ML20094M305
| ML20094M305 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/17/1995 |
| From: | Hansen A NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20094M308 | List: |
| References | |
| NUDOCS 9511210392 | |
| Download: ML20094M305 (8) | |
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION E'
WASHINGTON, o.C. 30086 4 001 WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 165' License No. DPR-24 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) submitted by letters dated September 13, 1995, and October 19, 1995, and supplemented by letter dated October 25, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the 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 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 Comission'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 Comission's regulations and all applicable requirements have been satisfied.
9511210392 951117 PDR ADOCK 05000266 P
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license j
amendment, and paragraph 3.B of Facility Operating License No.
DPR-24 is hereby amended to read as follows:
i B.
Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.165, are hereby incorporated i
in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
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3.
This license amendment is effective immediately.
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l FOR THE NUCLEAR REGULATORY COMMISSION t
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p Allen G. Hansen, Project Manager i
4 Project Directorate III-3 Division of Reactor Projects III/IV 4
Office of Nuclear Reactor Regulation
Attachment:
l Changes.to the Technical Specifications 4
j Date of issuance:
November 17, 1995 i
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AR RE UNITED STATES g
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NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20eeH001
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WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 l
l POINT BEACH NUCLEAR PLANT. UNIT NO. 2 i
AMENDMENT TO FACILITY OPEk: ING LICENSE Amendment No. 169 License No. DPR-27 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) submitted by letters dated September 13, 1995, and October 19, 1995, and supplemented by letter dated October 25, 1995, i
complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; j
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the i
Comission; j
C.
There is reasonable assurance (1) 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordTnce with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
)
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2.
Accordingly, the license is amended 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-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.169, 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.
FOR THE NUCLEAR REGULATORY COM ISSION t
Allen G. Hansen, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation J
Attachment:
j Changes to the Technical i
Specifications
.I Date of issuance:
November 17, 1995 i
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ATTACMENT TO LICENSE AMENDMENT NOS.165 AND 169 j
TO FACILITY OPERATING LICENSE NOS. DPR-24 AND DPR-27 1
DOCKET N05. 50-266 AND 50-301 I
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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.
4 REMOVE INSERT TS 15.1-4 TS 15.1-4 TS Figure 15.2.1-2 TS Figure 15.2.1-2 j
TS 15.3.1-19 TS 15.3.1-19 f
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2)
Cold shutdown The reactor is in the cold shutdown condition when the reactor has a shutdeun margin of at least 15 &/k and reactor coolant temperature is s200*F.
3)
Refueling Shutdown The reactor is in the refueling shutdown condition when the reactor is subcritical by at least 5% & /k and T is $140*F. A refueling shutdown refers to a shutdown to move fuel to and from the reactor core.
4)
Shutdown Ilargin Shutdown margin is the instantaneous amount of reactivity by which the reactor core would be subcritical if all withdrawn control rods were l
tripped 1sto the core but the highest worth withdrawn RCCA remains fully withdrawn.
If the reactor is shut down from a power condition, the hot shutdown temperature should be assumed.
In other cases, no change in temperature should be assumed.
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Power Goeration The reactor is in power operating condition when the reactor is critical and l
the average neutron flux of the power range instrumentation indicates greater than 25, of rated power.
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Refuelina Doeration Refueling operation is any operation involving movement of core components (those that comid affect the reactivity of the core) within the containmant I
when the vessel head is removed.
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Rated Power Rated power is bare defined as a steady state reactor core output of 1518.5 ftfT.*
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Thermal Power Thermal power is defined as the total core heat transferred from the fuel to-the coolant.
For Unit 1:
If the Reactor Coolant System raw measured total flow rate is
<174,000 gpa but 2169,500 gpe, Unit 2 shall be limited to s98% rated power.
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15.1-4 Unit 1 - Amendment No. 2,4^,*S 165 l
Unit 2 - Amendment No. 2,55,"^,169 l
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4 Figure 15.2.1-2 REACTOR CORE SAFETY LIMITS POINT BEACH UNIT 2 670 6@
650 2425 psia 640 t
2250 psia 630 C
5 620 2000 psia a
b610 N
600 m5 pila 590 580 570 560 O
0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1
1.1 1.2 Core Power (fraction of 1518.5 MWt)
Unit 2 - Amendment No. "6,150,169
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OPERATIONAL LIMITATIONS
.The following DNB related parameters shall be maintained within the limits shown during Rated Power operation:
1.
T, shall be maintained below 578*F.
2.
Reactor Coolant System (RCS) pressurizer pressure shall h.' maintained:
a.
Unit 1:
22205 psig during operation at 2250 psia, or 21955 psig during operation at 2000 psia, b.
Unit 2:
21955 psig during operation at 2000 psia.
3.
Reactor Coolant System raw measured Total Flow Rate (See Basis).
a.
Unit 1 2 181,800 gpm Unit 1 b.
Unit 2 2 174,000 gpa Unit 2*
Basis:
The reactor coolant system total flow rate for Unit 1 of 181,800 gpa is based on an assumed measurement uncertainty of 2.1 percent over thermal design flow (178,000 gpm). The reactor coolant system total flow rate for Unit 2 at rated power is 174,000 gps. This is based on an assumed measurement uncertainty of 2.1 percent over a thermal design flow of 170,400 gps. However, Unit 2 is analyzed to support operation with a reactor coolant system total flow rate limit of 169,500 gpe. This is based on an assumed measurement uncertainty of 2.1 percent over a thermal design flow of 166,000 gps.
If the Unit 2 RCS raw measured total flow rate is less than 174,000 gpa but greater than or equal to 169,500 gps, operation is limited to less than or equal to 98% rated power as described in the note to Specification 15.3.1.G.3.b. The raw measured flow is based upon the use of normalized elbow tap differential pressure which is calibrated against a precision flow calorimetric at the beginning of each cycle.
l For Unit 2:
If the Reactor Coolant System raw measured total flow rate is
<174,000 gpm but 2169,500 gps, Unit 2 shall be limited to s 98% rated power.
Unit 1 - Amendment No. ",81,86,120 15.3.1-1g 9 2,155,165 Unit 2 - Amendment No. 49,90,123, 145.150,169 1
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