ML19249B146
| ML19249B146 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 08/02/1979 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19249B149 | List: |
| References | |
| NUDOCS 7909040019 | |
| Download: ML19249B146 (14) | |
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WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 39 License No. DPR-24 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The facility will operate in cor;formity with the application, the provisions of the Act, and the rules and regulations of the Commission; 8.
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; C.
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 D.
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.
2.
Accordingly, the license is amended by adding the following paragraph 3.H.:
H.
The licensee may proceed with and is required to complete the modifications identified in Paragraphs 3.1.1 through 3.1.33 of the NRC's Fire Protection Safety Evaluation Report (SER) for the facility dated August 2,1979 These modifications shall be completed as specified in Table 3.1 of the SER or supplements thereto.
The licensee is required to implement and maintain the administrative controls identified in Section 6 of the NRC's Fire Protection Safety Evaluation Report on the Facility dated August 2,1979and supplements thereto.
7 9 090 400 R i S00141
> 3.
This license amendment becomes effective as of Augus t 2,1979*.
FOR THE NU LEAR REGULATORY COMMISSION lWAYhf A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reacto.'s Date of Issuance: August 2,1979
- Provided no hearing is requested under 10 CFR Part 2 paragraph 2.204.
80<)1.42
Amendment Pages for Operating License No. DPR-24 o % ' fi o
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Wisconsin Electric Power Company This amended license applies to the Point Beach Nuclear Plant Unit 1.
No. 2, a closed cycle, pressurized, light water moderated and cooled reactor, and associated steam generators and electric generating equipment (the facility).
The facility is located on the licensee's Point Beach site, in the Town of lwo Creeks, Manitowoc County, Wisconsin, and is described in the " Final Safety Analysis Report", as supplemented and amended.
Subject to the conditions and requirements incorporated here in the 2.
Commission hereby licenses A.
Pursuant to Section 104b of the Act and 10 CFR Part 50,
" Licensing of Production and Utilization Facilities", co possess, use, and operate the facility at the desigoted location on the Point Beach site in accoMance with the procedures and limitations set forth in this license; B.
Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accoNance with the limitations for storage and amounts required for reactor operation, as described in Final Facility Description and Safety Analysis Report, as supplemented ana amended as of March 17, 1976; C.
Pursuant to the Act and 10 CFR Parts 30, 40 and 70 to receive, possess and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; D.
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source of special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or essociated with radioactive apparatus or components; E.
Pursuant to the Act and 10 CFR Parts 30 and 70, to possess such byproduct and special auclear materials as may be produced by the operation of the facility, but not to separate such materials retained within the fuel cladding.
300.1'i0
Wisconsin Electric Power Company 3.
This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations:
10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Conmission now or hereafter in effect; and is subject to the additional conditions specified below:
A.
Maximum Power Levels The licensee is authorized to operate the facility at reactor core power levels not in excess of 1518 megawatts thermal.
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 39 are hereby incorporated in the license. The licensee shall operate the facility in accordance with Technical Specifications.
C.
Report The licensee shall make certain reports in accordance with the requirements of the Technical Specifications.
D.
Records The licensee shall keep facility operating records in accordance with the requirements of the Technical Specifications.
E.
Spent Fuel Pool Modification The licensee is authorized to modify the spent fuel storage pool to increase its storage capacity from 351 to 1502 assemblies as described in licensee's ap;.ication dated March 21, 1978, as supplemented and amended.
In the event that the on-site verification check for poison material in the poison assemblies discloses any missing boron plates, the NRC shall be notified and an on-site test on every poison assembly shall be performed.
30011'$
Wisconsin Elec.tric Powe-Company F.
The licensee shall maintain in effect and fully implement all provisions of the Commission-approved physical security plan, including amendments and changes made pursuant to the authority of 10 CFR 50.54(p). The approved security plan documents withheld from public disclosure pursuant to 10 CFR 2.790(d), are collective titled " Point Beach Nuclear Plant Modified Amended Security Plan", dated January 4, 1978, as revised September 25, 1978, February 2, and March 29, 1979.
G.
Safety Injection Logic The licensee is authorized to modify the safety injection actuation logic and actuation power supplies and related changes as described in licensee's application for amend-ment dated April 27, 1979, as supplemented May 7,1979.
In the interim period until the power supply modification has been completed, should any DC powered safety injection actuion channel be in a failed condition for greater than one hour, the until shall thereafter be shutdown using nonnal procedures and placed in a block-permissive condition for safety injection actuation.
H.
The licensee may proceed with an is required to complete the modifications identified in Paragraphs 3.1.1 through 3.1.33 of the NRC's Fire Protection Safety Evaluation Report (SER) for the facility dated August 2,1979. These modifications shall be completed as specified in Table 3.1 of the SER or supplements thereto.
The licensee is required to implement and maintain the administrative controls identified in Section 6 of the NRC's Fire Protection Safety Evaluation Report on the Facility dated August 2,1979 and supplements thereto.
4.
The issuance of this amended license is without prejudice to subsequent licensing action which may be taken by the Commission with regard to the on-going rulemaking hearing on the Interim Acceptance Criteria for Emergency Core Cooling Systems (Docket No. RM 50-1).
8091 %
Wisconsin Electric Power Company 5.
This amended license is effective a.s of the date of issuance, and shall expire at midnight on July 25, 2008.
FOR THE ATOMIC ENERGY COMMISSION Original Signed By A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing Attachments:
1.
Appendix A - Technical Specifications 2.
Appendix B - Environmental Technical Specifications Date of Issuance: March 8, 1973 90'11 0
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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.44 License No. DPR-27 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; B.
