ML20097A691
| ML20097A691 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 05/26/1992 |
| From: | Samworth R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20097A693 | List: |
| References | |
| NUDOCS 9206030104 | |
| Download: ML20097A691 (7) | |
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- " Y. I UNITED STATES n
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.E IJUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20556 o
WISCONSIN ELECTRIC POWER COMPANY DOCKET N0. 50-266 POINT BEACH NUCLEAR PLANT. UNIT NO. 1 AMENDMENT TO FACillTY OPERATING LICENSE Amendment No. 131 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 licensce) dated September 13, 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 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
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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 #FR Part 51 of the Commission's regulations and all applicable requiren.cnts have been satisfied.
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:
9206030104 920526 PDR ADOCK 05000266 p
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B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment flo.131, 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 Technicr.1 Specifications are to be implemented within 20 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
Robert B. Samworth, Sr. Project lianager Project Directorate 111-3 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: May 26, 1992 l
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UNITED STATES S
E NUCLEAR REGULATORY COMMISSION z
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WASHINoToN, D.C. 20565 o
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WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 E0lNT BEACH NUCLEAR PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERUING LICENSE Amendment No.135 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 September 13, 1991, complies with the standards and requirements of the Atomic Energy Ac of 1954, as amended (the Act), and the Commission's rules and regalations 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 car be conducted without endangeiing 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 ell applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as inificated in the cttachment to this lianse amendment, and paragraph 3.B of Facility Operating License No.
DPR-27 is hereby amended to read as follows:
2 B.
lechnical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.135, 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 within 20 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION kk
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Robert B. Samworth, Sr. Project Manager Project Directorate III-3 Division of Reactor Projects III/JV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Techrical
. Specifications Date of issuance:
May 26, 1992
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ATTACHMENT TO LICENSE AMEN 0 MENT NOS.131 AND 135 TO FACILITY OPERATING LICENSE N05. DPR-24 AND DPR-27 DOCKET NOS. 50-266 AND 50-301 Revise Appendix A Technical Specifications by remcVing the pages identified below and inserting the enclot2d pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 15.3.1-4 15.3.1-4 15.3.1-8 15.3.1-8 Table 15.3.1-1 (Unit 1)
Table 15.3.1-2 (Unit 2) t L
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t B.
Pressure / Temperature Limits Specification:
1.
The Reactor Coolant System temperature and pressure shall be limited in accordance with the limit lines shown in Figure 15.3.1-1 and 15.3.1-2 during heatup, cooldown, criticality, and inservice leak and hydrostatic testing with:
a.
A maximum heatup of 100 F in any one hour, b.
A maximum cooldown of 100 F in any one hour, and c.
An average temperature change of $10 F per hour during inservice leak and hydrostatic testing operations.
2.
The secondary side of the steam generator will not be pressurized above 200 psig if the temperature of the steam generator vessel shell is below 70 F.
3.
The pressurizer temperature shall be limited to:
a.
A maximum heatup of 100 F in any one hour and a maximum cooldown of 200 F in any one hour, and b.
A maximum spray water temperature differential between the pres-surizer and spray fluid of not greater than 320 F.
4.
The reactor vessel irradiation surveillance specimens are removed and examined, according to NRC approved schedules, to determine changes in material properties.
The results of these examinations snall be
' considered in the evaluation of the prediction method to be used to update Figures 15.3.1-1 and 15.3.1-2.
Revised figures shall be provided to the Commission at least sixty (60) days before the calculated exposure of the applicable reector vessel exceeds the exposure for which the figures apply.
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Unit 1 Amendment No. 24,3J, #16,131 Unit 2 Amendment No. 23,33, 128,135 15.3.1-4
M The actual temperature shift of the vessel material will be established periodi-cally during operation by remcving and evaluating reactor vessel material irradia-tion surveillance specimens installed near the inside wall of the reactor vessel in the core area.
Since the neutron spectra at the irradiation samples and vessel inside radius are identified by a specified lead factor, the measured tenperature shift for a sample is an excellent indicator of the effects of power operation on the adjacent section of the reactor vessel.
If the experimental temperature shif t (at the 30 ft-lb level) does not substantiate the predicted shift new prediction curves and heatup and cooldown curves must be developed.
The pressure-temperature limit lines shown on Figure 15.3.1-1 for reactor critical-ity and for inservice leak and hydrostatic testing have been provided to assure compliance with the minimum temperature requirements of Appendix G to 10 CFR 50 for reactor criticality and for inservice leak and hydrostatic testing.
The spray should not be used if the temoeratere difference between the pressurizer and spray fluid is greater than 320 F.
This limit is imposed to maintain the thermal stresses at the pressurizer spray line nozzle below the design limit.
The temperature requirements for the steam generator correspond with the measured NDT for the shell.
The reactor vessel materials surveillance capsule removal schedules have been developed based upnn the requirements of the Code of Federal Regulations, Title 10, Part 50, Appendix H, and with consideration of ASTM Standard E-185-82.
When the capsule lead factors are considered, the scheduled removal dates accommodate the weld data needs of all the participants in the dabcock and Wilcox Master Integraded Reactor Vessel Surveillance Program. Additionally, the schedule will provide plate / forging material data as well as fluence data corresponding to: the expiration of the current licenses and of any future license extensions.
References (1)
FSAR, Section 4.1.5 (2) Westinghouse Electric Corporation, WCAP-10638 (3) Westinghouse Electric Corporation, WCAP-8747 (4) Westinghouse Electric Corporation, WCAP-8738 (5) Babcock & Wilcox, BAW 1803 (6)
Regulatory Guide 1.99, Revision 2
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Unit Amendment No. 2/,9S,125,131 15.3.1-8 Unit 2 - Amendment No. E/,102,J2E,129,135
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