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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20206R0531999-05-13013 May 1999
Application for Amends to Licenses DPR-42 & DPR-60,removing Plant Organization Structure Requirement
ML20205S3291999-04-20020 April 1999
Application for Amends to Licenses DPR-42 & DPR-60,changing Implementation Date for Relocation from TS to UFSAR of Requirements in TS 3.1.E & Flooding Shutdown Requirements in TS 5.1
ML20205Q0261999-04-12012 April 1999
Application for Amends to Licenses DPR-42 & DPR-60, Relocating Shutdown Margin Requirements from TS to COLR
ML20204H3491999-03-19019 March 1999
Application for Amends to Licenses DPR-42 & DPR-60,removing Dates of Two NRC SERs & Correcting Date of One SER Listed in Section 2.C.4, Fire Protection
ML20207F2771999-03-0101 March 1999
Revised Application for Amends to Licenses DPR-42 & DPR-60, Incorporating Combustion Engineering SG Welded Tube Sleeve TR Rev
ML20203A1051999-02-0505 February 1999
Application for Amends to Licenses DPR-42 & DPR-60, Incorporating Changes to ABB-CE Sleeve Design Assumptions & Installation Techniques
ML20196B9571998-11-25025 November 1998
Application for Amends to Licenses DPR-42 & DPR-60,allowing Limited Inoperability of Bast Level Channels & Transfer Logic Channels to Provide for Required Testing & Maint of Associated Components
ML20155D9581998-10-30030 October 1998
Application for Amends to Licenses DPR-42 & DPR-60,to Revise License Condition 7 to Include Extended Implementation Date of 990901
ML20154S2061998-10-23023 October 1998
Application for Amends to Licenses DPR-42 & DPR-60, Clarifying Conditions That Constitute Operable Irpi Sys Channels
ML20154F7731998-10-0101 October 1998
Suppl 16 to License Amend Request to Licenses DPR-42 & DPR-60,replacing Paragraph for USAR Page 10.4-7 & Page 10.4-7 Annotated Showing Which Paragraph Replaced
ML20151Z8891998-09-15015 September 1998
Suppl 15 to 970129 Application for Amend to Licenses DPR-42 & DPR-60,revising Cooling Water Sys Emergency Intake Design Bases
ML20151U3471998-09-0404 September 1998
Application for Amends to Licenses DPR-42 & DPR-60, Clarifying SRs & LCOs for Operability for Reactor Coolant Vent Sys
ML20237B5001998-08-12012 August 1998
Suppl 8 to 951214 LAR for Licenses DPR-42 & DPR-60,providing Addl Info to Support Conformance of Administrative Controls Section 6 to Guidance of Std Tech Specs
ML20236T9801998-07-24024 July 1998
Supplemental Application for Amends to Licenses DPR-42 & DPR-60,providing Suppl Info in Support of 980129 Amend Request Re Cooling Water Sys Emergency Intake Design Bases
ML20249A7601998-06-11011 June 1998
Suppl 7 to 951214 LAR for Amends to Licenses DPR-42 & DPR-60,showing Tech Specs Pages Annotated to Incorporate Changes Proposed in Suppl
ML20248M1911998-05-29029 May 1998
Supplemental Application for Amend to License DPR-42, Providing Updated Flux Mapping Results for Cycle 19
ML20216G0331998-04-13013 April 1998
Application for Amends to Licenses DPR-42 & DPR-60, Supplementing LAR
ML20216D0221998-03-0606 March 1998
Application for Amends to Licenses DPR-42 & DPR-60,updating Heatup & Cooldown Rate Curves,Incorporating Use of Pressure & Temp Limits Rept & Changing Pressurizer PORVs Operability Temp
ML20217N9941998-03-0404 March 1998
Supplemental LAR to Licenses DPR-42 & DPR-60,providing Status of Relocated Tech Specs Requirements
ML20217N9671998-03-0202 March 1998
Application for Amends to Licenses DPR-42 & DPR-60,revising TS 3.8.D Re Spent Fuel Pool Special Ventilation Sys
