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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 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 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 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 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 1999-08-31
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UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET NO. 50-282 {
50-306 License Amendment Request Dated April 12,1999 Relocation of Shutdown Margin Requirements to the Core Operating Limits Report Northern States Power Company, a Minnesota corporation, with this letter is submitting information to support a requested license amendment.
This letter contains no restricted or other defense information.
l NORTHERN STATES POWER COMPANY BY
/ del P. Sorense'n Site General Manager Prairie Island Nuclear Generating Plant On this /c/d day of AMAd /999 before me a notary public in and for said County, perso6 ally appeared Joel P. Sorensen, Site General Manager, Prairie Island Nuclear Generating Plant; and being first duly sworn acknowledged that he is authorized to execute this document on behalf of Northern States Power Company, that he knows the contents thereof, and that to the best of his knowledge, information, and belief the statements made in it are true and that it is not interposed for delay.
, . Al YJAj m::::.v:==:===: m RACHEL A. KAITALA peOTAlqY PUSUC.ENNC30TA 9uycoswesem D;stesJa H,2000 HENNEPIN COUNTY 9904210066 990412 7h ADOCK 05000282;.
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- .3 EXHIBIT A PRAIRIE ISLAND NUCLEAR GENERATING STATION License Amendment Request dated April 12,1999 Evaluation of Proposed Changes to the Tchnical Specifications ,
Appendix A of Operating Licenses DPR-42 and DPR-60 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 the Technical Specifications contained in Appendix A of the Facility Operating Licenses:
BACKGROUND As part of the Prairie Island Nuclear Generating Plant (PINGP) Updated Safety Analysis Report (USAR) review and update pioject, a transient scenario was identified which could potentially place the plant in an unanalyzed condition. The current Chemical and Volume Control System (CVCS) Malfunction analysis in the USAR, Section 14, evaluates the effects from an inadvedent boron dilution in refueling, start-up and power (manual and automatic rod control) operation. The USAR review concluded that the plant is within the design basis as described in the I analyses for these plant conditions. However, per plant Technical Specifications other plant operating conditions are allowed which could be more limiting from a boron dilution analysis perspective. This condition was reported in LER 1-97-12 dated November 7,1997. Administrative controls were implemented to specify higher shutdown margins than specified in the plant Technical Specifications for these other plant conditions to ensure that the analyses in the USAR are bounding.
Consistent with the guidance in NRC Administrative Letter 98-10 "Dispositioning of Technical Specifications that are Insufficient to Assure Plant Safety," this License Amendment Request proposes changes to the Technical Specifications which will ensure that the analyses in the USAR remain bounding. This is being done through the following methods: (1) the shutdown margin requirements are being relocated to the Core Operating Limits Repod (COLR), and (2) the shutdown margin requirements in the COLR will be calculated using methods developed to provide sufficient shutdown margin for postulated dilution accidents for all plant conditions.
The shutdown margin limits being incorporated into the COLR will be developed utilizing methodology described in NSPNAD-8102-P, Revision 7, " Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods For Application to PI Units."
NSPNAD-8102-P, Revision 7, was submitted for NRC review and approval on January 29,1999. That methodology will establish the minimum required shutdown 1
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I l margin for a dilution accident during MODES 3,4,5 and 6. The shutdown margin
' limits will ensure that a complete loss of shutdown margin will not occur for at least twenty-four minutes from initiation of the dilution. Pending approval of this License Amendment Request and the new methodology, the USAR will be updated to include analyses for all operating modes.
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! PROPOSED CHANGES In order to relocate shutdown margin requirements to the COLR and ensure that the Technical Specification requirements are consistent with the USAR dilution analysis, several Technical Specification sections require changes. Brief descriptions of the proposed changes are provided below. The specific wording changes to the Technical Specifications are provided in Exhibits B and C. A sample of a portion of the Prairie Island COLR incorporating the shutdown margin limitations developed using the methodology in NSPNAD-8102-P, Revision 7, is provided as Exhibit D.
Table TS.1-1. Operational Modes A reference to the COLR is being incorporated to specify additional shutdown margin requirements for MODE 6 operation. The proposed change will ensure that the most restrictive shutdown margin requirement will be invoked during MODE 6 operation.
