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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
, _-
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UNITED STATES NUCLEAR REGULATORY COMMISSION 4
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l NORTHERN STATES POWER COMPANY 1
I h
PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET NO. 50-282 1
[
50-306 I
i REQUEST FOR AMENDMENT TO r
OPERATING LICENSES DPR-42 & DPR-60 LICENSE AMENDMENT REQUEST DATED FEBRUARY 5,1999 Northern States Power Company, a Minnesota corporation, requests authorization for changes to Appendix A of the Prairie Island Operating License as shown on the attachments labeled Exhibits A, B, and C. Exhibit A describes the proposed changes, l
reasons for the changes, safety evaluation and a significant hazards evaluation.
Exhibits B and C are copies of the Prairie Island Technical Specifications incorporating 1
the proposed changes.
This letter contains no restricted or other defense information.
l NORTHERN STATES P ER COMPANY By
/wM
- 61 P. 'Sorensen~
Bite General Manager Prairie Island Nuclear Generating Plant On this f day of blULA
/ff 9before me a notary public in and for said County, personally'a'pphased Joel P. Sorensen, Site General Manager, Prairie Island Nuclear Generatihg Plant, and being first duly sworn acknowledged that he is
'detidiad to execQte this document on behalf of Northern States Power Company, that
' he knows t?ie' contents thereof, and that to the best of his knowledge, information, and belief the statements made in i are t and that it is ot interposed for delay.
)
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l MARCIA K. LaCOIE
- l
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NOTARYPUBUCM91NE30TA i l
HENNEPW COUNTY
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' ADOCK 05000282 PDR 1
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Exhibit A Page 1 i
Exhibit A l
Prairie Island Nuclear Generating Plant
-l License Amendment Request February 5,1999 i
Evaluation of Proposed Changes to the Technical Specifications Appendix A of Operating License DPR 42 and DPR l a
1 c Pursuant to 10 CFR Part 50, Sections 50.59 and 50.90, the holders of Operating
- Licenses DPR-42 and DPR-60 hereby propose the following changes to Appendix A,
- Technical Specifications:
1 Irttroduction This amendment request proposes a change to Technical Specification (TS) 4.12,
" Steam ' Generator Tube Surveillance", to incorporate changes to the ABB Combustion
. Engineering (CE) sleeve design assumptions and installation techniques. ABB CE l
developed these changes to the sleeve design.
- Th'e current Prairie Island Technical Specifications (TS) allow steam generator tubes j
with eddy current indications requiring repair to be sleeved in accordance with
{
Combustion Engineering. Report CEN-629-P Revision 2 and Addendum 1. The purpose i
of this license amendment is to obtain approval for repair of steam gen'erator tubes
. using Revision 3 to the Combustion Engineering report CEN-629-P, " Repair of -
. Westinghouse Series 44 and 51 Steam Generator Tubes Using Leak Tight Sleeves."
l
. Revision 3 to CEN-629-P incorporates Addendum '1 Revision 1 and includes the i
following major changes.
e' The operating conditions in Section 3 reflect bounding operating conditions in the affected plants, particularly lower secondary side operating pressures The information in Addendum i has been incorporated into Revision 3 e' ' The analyses in Section 8 hav(. been revised using the new conditions defined in
~ Section 3 e 4 Analysis in Section 8 has used the ASME Code allowable tensile strength of 80.0 ksi at 600. F resulting in a lower repair limit.-
c el Reference to the welded sleeve plug has been eliminated. The welded plug has -
been replaced by a torque rolled mechanical sleeve plug e - An attemative high pressure air system has been developed for cleaning the tube
- after brushing.
_The draft Regulatory Guide 1.121 per cent allowable degradation has decreased to e
45.4% with the decrease in assumption of tensile strength n,
l 4
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Exhibit A Page 2 The ABB CE TIG welded sleeves can be used to repair degraded SG tubing at tube support plate intersections or free span locations, within and above the tubesheet
,l region, or a combination of both within the same tube. ABB CE TIG welded sleeving has been determined to be an effective repair method and has successfully been licensed at plants with both 3/4" and 7/8" tubing and in both Westinghouse and Combustion Engineering plants.
The steam generators at Prairie Island are Westinghouse Model 51 steam generators with 7/8 inch low temperature mill-annealed Alloy 600 tubing and a partial depth hard roll expansion tubesheet region. The sleeving materialis thermally treated Alloy 690 tubing. This material has been used for sleeving by Combustion Engineering at Prairie Island since 1987.