ML20217P9811998-03-0202 March 1998
Suppl to LAR to Licenses DPR-42 & DPR-60,supporting License Amend Request Re Conformance of Administrative Controls Section 6 to Guidance of Std
ML20203J9531998-02-27027 February 1998
Application for Amends to Licenses DPR-42 & DPR-60,modifying AMSAC W/Addition of Diverse Scram Feature as Described in Exhibit A.Nrc Approval Is Requested by 980907
ML20202E5571998-02-10010 February 1998
Application for Amends to Licenses DPR-42 & DPR-60,revising TS 1-1 Re One Time Reduction of Mode 6 Reactor Coolant Sys Boron Concentration
ML20198N8241998-01-15015 January 1998
Application for Amends to Licenses DPR-42 & DPR-60, Respectively.Amends Proposes one-time Only Changes Allowing Use of Moveable Incore Detector Thimble Reduction for Unit 1 Cycle 19
ML20198P0741998-01-0808 January 1998
Suppl 5 to 951214 LAR to Licenses DPR-42 & DPR-60 Re Proposed Changes to TS Section 6
ML20198B1401997-12-29029 December 1997
Application for Amends to Licenses DPR-42 & DPR-60, Respectively.Amends Provide Changes to TS Pages Associated w/951214 LAR
ML20212F9711997-10-28028 October 1997
Supplemental Application for Amend to Licenses DPR-42 & DPR-60 Re Cooling Water Sys Emergency Intake Design Bases
ML20217F4711997-10-0303 October 1997
Suppl Application for Amend to Licenses DPR-42 & DPR-60, Allowing Use of New SG Tube Sleeve Designs & Installation & Exam Techniques
ML20211H7431997-10-0101 October 1997
Suppl Application for Amends to Licenses DPR-42 & DPR-60, Allowing Physical Mods to Turbine Bldg Cooling Water Header Isolation Logic
ML20217C5801997-09-26026 September 1997
Application for Amends to Licenses DPR-42 & DPR-60.Amend Proposes Changes to TS 3.4.B to Change Minimum Conditions for AFW & Permit Startup Operations to Continue W/Inoperable Turbine Driven AFW Pump or Associated Sys Valves
ML20216E4461997-09-0404 September 1997
Application for Amends to Licenses DPR-42 & DPR-90,providing Supplemental Info Which Supports Conformance of TS Overtime to NRC Guidance Issued 950409
ML20217M5961997-08-15015 August 1997
Suppl to LAR Dtd 961127,incorporating C-E SG Welded Tube Sleeve Topical Rept CEN-629-P,Rev 1.Proprietary & non-proprietary TRs CEN-629-P,encl.Proprietary Rept Withheld Per 10CFR2.790.Affidavit,encl
ML20148Q9491997-06-30030 June 1997
Application for Amends to Licenses DPR-42 & DPR-60,providing Suppl 9 to LAR Re Amend of CWS Emergency Intake Design Bases
ML20141F4851997-05-15015 May 1997
Application for Amends to Licenses DPR-42 & DPR-60, Requesting Proposes Changes to Tech Specs 3.1.C, Reactor Coolant Sys Leakage & 4.12, SG Tube Surveillance
ML20141A0751997-05-0707 May 1997
Application for Amends to Licenses DPR-42 & DPR-60,amending Spent Fuel Pool Special Ventilation Sys
ML20138G4161997-04-29029 April 1997
Application for Amends to Licenses DPR-42 & DPR-60, Supplementing 970129 Application Re Rev to Cooling Water Sys Emergency Intake Design Bases
ML20137T2031997-04-10010 April 1997
Application for Amends to Licenses DPR-42 & DPR-60, Clarifying Amend Request Re Conformance of Administrative Controls Section 6 to Guidance of STS
ML20137D9041997-03-20020 March 1997
Application for Amends to Licenses DPR-42 & DPR-60,providing Supplemental Info to Amend Re Cooling Water Sys Emergency Intake Design Bases
ML20136H0041997-03-11011 March 1997
Application for Amends to Licenses DPR-42 & DPR-60,providing Suppl Info to Support Amend Re CWS Emergency Intake Design Bases
ML20136F5131997-03-10010 March 1997
Application for Amends to Licenses DPR-42 & DPR-60,revising CWS Emergency Intake Design Bases
