ML20069A113
| ML20069A113 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/17/1994 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20069A116 | List: |
| References | |
| NUDOCS 9405240263 | |
| Download: ML20069A113 (10) | |
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UNITED STATES j.kn(( t}
NUCLEAR REGULATORY COMMISSION
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WASHINGTON. D.C. 20555-0001
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NORTHERN STATES POWER COMPANY DOCKET N0. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.110 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 14, 1994, 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
-i 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.
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:
9405240263 940517 PDR ADOCK 05000282 i
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Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amt dment No.110, are hereby incorporated in the license.
The licer*
- hall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance.
FOR TH NUCLEAR REGULATORY COMMISSION
/
Ik l.W L. B. Marsh, Director Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 17. - 1994
ATTACHMENT TO LICENSE AMENDMENT NO.110 FACILITY OPERATING LICENSE N0. DPR-42 DOCKET NO. 50-282 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT Ts.3.7-1 Ts.3.7-1 TS.3.7-3 TS.3.7-3 4
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l TS.3.7-1 3.7 AUXILIARY ELECTRICAL SYSTEMS Apolicability Applies to the availability of electrical power for the operation of plant auxiliaries.
Obiectives To define those conditions of electrical power availability necessary to assure safe reactor operation and continuing availability of engineered safeguards.
Specification A. A reactor shall not be made or maintained critical nor shall reactor coolant system average temperature exceed 200*F unless all of the following requirements are satisfied for the applicable unit (except as specified in 3.7.B below):
- 1. At least two separate paths from the transmission grid to the unit 4 kV safeguards distribution system each capable of providing adequate power to minimum safety related equipment, shall be OPERABLE.
- 2. The 4 kV safeguards buses 15 and 16 (Unit 2 buses: 25 and 26) shall be energized.
- 3. The 480 V safeguards buses 111, 112, 121, and 122 (Unit 2 buses: 211, l
212, 221 and 222), and their safeguards motor control centers shall be energized.
- 4. Reactor protection instrument AC buses shall be energized:
111, 112, 113 and 114 (Unit 2 buses: 211, 212, 213 and 214).
- 5. The following unit specific conditions apply:
(a)
Unit 1:
D1 and D2 diesel generators are OPERABLE, and a fuel supply of 51,000 gallons is available for the D1 and D2 diesel generators in the Unit 1 interconnected diesel fuel oil storage tanks.
A total fuel supply of 70,000 gallons is available for the D1 and D2 diesel generators and the diesel-driven cooling water pumps in the Unit 1 interconnected diesel fuel oil storage tanks.
(b)
Unit 2: D5 and D6 diesel generators are OPERABLE and a fuel supply of 75,000 gallons is available for DS and D6 diesel generators in the Unit 2 interconnected diesel fuel oil storage tanks.
- 6. Both batteries with their associated chargers and both d-c safeguard systems shall be OPERABLE.
- 7. No more than one of the Instrument'AC Panels 11.1, 112; 113 and 114 (Unit 2 panels: 211, 212, 213 and 214) shall be powered from Panel 117 (Unit 2 panel: 217) or its associated instrument inverter bypass source.
Prairie Island Unit No. 1 Amendment No. //, 193,110 Prairie Island Unit No. 2 Amendment No. $A, 96,103
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TS.3.7~3 I
3.7.B.5. D1 and D2 (Unit 2: D5 and D6) diesel generators may be inoperable for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> provided the two required paths from the grid to the unit 4 kV safeguards distribution system are OPERABLE and the OPERABILITY of the two required paths from the grid are verified OPERABLE within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
- 6. One 4 kV safeguards bus (and/or its associated 480 V buses including associated safeguards motor control centers) may be inoperable or not fully energized for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided the redundant 4 kV safeguards bus and its associated 480 V safeguards buses are verified OPERABLE l
and the diesel generator and safeguards equipment associated with the redundant train are OPERABLE.
- 7. One battery charger may be inoperable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided, (a) its associated battery is OPERABLE, (b) its redundant counterpart is verified OPERABLE, and (c) the diesel generator and safeguards equipment associated with its counterpart are OPERABLE.
B. One battery may be inoperable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided that the other battery and both battery chargers remain OPERABLE.
- 9. In addition to the requirements of Specification TS.3.7. A.7 a second inverter supplying Instrument AC Panels 111, 112, 113, and 114 may (Unit 2 panels 211, 212, 213 and 214) be powered from an inverter bypass source for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
Prairie Island Unit No. 1 Amendment No. 9I. I 3 110 Prairie Island Unit No. 2 Amendment No. $4, $$,103
pp Pic j.kA[k 7
UNITED STATES j
NUCLEAR REGULATORY COMMISSION 6
ff WASHINGTON, D.C. 20555-0001 gs NORTHERN STATES POWER COMPANY DOCKET N0. 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT NO. 2 AMENDMENT TO FAClllTY OPERATING LICENSE Amendment No. 103 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 February 14, 1994, 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 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.