TS.3.10.1.A. Control Rod and Power Distribution Limits - Specification The proposed changes incorporate a reference to the COLR for shutdown margin requirements and eliminate the reference to Figure TS.3.10-1. A sample of a portion of the Prairie Island COLR incorporating the shutdown margin limitations is provided as Exhibit D.
TS.3.10.D.3. Rod Insertion Limits The proposed changes relocate the shutdown margin requirements from Figure TS 3.10-1 to the COLR.
Fiaure TS.3.10-1 Reauired Shutdown Marain vs Reactor Boron Concentration The proposed changes delete this figure. The COLR will specify the shutdown margin requirements as shown in Exhibit D. Therefore, this figure will no longer be applicable.
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TS.6.7.A.6. Core Operatina Limits Report Specification 6.7.A.6.a is being revised to add shutdown margin as an operating limit ;
specified in the COLR. No change to Specification 6.7A.6.b is required because a '
reference to the " latest approved version" of the NSP Topical Report NSPNAD-8102-P is already included in Specification 6.7.A.6.b.
License Amendment 141 was issued by the NRC on December 7,1998. That ;
License Amendment revised the Administrative Controls section of the Technical Specifications. Because of the amount of effort necessary to fully implement the
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j changes resulting from License Amendment 141, fullimplementation of the changes j is not required until September 1,1999. During the interim period, the NRC '
requested that NSP submit two sets of Technical Specification pages for any pages affected in future amendments by the issuance of License Amendment 141. The Technical Specification pages should reflect the conditions before and after full implementation of License Amendment 141 so that the correct Technical pages may be issued in any future amendments. In response to that request, Exhibits E and F contain a revision to Technical Specification page TS.6.0-13. Page TS.6.0-13 was issued with License Amendment 141, and it has been revised to reflect the changes to Section 6.7.A.6.a proposed by this License Amendment Request. l l
B.3.8. Refuelina and Fuel Handlina The Bases for Section 3.8 are being revised in accordance with the Technical Specification changes described above. The changes to the bases are shown in Exhibit B.
B.3.10.A. Control Rod and Power Distribution Limits Bases The Bases for Section 3.10.A are being revised in accordance with the Technical Specification changes described above. A paragraph is also being added to support Technical Specification 3.10.A.2. This paragraph is intended to clarify the bases for the 15 minutes allowed to initiate boration if shutdown margin is less than the applicable limit. The proposed bases for the 15 minute action statement is consistent with that provided in the Improved Standard Technical Specifications (NUREG-1431).
The changes to the Bases are shown in Exhibit B.
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JUSTIFICATION OF CHANGES The proposed changes to Table TS.1-1 invoke an additional third criteria for shutdown margin in order to ensure that adequate shutdown margin is maintained during MODE 6 operation.
This License Amendment Request proposes to relocate the shutdown margin requirements from the Technical Specifications to the COLR. Generic Letter 88-16, dated October 4,1988, was issued to encourage licensees to prepare changes to Technical Specifications related to cycle-specific parameters. The generic letter provided guidance for the relocation of certain cycle-dependent core operating limits from the Technical Specifications. This would allow changes to the values of tnese cycle-dependent core operating limits without prior NRC approval, provided the NRC-approved methodology for the calculations is followed. Shutdown margin was not one of the parameters included in Generic Letter 88-16 that could be relocated to the COLR. However, Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler TSTF-9, Revision 1, proposed the relocation of shutdown margin requirements from the Technical Specifications to the COLR. That TSTF traveler was approved by the NRC on September 18,1996.
The shutdown margin limits being incorporated into the COLR will be developed utilizing the methodology described in NSP topical report NSPNAD-8102-P, Revision 7. That revision to NSPNAD-8102-P was submitted for NRC review and approval on January 29,1999. That methodology will establish the minimum required shutdown margin for a dilution accident during Modes 3,4,5 and 6.
SAFETY EVALUATION i
The proposed changes to the Prairie Island Technical Specifications relocate the shutdown margin requirements to the COLR.
The shutdown margin requirements being incorporated into the COLR will utilize the methodology submitted by NSPNAD-8102-P, Revision 7, " Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods For Application to PI Units" dated January,1999. NSPNAD-8102-P, Revision 7, was submitted to the NRC for review and approval on January 29,1999. That methodology will establish the minimum required shutdown margin for a dilution accident during Modes 3,4,5 and 6 and will ensure that a complete loss of shutdown margin will not occur for at least twenty-four minutes from initiation of the dilution as specified in the Prairie Island USAR.