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 Commission's regulations; C.
The issuance of this amendment will not be inimical to thee common defense and security or to the health and safety of the public; and D.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements i
have been satisfied.
Accordingly, the license is amended by adding the following paragraph 3.H.:
H.
The licensee may proceed with an is required to complete the modifications identified in Paragraphs 3.1.1 through 3.1.33 of the NRC's Fire Protection Safety Evaluation Report (SER) for the facility dated August 2,1979.
These modifications shall be cmleted as specified in Table 3.1 of the SER or supplements thereto.
The licensee is required to implement and maintain the administrative controls identified in Section 6 of the NRC's Fire Protection Safety Evaluation Report on the Facility dated August 2,1979 and supplements thereto.
80n1<'1B e
. 3.
This license amendment becomes effective as of August 2,1979*.
FOR THE N CLEAR REGULATORY COMMISSION hilLdWJs A. Schwencer, Chief Operating Reactors Eranch #1 D. vision of Operatirig Reactors Date of Issuance:
August 2,1979
- Provided no hearing is requested under 10 CFR Part 2 paragraph 2.204.
90 t.I.<l.3
Amendment Pages for Operating License No. DPR-27 30'd 30
Wisconsin Electric Power Company 1.
This amended license applies to the Point Beach Nuclear Plant Unit No. 2, a closed cycle, pressurized, light water moderated and cooled reactor, and associated steam generators and electric generating equipment (the facility).
The facility is located on the licensee's Point Beach site, in the Town of Two Creeks, Vanitowoc County, Wisconsin, and is described in the " Final Safety Analysis Report", as supplemented and amended.
2.
Subject to the conditions and requirements incorporated here in the Commission hereby licenses A.
Pursuant to Section 104b of the Act and 10 CFR Part 50,
" Licensing of Production and Utilization Facilities", to possess, use, and operate the facility at the designated location on the Point Beach site in accordance with the procedures and limitations set forth in this license; B.
Pursuant to the Act and 10 CFR Part 70, to receive, possess and usa at any time special nuclehr material as reactor fuel, in accortiance with the limitations for storage and amounts regi: ired for reactor operation, as described in Final Facility Description and Safety Analysis Report, as supplemented and amend-i as of March 17, 1976; C.
Pursuant to the Act and 10 CFR Farts 30, 40 and 70 to receive, possess and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; D.
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amwnts as required any byproduct, scarce of special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or component s; E.
Pursuant to the Act and 10 CFR Parts 30 and 70, to possess such byproduct and special nuclear materials as may be produced by the operation of the facility, but not to separate ruch materials retained within the fuel cladding.
SOG_?. 31
s Wisconsin Electric Power Company 3.
This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations:
10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional cor:ditio.1s specified below:
A.
Maximum Power Levels The licensee is authorized to operate the facility at reactor core power level s r,ct in excess of 1518 megawatts thermal.
B.
Technical Specifications The Technical Specifications contained in Appendices A ard B, as revised through Amendment No. 44 are hereby incorporated in the license.
The licensee shall operate the facility in accordance with Technical Specifications.
C.
Report The licensee shall make certain. reports in accordar.ce with the requirements of the Technical Specifications.
D.
Records The licensee shall keep facility operating records in accordance with the requirements of the Technical Specifications.
E.
Spent Fuel Pool Modification The licensee is authorized to modify the spent fuel storage pool to increase its storage capacity from 351 to 1502 assemblies as described in licensee's application dated March 21, 1978, as supplemented and amended.
In the event that the on-site verificacion check for poison material in the poison assemblies discloses any missing boron plates, the NRC shall be notified and an on-site test on every poison assembly shall be performed.
909132
Wisconsin Electric Power Company F.
The licensee shall maintain in effect and fully implement alI provisions of the Commission-approved physical security plan, including amendments and changes made pursuant to the authority of 10 CFR 50.54(p). The approved security plan documents withheld from public disclosure pursuant to 10 CFR 2.790(d), are collective titled " Point Beach Nuclear Plant Modified Amended Security Plan", dated January 4, 1978, as revised September 25, 1978, February 2, and March 29, 1979.
G.
Safety Injection Logic.
The licensee is authorized to modify the safety injection actuation logic and actuation power supplies and related changes as described in licensee's application for amend-ment dated April 27, 1979, as supplemented liay 7,1979.
In the interim period until the power supply modification has been completed, should any DC powered safety injection actuion channel be in a failed condition for greater than one hour, the until shall thereafter be shutdown using normal procedures and placed in a block-permissive condition for safety injection actuation.
H.
The licensee may proceed with an is required to complete the modifications identified in Paragraphs 3.1.1 through 3.1.33 of the NRC's Fire Protection Safety Evaluation Report (SER) for the facility dated August 2,1979. These modifications shall be completed as specified in Table 3.1 of the SER or supplements thereto.
The licensee is required to implement and maintain the administrative controls identified in Section 6 of the NRC's Fire Protection Safety Evaluation Report on the Facility dated August 2,1979 and supplements thereto.
4.
The issuance of this amended license is without prejudice to subsequent licensing action which may be taken by the Commission with regard to the on-going rulemaking hearing on the Interim Acceptance Criteria for Emergency Core Cocling Systems (Docket No. RM 50-1).
SO'd 33
Wisconsin Electric Power Company 5.
This amended license is effective as of the date of issuance, and shall expire at midnight on July 25, 2008.
FOR THE ATOMIC ENERGY COMMISSION Original Signed By A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing Attachments:
1.
Appendix A - Technical Specifications 2.
Appendix B - Environmental Technical Specificatior.3 Date of Issuance: March 8, 1973
.i