A non-heat treated sleeve installed at Prairie Island in 1987 was removed in 1997 and metallurgically examined. This sleeve with 3358 EFPD of service showed no field service degradation in the sleeve, weld, or parent tubing in the above the tubesheet weld region.
A complete description of the sleeve designs and qualification testing is provided in Combustion Engineering Report CEN-629-P, Revision 03, " Repair of Westinghouse Series 44 and 51 Steam Generator Tubes Using Leak Tight Sleeves", September 1998.
Proposed Chances Technical Specification 4.12, " Steam Generator Tube Surveillance", describes the inservice inspection program used to demonstrate steam generator operability. In order to incorporate Revision 3 to CEN 629-P, two items in Technical Specification 4.12 must be revised. A brief description of the proposed revisions is provided below. The specific wording changes to the Technical Specifications are shown in Exhibits B and C.
- 1. Proposed Changes to Technical Specification 4.12.D.1.(f)
The plugging limit for the Combustion Engineering sleeves is changed. "The repair limit for the pressure boundary region of any sleeve is 25% of the nominal sleeve wall thickness."
- 2. Proposed Changes to Technical Specification 4.12.0.3 The reference to the sleeving topical report is changed.
Tube repair, after April 1,1999 using Combustion Engineering welded sleeves shall be in accordance with the methods described in the following:
CEN-629-P, Revision 03-P," Repair of Westinghouse Series 44 and 51 Steam Generator Tubes Using Leak Tight Sleeves"
r c.
f s'
Exhibit A Page 3 i
' Justification l
The current Prairie Island Technical Specification 4.12.D.3 specifies the sleeving topical report revision number. The proposed Technical Specification change is requested to l
update the topical report revision number and to change the sleeve repair limit.in j
accordance with the topical report requirements.. The changes introduced in Revision 3 to the ABB CE sleeving topical report do not chang; the final installed configuration of l
tube sleeves.~ The net effect of these changes yields more conservative sleeve -
plugging criteria than that which is already approved and incorporates some j
improvements in the installation process that have been gained by experience.
t Safety Evaluation Introduction '
Repair of tubes by sleeving addresses tube degradation which requires plugging and which can occur in tubes within the tubesheet region, above the top of the tubesheet, at j
tube support plates, or in straight leg free span regions accessible to the sleeve j
installation equipment. Sleeves'can be used to span the degraded region in order to.
maintain structural.and leakage integrity of the steam generator tube during normal operating and postulated accident conditions. Currently, the Combustion Engineering welded sleeve is authorized for use at Prairie Island in accordance with Revision 2 and
- Addendum 1 to CEN 629-P. Modifications to the repair limit due to changes in the f
. assumption for tensile strength, minor changes in the installation process, and j
consolidation of the topical report warrant review by the NRC at this time.
l
. The prcposed amendment will modify Technical Specification 4.12, Steam Generator
. Tube Surveillance to accommodate the revised repair limit. A description of the sleeve
_ designs and installation requirements is provided in Combustion Engineering Report -
CEN-629-P, Revision 03-P, " Repair of Westinghouse Series 44 and 51 Steam Generator Tubes Using Leak Tight Sleeves", September 1998.
Evaluation This amendment incorporates changes in the '
- tural Analysis and installation
{
Process. The Sleeve Design, Installation Et ation, inservice Examination,
. Corrosion Testing, Mechanical. Testing, and
.kage' Assessment are unchanged from
.the previous license amendment.
j installation Process l
The basic installation process for each type of sleeve involves cleaning of the inside diameter of the tube in the joint region, installation of the sleeve, hydraulic l
expansion of the sleeve in the weld joint region to provide sleeve to parent tube -
" contact, welding of the joint, ultrasonic examination of the weld, optional visual l examination of the weld, optional post weld heat treatment of the weld, i
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e Exhibit A Page 4 completion of the lower joint (welded or rolled), and eddy current examination of the sleeve.
Revision 3 to CEN 629-P discusses a new high pressure air method of cleaning the tube after brushing has been completed. Several programs tested for the effectiveness of the airjet cleaning method. The first program used air oxidized tubes with a visual examination of the inside diameter surface. The second and I
third programs involved cleaning contaminated tubing removed from operating steam generators. These samples were then sleeved, welded, and fully inspected with UT, VT, and ET producing acceptable welds.
1 Vacuum is applied to the end of the tube to collect debris dislodgeo b the airjet j
/
to minimize the spread of radioactive contamination.