The relocation of the shutdown margin requirements to the COLR is an administrative change which has no impact upon plant operation or safety. No safety-related equipment, safety function, or plant operations will be altered as result of the proposed changes. The current Technical Specification shutdown margin 4
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l requirements and the interim additional administrative controls will be maintained and followed until the NRC approves the new methodology.
The proposed changes to Table TS.1-1 which invoke an additional third criteria for l shutdown margin will ensure that adequate shutdown margin is maintained during i MODE 6 operation.
In conclusion, Northern States Power Company 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 SIGNIFICANT HAZARDS CONSIDERATIONS The proposed changes to the Prairie Island Operating Licenses have been evaluated to determine whether they constitute a significant hazards consideration l as required by 10 CFR 50, Section 50.91 using the standards provided in Section 50.92. This analysis is provided below:
i 1. The proposed amendment will not involve a sianificant increase in the probability or conseauences of an accident previousiv evaluated.
The proposed changes do not affect any system that is a contributor to initiating events for previously evaluated design basis accidents. The proposed changes do not involve any system changes or modifications. No systems or equipment will be operated in a new manner as a result of the proposed changes.
Therefore, the proposed changes do not involve a significant increase in the probability of an accident previously evaluated.
l Relocation of the shutdown margin requirements to the COLR is an administrative change. The shutdown margin requirements being incorporated into the COLR will be developed using NRC approved methodology. That methodology will establish the minimum required shutdown margin for a dilution accident during Modes 3,4,5 and 6 and will ensure that a complete loss of shutdown margin will not occur for at least twenty-four minutes from initiation of the dilution as specified in the Prairie Island USAR. Therefore, the relocation of the shutdown margin requirements to the COLR will not result in any increase in the consequences of an accident previously evaluated.
The proposed changes to Table TS.1-1 invoke an additional third criteria for shutdown margin during MODE 6. This proposed change involves an additional restriction designed to ensure that shutdown margin is maintained during MODE 6 operation, and as such will not result in any increase in the consequences of
[.. an accident previously evaluated.
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1 Therefore, based on the conclusions of the above analysis, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. The, proposed amendment will not create the possibility of a new or different kind l of aocident from any accident previously analyzed.
The proposed changes do not alter the design or function of any plant l component and do not install any new or different equipment. The proposed !
changes do not alter the operation of any plant component in a manner which could lead to a new or different kind of accident. Therefore the possibillty of a new or different kind of accident from those previously analyzed has not been created.
- 3. The proposed amendment will not involve a sianificant reduction in the marain of !
safety.
Relocation of the shutdown margin requirements to the COLR is an administrative change. The shutdown margin requirements being incorporated into the COLR will be developed using NRC approved methodology. That methodology wiil establish the minimum required shutdown margin for a dilution accident during Modes 3,4,5 and 6 and will ensure that a complete loss of shutdown margin will not occur for at least twenty-four minutes from initiation of the dilution as .specified in the Prairie Island USAR. Therefore, the relocation of the shutdown margin requirernents to the COLR will not reduce the margin of safety because it has no effect on any safety analyses assumptions.
The proposed changes to Table TS.1-1 invoke an additional third criteria for l
shutdown margin during MODE 6. This proposed change involves an additional restriction designed to enhance plant safety by ensuring that shutdown margin is maintained during MODE 6 operation. The imposition of more restrictive requirements either has no effect on or increases the margin of plant safety. The change maintains requirements within the safety analyses and licensing basis.
Therefore, the proposed changes to Table TS.1-1 do not involve a significant reduction in the margin of safety.
Therefore, based on the conclusions of the above analysis, the proposed changes do not involve a significant reduction in the margin of safety.
Considering the above evaluation and pursuant to 10CFR50.91, 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 a significant hazards consideration as defined by Nuclear Regulatory Commission regulations in 10CFR50.92.
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ENVIRONMENTAL ASSESSMENT Northern States Pcwer Company has evaluated the proposed changes and determined that:
- 1. 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, and
- 3. The changes do not involve a significant increase in individual or cumulative occupational radiation exposure.
Accordingly, the proposed change meets the eligibility criterion for categorical exclusion set forth in 10CFR51.22(c)(9). Therefore, pursuant to 10CFR51.22(b), an environmental assessment of the proposed changes is not required.
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