ML20247N873
| ML20247N873 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/31/1989 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247N878 | List: |
| References | |
| NUDOCS 8908030207 | |
| Download: ML20247N873 (7) | |
Text
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UNITED STATES
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l WISCONSIN ELECTRIC. POWER COMPANY l
DOCKET NO. 50-266 1'
POINT BEACH NUCLEAR PLANT, UNIT NO. 1-AMENDMENT TO. FACILITY OPERATING LICENSE Anendment No.
123 l
Licer.se No. DPR-24 1.
The Euclear Regulatory Comission (the Consission) has found that:
l A.
The application for amendment by Wisconsin Electric Power Company (thelicensee)datedMarch 17, 1989 complies with the stardards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 l
CFR Chapter I; 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 conoliance with the Connission'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; l
and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of t.he Commission's regulations and all applicable requirnents have been satisfied.
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l 8908030207 890731 FDR ADOCK 05000266 p
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Accordingly, the license is anended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No.
DPR-24 is.hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.123, are hereby incorporated
.in the license. The licensee shall. operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective immediately upon issuance. The Technical Specifications are to be implemented withir. 20 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l,
John N. Hannon, Director Project Directorate III-3 Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulat1on l
l Attechment:
Changes to tFe Technical Specifications l
Date of Issuance:
July 31, 1989 r-o i
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NUCLEAR REGULATORY COMMISSION ~
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WISCONSIN ELECTRIC POWER CONPANY DOCKET NO.'50-301 POINT.EEACH NUCLEAR PLANT. UNIT.NO. 2 AMENDMENT TO. FACILITY.0PERATING LICENSE Amendment No. 126 License No. DPR-27 1.-
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for anendment by Wisconsin Electric Power Company L(the licensee) dated March 17, 1989 complies with the standards and requirearnts of the Atomic Energy Act of 1954, as arnended (th(
Act), and the Comission'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 Comission; C.
There is reasonable assurance (1) that the activities authorized by this' ainendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be-conducted in compliance with the Comission's regulations; D.
The issuance of this amendnent 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 accordarce with 10 CFR Part 51 of the Comission's regulations and all appitcable requirements have been satisfied.
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachnant to this license 1
amendment, and paragraph 3.B of. Facility Operating License No.
DPF,-27. is hereby amended to read as follows:
B.
Technical. Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 126, are hereby incorporated in'the. license. The licensee shall operate.the facility in accordance with the Technical Specifications.
3.
.This license amendment is effective November 1, 1989.
FOR THE NUCLEAR REGULATORY COMMISSION John N. Hannon, Director Project Directorate III-3 Division of Reactor Projects - III, IV,. Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications l
Date of Issuance: July 31,1989 l
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ATTACHMENT TO LICENSE AMENDMENT NOS. 193 AND 126 TO FACILITY OPERATING LICENSE N05. DPR-24 AND DPR-27 DOCKET NOS. 50-266 AND 50-301 Revise Appendix A Technical Specifications by removing the pages identified below and-inserting the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 15.2.3-3 15.2.3-3 15.2.3-5 15.2.3-5
1,-..
9 Lj;+
c (c). for each percent that the magnitude of qt gb exceeds -17 percent,
-the AT trip setpoint shall be automatically reduced by an equivalent l
of 2.0 percent of rated power.
(5) Overpewer AT (1+f 5) 3 Tb 5
1 1
1AT,[K4 -Kf 5 + 1) % ) T - K Uh~
5 6
T5 1
~
where indicated AT at rated power, *F ATo
=
average temperature, 'F T
=
T' f
573.9 F K
5 1.089 of rated power 4
0.0262 for increasing T K
=
5 0.0 for decreasing T
=
K
=
6 0.00123 for T 1 T' 0.0 for T < T'
=
T
=
10 sec l
5 2 sec for Rosemont or equivalent RTD T
=
3 0 set for Sostman or equivalent RTD 4
2 set for Rosemont or equivalent RTD T-
=
0 sec for Sostman or equivalent RTD (6) Undervoltage - 175 percent of normal voltage (7) Indicated reactor coolant flow per loop -
l 190 percent of normal indicated loop flow (8) Reactor coolant pump motor breaker open (a) Low frequency set point 155.0 HZ
~
(b) tow voltage set point 175 percent of normal voltage.
Unit 1 - Auendment No. 3,28,E6,90, 15.2.3-3 9A,720,123 Unit 2 - Amendment No. 32,90,97, l
95,125,126 j
l t
Basis L
The source range high flux reactor trip prevents a startup accident l-from subcritical conditions from proceeding into the power range. Any set point within its range would prevent an excursion from proceeding to the point at which significant thermal power is generated.II)
. The high flux low power reactor trip provides redundant protection in the power range for a power excursion beginning from low power.
This trip insures that a more restrictive trip point is used for this case than for an excursion beginning from near full power.II)
The overpower nuclear flux reactor trip protects the reactor core against reactivity excursions which are too rapid to be protected by temperature and pressure circuitry. The prescribed set point, with allowance for errors, is consistent with the trip point assumed in the accident analysis.I3)
The overpower AT reactor trip prevents power density anywhere in the core from exceeding 108% of design power density, and includes corrections for change in density and heat capacity of water with j
temperature, and dynamic compensation for piping delays from the core to the loop temperature detectors. The specified set points meet this requirement and include allowance for instrument errors.I2)
The overtemperature AT reactor trip provides core protection against DNB for all combinations of pressure, power, coolant temperature, and axial power distribution, provided only that (1) the transient is slow with respect to piping transit delays from the core to the temperature detectors. (about 4 seconds),(5) and (2) pressure is within the range between the high and low pressure reactor trips. With normal axial Unit 1 - Amendment No.123 15.2.3-5 Unit 2 - Amendment No.126
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