)
Structural Analysis The Combustion Engineering welded and welded-hard rolled sleeves were designed to conform to the stress limits and margins of safety of the ASME i
Boiler and Pressure Vessel Code. The methodology used is in accordance with the Section ill of the 1989 Edition of the ASME Boiler and Pressure Vessel Code. Safety factors of 3 for normal operating conditions and 1.5 for accident conditions were applied. In performing the analytical evaluation on the sleeves, the operating and design conditions for all of the Westinghouse operating plants with 7/8 inch inconel tubes were considererl. Stress evaluations were done for j
the above the tubesheet sleeve weld (which is also the weld for the tube support sleeve) at the nominal weld height and at the minimum weld height and for the lower sleeve weld. Stress intensity values are less than the ASME Code allowable values and fatigue usage factors are less than 1. Evaluations of the i
tube support plate sleeve upper and lower welds show that the stresses and loads calculated for the FDTS upper weld are bounding. Details of this analysis are in CEN-629-P.
Using guidance in draft Regulatory Guide 1.121, " Bases for Plugging Degraded PWR Steam Generator Tubes" and the ASME Code, the % allowable degradation for Prairie Island is 45.4% sleeve wall thickness. Making allowances for non-destructive examination (NDE) uncertainty and degradation growth, a plugging criterion of 25% through wall degradation is proposed for degradation that can be appropriately sized. Other types of degradation located in the pressure boundary would be plugged on detection.
Conclusions
t Exhibit A Page 5 lh conclusion, Northern States Power believes there is reasonable assurance that the health and safety of the public will not be adversely affected by the proposed Technical Specification changes.
Determination of Sionificant Hazards Considerations The proposed amendment incorporates revision 3 to the ABB/ Combustion Engineering Topical Report CEN-629-P. Three types of changes are incorporated in CEN-629-P, Revision 3:
Editorial Changes (the inclusion of Addendum 1 to the Topical Report and the removal of reference to welded sleeve plug)
Changes in sleeve installation practices (the use of high pressure air for cleaning tubes)
Changes to the sleeve repair limit (the lower secondary side operating pressure of section 3 and the use of ASME Code allowable tensile strength result in changes to the analyses of Section 8 which, in turn, result in a lower repair limit and reduced allowable degradation)
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, Sec on 50.91 using the standards provided in Section 50.92. This analysis is provided below:
1.
The proposed amendment will not involve a sianificant increase in the probability or consecuences of an accident oreviously evaluated.
Editorial changes have no effect on probability or consequences of accidents previously evaluated. Changes in installation practices incorporate improvements gained by (,xperience in installing sleeves. Further, the changes in the installation practices wi!! change neither the final configuration of installed sleeves nor the post-installation NDE from that which is already approved. Accident induced steam generator tube leakage is not effected by these changes. Post installation non-destructive examination will be conducted using VT, UT, and ET as previously licensed. The changes in repair limits have lead to repair limits that are more conservative than those which have been previously approved. Thus, none of these changes willincrease the probability or consequences of previously evaluated accidents.
2.
The proposed amendment will not create the possibility of a new or different kind of accident from any accident previousiv analyzed.
Editorial changes cannot create the possibility of a new or different kind of accident.
Changes in installation practices incorporate improvements gained by experience in installing sleeves. Further, changes in installation practices do not change the final configuration ofinstalled sleeves from that which is already approved. The
';.Y v
.j Exhibit A -
Page 6 chhnges'in repair limits have lead to repair limits that are more conservative than -
those which have been previously approved. Thus, none of these changes will create the possibility of a new or different kind of accident from any accident previously analyzed.
- 3. 'The proposed amendment will'not involve a sianificant reduction in the marain of safety.
Editorial changes have no effect on the margin of safety. Changes in installation practices incorporate improvements gained by experience in installing sleeves.
Further, changes in installation practices do not change the final configuration of-installed sleeves from that which is already approved. The changes in repair limits have1ead to repair limits that are more conservative than those which have been -
. previously approved. None of these changes will affect the tube plugging assumptions used in the PINGP accident analyses. Thus, none of these changes will reduce the margin of safety.
Based on the evaluation described above, and pursuant to 10 CFR Part 50, Section
' 50.91, Northern States Power Company has determined that operation of the Prairie Island Nuclear Generating Plant in accordance with the proposed license amendment request does not involve any significant hazards considerations as defined by NRC regulations in 10 CFR Part 50, Section 50.92.
Environmental Assessment Northern States Power has evaluated the proposed changes and determined that:
- 1. 3 The changes do not involve a significant hazards consideration, 2.
The changes do not involve a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or 3.
The changes do not involve a significant increase in individual or cumulative occupational radiation exposure.
Therefore, the proposed Technical Specification changes would not result in a significant radiological environmental impact.
- ~.