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| | docket = 05000306 | | | docket = 05000306 |
| | license number = DPR-060 | | | license number = DPR-060 |
| | contact person = Regner L M | | | contact person = Regner L |
| | case reference number = TAC MD8514 | | | case reference number = TAC MD8514 |
| | package number = ML11147A141 | | | package number = ML11147A141 |
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| | page count = 4 | | | page count = 4 |
| | project = TAC:MD8514 | | | project = TAC:MD8514 |
| | stage = RAI | | | stage = Other |
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| =Text= | | =Text= |
| {{#Wiki_filter:Appendix A: Technical SpecificationsPrairie Island 2 uses the same Appendix A as Prairie island 1. Please refer to Prairie Island 1for Appendix A (ML | | {{#Wiki_filter: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). |
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| 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.
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| : 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
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| ===1.3. Based===
| | 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: |
| 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 LicenseCondition 2 activities. | | Amendment Implementation. |
| : 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.
| | 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. |
| Date Prior to Unit 2 entering Mode 2 Completed
| | 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. |
| -See Amendment No. 131 July 1, 1997, and December 31, 1998, as stated in Condition 2.Completed
| | 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. |
| -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.
| | dedicated operator specified in License Condition 1. |
| This is effective immediately upon issuance of the amendment.
| | 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. |
| 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. lBy September 1, 1999.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.
| | 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, 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 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. | | 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,' | | 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. |
| and Table R, 'Relocated Specifications," attachedto 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}} | | Those requirements shall be relocated to the appropriate documents no later than October 31, 2002. |
| | I B-3 Amendment No. 152}} |
Letter Sequence Other |
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TAC:MD8514, Control Room Habitability (Approved, Closed) |
|
MONTHYEARML0830105852008-11-19019 November 2008
Request for Additional Information for the Review of the Prairie Island Nuclear Generating Plant, Units 1 & 2, License Renewal Application (TAC Nos. MD8513 and MD8514)
Project stage: RAI
ML0831805582008-11-25025 November 2008
Request for Additional Information for the Review of the Prairie Island Nuclear Generating Plant Units 1 & 2, License Renewal Application (TAC Nos. MD8513 and MD8514)
Project stage: RAI
ML0908600632009-02-10010 February 2009
02/10/2009 Meeting Summary, Telephone Conference Call Between the NRC and Prairie Island, Concerning Requests for Additional Information Pertaining to the Prairie Island Units 1 and 2, License Renewal Application
Project stage: Meeting
ML0908600612009-02-23023 February 2009
Summary of Telephone Conference Call Held Between NRC and Prairie Island, Concerning Request for Additional Information Pertaining to the Prairie Island Units 1 and 2
Project stage: RAI
ML0906305452009-03-0202 March 2009
Meeting Slides, Praire Island Refueling Cavity Leakage.
Project stage: Meeting
ML11147A1232011-06-27027 June 2011
Issuance of Renewed Facility Operating Licenses for Prairie Island Nuclear Generating Plant
Project stage: Approval
ML11172A0222011-06-27027 June 2011
Technical Specifications, Unit 2, Renewed Facility Operating License for Prairie Island Nuclear Generating Plant
Project stage: Other
ML11147A1372011-06-27027 June 2011
Renewed Facility Operating License
Project stage: Request
ML11147A1402011-06-27027 June 2011
Notice of Issuance of Renewed Facility Operating License Nos. DPR-42 and DPR-60 for an Additional 20-Year Period Record of Decision
Project stage: Request
ML11147A1392011-06-27027 June 2011
Enclosure 2: Prairie Island Nuclear Generating Plant, Unit 2, Renewed Facility Operating License
Project stage: Request
2009-02-10
[Table View] |
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Category:Technical Specifications
MONTHYEARML22357A1002023-03-31031 March 2023
and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendments Standard Emergency Plan and Consolidated Emergency Operations Facility
ML22181A0002022-08-17017 August 2022
Issuance of Amendments Reactor Trip System Power Range Instrumentation Channels
L-PI-22-003, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-06-0707 June 2022
Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections
ML22061A2062022-04-0101 April 2022