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:
O
_2-Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.103, 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 issuance.
FOR T NUCLEAR REGULATORY COMMISSION
{k[, My for L. B. Marsh, Director Project Directorate III-l Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 17,1994 I
. m-
ATTACHMENT TO LICENSE. AMENDMENT NO.103 FACILITY OPERATING LICENSE NO. DPR-60 DOCKET N0. 50-306 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT TS.3.7-1 T3.3.7-1 TS.3.7-3 TS.3.7-3 P
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e TS.3.7-3 3.7.B.S. D1 and D2 (Gnit 2:
D5 and D6) diesel generators may be inoperable f or 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> provided the two required paths from the grid to the unit 4 kV safeguards distribution system are OPERABLE and the.
OPERABILITY of the two required paths from the grid are verified OPERABLE within I hour.
- 6. One 4 EV safeguards bus (and/or its associated 480 V buses including associated safeguards motor control centers) may be inoperable or not fully energized for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided the redundant 4 kV safeguards bus and its associated 480 V safeguarde buses are verified OPERABLE l
and the diesel generator and safeguartis equipment associated with the redundant train are OPERABLE.
- 7. One battery charger may be inoperable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided, (a) its associated battery is OPERABLE, (b) its redundant counterpart is verified OPERABLE, and (c) the diesel generator and safeguards equipment associated with its counterpart are OPERABLE.
- 8. One battery may be inoperable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided that the other battery and both battery chargers remain OPERABLE.
- 9. In addition to the requirements of Specification TS.3.7.A.7 a second inverter supplying Instrument AC Panels lil, 112, 113, and 114 may (Unit 2 panels 211, 212, 213 and 214) be powered from an inverter bypass source for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
i l
Prairie Island Unit No. 1 Amendment No. 91,103,110 Prairie Island Unit No. 2 Amendment No. $4, 96,103
6 a:
I TS.3.7-l' 3.7 AUXILIARY ELECTRICAL SYSTEMS Aeolicability Applies to the availability of electrical power for the opera 3 on of plant i
auxiliaries.
Obiectives To define those conditions of electrical power availability necessary to assure safe reactor operation and continuing availability of engineered safeguards.
Specification A reactor shall not be made or maintained critical nor shall reactor A.
system average temperature exceed 200'F unless all of the following coolant requirements are satisfied for the applicable unit (except as specified in 3.7.B below):
I least two separate paths from the transmission grid to the unit 4 kV
- 1. Atsaf eguards distribution system each capable of providing adequate power to minimum safety related equipment, shall be OPERABLE.
i 1
- 2. The 4 kV safeguards buses 15 and 16 (Unit 2 buses: 25 and 26) shall be 1
energized.
- 3. The 480 V safeguards buses 111, 112, 121, and 122 (Unit 2 buses: 211, l
212, 221 and 222), and their safeguards motor control centers shall be energized.
- 4. Reactor protection instrument AC buses shall be energized:
.111, 112,-
113 and 114 (Unit 2 buses: 211, 212, 213 and 214).
- 5. The f ollowing unit specific conditions apply (a)
Unit 1: D1 and D2 diesel generators are OPERABLE, and a fuel supply of 51,000 gallons is available'for the D1 and D2 diesel generators in.the Unit 1 interconnected diesel fuel oil stwiege A total fuel supply of 70,000 gallons is.available for the tanks.
D1 and D2 diesel generators and the diesel-driven cooling water pumps in the Unit 1 interconnected diesel fuel oil storage tanks.
(b)
Unit 2: DS and D6 diesel generators are OPERABLE and a fuel supply of 75,000 gallons-is available for D5 and D6 diesel generators in the Unit 2 interconnected diesel fuel oil storage-tanks.
- 6. Both batteries with their associated chargers and both d-c safeguard systems shall be. OPERABLE.
- 7. No more than one of the Instrument AC Panels.lli, 112, 113 and'114 (Unit 2 panels: 211, 212, 213 and 214) shall be powered from Panel 117 (Unit 2'
. panel: 217) or its associated instrument inverter bypass source.
i Prairie Island Unit No.~1 Amendment No. 71, 103, 110 i
Prairie' Island Unit No. 2
' Amendment No. $4, 96,103.
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