ML20135F7441997-03-0707 March 1997
Suppl 3 to Application for Amends to Licenses DPR-42 & DPR-60 Re Cooling Water Sys Emergency Intake Design Bases
ML20135A9371997-02-21021 February 1997
Application for Amends to Licenses DPR-42 & DPR-60,allowing Use of Credit for Soluble Boron in Spent Fuel Pool Criticality Analyses
ML20134J6211997-02-0606 February 1997
Application for Amends to Licenses DPR-42 & DPR-60,revising Restrictions on Safety Injection Sys Operations When Reactor Coolant Sys Is at Low Temperatures
ML20134E9341997-01-29029 January 1997
Application for Amend to Licenses DPR-42 & DPR-60,revising TS Re Cooling Water Sys Emergency Intake Design Bases. Subj Amends Base on Response to Notice of Violations Noted Noted in Insp Repts 50-282/96-15 & 50-306/96-15
ML20135A8191996-11-27027 November 1996
Application for Amends to Licenses DPR-42 & DPR-60,revising TS 4.12, SG Tube Surveillance & TS Section B-4-12
ML20134H3641996-11-0606 November 1996
Application for Amends to Licenses DPR-42 & DPR-60, Requesting Rev to Appendix a Re Cooling Water Sys
ML20134E4451996-10-25025 October 1996
Application for Amends to Licenses DPR-42 & DPR-60,changing TS 4.4.A, Containment Leakage Tests, Bases to TS Section B.4.4, Containment Sys Tests & Adding TS.6.5.J, Containment Leakage Rate Testing Program
ML20129E2451996-09-24024 September 1996
Application for Amends to Licenses DPR-42 & DPR-60, Respectively,Changing TS 4.12, SG Tube Surveillance, to Incorporate Revised Acceptance Criteria for SG Tubes W/ Degradation in Tubesheet Region
ML20117P4291996-09-11011 September 1996
Application for Amends to Licenses DPR-42 & DPR-60,revising Plant TS Governing Cw Sys
ML20117B2341996-08-15015 August 1996
Application for Amends to Licenses DPR-42 & DPR-60,revising TS 3.3.B.2 Re Containment Cooling Sys & Bases to Conform to Supporting Analyses
1999-05-13
[Table view]
Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20211K6101999-08-31031 August 1999
Application for Amend to License SNM-2506,proposing Change to License Conditions 6,7 & 8 & TSs to App a of License by Permitting Inclusion of Bpras & Thimble Plug Devices in Sf Assemblies Stored in TN-40 Casks
ML20211J2781999-08-26026 August 1999
Amends 146 & 137 to Licenses DPR-42 & DPR-60,respectively, Revising TS 6.2.A.2, Onsite & Offsite Organizations, to Reflect Change in Plant Organizational Structure That Was Implemented on 990301
ML20206R0531999-05-13013 May 1999
Application for Amends to Licenses DPR-42 & DPR-60,removing Plant Organization Structure Requirement
ML20205S3291999-04-20020 April 1999
Application for Amends to Licenses DPR-42 & DPR-60,changing Implementation Date for Relocation from TS to UFSAR of Requirements in TS 3.1.E & Flooding Shutdown Requirements in TS 5.1
ML20206A2341999-04-15015 April 1999
Amends 144 & 135 to Licenses DPR-42 & DPR-60,respectively, Changing Certain Requirements for Repair of Defective Steam Generator Tubes Specified in TS 4.12 Based on Latest Rev to Previously Approved Methodology
ML20205Q0261999-04-12012 April 1999
Application for Amends to Licenses DPR-42 & DPR-60, Relocating Shutdown Margin Requirements from TS to COLR
ML20204H3491999-03-19019 March 1999
Application for Amends to Licenses DPR-42 & DPR-60,removing Dates of Two NRC SERs & Correcting Date of One SER Listed in Section 2.C.4, Fire Protection
ML20205B3221999-03-17017 March 1999