Issuance of Amendments TSTF-471, Rev. 1, TSTF-571-T, and Administrative Changes to Technical Specification Section 5.0
L-PI-21-029, Exigent License Amendment Request to Revise Technical Specification 3.7.8 to Allow a One-Time Extension of the Completion Time of Required Action B.12021-10-0707 October 2021
Exigent License Amendment Request to Revise Technical Specification 3.7.8 to Allow a One-Time Extension of the Completion Time of Required Action B.1
ML20346A0202021-03-15015 March 2021
Issuance of Amendment Nos. 235 and 223, Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
ML20356A0022021-02-0505 February 2021
Issuance of Amendment Nos. 234 and 222, Revise Technical Specifications 3.2.1 and 5.6.5 Identified in Westinghouse Nuclear Safety Advisory Letters NSAL-09-05, Revision 1, and NSAL-15-1
ML20210M0142020-09-0808 September 2020
and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendment Nos. 204, 231, and 219 TSTF-529 Clarify Use and Application Rules
L-PI-20-001, License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-12020-01-29029 January 2020
License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-1
L-PI-19-041, Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2019-12-23023 December 2019
Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements
L-PI-19-040, License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency2019-10-0707 October 2019
License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency
ML19045A4802019-04-16016 April 2019
Issuance of Amendment Nos. 226 and 214 Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B
ML19029A0942019-01-29029 January 2019
Issuance of Amendment No. 213, One-Time Technical Specification Change to Extend Completion Time for EDGs D5 and D6 (Emergency Circumstances)
ML17362A2022018-03-0505 March 2018
Issuance of Amendment Concerning Revision to the Prairie Island Nuclear Generating Plant, Units 1 and 2 Emergency Plan (CAC Nos. MF9345 and MF9346; EPID L-2017-LLA-0175)
ML16133A4062016-06-16016 June 2016
Issuance of Amendment Nos. 217 and 205, Adoption of Technical Specifications Task Force TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation (CAC Nos. MF6449 and MF6450)
ML15264A2092015-11-30030 November 2015
Issuance of Amendment Nos. 216 and 204 Regarding Revisions to Technical Specification 3.3.3 and Renewed Facility Operating License
ML15229A1762015-08-26026 August 2015
Issuance of Amendment Nos. 215 and 203 Regarding Revision to Licensing Basis Analysis for a Waste Gas Decay Tank Rupture
ML15209A5122015-07-17017 July 2015
Technical Specifications - Updating Instructions -Effective Date: 7/24/2015
ML15209A5092015-07-17017 July 2015
Technical Specifications - Updating Instructions
L-PI-15-030, Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process2015-06-29029 June 2015
Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process
ML15086A0462015-05-21021 May 2015
Issuance of Amendment Nos. 214 and 202 Regarding Revisions to Technical Specification 3.8.1, AC Sources - Operating
ML15062A0132015-05-20020 May 2015
Issuance of Amendments 213 and 201 to Revise TS 3.5.3, ECCS - Shutdown
L-PI-15-004, Supplement to License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3, ECCS (Emergency Core Cooling System)- Shutdown2015-02-26026 February 2015
Supplement to License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3, ECCS (Emergency Core Cooling System)- Shutdown
L-PI-14-034, License Amendment Request (LAR) to Revise Technical Specification (TS) 3.3.3, Event Monitoring (EM) Instrumentation, and Additional Conditions Related to Alternative Source Term License Amendment Implementation2014-12-11011 December 2014
License Amendment Request (LAR) to Revise Technical Specification (TS) 3.3.3, Event Monitoring (EM) Instrumentation, and Additional Conditions Related to Alternative Source Term License Amendment Implementation
ML14058A2072014-02-19019 February 2014
Technical Specifications (3801 TS Markup)
ML13214A0292013-08-0202 August 2013
Correction Letter for License Amendment Nos. 207 (Unit 1) and 194 (Unit 2)
ML13113A4002013-07-0202 July 2013
License Amendments TSTF-510
L-PI-13-030, License Amendment Request (LAR) to Add a Methodology to Technical Specification (TS) 5.6.5, Core Operating Limits Report (Colr).2013-05-23023 May 2013
License Amendment Request (LAR) to Add a Methodology to Technical Specification (TS) 5.6.5, Core Operating Limits Report (Colr).
ML13093A3442013-05-0909 May 2013
License Amendments for Fuel Oil System and TSTF-501
L-PI-12-028, License Amendment Request (LAR) to Revise Technical Specification (TS) 3.8.1, AC Sources - Operating Emergency Diesel Generator Voltage Limits2012-05-15015 May 2012
License Amendment Request (LAR) to Revise Technical Specification (TS) 3.8.1, AC Sources - Operating Emergency Diesel Generator Voltage Limits
L-PI-12-013, Response to Requests for Additional Information Associated with Adoption of the Alternative Source Term (AST) Methodology2012-02-24024 February 2012
Response to Requests for Additional Information Associated with Adoption of the Alternative Source Term (AST) Methodology
ML1129011152011-12-0101 December 2011
Issuance of Amendments Revision of Technical Specifications 5.2.1, Onsite and Offsite Organizations and TS 5.3, Plant Staff Qualifications.
