ML062420136: Difference between revisions

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{{#Wiki_filter:-3-(5) Pursuant to the Act and 10 CFR Parts 30 and 70, NMC to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility;(6) Pursuant to the Act and 10 CFR Parts 30 and 70, NMC to transfer byproduct materials from other job sites owned by Northern States Power Company for the purposes of volume reduction and decontamination.
{{#Wiki_filter:     (5)   Pursuant to the Act and 10 CFR Parts 30 and 70, NMC to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility; (6)   Pursuant to the Act and 10 CFR Parts 30 and 70, NMC to transfer byproduct materials from other job sites owned by Northern States Power Company for the purposes of volume reduction and decontamination.
C. This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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 conditions specified or incorporated below: (1) Maximum Power Level NMC is authorized to operate the facility at steady state reactor core power levels not in excess of 1650 megawatts thermal.(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 163, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
C. This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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 conditions specified or incorporated below:
(3) Physical Protection NMC shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
(1)     Maximum Power Level NMC is authorized to operate the facility at steady state reactor core power levels not in excess of 1650 megawatts thermal.
The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled"Prairie Island Nuclear Generating Plant Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program," Revision 0, submitted by letter dated October 18, 2004.Unit 2 Amendment No. 163 I Revised by letter dated August 29 2006. (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, NMC to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70, NMC to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility;(6) Pursuant to the Act and 10 CFR Parts 30 and 70, NMC to transfer byproduct materials from other job sites owned by Northern States Power Company for the purpose of volume reduction and decontamination.
(2)   Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 163, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
C. This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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 conditions specified or incorporated below: (1) Maximum Power Level NMC is authorized to operate the facility at steady state reactor core power levels not in excess of 1650 megawatts thermal.(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 173, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3)   Physical Protection NMC shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled "Prairie Island Nuclear Generating Plant Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program," Revision 0, submitted by letter dated October 18, 2004.
(3) Physical Protection NMC shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
Unit 2 Amendment No. 163     I Revised by letter dated August 29 2006.
The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: "Prairie Island Nuclear Generating Plant Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program," Revision 0, submitted by letter dated October 18, 2004.Unit 1 Amendment No. 173 Revised by letter dated August 29, 2006.
 
(4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, NMC to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70, NMC to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility; (6) Pursuant to the Act and 10 CFR Parts 30 and 70, NMC to transfer byproduct materials from other job sites owned by Northern States Power Company for the purpose of volume reduction and decontamination.
C. This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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 conditions specified or incorporated below:
(1) Maximum Power Level NMC is authorized to operate the facility at steady state reactor core power levels not in excess of 1650 megawatts thermal.
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 173, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Physical Protection NMC shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: "Prairie Island Nuclear Generating Plant Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program," Revision 0, submitted by letter dated October 18, 2004.
Unit 1 Amendment No. 173 Revised by letter dated August 29, 2006.
 
Containment Spray and Cooling Systems 3.6.5 ACTIONS (continued)
Containment Spray and Cooling Systems 3.6.5 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. One or both containment C.1 Restore containment 7 days cooling fan coil unit(s) cooling FCU(s) to (FCU) in one train OPERABLE status. AND inoperable.
CONDITION               REQUIRED ACTION                 COMPLETION TIME C. One or both containment   C.1 Restore containment           7 days cooling fan coil unit(s)     cooling FCU(s) to (FCU) in one train           OPERABLE status.             AND inoperable.
10 days from discovery of failure to meet the LCO D. One containment cooling D.1 Initiate action to isolate Immediately FCU in each train both inoperable FCUs.inoperable.
10 days from discovery of failure to meet the LCO D. One containment cooling   D.1 Initiate action to isolate   Immediately FCU in each train           both inoperable FCUs.
AND D.2 Restore all FCUs to 7 days OPERABLE status.AND 10 days from discovery of failure to meet the LCO E. Required Action and E.1 Be in MODE 3. 6 hours associated Completion Time of Condition C or D AND not met.E.2 Be in MODE 5. 36 hours Prairie Island Units 1 and 2 Unit 1 -Amendment No. 4-59 173 Unit 2 -Amendment No. 449 163 1 3.6.5-2 Revised by letter dated August29, 2006.
inoperable.
Containment Spray and Cooling Systems 3.6.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.5.1 Verify each containment spray manual, power 31 days operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.SR 3.6.5.2 Operate each containment fan coil unit on low motor 31 days speed for > 15 minutes.SR 3.6.5.3 Verify cooling water flow rate to each containment 24 months fan coil unit is > 900 gpm.SR 3.6.5.4 Verify each containment spray pump's developed In accordance head at the flow test point is greater than or equal to with the the required developed head. Inservice Testing Program SR 3.6.5.5 Verify each automatic containment spray valve in the 24 months flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.SR 3.6.5.6 Verify each containment spray pump starts 24 months automatically on an actual or simulated actuation signal.I I Prairie Island Units 1 and 2 Unit 1 -Amendment No. 4 173 Unit 2 -Amendment No. 449 163 3.6.5-3 Revised by letter dated August 29, 2006.}}
AND D.2 Restore all FCUs to           7 days OPERABLE status.
AND 10 days from discovery of failure to meet the LCO E. Required Action and       E.1 Be in MODE 3.                 6 hours associated Completion Time of Condition C or D AND not met.
E.2 Be in MODE 5.                 36 hours Prairie Island                                     Unit 1 - Amendment No. 4-59 173 Units 1 and 2                      3.6.5-2        Unit 2 - Amendment No. 449 163 1 Revised by letter dated August29, 2006.
 
