ML11172A022

Technical Specifications, Unit 2, Renewed Facility Operating License for Prairie Island Nuclear Generating Plant

ML11172A022
Person / Time
Site:	Prairie Island
Issue date:	06/27/2011
From:	Office of Nuclear Reactor Regulation
To:
Regner L
Shared Package
ML11147A141	List: ML11147A123 ML11147A137 ML11147A139 ML11147A140 ML11172A020 ML11172A022 NRC-2009-0507, Prairie Island Nuclear Generating Plant, Units 1 and 2 Notice of Issuance of Renewed Facility Operating License Nos. DPR-42 and DPR-60 for an Additional 20-Year Period Record of Decision
References
TAC MD8514
Download: ML11172A022 (4)

Text

Appendix A: Technical Specifications Prairie Island 2 uses the same Appendix A as Prairie island 1. Please refer to Prairie Island 1 for Appendix A (ML11147A137).

Unit 2 APPENDIX B ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. DPR-60 Northern States Power Company (NSPM) shall comply with the following conditions on the schedules noted below:

Amendment Implementation.

Number Additional Condition Date 120 1. NSPM will provide a licensed operator in the control room Prior to Unit 2 entering on an interim basis for the dedicated purpose of identifying Mode 2 an earthquake which results in a decreasing safeguards I cooling water bay level. This operator will be in addition to Completed - See the normal NSPM administrative control room staffing Amendment No. 131 requirements and will be provided until License Condition 2 is satisfied.

120 2. NSPM will submit dynamic finite element analyses of the July 1, 1997, and intake canal banks by July 1, 1997 for NRC review. By December 31, 1998, as December 31, 1998, NSPM will complete, as required, stated in Condition 2.

additional analyses or physical modifications which provide the basis for extending the time for operator post-seismic Completed - See cooling water load management and eliminating the Amendment No. 131.

dedicated operator specified in License Condition 1.

120 3. Based on the results of License Condition 2, NSPM will. At the next USAR I revise the Updated Safety Analysis Report to incorporate the update *following changes into the plant design bases. These changes will be completion of included in the next scheduled revision of the Updated Cohdition 2, but no Safety Analysis Report following completion of License later-than -June 1, Condition 2 activities. 1999.

122 4. Prairie Island will assure that heavy loads do not present This is effective a potential for damaging irradiated fuel through use of: 1) a immediately upon single-failure-proof crane with rigging and procedures which issuance of the implement Prairie Island commitments to NUREG'0612; or amendment.

2) spent fuel pool covers with their implementing plant procedures for installation and use.

125 5. NSPM will assure that during the implementation of steam This is effective generator repairs utilizing the voltage-based repair criteria, immediately upon the total calculated primary to secondary side leakage from issuance of the the faulted steam generator, under main steam line break amendment.

conditions (outside containment and upstream of themain steam isolation valves), Will not exceed 1.42 gallons-per minute (based on a reactor coolant system temperature of 578-F).

Amendment No.. +44,177 1

IS/ Unit 2 APPENDIX B ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. DPR-60 Amendment Implementation Number Additional Condition Date 136 6. Relocate current Technical Specfifcation 3.1.S, Maximum By September 1, 1999. l Reactor Oxygen, Chloride, and Fluoride Concentration, Technical Specification 5.1 food shutdown requirements to the USAR.

132 7. Relocate current Technical Specification 4.6A1 .c, Diesel By September 1, 1999.

Fuel Oil Testing, requirements to the Diesel Fuel Oil Testing Program.

k B-2

_ _~---_JUN

. 02 1999

APPENDIX B ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. DPR-60 Amendment Implementation Number Additional Conditions Date 149 The schedule for performing Surveillance Requirements October 31, (SRs) that are new or revised InAmendment No. 149 shall 2002 be as follows:

For SRs that are new Inthis amendment, the first performance is due at the end of the first surveillance Interval, which begins on the date of Implementation of this amendment.

For SRs that existed prior to this amendment, whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance perforried after Implementation of this amendment.

For SRs that existed prior to this amendment that have modified acceptance:criteria, the first performance Is due at the end of the surveillance Interval that began on the date the surveillance was last performed prior to the implementation of this amendment.

For SRs that existed prior to this amendment, whose Intervals of performance are being extended, the first extended surveillance Interval begins upon completion of the last surveillance performed prior to the implementation of this amendment.

149 The licensee is authorized to relocate certain Technical October 31, Specification requirements previously Included in 2002 Appendix A to licensee-controlled documents, as described in Table LR, "Less Restrictive Changes - Relocated Details,' and Table R,'Relocated Specifications," attached to the NRC staffs safety evaluation dated July 26, 2002.

Those requirements shall be relocated to the appropriate documents no later than October 31, 2002.

I B-3 Amendment No. 152