L-PI-11-037, License Amendment Request to Add Diesel Fuel Oil License Bases and Revise Technical Specifications 3.7.8 Re Cooling Water System & 3.8.3 Re Diesel Fuel Oil2011-08-11011 August 2011
License Amendment Request to Add Diesel Fuel Oil License Bases and Revise Technical Specifications 3.7.8 Re Cooling Water System & 3.8.3 Re Diesel Fuel Oil
ML11172A0222011-06-27027 June 2011
Technical Specifications, Unit 2, Renewed Facility Operating License for Prairie Island Nuclear Generating Plant
ML11172A0202011-06-27027 June 2011
Technical Specifications, Unit 1, Renewed Facility Operating License for Prairie Island Nuclear Generating Plant
L-PI-11-016, License Amendment Request (LAR) to Revise Surveillance Requirement (SR) Footnote in Technical Specification (TS) 3.8.1, AC Sources - Operating.2011-02-0303 February 2011
License Amendment Request (LAR) to Revise Surveillance Requirement (SR) Footnote in Technical Specification (TS) 3.8.1, AC Sources - Operating.
L-PI-10-104, Supplement to Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1.102010-10-20020 October 2010
Supplement to Exigent License Amendment Request to Modify Technical Specifications Surveillance Requirement 3.8.1.10
ML1025715492010-09-16016 September 2010
Correction to Amendment Nos. 195 and 184 Regarding Technical Specification Changes to Control Room Habitability Requirements
ML0925703672009-09-15015 September 2009
Correction to Technical Specifications (TAC Nos. MD9142 and MD9143)
L-PI-08-080, License Amendment Request (LAR) to Revise Emergency Diesel Generator (EDG) Test Loads in Surveillance Requirement (SR) 3.8.1.3 and SR 3.8.1.92008-11-0404 November 2008
License Amendment Request (LAR) to Revise Emergency Diesel Generator (EDG) Test Loads in Surveillance Requirement (SR) 3.8.1.3 and SR 3.8.1.9
ML0826815912008-09-22022 September 2008
(PINGP-1 and 2), Technical Specifications ISFSI, Issuance of Amendments to Conform the Facility Operating Licenses to Reflect Transfer of Operating Authority (TAC L24245)
ML0826812912008-09-22022 September 2008
Revised Operating Licenses & Technical Specifications, Issuance of Amendments to Conform the Facility Operating Licenses to Reflect Transfer of Operating Authority (TAC L24245, MD9622 and MD9623)
ML0820504452008-07-18018 July 2008
Tech Spec Pages for Amendments 186 & 176 Adopting Provisions of Regulatory Guide (Rg) 1.52 Revision 3
ML0818402342008-06-27027 June 2008
Prairie, Units 1 and 2, Tech Spec Pages for Amendments 185 and 175 Regarding Incorporation of TS Task Force Travelers TSTF-479, TSTF-485 and TSTF-497
ML0812705062008-05-0101 May 2008
Submittal of Entire Re-Issue of ISFSI Technical Specifications
ML0801404252008-01-28028 January 2008
Issuance of Amendments (TAC Nos. MD4209 & MD4210) - Tech Specs
ML0735204002007-12-14014 December 2007
Technical Specifications in Support of Containment Sump Resolution
L-PI-07-086, License Amendment Request (LAR) to Revise Containment Spray Nozzle Surveillance Requirements (SR)2007-11-19019 November 2007
License Amendment Request (LAR) to Revise Containment Spray Nozzle Surveillance Requirements (SR)
ML0728403542007-10-31031 October 2007
Tech Spec Page for Amendments 181 and 171, Revise TS 3.7.2 Main Steam Valves Closure Times by Relocating the Isolation Valve Closure Times to a Licensee-Controlled Document Identified as a Bases Reference
L-PI-07-061, License Amendment Request (LAR) to Increase the Unit 1 Emergency Diesel Generators' (EDG) Monthly Test Load2007-08-16016 August 2007
License Amendment Request (LAR) to Increase the Unit 1 Emergency Diesel Generators' (EDG) Monthly Test Load
2023-03-31
[Table view] |
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
