Low-Pressure Setting 5.
Steam Generator Not Lower Than the Not Lower Than the Center Low Water Level Center Line of Line of Feed Water Ring feed Water Ring 6.
SteamGeneragor 2500 Psia 1500 Psia low Pressure )
7.
Containment High
$3.70 Psig
$3.70 Psig Pressure (1)
The VHPT can be 30% of rated power for power levels s 20% of rated power.
(2)
May be bypassed below 10% of rated power provided auto bypass removal circuitry is operable.
For low power physics tests, thermal margin / low
>ressure, primary coolant flow and low steam generator pressure trips may be
)ypassed until their react-points are reached (approximately-1750 psia and 500 psia, respectively), provided automatic bypass renoval circuitry at 10"%
rated power is operable.
(3)
Minimum trip setting shall be 1750 psia.
(4)
Operation with three pumps for a maximum of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is permitted to provide a limited time for repair / pump restart, to provide for an orderly shutdown or to provide for the conduct of reactor internals noise monitoring test measurements.
2-5 l
l Amendment No. }], pp, 115,115
- 145, i
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2.3 LIMITING SAFETY SYSTEM SETTINGS - REACTOR PROTECTIVE SYST G (Contd)
Basis
,1 i
The reactor protective t/ stem consists of four instrument channels to monitor selected plant conditions which will cause a reactor i
trip if any of these conditions deviate from a preselected l
operating range to the degree that a safety limit may be reached.
1.
Yariable Hiah Power - The variable high power trip (VHPT) is incorporated in the reactor protection system to provide a reactor trip for transients exhibiting a core power increase starting from any initial power level (such as the boron dilution i
The VHPT system provides a trip setpoint no more than a p)r ttermined amount asove the indicated core power (515%)'
ins also sets a maximum value. Operator action is requiredtoincreasethesetpointascorepowerisincreased;thel setpoint is automaticallr decreased as core power decreases.
Provisions have been made to select different set points for three pump and four pump operations.
Ouring normal plant operation with all primary coolant pumps operating, reactor trip is initiated when the reactor power level reaches 106.5% of indicated rated power. Adding to this the i
possible variation in trip point due to calibration and instrument errors, the maximum actual steady state power at which a trip would be actuated is 115%, which was used for the purpose of safety analysis.
- l 2.
Primary Coolant System low Flow - A reactor trip is provided to protect the core agains decrease significantly."t JNB should the coolant flow suddenly
) Flow in each of the four coolant loops is determined from a measurement of pressure drop from inlet to outlet of the steam generators.
The total flow through the reactor core is measured by summing the loop pressure drops across the steam generators and correlating this pressure sum with the pump calibration flow curves.
The percent of normal core flow is shown in the following table:
4 Pumps 100.0%
3 Pumps 74.7%
During four pump operation, the low flow trip setting of 95%
insures that the reactor cannot operate when the flow rate is Less than 93% of the nominal value considering instrument errors.N 2-6 Amendment No. JJ, JJE, JJ/
145
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