ML20054C835
| ML20054C835 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 03/05/1982 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20054C836 | List: |
| References | |
| NUDOCS 8204220012 | |
| Download: ML20054C835 (7) | |
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UNITED STATES g
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NORTHERN STATES POWER COMPAN'Y DOCKET NO. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT NO. 1
' AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.5 5 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 February 1,1982, complies with the standards and requirements of the Atomic Energy Act ef 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 confonnity with the application, the provisions of the Act, and the rules and regulations of the Commission;
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C.
There is reasonable assurance (i) that the activit'ies 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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PDR 1
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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 2.C.(2) of Facility Operating License No. OPR-42 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 5 5, 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 w
Robert A. Clark, Chief
ss Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: MAR 5 1982 D
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UNITED STATES
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7 NORTHERN STATES POWER COMPANY DOCKET NO. 50-306 PRAIRIEISLANDNUCLEARGENERATINGPLANTUNITNO.2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 4 9 License No. DPR-60 t
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northern _ States Power Company (the licensee) dai d February 1,1982, complies with the standards and requirements of the Atomic Energy Act..o,f 1154, 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.
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2.
Accordingly, the license.is amended by changei to.the Technical
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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 Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 4 9, 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 D
&f b Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: MAR 5 1992 l'
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a ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT-N0.5 5 TO FACILITY OPERATING LICENSE NO. DPR-42
" AMENDMENT NO. 4 9 TO FACILITY OPERATING LIC5NS$ NO. DPR-60 DOCKET NOS. 50-282 AND 50-306 Revi,se Appendix A as follows:
i Recove Pages Insert Pages f
Table TS.4.1-1 (4 of 5)
Table TS.4.1-1 (4 of 5)
TS.4.4-3 TS.4.4-3 S
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TABLE TS.4.1-1 (Page 4 of 5)
Functional Response Channel ee D
Description Check Calibrate Test Test Remarks N M
- 19. Radiation Monitoring
- D R
M NA Includes all channels used for leak
' 8 detection per Spec. 3.1.D. and g$
effluent release monitoring per Spec. 3.9 and 5.5.
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- 20. Boric Acid Make-up Flow NA R
NA NA yy Channel
- 21. Containment Sump Level.
NA R
R NA Includes Sumps A, B, and C O O
- 22. Accumulator Level and gg Pressure S
R R
NA k
- 23. Steam Generator Pressure S
.R M
NA
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- 24. Turbine First Stage S
R H
NA Pressure
- 25. Emergency Plan Radiation
- M R
H NA Includes those. named in the, emergency Instruments procedure (referenced in' Spec. 6.5 A.6) i i
Includesautofoadsequencers
- 26. Protection Systems Logic NA NA M
NA Channel Testing
- 27. Turbine Overspeed Protec-NA R
M NA I
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tion Trip Channel l
- 28. Deleted j.
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- 29. Deleted
.I Includes.thosel.
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,used.per" Spec. 4.10
- 30. Environmental Monitors M
NA NA NA Includes those! reported in Item 4 of
- 31. Seismic Monitors R
R NA NA Table TS.6.7-1
- 32. Coolant Flow-RTD Bypass S
R H
NA l-l Flowmeter s
- 33. CRDM Cooling Shroud Exhaust-S NA R
NA FSAR page 3.2-56 Air Temperature
- 34. Reactor Gap Exhaust Air S
NA R
NA FSAR page 5.4-2 Temperature
TS.4.4-3
~4.
Type. A tests will be considered to be satisfactory if the acceptance criteria delineated in Appendix J,Section III.A are met.
5.
Type B and C tests will be considered to be satisfactory if the combined leakage rate of all components subjected to Type B and C tests does not exceed 60% of the L and if the following conditions are met.
For pipes connected to systems that are in the ABSVZ a.
(Designated ABSVZ in Table TS.4.4-1) the total leakage past isolation valves shall be less than 0.1 weight percent per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at pressure P.
b.
For pipes connected to systems that are exterior to both the shield building and the ABSVZ (designated EXTERIOR in Table TS.4.4-1) the total leakage past isolation valves shall be less than 0.01 weight per-cent per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at pressure P.
For airlocks, the leakage shall be less than 256 sec/m c.
at 10 psig for door intergasket tests and 1500 sec/m' at 46 psig for overall airlock tests.
6.
The retest schedules for Type A, B, and C tests will be in accordance with Section III-D of Appen' dix J.
'Each shield building shall be retested in accordance with the Type A test schedule for its containment.
The auxiliary building special ventilation zone shall be retested in ac.cordance with the Type A test schedule for Unit 1 containment.
7.
Type A, B and C tests will be in accordance with Section V of Appendix J.
Inspection and reporting requirements of each shield-building test shall be the same as for Type A tests.
The auxiliary building special ventilation zone shall have the same inspection and reporting requirements as for the Type A tests of Unit 1.
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l Unit 1 Amendment' No.11, 5 5 Unit 2 Amendment No. 5,4 g I
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