Amends 143 & 134 to Licenses DPR-42 & DPR-60,respectively, Revise TS 3.2 & Table 3.5-2B to Allow Limited Inoperability of Bast Level Channels & Transfer Logic Channels to Provide for Required Testing & Maintenance of Associated Components
ML20207F2771999-03-0101 March 1999
Revised Application for Amends to Licenses DPR-42 & DPR-60, Incorporating Combustion Engineering SG Welded Tube Sleeve TR Rev
ML20203A1051999-02-0505 February 1999
Application for Amends to Licenses DPR-42 & DPR-60, Incorporating Changes to ABB-CE Sleeve Design Assumptions & Installation Techniques
ML20198L0011998-12-17017 December 1998
Amends 142 & 133 to Licenses DPR-42 & DPR-60,respectively, Revising TSs for Units 1 & 2 to Clarify SRs & Limiting Conditions for Operation of Reactor Coolant Vent Sys
ML20198L2111998-12-0707 December 1998
Amends 141 & 132 to Licenses DPR-42 & DPR-60,respectively, Revising TS 6.0,administrative Controls & Following TS Sections Affected by Relocating,Removing & Modifying Requirements to TS 6.0
ML20196B9571998-11-25025 November 1998
Application for Amends to Licenses DPR-42 & DPR-60,allowing Limited Inoperability of Bast Level Channels & Transfer Logic Channels to Provide for Required Testing & Maint of Associated Components
ML20195C8851998-11-0404 November 1998
Amends 140 & 131 to Licenses DPR-42 & DPR-60,respectively, Changing Design Basis of Cooling Water Sys Emergency Intake Line Flow Capacity
ML20155D9581998-10-30030 October 1998
Application for Amends to Licenses DPR-42 & DPR-60,to Revise License Condition 7 to Include Extended Implementation Date of 990901
ML20154S2061998-10-23023 October 1998
Application for Amends to Licenses DPR-42 & DPR-60, Clarifying Conditions That Constitute Operable Irpi Sys Channels
ML20154F7731998-10-0101 October 1998
Suppl 16 to License Amend Request to Licenses DPR-42 & DPR-60,replacing Paragraph for USAR Page 10.4-7 & Page 10.4-7 Annotated Showing Which Paragraph Replaced
ML20154B9161998-09-22022 September 1998
Amends 138 & 129 to Licenses DPR-42 & DPR-60,respectively, Authorizing Design Modification of Existing ATWS Mitigation Sys Actuation Circuitry
ML20151Z8891998-09-15015 September 1998
Suppl 15 to 970129 Application for Amend to Licenses DPR-42 & DPR-60,revising Cooling Water Sys Emergency Intake Design Bases
ML20151U3471998-09-0404 September 1998
Application for Amends to Licenses DPR-42 & DPR-60, Clarifying SRs & LCOs for Operability for Reactor Coolant Vent Sys
ML20237D6451998-08-13013 August 1998
Amends 137 & 128 to Licenses DPR-42 & DPR-60,respectively, Revising TSs for Plant,Units 1 & 2 to Allow Use of Alternate SG Tube Repair Criteria in Tubesheet Region When Used with Repair Method of Addl Roll Expansion
ML20237B5001998-08-12012 August 1998
Suppl 8 to 951214 LAR for Licenses DPR-42 & DPR-60,providing Addl Info to Support Conformance of Administrative Controls Section 6 to Guidance of Std Tech Specs
ML20236V4031998-07-28028 July 1998
Amend 136 to License DPR-42,allowing Reduction in Required Number of Incore Instrumentation Detectors for Remainder of Unit 1,Cycle 19 Operation
ML20236T9801998-07-24024 July 1998
Supplemental Application for Amends to Licenses DPR-42 & DPR-60,providing Suppl Info in Support of 980129 Amend Request Re Cooling Water Sys Emergency Intake Design Bases
ML20249A7601998-06-11011 June 1998
Suppl 7 to 951214 LAR for Amends to Licenses DPR-42 & DPR-60,showing Tech Specs Pages Annotated to Incorporate Changes Proposed in Suppl
ML20248M1911998-05-29029 May 1998
Supplemental Application for Amend to License DPR-42, Providing Updated Flux Mapping Results for Cycle 19
ML20247F9161998-05-0404 May 1998
