ML20100E201
| ML20100E201 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 03/07/1985 |
| From: | John Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20100E205 | List: |
| References | |
| TAC-55330, TAC-55331, NUDOCS 8504030313 | |
| Download: ML20100E201 (7) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION h
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- O WISCONSIN ELECTRIC POWER CCMPANY DOCKET N0. 50-266 POINT BEACH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 88 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) dated June 8, 1984 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 comon 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.
8504030313 850307 PDR ADOCK 05000266 P
PDR.
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 Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 88, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective 20 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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1 9y James R. Miller, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 7, 1985
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g NUCLEAR REGULATORY COMMISSION 5
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WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 93 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) dated June 8, 1984 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 (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 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.
2.
Accordingly, the license is amended by changes to the Technical.
Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No.
OPR-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. 93, are hereby incorporated in the license. The lice.nsee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective 20 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION P
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lV ames R. Miller, Chief Mpr Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 7, 1985
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[o, UNITED STATES NUCLEAR REGULATORY COMMISSION n
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WASHINGTON, D. C. 20555
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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 88 TO FACILITY OPERATING LICENSE NO. DPR-24 AMENDMENT NO. 93 TO FACILITY OPERATING LICENSE NO. DPR-27 DOCKET NOS. 50-266 AND 50-301 Revise Appendix A as follows:
Remove Page Insert Page (Units 1and2)15.3.10-1 15.3.10-1 (Unit 1 only) Figure 15.3.10-1 Figure 15.3.10-1
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15.3.10 CONTROL R0D AND POWER DISTRIBUTION LIMITS Applicability Applies to the operation of the control rods and to core power distribution limits.
' Objective To insure (1) core subcriticality after a reactor trip, (2) a limit on potential reactivity insertions from a hypothetical rod cluster control assembly (RCCA) ejection, and (3) an acceptable core power distribution during power operation.
Specification A.
Bank Insertion Limits 1.
Whe1 the reactor is critical, except for physics tests and control rod exercises, the shutdown banks shall be fully withdrawn.II) 2.
When the reactor is critical, the control banks shall be inserted no further than the limits shown by the lines on Figure 15.3.10-1.
Exceptions to the insertion limit are permitted for physics tests and control rod exercises.
3.
The shutdown margin shall exceed the applicable value as shown in Figure 15.3.10-2 under all steady-state operating conditions from 350 F to full power. An exception to the stuck RCCA component of the shutdown margin requirement is permitted for physics tests.
4.
Except for physics tests a shutdown margin of at least 1% ak/k shall be maintained when the reactor coolant temperature is less 0
than 350 F, 5.
When the reactor is in the hot shutdown condition or during any approach to criticality, except for physics tests, the critical rod position shall not be lower than the insertion limit for zero power. That is, if the control rods were withdrawn in normal sequence with no other reactivity change, the reactor would not be critical until the control banks were above the insertion limit.
(1) Fully withdrawn is defined as a bank demand position equal to or greater than 225 steps. This definition is applicable to shutdown and control banks.
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15.3.10-1 Unit 1 - Amendment No. 49, 88 Unit 2 - Amendment No. 55, 93
FIGURE 15.3.10-1 CONTROL BANK INSERTION LIMITS 1
i POINT BEACH UNITS 1 AND 2 (22)
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