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 Number 120 120 120 Additional Condition

1. NSPM will provide a licensed operator in the control room on an interim basis for the dedicated purpose of identifying an earthquake which results in a decreasing safeguards cooling water bay level. This operator will be in addition to the normal NSPM administrative control room staffing requirements and will be provided until License Condition 2 is satisfied.

2. NSPM will submit dynamic finite element analyses of the intake canal banks by July 1, 1997 for NRC review. By December 31, 1998, NSPM will complete, as required, additional analyses or physical modifications which provide the basis for extending the time for operator post-seismic cooling water load management and eliminating the dedicated operator specified in License Condition 1.

3. Based on the results of License Condition 2, NSPM will.

revise the Updated Safety Analysis Report to incorporate the changes into the plant design bases. These changes will be included in the next scheduled revision of the Updated Safety Analysis Report following completion of License Condition 2 activities.

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

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

5. NSPM will assure that during the implementation of steam generator repairs utilizing the voltage-based repair criteria, the total calculated primary to secondary side leakage from the faulted steam generator, under main steam line break 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).

Implementation.

Date Prior to Unit 2 entering Mode 2 Completed - See Amendment No. 131 July 1, 1997, and December 31, 1998, as stated in Condition 2.

Completed - See Amendment No. 131.

At the next USAR update *following completion of Cohdition 2, but no later-than -June 1, 1999.

This is effective immediately upon issuance of the amendment.

This is effective immediately upon issuance of the amendment.

I I

122 125 1

Amendment No.. +44,177

IS/

Unit 2 APPENDIX B ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. DPR-60 Amendment Number Additional Condition 136 132

6. Relocate current Technical Specfifcation 3.1.S, Maximum Reactor Oxygen, Chloride, and Fluoride Concentration, Technical Specification 5.1 food shutdown requirements to the USAR.

7. Relocate current Technical Specification 4.6A1.c, Diesel Fuel Oil Testing, requirements to the Diesel Fuel Oil Testing Program.

Implementation Date By September 1, 1999. l By September 1, 1999.

k

B-2

_~---._JUN 02 1999

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

Implementation Date October 31, 2002 For SRs that are new In this 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 Specification requirements previously Included in 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.

October 31, 2002 I

B-3 Amendment No. 152