ML20206A495
| ML20206A495 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/23/1999 |
| From: | Dick G NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20206A500 | List: |
| References | |
| NUDOCS 9904280189 | |
| Download: ML20206A495 (8) | |
Text
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t UNITED STATES 3
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 30eeHo01
- %...../
WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.189 License No. DPR-24 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated May 28,1998, as supplemented with additional information in letter dated December 11,1998, 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 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.
9904290189 990423 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 amendment, and paragraph 3.B of Facility Operating License No. DPR-24 is hereby amended to read as follows:
B.
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 189, are hereby incorporated in the license. The licensee shall operate the facility in accordance with Technical Specifications.
3.
This license amendment is effective immediately upon issuance. The Technical Specifications are to be implemented within 45 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Geo Dick, Acting hief, Section 1 Project Directorate til Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: April 23, 1999 1
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UNITED STATES fg y
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 30cm1
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WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.194 License No. DPR-27 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated May 28,1998, as supplemented with additional information in letter dated December 11,1998, 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 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.
e o
e.
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.194, are hereby incorporated in the license. The licensee shall operate the facility in accordance with Technical Specifications.
3.
This licenso amendment is effective immediately upon issuance. The Technical Specifications are to be implemented within 45 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION d)f George F. Dick, Acting hief, Section 1 Project Directorate lll Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: April 23, 1999
t ATTACHMENT TO LICENSE AMENDMENT NO.189 TO FACILITY OPERATING LICENSE NO. DPR-24 6@j.lCENSE AMENDMENT NO.194 TO FACILITY OPERATING LICENSE NO. 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 vertical lines indicating the area of change.
HEMOVE INSERT 15.2.3-3 15.2.3-3 15.2.3-7 15.2.3-7 Tat 4e 15.3.5-1, bage 1 Table 15.3.5-1, Page 1 l
o I
(c) for each percent that the magnitude ofq,- q exceeds -17 percent, the AT trip setpoint shall be automatically reduced by an equivalent of 2.0 percent of rated power.
I (5)
Overpower 3
AT (1 + 53S) 5 S A T.[K. - Ks(
3)(
g)T-K.[T(
)-T'))
g where (values are applicable to operation at both 2000 psia and 2250 psia) q indicated AT at rated power, 'F q
AT,
=
T average temperature, 'F
=
T 5
572.9'F' K
s 1.09 of rated power
- 4 0.0262 for increasing T K
=
3 0.0 for decreasing T
=
0.00123 for T 2 T K
=
6 0.0 for T < T
=
10 see t3
=
2 sec for Rosemont or equivalent RTD t3
=
0 sec for Sostman or equivalent RTD 2 sec for Rosemont or equivalent RTD t.
=
0 sec for Sostman or equivalent RTD (6)
Undeivoltage - 2 3120V l
(7)
Indicated rcactor coolant flow per loop -
290 percent of normal indicated loop flow (8)
Reactor coolant pump motor breaker open (a)
Low frequency set point 255.0 HZ t
(b)
Low voltage set point 2 3120V l
1 These values apply to Unit 2 following U2R22 and to Unit I following UlR24. Prior to j
UIR24, the values for Unit I are: T s 573.9'F and K, s 1.089 of rated power.
1 Unit 1 - Amendment No.189 15.2.3-3 Unit 2 - Amendment No.194
r 4
as actuated by either high current, low supply voltage or low electrical frequency, or by a manual control switch. The significant feature of the breaker trip is the frequency setpoint,55.0 HZ, which assures a trip signal before the pump inertia is reduced to an unacceptable value. The high pressurizer water level reactor trip protects the pressurizer safety valves against water relief. The specified setpoint allows adequate operating instrument erroF and transient overshoot in level before the reactor trips.
The low-low steam generator water level reactor trip protects against loss of feedwater flow accidents. The specified setpoint assures that there will be sufficient water inventory in the steam generators at the time of trip to allow for starting delays for the auxiliary feedwater system.m Numerous reactor trips are blocked at low power where they are not required for protection and would otherwise interfere with normal plant operations. The prescribed setpoint above which these trips are unblocked assures their availability in the power range where needed.
Specifications 15.2.3.2.A(1) and 15.2.3.2.C have *1% tolerance to allow for a 2% deadband of the P10 bistable which is used to set the limit of both items. The difference between the nominal and maximum allowed value (or minimum allowed value) is to account for "as measured" rack drift effects.
Sustained power operation is not permitted with only one reactor coolant pump. If a pump is lost while operating below 50 percent power, an orderly shutdown is allowed. The power-to-flow ratio will be maintained equal to or less than unity, which ensures that the minimum DNB ratio increases at lower flow because the maximum enthalpy rise does not increase above the maximum enthalpy rise which occurs during full power and full flow operation.
References m FSAR 14.1.1 W FSAR 14.3.1 W FSAR 3.2.1 W FSAR, Page 14-5 W FSAR 14.1.2 m FSAR 14.1.9 m FSAR 14.2.6 W FSAR 7.2,7.7 W FSAR 14.1.11 Unit 1 - Amendment No.189 15.2.3-7 Unit 2 - Amendment No.194
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