Amends 135 & 127 to Licenses DPR-42 & DPR-60,respectively, Updating TS Heatup & Cooldown Rate Curves & Extending Reactor Vessel Fluence Limit from Current 20 Effective Full Power Yrs to New Value of 35 EFPY
ML20216G0331998-04-13013 April 1998
Application for Amends to Licenses DPR-42 & DPR-60, Supplementing LAR
ML20216D0221998-03-0606 March 1998
Application for Amends to Licenses DPR-42 & DPR-60,updating Heatup & Cooldown Rate Curves,Incorporating Use of Pressure & Temp Limits Rept & Changing Pressurizer PORVs Operability Temp
ML20217N9941998-03-0404 March 1998
Supplemental LAR to Licenses DPR-42 & DPR-60,providing Status of Relocated Tech Specs Requirements
ML20217P9811998-03-0202 March 1998
Suppl to LAR to Licenses DPR-42 & DPR-60,supporting License Amend Request Re Conformance of Administrative Controls Section 6 to Guidance of Std
ML20217N9671998-03-0202 March 1998
Application for Amends to Licenses DPR-42 & DPR-60,revising TS 3.8.D Re Spent Fuel Pool Special Ventilation Sys
ML20203J9531998-02-27027 February 1998
Application for Amends to Licenses DPR-42 & DPR-60,modifying AMSAC W/Addition of Diverse Scram Feature as Described in Exhibit A.Nrc Approval Is Requested by 980907
ML20202E5571998-02-10010 February 1998
Application for Amends to Licenses DPR-42 & DPR-60,revising TS 1-1 Re One Time Reduction of Mode 6 Reactor Coolant Sys Boron Concentration
ML20198N8241998-01-15015 January 1998
Application for Amends to Licenses DPR-42 & DPR-60, Respectively.Amends Proposes one-time Only Changes Allowing Use of Moveable Incore Detector Thimble Reduction for Unit 1 Cycle 19
ML20198P0741998-01-0808 January 1998
Suppl 5 to 951214 LAR to Licenses DPR-42 & DPR-60 Re Proposed Changes to TS Section 6
ML20198B1401997-12-29029 December 1997
Application for Amends to Licenses DPR-42 & DPR-60, Respectively.Amends Provide Changes to TS Pages Associated w/951214 LAR
ML20198G2751997-12-23023 December 1997
Errata to Amends 134 & 126 of Licenses DPR-42 & DPR-60, Respectively.Table Number Changed on TS Page 5 of 9 of Table 3.5-2 to Read Table TS.3.5-2B
ML20202B7081997-11-25025 November 1997
Amends 134 & 126 to Licenses DPR-42 & DPR-60,respectively, Revising TS 3.4.B, Afs, to Provide Specific Guidance for Conducting post-maint Operational Testing of turbine-driven Afp & Associated Sys Valves
ML20199H7171997-11-18018 November 1997
Amends 133 & 125 to Licenses DPR-42 & DPR-60,respectively, Revising Certain TS Limitation on RCS Leakage & SG Tube Surveillance & Implement voltage-based Repair Criteria,Per Requirements of GL 95-05
ML20212F9711997-10-28028 October 1997
Supplemental Application for Amend to Licenses DPR-42 & DPR-60 Re Cooling Water Sys Emergency Intake Design Bases
ML20217F4711997-10-0303 October 1997
Suppl Application for Amend to Licenses DPR-42 & DPR-60, Allowing Use of New SG Tube Sleeve Designs & Installation & Exam Techniques
ML20211H7431997-10-0101 October 1997
Suppl Application for Amends to Licenses DPR-42 & DPR-60, Allowing Physical Mods to Turbine Bldg Cooling Water Header Isolation Logic
ML20217C5801997-09-26026 September 1997
Application for Amends to Licenses DPR-42 & DPR-60.Amend Proposes Changes to TS 3.4.B to Change Minimum Conditions for AFW & Permit Startup Operations to Continue W/Inoperable Turbine Driven AFW Pump or Associated Sys Valves
ML20211E7761997-09-15015 September 1997
Amends 130 & 122 to Licenses DPR-42 & DPR-60,respectively, Changing TS Limitations on Crane Operations in SFP Encl Re SFP Special Ventilation Sys Operability
ML20216E4461997-09-0404 September 1997