Containment Spray and Cooling Systems 3.6.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE                                   FREQUENCY SR 3.6.5.1   Verify each containment spray manual, power               31 days operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.
SR 3.6.5.2   Operate each containment fan coil unit on low motor       31 days             I speed for > 15 minutes.
I SR 3.6.5.3   Verify cooling water flow rate to each containment       24 months fan coil unit is > 900 gpm.
SR 3.6.5.4   Verify each containment spray pump's developed           In accordance head at the flow test point is greater than or equal to   with the the required developed head.                             Inservice Testing Program SR 3.6.5.5   Verify each automatic containment spray valve in the     24 months flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.
SR 3.6.5.6   Verify each containment spray pump starts                 24 months automatically on an actual or simulated actuation signal.
Prairie Island                                           Unit 1 - Amendment No. 4 173 Units 1 and 2                              3.6.5-3        Unit 2 - Amendment No. 449 163 Revised by letter dated August 29, 2006.}}

Latest revision as of 14:36, 23 November 2019

Technical Specification, Amendment Correction 173 & 163
ML062420136
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 08/29/2006
From:
NRC/NRR/ADRO/DORL/LPLIII-1
To:
M. Chawla LPL3-1
Shared Package
ML062420317 List:
References
TAC MC8942, TAC MC8943
Download: ML062420136 (4)
v • d • e


Text

(5) Pursuant to the Act and 10 CFR Parts 30 and 70, NMC to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility; (6) Pursuant to the Act and 10 CFR Parts 30 and 70, NMC to transfer byproduct materials from other job sites owned by Northern States Power Company for the purposes of volume reduction and decontamination.

C. This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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 conditions specified or incorporated below:

(1) Maximum Power Level NMC is authorized to operate the facility at steady state reactor core power levels not in excess of 1650 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 163, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Physical Protection NMC shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled "Prairie Island Nuclear Generating Plant Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program," Revision 0, submitted by letter dated October 18, 2004.

Unit 2 Amendment No. 163 I Revised by letter dated August 29 2006.

(4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, NMC to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70, NMC to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility; (6) Pursuant to the Act and 10 CFR Parts 30 and 70, NMC to transfer byproduct materials from other job sites owned by Northern States Power Company for the purpose of volume reduction and decontamination.

C. This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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 conditions specified or incorporated below:

(1) Maximum Power Level NMC is authorized to operate the facility at steady state reactor core power levels not in excess of 1650 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 173, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Physical Protection NMC shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: "Prairie Island Nuclear Generating Plant Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program," Revision 0, submitted by letter dated October 18, 2004.

Unit 1 Amendment No. 173 Revised by letter dated August 29, 2006.

Containment Spray and Cooling Systems 3.6.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or both containment C.1 Restore containment 7 days cooling fan coil unit(s) cooling FCU(s) to (FCU) in one train OPERABLE status. AND inoperable.

10 days from discovery of failure to meet the LCO D. One containment cooling D.1 Initiate action to isolate Immediately FCU in each train both inoperable FCUs.

inoperable.

AND D.2 Restore all FCUs to 7 days OPERABLE status.

AND 10 days from discovery of failure to meet the LCO E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition C or D AND not met.

E.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Prairie Island Unit 1 - Amendment No. 4-59 173 Units 1 and 2 3.6.5-2 Unit 2 - Amendment No. 449 163 1 Revised by letter dated August29, 2006.

Containment Spray and Cooling Systems 3.6.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.5.1 Verify each containment spray manual, power 31 days operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.

SR 3.6.5.2 Operate each containment fan coil unit on low motor 31 days I speed for > 15 minutes.

I SR 3.6.5.3 Verify cooling water flow rate to each containment 24 months fan coil unit is > 900 gpm.

SR 3.6.5.4 Verify each containment spray pump's developed In accordance head at the flow test point is greater than or equal to with the the required developed head. Inservice Testing Program SR 3.6.5.5 Verify each automatic containment spray valve in the 24 months flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.6.5.6 Verify each containment spray pump starts 24 months automatically on an actual or simulated actuation signal.

Prairie Island Unit 1 - Amendment No. 4 173 Units 1 and 2 3.6.5-3 Unit 2 - Amendment No. 449 163 Revised by letter dated August 29, 2006.

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