ML20064H011
| ML20064H011 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 01/04/1983 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20064H016 | List: |
| References | |
| TAC-53456, TAC-53457, NUDOCS 8301120472 | |
| Download: ML20064H011 (7) | |
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION s
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NORTHERN STATES POWER COMPANY DOCKET NO. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 60 License No. DPR-42 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated October 15, 1976, 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) tha?. 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 rbgulations; 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.
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i 80K)1120472 830104 PTNt ADOCK 05000282 P
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e 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-42 is hereby amended to read as follows:
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(2) Technica1 ' Specifications,
The Technical Specifications contained in Appendix A, as revised through Amendment No. 60, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION a
Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 4, 1983
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UNITED STATES
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DOCKET NO. 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 54 i
License No. DPR-60 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated October 12, 1977, 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; 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.
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' c, 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-60 is hereby amended to read as follows:
(2) Technical $p'ecifications.
The Technical Specifications contained in Appendix A, as revised through Amendment No. 54, are hereby incorporated in the license. The ifcensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendcient is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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A Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: January 4, 1983 r'
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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 60 TO FACILITY OPERATING LICENSE NO. DPR-42 c
AMENDMENT NO. 54 TO FACILITY OPERATING LICENSE NO. DPR-60
- DOCKET NOS. 50-282 AND 50-306 Revise Appendix A as follows:
Remove Pages Insert Pages Table TS.4.1-2A Table TS.4.1-2A TS.4.2-1 TS.4.2-1 A
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4 TS.4.2-1 4.2 INSERVICE INSPECTION'AND TESTING OF PUMPS AND VALVES REQUIREMENTS l
l Applicability
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Applies to in-service structural surveillance of the reactor coolant pressure boundary',~other systems important to safety and testing of l
pumps and valves.
Objective To assure the continued integrity of the reactor coolant pressure boundary and other systems important to safety.
Specification r
A.
Inspection Requirements 1.
Inservice inspection of ASME Code Class 1, Class 2, and Class 3 l
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components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55(g), except where relief has been granted by the Commission pursuant to i
10 CFR 50, Section 50.55(g)(6)(i). The additional inspections l
listed in Table TS.4.2-1 shall also be performed as specified.
2.
In addition to other specified tests, inservice testing of ASME Code Class 1, Class 2 and Class 3 pumps and valves shall be i
performed in accordance with Section XI of the ASME Boiler
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and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55(g), except where specific written l
relief has been granted by the NRC.
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DPR-42 Amendment No. 43, 60 DPR-60 Amendment No. 37, 54 3-7 e
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. TABLE TS.4.1-2A MINIMUM FREQUENC7ES FOR EQUIPMENT TESTS FSAR Section Test Freauency Reference 1.
Control Rod Assemblies Rod drop times All rods during each 7
of full length refueling shutdown rods or following each removal of the reac-tor vessel head; affected rods follow-ing maintenance on or modification to the control rod drive system which could affect performance of those specific rods la. Reactor Trip Breakers Open trip Monthly 2.
Control Rod Assemblies Partial move-Every 2 weeks 7
ment of all rods 3.
Pressurizer Safety Set point Per ASME Code,Section XI Valves Inservice Testing Program 4.
Main Steam Safety Set point Per ASME Code,Section XI Valves Inservice Testing Program 5.
Reactor Cavity Water level Prior to moving fuel assemblies or control rods and at least once every day while the cavity is flooded.
6.
Pressurizer PORV Functional Quarterly Block Valves 7.
Pressurizer PORV's Functional Every 18 months 8.
(Deleted) 9.
Primary System Leakage Evaluate Daily-4 10.
(Deleted) 11.
Turbine stop valves, Functional Monthly 10 governor valves, and intercept valves. (Part of turbine overspeed protection.)
12.
(Deleted)
Prairie Island Unit 1 Amendment No. 26, 47, 49,60 Prairie Island Unit 2 Amendment No. 20, 41, gg,54
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