Application for Amends to Licenses DPR-42 & DPR-90,providing Supplemental Info Which Supports Conformance of TS Overtime to NRC Guidance Issued 950409
ML20217M5961997-08-15015 August 1997
Suppl to LAR Dtd 961127,incorporating C-E SG Welded Tube Sleeve Topical Rept CEN-629-P,Rev 1.Proprietary & non-proprietary TRs CEN-629-P,encl.Proprietary Rept Withheld Per 10CFR2.790.Affidavit,encl
ML20148Q9491997-06-30030 June 1997
Application for Amends to Licenses DPR-42 & DPR-60,providing Suppl 9 to LAR Re Amend of CWS Emergency Intake Design Bases
ML20141B0261997-06-12012 June 1997
Amends 129 & 121 to Licenses DPR-42 & DPR-60,respectively, Revising TS for Plant to Allow Credit for Soluble Boron in Sf Criticality Analyses
ML20141F4851997-05-15015 May 1997
Application for Amends to Licenses DPR-42 & DPR-60, Requesting Proposes Changes to Tech Specs 3.1.C, Reactor Coolant Sys Leakage & 4.12, SG Tube Surveillance
1999-08-31
[Table view] |
Text
.
-t Exhibit A l
Prairie Island Nuclear Generating Plant License Amendment Request Dated February 26, 1991 Evaluation of Proposed Changes to the Technical Specifications Appendix A of Operating License DPR-42 and DPR 60 Pursuant to 10 CPR Part 50, Sections 50.59 and 50.90, the holders of Operating Licenses DPR-42 and DPR 60 heretv propose the following changes to Appendix A, Technical Specifications:
Proposed Changes Revise specification 3-4.A as shown on page TS,3,4 1 in Exhibit B to incorporate an action statement for the inoperability of one steam generator power operated relief valve, Revisc-the bases for Technical _ Specification Section 3.4 as shown on page B,3,4-1 in Exhibit B, Renson For Chances License amendments 91 and 84 to the Prairie Island facility operating licenses, approved October 27, 1989 incorporated a large upgrade into the Prairie Island Technical Specifications, Included in that upgrade was a completely rewritten Section 3,4, " Steam and Power Conversion System".
Prior to amendments 91 and 84, Sectiv.. 3.4 included the following specification for the steam generator safety and power operated relief valves:
"A.
A reactor shall not be heated-above 350* F unless the following conditions are satisfied:
1, S a fe ty and Relief Vnives a.
Rated relief capacity of ten steam system safety valves is available for that reactor, except duriug testing.
- b. - Both steam generator power operated relief valves for that reactor are operable."
Prior to amendments 91 and 84, Specification 3.4.B provided the following action statement for Specification 3,4,A 1:
"B.
If, during startup operation or power operation, any of the conditions of Specification 3.4. A, except as noted below for 2.a, 2.b or 4 cannot be-met, startup operations shall be discontinued and if operability cannot be restored within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the affected reactor shall be placed in the cold shutdown condition using normal operating procedures."
9103050312 910226 PDR ADOCK 05000282 P
PDR
Exhibit A Page 2 of 3 l
During the preparation of the rewrite of Section 3.4, which was approved by amendments 91 and 84, the action statements provided for the steam generator safety and power operated relief valves were unintentionally not included in the revision to Section 3.4.
As a result, the current Prairie Island Technical Specification does not provide action statements for the steam generator safety and power operated relief valves beyond the standard one hour to prepare for shutdown and six hours to reach hot shutdown.
The proposed changes to Section 3.4, shown in Exhibit B, incorporate an action statement for the steam generator power operated relief valves back into the Prairie Island Technical Specifications. The proposed action statemeat allows one steam generator power operated relief valve to be inoperable for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
This is similar to the old statement described above, which allowed both steam generator power operated relief valves to be inoperable for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
No action statement for the steam generator safety relief valves is being proposed at this time.
An appropriate action statement for the safety relief valves is under evaluation and will be submitted as part of a future license amendment request.
The bases for Technical Specification 3.4 are being revised to better describe the bases of the steam generator power operated relief valve specification and to provide guidance on the operability of the steam generator power operated relief valves.
Safety Evaluation and Determination of Sirnificant Hazards Considerations The proposed changes to the Operating License have been evaluated to determine whether they constitute a significant hazards consideration as required by 10 CFR Part 50, Section 50.91 using the standards provided in Section 50.92.
This analysis is provided below:
1.
The proposed amendment will not involve a significant increase in the probability or consecuences of an accident previousiv evaluated.
The proposed amendment incorporates an action statement into Technical Specification Section 3.4 that is similar to the action statement previously included in Section 3.4 for the stcam generator power operated relief valves.
However, the proposed action statement is more restrictive than the action statement that was inadvertently deleted.
The allowed out of service time is the same as the previous action statement, but the proposed action statement only allows one steam generator power operated relief valve to be out of service for the 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period.
The previous action strtement implied that both steam generator power operated relief valves could be inoperaole for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
Therefore, because the proposed action statement is more restrictive than the action statement previorsly included in the Technical Specifications, the proposed changes will no-involv' a significant increase in the probability or consequences of an accident previously evaluated.
~ --~. ~ ~.- ~. -
~ ~. -.-.
hhibit A Page 3 of 3 2.
The proposed amendment will not create the possibility of a new or different kind of accident from any accident oreviousiv nnalyzed.
There are no new failure modes or mechanisms associated with the proposed changes.
The proposed changes do not involve any modification in the operational limits or physical design of the involved systems.
The change merely it corporates an action statement for the steam generator power operated relief valves which is more restrictive than an action statement that was previously included in the Prairie Island Technical Specifications.
As discussed above, the proposed changes do not result in any significant change in the configuration of the plant, equipment design or equipment use nor do they require any change in the accident analysis methodology.
Therefore, no different type of accident is created.
No safety analyses are affected. The_ accident analyses presented in the Updated Safety Analysis Report remain bounding.
3.
The proposed amendment will not involve a significant reduction in the marr_in of safety.
The proposed ~ changes do not involve a reduction in any Technical Specification margin of safety.
The change is incorporating an action statement-for the steam generator power operated relief valves which is more restrictive than an action statement that was previously included in the Prairie Island Technical Specifications. Therefore, the proposed changes will not result in any reduction in the plant's margin of safety.
The Commission has provided guidance concerning the application of the standards in 10 CFR 50.92 for determining whether a significant hazards consideration exists by providing certain examples of amendments that will likely be found to involve no significant hazards considerations.
These examples'were published in the Federal Register on March 6, 1986.
The changes to the Prairie Island Technical Specifications proposed above are equivalent to_NRC example (vi), because they involve changes which either may result in some-increase to the probability or consequences of a previously analyzed accident or may reduce in some way a safety margia, but where the'results of the change are clearly within all acceptable criteria with respect to the system or component specified in the Standard Review Plan.
Based on this guidance and the reasons-discussed above, we have concluded that the proposed changes do not involve a significant hazards consideration.
Environmental Assessment This license amendment request does not change effluent types or total effluent amounts nor does it involve an increase in power level.
Therefore, this change will not result in any significant environmental impact.
j
-I j
. Exhibit B Prairic Island Nuclear Generating Plant
' License Amendment Request Dated February 26, 1991 Proposed Changes Marked Up On Existing Technical Specification Pages Exhibit B consists of existing Technical Specification pages with the preposed changes written on those pages.
The existing pages affected by this License Amradment Request are listed below:
TS.3.4 1 B.3.4 1 4
~
L l
~
-.
